LICENSEE CONTRACTOR AND VENDOR INSPECTION ...

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NUREG-0040, Vol. 2, No. 5QUARTERLY REPORTSEPTEMBER 30,1978 -

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j AND VENDOR INSPECTIONs A * STATUS REPORTs,

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NUCLEAR REGULATORY COMMISSION

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Available from

National Technical Information ServiceSpringfield, Virginia 22161

A year's subscription, 4 issues, forthis publication is $45.00; multiplesubscriptions entered at the sametime to the same address are S37.00;

single copies available at $12.50.

Microfiche of single copies isavailable at current rate.

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! QUESTIONNAIRES3r

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PERSON COMPLETING QUESTIONNAIRE.

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ISSUE DISTRIBUTION LISTING : J THE BOOK IS:Ig

Gentlemen : ,5.m

As you know, the Licensee-Contractor and Vendor 5 csInspection Status Report The White Book 'y 4. DO YOU WISH TO CONTINUE RECEIVING THE BOOK?

YES NO

has been issued quarterly for the past three years.,

At this point in time, issue of the Book has becomea considerable effort bnth in terms of data - - - - - - - - - - - - - - F0 LD - - H E R E - - - - - - - - - - - - - - - - -accumulation and issue logistics and we want ijto justify contirued publication based on: (1) an :W 5. WOULD YOU FAVOR SEMI-ANNUAL VS. OUARTERLY ISSUES?

YFS No

industry expression of need and (2) changes desiqned eto provide maximum value to recipients of the Book. *8

6. ARE THERE SECTIONS OF THE BOOK YOU THINKConcerning the above, we request t.at the question- SHOULD BE EXPANDED? IF S0, LIST hnaire on the right be completed as soon as possible, g

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folded, stapled, and placed in the mail. *[ __

:E 7 ARE THERE SECTIONS OF THE BOOK YOU FEELncerely, ARE OF LITTLE OR NO VALUE? IF S0, LIST h_

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IF QUESTIONS 6 OR 7 RECEIVED YES ANSWERS, PLEASE ElABORATtBELOW

Ka rl . Seyfrit j AND/OR PPOVIDE OTHER COMMENTS.*Di rector

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UNITED ST ATES F ]NUCLEAR RE GU LA TO R Y COMMISSION

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OFFICI AL BUSINESS c ou u sssION-

EPEN ALTY F OR PRIV ATE USE,$300

U. S. NUCLEAR REGULATORY COMMISSIONATTN: MR. W. E. VETTER

ASSISTA::T TO THE DIRECTOR611 RIAN PLAZA DRIVE, SUITE 1000ARLINGTON, TEXAS 76011

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TABLE 0F C0NTENTS 'J J3

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SPECIAL SECTION - Questionnaire. .. . 1

SECTION I - General Information. . . 3

TABLE OF CONTENTS . . . 4

PREFACE . . .. . . . . . 5PROGRAM HIGHLIGHTS . . . 7

DATA PAGE DESCRIPTION . .. . . . . 10CONTRACTOR AND VENDOR LISTING . . . 11

SECTION II - Inspection Results. . . . 19

NUCLEAR STEAM SUPPLY SYSTEMS. . .. . 21ARCHITECT ENGINEERS. . . . . .. 25NUCLEAR FUEL SUPPLIERS. . . 33VENDORS. . 36

SECTION III - " Approved Program" Listing. . . . 97

CONTRACTORS WITH IE LETTE RS CONFIRit t :GQA PROGRAM IMPLEMENTATION. 99

SAMPLE CONTENT LETTER. . .100

SECTION IV - Licensee Event Reports. . .. .101

This section of the report contains informationconcerning the timing, source, significance,and cause accountability c o min o n to LicenseeEvent Reports.

Alphabetized Listing of LER'sIncluded This Report Period. .103

<rCTION V - IE Bulletins and Circt!.>rs. .219

This section of the report contails IE Bulletinsand Circulars issued this Re;crt Period.

Nuncrical Listing of IE Bulletiis. .221'umerical Listii.g of Ir rirculars. .228,

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V

PREFACEy

A fubdamental premise of the Nuclear Regulatory Commission's nuclear in the case of principal licensee contractors, such as nuclear steam sy: temfacility licensing and inspection program is that the licensee is respon- suppliers and architect engineering firms, the Nuclear Regulatory Commh sionsible for the proper construction and safe operation of his nuclear power > encourages submittal of descriptions of corporate-wide quality assu anceplant. The total government-industry system for the inspection of nuclear programs for review and acceptance by the Office of Nuclear Reactor Regula-facilities has been designed to provide for multiple levels of inspection tion (NRR). Upon acceptance by NRR, these quality assurance programs provideand verification. The licensee and his contractors and vendors each partic- bases for inspection by the Office of Inspection and Entorcement (IE) on aipate in the inspection process in accordance with requirements prescribed generic basis, rather than with respect to specific commitments made to ain the NRC rules and regulations. The NRC inspects to determine whether particular licensee. Once accepted by NRR, a corporate quality assuranceits requirements are being met by the licensee and his contractars. The program of a licensee contractor will be acceptable fo- all license applica-total nuclear inspection activity is pyramided, with each layer of activity tions that incorporate the program by reference in the Safety Analysis Report.verified, inspected or audited by those above. The NRC's position is at In such cases, the contractor's quality assuran . program will not be re-the apex, while the great Lulk of the inspection activity is performed by viewed by NRR as part of the licensing review process, providad the incor-industry within the base. poration in the SAR is without change or modification.

In implementing this multiple layer approach, the licensee is responsible Through the NRC Region IV Office in Dallas, IE inspects the implementationfor developing a detailed quality assurance plan as part of his license of quality assurance programs which have been submitted to and approved byapplication. This plan includes the quality assurance programs of the NRR in the form of Topical Reports or standardized programs from nuclearlicensee's contractors and vendors. The NRC reviews the licensee's and steam system suppliers and architect engineering firms. Upon completioncontractor's quality assurance plans to determine that implementation of of inspections confirming satisfactory implementation of the QA program, IEthe proposed quality assurance program would be satisfactory and respon- will issue a confirming latter to the nuclear steam system supplier orsive to NRC regulations. architect engineering firm. Those licensees and applicants that have ref-

erenced the NRR approved Topical Report or standardized program in theirThe firms designing nuclear steam systems, the architect engineering firms Cafety Analysis Reports or have adapted the total quality assurance programdoing design work on nuclear power plants, and certain selectad vendors are described in the Topical Report or standardized program may, at their option,currently inspected on a regular basis by NRC. NRC inspectors, during use the confirming letter from IE contained in Section III of this documentperiodic inspections, ascertain through direct observation at selected to fulfill the obligation under Criterion Vil, Appendix B, 10 CFR 50 toactivities, including review of processes and selected hardware, discussions establish that those contractors and subcontractors who have been issuedwith employees and selected record review whether the licensee or contractor such a confirming letter are effectively implementing their QA pcograms asis satisfactorily implemeneing his quality assurance program, described in their Topical Reports or standardized programs.

If defects or malfunctions in safety-related con ponents or systems cecur The NRC expression of satisfaction confirms only that the programmaticwhich may be attributed to a failure in quality assurance, the NRL Jooks aspecte of the NRC approved QA program have been implemented, and does notclosely at the quality assurance program in order to achieve improvement assure that aay unique programmatic requirements imposed by licensee arein implemertation of the program. NRC also veriftas the adequacy of the being implemented er that a specific product or service prov ded to acorrective action taken with regard to the specific -leficiency that led to licensee is of acceptable quality. Subject to applicable NRC requirements,the defect or malfunction. the licensee still must provide cualit y assurance / cont rol rueasures, nec-

essary to assure the implementation of the licensee's unique prcgrammat icIn summary, the NRC relies principally oc a goverr. ment-approved quality requirements, if any, and the quality of specific products or services.assurance program which the NRC confirms to be satisf actorily implementedby the licensee or contractor. Assurance of the effectiveness of thisprogram is maintained by continuing government evaluation and audit. (continued next page )

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The IE letter confirming satisfactory implementation of the QA program does Reports of inspections which provide the data contained in this statusnot constitute an ur. conditional or continuing expression of NRC's satisfac- report will be placed in the CSNRr Public Document Room, located intion with the implementation of a contractor's QA program. Continued ac- Washi n gt on , D. C., subsequent to review of the inspection report by theceptability is contingent upon maintenance of a satisfactory level of inspected organization.program implementation verified through periodic IE inspections. Shouldthe program implementation at any time be found unacceptable, licensees Copies of the White Book are routinely provided organizations identifiedwill be notified by letter to t''- effect and this fact will also be spe- within the book. For other interested persons, copies of this book may becifically noted in this document From the date of such a letter, affected obtained at a nominal cost by writing to the National Technical Inf ormationapplicants and licensees individually must provide the necessary assurance Service. Springfield, Virginia 22161.required under Criterion VII of Appendix B, 10 CFR 50.

The NRC currently is evaluating a proposed program for NRC acceptance ofthird-party inspections of vendors. Should such third-party inspectionsbe approved, it is anticipated that, subject to NRC audit of the inspectionprogram, approved third-party inspections of vendors may be used to fulfillapplicants' and licensees' obligations under Criterion VII. Pending approvalof the third-party inspections, direct IE inspections will continue to bemade. Those interim IE inspections will not relieve applicants or licenseesfrom Criterion VII obligations.

A third category of firms consists of organizations whose quality assur-ance programs or manufacturing processes have not oeen reviewed andapproved by NRR, or by a third party (ASME). This category of firms willbe subject to IE inspection based on the performance of products or serv-ices provided by such firms. Results of direct IE inspections of suchfirms may not be used to fulfill licensees' obligations under CriterionVII.

In addition to providing information on inspection results, this LicenseeContractor and Vendor Inspection Status Report - the " White Book" -will contain information submitted by licensees in accordance with NRCrules and regulations covering events attributed by the licensee to designdeficiencies and equipment malfunctions. These licensee event reportswhich will cover one calendar quarter, will identify both the vendor and theorganization responsible for the procurement and/or de-ign document.

The White Book contains inf ormation wiich is neces sary in establishing a

" qualified suppliers" list; however, the inf ormation contained in thisdocument is not adequate nor is it intended to stand by itself as a sourceof information concerning qualified suppliers.

6

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M PROGRAM HIGHLIGHTS @

DURING THE CALENDAR YEAR QUARTER SEPTEMBER 30, 1978 THE 58 INSPECTIONS, INDEXED BELOW (THOSE NOT FOLLOWED BY A DATE IN PARENTHESES),WERE CONCUCTED:

NUCLEAR STEAM SYSTEM SUPPLIERS PAGE NUCLEAR FUELS SUPPLIERS MGL

BABCOCK & WILCOX COMPANY, NUCLEAR POWER COMBUSTION ENGINEERING. INC., NUCLEARPRODUCTS MANUFACTURING WINDSOR, CT 33GENERATION DIVISION * LYNCHBURG, VA *

COMBUSTION ENGINEERS, INC. (6/26-30/78) WINDSOR, CT 21 EXXON NUCLEAR COMPANY, INC., NUCLEARFUELS DEPARTMENT * RICHLAND, WA *

COMBUSTION ENGINEERS, INC. * WINDSOR CT *

GENERAL ELECTRIC COMPANY, NUCLEAR ENERGY GENERAL ELECTRIC COMPANY, WILMINGTON

BUSINESS GROUP SAN JOSE, CA 22 MANUFACTURING DEPARTMENT WILMINGTON, NC 34

GENERAL ELECTRIC COMPANY, NUCLEAR ENERGY WESTINGHOUSE ELECTRIC CORP., NUCLEAR

FUEL DIVISION (5/22-26/78) PITTSBURGH, PA 35BUSINESS GROUP * SAN JOSE, CA *

WESTINGHOUSE ELECTRIC CORP., PRESSURIZED

WATER REACTOR SYSTEMS DIV. (6/6-8/78) MONR0EVILLE, PA 23WESTINGHOUSE ELECTRIC CORP., PRESSURIZED

WATER REACTOR SYSTEMS DIVISION MONROEVILLE, PA 24 VENDORS

WESTINGHOUSE ELECTRIC CORP., PRESSURIZEDAMETEK, INCORPORATED, STRAZA DIVISION * EL CAHON, CA *

WATER REACTOR SYSTEMS DIVISION * MONROEVILLE, PA *

ARMCO, INCORPORATED, ADVANCED MATERIALDIVISION * LOUSTON, TX *

ASSOCIATED PIPING & ENGINEERING CORP.,DIVISION OF JOHNSON CONTROLS * COMPTON, CA *

ARCHITECT ENGINEERS AWOOD FND MORRILL COMPANY, INC. * SALEM, MA *

BABC0CK & WILC0X COMPANY MT. VERNON, IN 36

BECHTEL POWER CORPORATION, LOS ANGELES BARTON INSTRUMFNTS - A UNIT OF ITT

POWER DIVISION (6/26-29/78) NORWALK, CA 25 (2/21-24/78) CITY OF INDUSTRY, CA 37BECHTEL POWER CORPORATION, GAITHERSBURG BENJAMIN F. SHAW LAURENS, SC 40

POWER DIVISION (5/8-12/78) GAITHERSBURG, MD 26 BERGEN-PATERSON PIPESUPPORT CORP.(6/5-8/78) LACONIA, NH 41

BECHTEL POWER CORPORATION, GAITHERSBURG B0EING ENGINEERING AND CONSTRUCTION,

POWER DIVISION GAITHERSBURG, MD 27 DIVISION OF BOEING COMPANY * SEATTLE, WA *

BECHTEL POWER CORPORATION, SAN FRANCISCO BOSTON INSULATED WIRE AND CABLE COMPANY * BOSTON, MA *

POWER DIVISION (5/22-25/78) SAN FRANCISCO, CA 28 BRECA TERM 0MECCANICA S.p.A. (5/30-6/2/78) MILAN, IT 43

BLACK & VEATCH CONSULTING ENGINEERS KANSAS CITY, KS 29 BYRON JACKSON PUMP DIVISION, BORG-WARNER

EBASCO SERVICES, INC. (6/19-23/78) NEW YORK, NY 30 CORPORATION * VERNON, CA *

SARGENT & LUNDY CHICAG0, IL 31 COMBUSTION ENGINEERING, INC. * CHATTAN0OGA, TN *

STONE & WEBSTER ENGINECRING CORPORATION BOSTON, MA 32 CONAX CORPORATION (5/15-19/78) BUFFALO, NY 45CONSOLIDATED CONTROLS CORP. (6,'20-22/78) BETHEL CT 47STONE & WEBSTER ENGINEERING CORPORATION * BOSTON, MA *

* CRANE MIDWEST FITTINGS * ST. LOUIS, M0 *UNITED ENGINEERS & CONSTRUCTORS. INC. * PHILADELPHIA, PA

*See footnote, page 9(continued next page)

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PROGRAM HIGHLIGHTS (continued)

VENDORS (continued) PAGF VENDORS (continued) PAGF

CROSBY VALVE & GAGE COMPANY WRENTHAM, MA 49 NPS INDUSTRIES, INC., A SUBSIDIARY OFDRAVO CORPORATION, PIPE FABRICATION NUCLEAR POWER SERVICES, INC. * AUSTIN, TX *

DIVISION (4/10-13/78' MARIETTA, OH 51 D. G. O'BRIEN, INC. (6/6-9/78) SEABROOK, NH 74DRESSER INDUSTRIES, INC., INDUSTRIAL VALVES PACIFIC PUMPS, DIVISION OF DRESSER

AND INSTRUMEt:T DIVISION (5/30-6/2/78) ALEXANDRIA, LA 54 INDUSTRIES HUNTINGTON PARK, CA 77ENERGY PRODUCTS GROUP, GULF & WESTERN PAUL-MUNROE HYDRAULICS, INC. (6/5-9/78) ORANGE, CA 78

PITTSBURGH-DES MOINES STEEL (6/19-23/78) PROV0, UT 79MFG. COMPANY * W# NICK, RI *

ENERGY PRODUCTS GROUP, GULF & WESTERN PROCESS EQUIPMENT CO., INC. * BROCKTON, MA *

MFG. COMPANY * NORTH BRANCH, NJ PULLMAN POWER PRODUCTS, DIVISION OF*

E-SYSTEMS, MONTEK DIVISION (5/23-26/78) SALT LAKE CITY, UT 55 PULLMAN, INC. * WILLIAMSPORT, PA *

EXCELC0 DEVELOPMENTS, INC. (3/27-31/78) SILVER CREEK, NY 56 PULLMAN POWER PRODUCTS, DIVISION OFEXCELC0 DEVELOPMENTS, INC. (6/26-30/78) SILVER CREEK, NY 57 PULLMAN, INC. (6/19-22/78) PARAMOUNT, CA 80FISHER CONTROLS COMPANY (6/5-9/78) MARSHALLTOWN IA 59 PX ENGINEERING CO., INC. WOBURN, MA 81

FOU.EY ENGINEERING COMPANY (5/30-6/2/78) ADDISON, TX 60 RHINE-SCHELDE-VER0LME APPARATENBOUW b.v.GENERAL ELECTRIC COMPANY, SWITCHGEAR (6/12-16/78) ROTTERDAM, NETH 82

BUSINESS DEPARTMENT (2/13-17/78) PHILADELPHIA, PA 61 ROSEMOUNT, INCORPORATEL EDEN PRAIRIE, MN 84GENERAL ELECTRIC COMPANY, SMALL AC MOTOR SIEMENS-ALLIS, INCORPORATED * LITTLE ROCK AK *

PRODUCTS DEPARTMENT (5/15-18/78) SAN JOSE, CA 63 SOUTHWEST FABRICATING & WELDING CO., INC. * HOUSTON, TX *

G0ULD, INC. ELECTRICAL APPARATUS TEXAS PIPE BENDING COMPANY HOUSTON, TX 85TRENT TUBES, DIV. OF CRUCIBLE, INC. * CARROLLTON, CADIVISION (6/27-29/78) * FINKSBURG, MD **

GOULD, INC., SWITCHGEAR OPERATIONS DIV. FT. WASHINGTON, PA 65 TUBE TURNS, DIVISION OF CHEMCTRON CORP. * LOUISVILLE, KY *

HAYWARD TYLER PUMP COMPANY, DIVISION OF UNION PUMP COMPANY * BATTLE CPEEK, MI *

STONE PRATT BURLINGTON, VT 66 VALTEX, INCORPORATED (6/19-22/78) SPRINGVILLE, UT 86

HENRY PRATT COMPANY (6/27-30/78) AURORA, IL 67 VELAN ENGINEERING, LTD. * MONTPEAL, CAN *

HOPKINSONS LIMITED (6/19-22/78) HUDDERSFIELD, ENG 68 VELAN VALVE COMPANY WILLISTON, VT G7

WALWORTH COMPANY, ALOYC0 PLANT LINDEN, NJ 83INGERSOLL-RAND COMPANY, CAMERON PUMP DIV. * PHILLIPSBURG, NJ *

ITT GRINNELL COMPANY, INC., DYNAFLOW WALWORTH COMPANY , GREENSBURG DIVISION * GREENSBURG, PA *

WELK BROS. METAL PRODUCTS, INC. SP0rANE, WA 89DIVISION * LANCASTER, PA *

WESTINGHOUSE ELECTRIC CORPORATION,ITT GRINNELL, PIPE HANGER DIVISION * WARREN, OH *

THE KERITE COMPANY, SUBSIDIARY OF ELECTRO MECHANICAL DIVISION (5/16-19/ 78) CHESWICV, PA 90WESTINGHOUSE ELECTRIC CORPORATION TAMPA, FL 91HARVEY HUBBELL, INC. * SEYMOUR, CT *

LAKESIDE BRIDGE & STEEL COMPANY WESTINGHOUSE ELECTRIC CORP., POWER

(6/26-30/78) MILWAUKEE, WI 70 SYSTEMS, SWITCHGEAR DIVISION (6/12-16/78) E.PITTSBURGH, PA 92

WESTINGHOUSE ELECTRIC CORPORATION PENSACULA, FL 93LAMCO INDUSTRIES, INC. * EL CAJON, CA *

LIMITORQUE CORPORATION (6/13-16/78) LYNCHBURG, VA 71 WESTINGHOUSE ELECTRIC CORPORATION

MURDOCK, INCORPORATED COMPTON, CA 72 INDUSTRIAL & GOVERNMENT TUBE DIVISION HORSEHEADS, NY 94

NL INDUSTRIES, INC., NUCLEAR DIVISION THF WILLIAM POWELL COMPANY, PLANT NO. 2 CINCINNATI, OH 95

(4/24-28/78) 73

*See footnote, next pageg(continued next page)

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PROGRAM HIGHLIGHTS (continued)

THE 59 INSPECTIONS, LISTED ON THIS AND THE PRECEDING PAGE (THOSE NOT FOLLOWED BY AN ASTERISK), RESUlTED IN THE IDENTIFICATION OF 201 DEVI ATIONSFROM COMMITFENTS. THE NUMBER OF DEVI ATIONS PER INSPECTION RANGED FROM 21 AT ONE FACILITY TO NONE AT I6 FACILITIES. THE AVERAGE RATE OF DEVIA-TION IDENTIFICATION WAS 3.41 DEVIATIONS PER INSPECTION. THIS REFLECTS A 0.07 INCREASE FROM lHE PREVIOUS REPORT PERIOD AVEPAGE DEVIATION DETECTIONPER INSPECTION RATE OF 3.34. IN MOST CASES, THE DEVIATIONS REFLECTED A FAILURE TO IMPLEMENT OR FOLLDW EXISTING PROCEDURES, OR FAILURE TO PROVIDE

IMPLEMENTING PROCEDURES.

FROM EACH FACILITY WHICH HAS DEVIATED FROM COMMITMENTS, LETTERS HAVE BEEN, OR WILL BE, SENT TO APPROPRIATE MANAGEMENT PERSONNEL, PROVIDING THEMWITH AN OPPORTUNITY TO RESPOND IN TERMS OF AGREEMENT OR DISAGREEMENT, AND TO DESCRIBE ANY CORRECTIVE ACTIONS WHICH HAVE BEEN, OR WILL BE, TAKEN.

INSPECTIONS DURING THIS REPORTING PERIOD CONSISTEDOF THE FOLLOWING CATEGORIES-NUMBER BREAKDOWN:

VENDOR. .. . .... . 71

ARCHITECT ENGINEER. . 10...

NUCLEAR STEAM SYSTEM SUPPLIER . . 8NUCLEAR FUELS SUPPLIER. . . ..,,4,

TOTAL 93

FOOTNOTE

* INSPECTIONS PERFORMED WitEREIN DEVIATIONS FROM COMMIIMENTS WEREIDENTIFIED, AND VENDORS llAVE NOT RESPONDED TO Tite IE NOTICE OFDEVIATION, DO NOT APPEAR IN SFCTION II. THE RESULTS OF TitESE

INSPECTIONS WILL APPEAR IN A SUBSFQUENT REPORT. FOR RFASONSJUST DISCUSSED, ORGANI7.ATIONS INSPECTED Dt' RING Tile PRENIOUS REPORTPERIOD ARE FOLLOWED BY A DATE AND APPEAR IN SECTION II OF Tills REPORT.

97,;;';Cs;

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eboC:NCORPORATE NAME, DIVISION, GROUP, OR SUBDIVISION - CITY AND STATE PROGRAM-DOCKET NUMBER k,

APPEARING ON SECTION II PAGES

BACKGROUND INFORMATION INSPECTION RESULTS

PRINCIPAL PRODUCT (S) Identified here are the nuclear related DATE(S) 0F INSPECTION INSPECTION REPORT NO. UPDATED ON:products and/or services, provided.

j gNUCLEAR INDUSTRY INVOLVEMENT DEVIATION (S)FROMC0tt$ MENT ( \

%

rom \ hh.In h (onNUCLEAR STEAM SUPPLIERS AND ARCHITECT ENGINEERS Shown here e inspe ion sults which deviat3ase(identf(ied at e le V bottom of s yge). SychsdeviationsB

Number of reactor units in service, under construction. may x%ISe(t thg princi p document, jeep ts (ncorporate @ s commit-and under contract. f* ments thh grincipal docuzcent.,pe y oth. nspe tionfesultsmay

toftkeb{aseecriteria.4 re14ect aspect %n of all,odly pa{he basip element (s) which

TheI desdript n of deviationsCONTRACTORS. VENDORS, O'IEERS f tifies t

# *\ g conslitu a deviatio . A \I

eM[KNOWLEDCED-IEREVPercent of production devoted to nuclear production. e* g \

CO LETED MA response p Q een\ rec ived from the organization and corrective1he above data is supplied by the inspected o n ation and g ) ,ac has en pm e r initiated. These deviations norinallyindicates the previous, present, and/or ange tad involve- g

i # app tyin on one qu r erly report.sent in the nuclear industry. \ k[ f\ ,i ACKNO DGED RyIEW CONTINUINGg

g',, DeviItions on which the organization disagrees or has proposed org ) e* ] \ initikted inappropriate corrective action."'

,

g L g These items will con-g" / * g g/ ,ORGANIZATIONAL CONTACT 5/ \ ti to appear in subsequent issues (identified by Report No.)u

A d V 11 IE Review has been co:apleted.#

ctedorganiza(on Uh0LVEDITEM(S)Identifies the individual within the as

to be contacted, on a routine basis, by NRC/IE:IV personrgl., *

,Items identified during inspections that require additional infor-

A (is\ }he\x i ,b y mation to establish whether or not a deviation exists, and/or\"\ y'' discrepancies, which are not considered to be A v 4rfons but which

NRC CONTACTS \ % y are to receive attention, as indicated in inspection repor s. on% \ the part of the organization involved.

IdentifiesNRCpersonnellojat%fnntheMegt Dallas,COPf4ENTSTexas, of fice of the Of fig of Ingpgon%gd orcement.

g gg Significant matters other than Deviations or Unresolved Items.

8\ / )-%INSPECTION The principal AgeGment being used by the inspectedBASES organization to control the conduct of his nuclear

related business.'

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10

CURRENT CONTRACTOR AND VENDOR LISTINGS.

The current listing reflects a selection, by NRC, of organizations heavily involved in the nuclear industry, in terms of scope, or organizationsin terms of scope but significantly involved in terias of impact, or uniqueness, of product.having minimal involvement

Sequential issues of this report will reflect changes in terms of both newly added organizations and organizations which have been deleted ... Inboth cases, on the basis of the above criteria.

their activities are applicable in terms of scope, impact, or significance,Organizations desiring to be included in this listing, who feel thatshould contact the NBC's inspection and enforcement Region IV office, located at 611 Ryan Plaza Drive, Suite 1000, Arlington, Texas

76011.

VENDOR VENDOR STATE COUNTRY

PRODUCT CODE CITY CODF CODF

DOCKET PROCRAM VENDOR

99900001 44010 BABC0CK & WILCOX COMPANY, NUCLEAR MATERIALS DIV. FUEL BW LYNCHBURG VA US

99900002 COMBUSTION ENGINEERING, INC., NUCLEAR PRODUCTS MFG. FABRICATION CE WINDSOR CT US

GE WILMINGTON NC US

99900003 GENERAL ELECTRIC COMPANY. WILMINGTON MFG. DEPT. GAC SAN DIEGO CA US

99900004 GENERAL ATOMIC COMPANY WEST PITTSBURGH PA US

99900005 WESTINGHOUSE ELECTRIC CORP., NUCLEAR FUEL DIV.EX RICHLAND WA US

99900081 EXXON NUCLEAR COMPANY. INC., NUCLEAR FUELS DEPT.

99900014 44020 CRANE MIDWEST FITTINGS PIPE AND CMF ST. LOUIS M0 US

99900017 DRAVO CORPORATION, PIPE FABRICATION DIVISION FITTINGS DC MARIETTA OH US

FC NEW CASTLE PA US

99900018 FLOWLINE CORPORATION GC0 KERNERSVILLE NC US

99900019 ITT GRINNELL INDUSTRIAL PIPING, INC.PPPA WILLIAMSPORT PA US

99900021 PULLMAN POWER PRODUCTS, DIVISION OF PULLMAN, INC.NVMCO PITTSBURGH PA US

99900023 NATIONAL VALVE & MANUFACTURING COMPANY SWF HOUSTON TX US

99900025 SOUTHWEST FABRICATING & WELDING COMPANY. INC. SWPC0 CLIFTON NJ US

99900026 SWEPC0 TUBE CORPORATION TT LOUISVILLE KY US

99900028 TUBE TURNS DIVISION, CHEMETRON CORPORATIONYWE YOUNGSTOWN OH US

99900029 THE YOUNGSTOWN WELDING AND ENGINEERING COMPANY TPBCO HOUSTON TX US

99900066 TEXAS PIPE BENDING CO., SUBSIDIARY OF BENDIX CORP.

99900070 ASSOCIATED PIPING & ENGINLERING CORPORATION,APE COMPTON CA US

DIVISION OF JOHNSON CONTROLS PPCA PARAMOUNT CA US

99900077 PULLMAN POWER PRODUCTS, DIVISION PULLMAN, INC.HI MERIDIAN ID US

99900089 HUICO. INC. TC BROOKLYN NY US

99900216 TUBECO. INCORPORATED BFS LAURENS SC US

99900250 BENJAMIN F. SHAW COMPANY TT HOUSTON TX US

99900267 TUBE TURNS DIVISION, CHEMETRON CORPORATIONA HOUSTON TX US

99900268 ARMCO. INC., ADVANCED MATFRIAL DIVIVION

99900291 ASSOCIATED PIPING AND ENGIht'ERING CORPORATION,AP&E CLEARFIELD UT US

DIVISION OF JOHNSON CONTROLS TTDC CARROLLTON GA US

y 99900314 TRENT TUBE, DIVISION OF CRUCIBLE, INC.G HOUSTON TX US

99900343 GULFALLOY, INC.EPG NORTH BRANCH NJ USg- ENERGY PRODUCTS GROUP, GULF & WESTERN MFG. CO.a 99900347

v.O-dM

ObO.-

CURRENT CONTRACTOR AND VENDOR LISTINGS (Cost) GaVENDOR VENDOR STATE CO NTRYDOCKET PROGRAM VENDOR PRODUCT CODE CITY CODE CODE

99900030 44030 BYRON JACKSON PUMP DIVISION, BORG-WARNER CORP. PUMPS BJ VERNON CA US99900031 BINGHAM-WILLAMETTE COMPANY BPC0 PORT'_AND OR US99900033 WESTINGHOUSE ELECTRIC CORPORATION, ELECTROMECHANICAL DIVISION W CHESWICK PA US99900040 SULZER BROTHERS, LTD SB WINTERTHUR SWITZ99900063 PACIFIC PUMPS, DIV. OF DRESSER INDUSTRIES PPD HUNTINGTON PARK CA US99900064 INGERSOLL-RAND COMPANY, CAMERON PUMP DIVISION IR PHILLIPSBURG NJ US99900067 B&W CANADA LIMITED BWLTD GALT ON CAN99900068 BYRON JACKSON, DIVISION OF BORG WARNER BJLTD TORONTO ON CAN99900072 KLEIN, SCHANZLIN & BECKER AG KSB FRANKENTHAL PFALZ GER99900248 RiiON PUMP COMP /.NY UPC BATTLE CREEK MI US99900257 JOHtiSTON PUMP COMPANY JPC GLENDORA CA US99900286 GAULIN CORPORATION GC EVERETT MA US99900345 HAYWARD TYLER PLMP COMPANY, DIV. Of STONE PRATT HTP BURLINGTON VT US

99900036 44040 COMBUSTION ENGINEERING. INC. REACTOR CB CHATTAN0OGA TN US99900039 RHINE-SCHELDE-VEROLME APPARATENBOUW b.v. PRESSURE R-S- V- A ROTTERDAM NETH99900042 BABC0CK & WILCOX COMPANY VESSELS BW MT. VERNON IN US99900073 KLOCKNER-WERKE AG KSC OSNABRUCK GER99900097 CHICAGO BRIDGE & IRON COMPANY CBI BIRMINGHAM AL US99900098 CBI NUCLEAR COMPANY CBI MEMPHIS TN US99900318 3REDA TERM 0MECCANICA S.p.A. BT MILAN IT

99900045 44050 STEARNS-R06ER, INC., MANUFACTURING DIVISION STEAM GENS. & S-R DENVER CO US99900047 WESTINGHOUSE ELECTRIC CORPORATION PRESSURIZERS W TAMPA FL US99900104 WESTINGHOUSE ELECTRIC CORPORATION WESTH PENSACOLA FL US99900110 ALLIS CHALMERS A-C YORK PA US99900202 YUBA HEAT TRANSFER CORPORATION YH TULSA OK US99900207 FOSTER-WHEELER ENERGY CORPC ' ION FW LIVINGSTON NJ US99900241 NUCLEAR POWER PRODUCTS CORPt + 'ON NPPC PANAMA CITY FL US99900266 ROCKWELL INTERNATIONAL CORP 0k. .1

INTERNATI0t:AL DIVISION RIC CANOGA PARK CA US99900299 HAHN & CLAY H&C HOUSTON TX US99900301 ATLAS INDUSTRIAL MANUFACTURING COMPANY AIMC CLIFTON NJ US99900303 APPLIED ENGINEERING COMPANY AEC ORANGEBURG SC US99900305 AMERICAN AIR FILTER COMPANY INC. AAFC BROWNSVILLE TN US99900313 MURDOCK INCORPORATED MI COMPTON CA US99900320 ENGINEERS AND FABRICATORS INC. EFI HOUSTON TX US99900321 AMETEK, INCORPORATED, STRAZA DIVISION A/S EL CAHON CA US99900322 GREER HYDRAULICS, INC. CH CITY OF COMMERCE CA US

12

.

CURRENT CONTRACTOR AND VENDOR LISTINGS (Corn

| VENDOR STATE COUNTRYVENDOR

DOCKET PROGRAM VENDOR PRODUCT CODE CI TY CODE CODE

99900109 44055 PITTSBURGH-DES MOINES STEEL COMPANY, EASTERN DIV. CONTAINMENTS PDM PITTSBURGH PA US

99900242 PITTSBURGH-DES MOINES STEEL & PDSC PROVO UT US

99900243 PITTSBURGH-DES M0INES STEEL (DES M0INES STEEL) PtNETRATIONS PDSCD CLIVE IA US

99900254 PITTSEURCH-DES M0INES STEEL COMPANY, SOUTHERN DIV. PDSCB BIRMINGHAM AL US

99900292 NEWPORT NEWS INDUSTRIAL CORPORATION NNIC NEWPORT NEWS VA US

99900302 WESTERN PIPING & ENGINEERING COMPANY, INC. WPAEC SAN FRANCISCO CA US

99900304 PROGRESSIVE FABRICATORS, INC. PF ST. LOUIS MO US

99900048 44060 ANCHOR / DARLING VALVE COMPANY , HAYWARD VALVES

CALIFORNIA PLANT ADVC HAYWARD CA US

99900049 ATWOOD AND MORRILL COMPANY INC. AM SAL EM MA US

95900051 CRANE COMPANY CCO CHICAGO IL US

99900052 CROSBY VALVE & GAGE COMPANY CVG WRENTHAM MA US

99900053 ANCHOR / DARLING VALVE COMPANYADVC WILLIAMSPORT PA US

99900054 DRESSER INDUSTRIES, INC., INDUSTRIAL VALVESAND INSTRUMENT DIVISION DI ALEXANDRIA LA US

99900056 HENRY PRATT COMPANY HPC AURORA IL US

99900057 THE WILLIAM POWELL COMPANY, PLANT NO. 2 PL C]NCINNATI OH US

99900058 ROCKWELL INTERNATIONAL, FLOW CONTROL DIVISION RW RfLEIGH NC US

99900060 TARGET ROCK CORPORATION, SUBSIDIARY OFCURTISS-WRIGHT CORPORATION TR EAST FARMINGDALE NY US

99900061 VELAN ENGINEERING, LTD. VEC0 MONTREAL PQ CAN

99900075 PACIFIC VALVES PV LONG BEACH CA l'S

99900079 LUNKENHEIMER COMPANY LUN CINCINNATI OH US

CDP LAKE ClIV PA US99900080 COPES-VULCAN INC.99300086 HOPKINSON LIMITED HL HUDDf RSf f!LD ENG

99300087 WALWORTik COMPANY, ALOYC0 PLANT WAVC LINDEN NJ US

99900094 MASONEILAN INTERNATIONAL INC. MAS NORWOOD MA US

99300105 FISHER CONTROLS COMPANY, MARSHALLTOWN DIV. FCC MARSHAlLTOWN IA U5

99900112 AMETEK CORP., CALMEC DIVISION ACCD PICO RIVIRA CA 13

99300118 WALWORTH COMPANY, GREENSBURG DIVISION WAL GRl!NSLURG PA US

99900214 ANDERSON GREENWOOD AND COMPANY AGW n005fG TX

99900239 FISHER CONTROLS COMPANr FC t.Wfhifuli V '

99900244 ITT GRINNELL COMPANY, INC. , DYNAFLOW DIV. GO' Lt W'. .l L W *>

99900245 J. E. LONERGAN CGMPANY JFI( PHit AI,L1 Ph! A PA US

99900262 BABC0CK & WILCOX CONTROL COMPONENTS, INC. BWR I RV l NI U tl5

99900263 CIRCLE SEAL CORPORATION CSC / NW I F' 'A %

99900264 DRAGON VALVES, INC. CVI f.0PWT I. F iA US

99900269 THE WILLIN4 POWELL COMPANY, PL ANT NO. I WP ( . |'..?f! w US

99900281 All !S-CHAl f/E RS. val VE DIVISIGN A-fVD YS 19 US

C..es..

iN

@t-Oe

CURRENT CONTPACTOR AND VEND 0R LISTINGS (Coro N(f.-

VENDOR VENDOR STATE COUNTRYDOCKET PROGRAM VENDOR PRODUCT CODE CMT CODE CODE

99900287 44060 TRW MISSION MANUFACTURING COMPANY, A DIVISION OF VALVESTRW, INC. (CONT) TRW HOUSTON TX US

99900289 NUCLEAR VALVE DIVISION, BORG WARNER CORPORATION NVD VAN NUYS CA US99900290 ITT HAMMEL DAHL/ CON 0 FLOW HD/C WARWICK RI US99900293 ENERGY PRODUCTS GROUP, GULF & WESTERN MFG. CO. EPG WARWICK RI US99900306 LESLIE COMPANY tC PARSIPPANY NJ US99900307 CONTR0MATICS DIVISION, LITTER INDUSTRIAL

PRODUCTS, INC. CC E. HARTFORD CT US

9990308 ACF INDUSTRIES INC. W-K-M VALVE DIVISION ACF MISSOURI CITY TX US999UWO9 VALTEX, INCORPORATED VI SPRINGVILLE UT US99900316 GOULD, INC., VALVE AND FITTING DIVISION GI CHICAGO IL US99900340 YARWAY CORPORATION YC BLUE BELL PA US99900346 VELAN VALVE COMPANY VVC WILLISTON VT US

99900034 44070 BABC0CK & WILCOX COMPANY MISCELLANEOUS BW BARBERTON OH US99900074 DIAMOND POWER SPECIALTY CORPORATION DPSCO LANCASTER OH US99900083 ROYAL INDUSTRIES, ENERGY PRODUCTS DIVISION RIC SANTA ANA CA US99900084 BERGEN-PATERSON PIPESUPPGRT CORPORATION BP BOSTON MA US99900090 NL INDUSTRIES, INC., NUCLEAR DIVISION NLI WILMINGTON DE US99900091 TRAN5 NUCLEAR INCORPORATED TRNSN WHITE PLAINS NY US99900092 R0BATEL-SLPI SLPI GENAS FR99900100 LIMITORQUE CORPOPATION LC LYNCHBURG VA US99900114 LAMCO INDUSTRIES, INCORPORATED LAM EL CAJ0N CA US99900204 P X ENGINEERING COMPANY, INC. PXE WOBURN MA US99900205 PROCESS EQUIPMENT COMPANY, INC. PEC BROCKTON MA US99900209 BERGEN-PATERSON PIPESUPPORT CORPORATION BERG-P LACONIA NH US99900211 BUEHLER NUCLEAR PRODUCTS BNP INDIANAPOLIS IN US99900247 WESTINGHOUSE HANFORD COMPANY HEDL RICHLAND WA US99900251 JOSEPH OATS CORPORATION JOC CAMDEN NJ US99900255 PACIFIC SCIENTIFIC COMPANY, KIN-TECH DIVISION PSC ANAHEIM CA US99900256 AEROJET MANUFACTURING COMPANY AMC FULLERTON CA US99900258 REXNORD INC., CYLINDER DIVISION RI CHICAGO IL US99900259 P. F. AVERY CORPORATION PFAC NEWINGTON NH US99900265 GENERAL ATOMIC CORPORATION GA SAN DIEGO CA US99900282 ITT GRINNELL, PIPE HANGER DIVISION ITTW WARREN OH US99900235 ITT GRINNELL CORPORATION, PIPE HANGER DIVISION,

ENGINEERING DEPARTMENT ITTP PROVIDENCE RI US99900312 CARPENTER TECHNOLOGY CORPORATION CTC READING PA US99900315 E-SYSTEMS, MONTEK DIVISION E SALT LAKE CITY UT US99900327 SARGENT INDUSTRIES, AIRITE DIVISION SI EL SEGUNDO CA US

14

CURRENT CONTRACTOR AND VEND 0R LISTINGS (mNT)VENDOR VENDOR STATE COUNTRY

PRODUCT CODF CT1T CODE CODE

dry 1TT P W RAM VFN#R

95903328 44070 STRUTHERS WELLS CORPORATIONMISCELLANEOUS SWC WARREN PA US

99900331 EXCELCO DEVELOPMENTS, INC. (CONT) ED SILVER CREEK NY US

9990033S B0EING ENGINEERING AND CONSTRUCTION, DIVISIONBE&C SEATTLE WA US

OF BOEING COMPANY P-M ORANGE CA US

99900337 PAUL-MUNROE HYDRAULICS, INC.WBMP SP0KANE WA US

99900341 WELK BROS. METAL PRODUCTS, INC.LB&S MILWAUKEE WI US

99900342 LAKESIDE BRIDGE & STEEL CO. ACRHD WILLITS CA US

99900344 ABEX CORP. , REMCO HYDRAULICS DIVISION

99900348 NPS INDUSTRIES, INC., A SUBSIDIARY OF NUCLEARNPS AUS TIN TX US

POWER SERVICES INC.

99900111 4407S WESTINGHOUSE ELECTRIC, LARGE MOTORS DIVISION ELECTRIC CABLE W BUFFALO NY US

99900113 BARTON INSTRUMENTS - A UNIT OF ITT & INSTRUMENT BI CITY OF INDUSTRY CA US

COMPONENTS BRC CHATSWORTH CA US

99900116 BUNKER RAMO CORPORATION

99900217 WESTINGHOUSE ELECTRIC CORPORATION W HUNT VALLEY MD US

NUCLEAR INSTRUMENTATION & CONTROLS DEPARTMENT GEC WEST LYNN MA US

99900218 GENERAL ELECTRIC COMPANY, INST. PROD. DEPT.GEC PHILADELPHIA PA US

99900219 GENERAL ELECTRIC COMPANY , SWITCHGEAR BUSINESS DEPT.CEC WINDSOR CT US

99900220 COMBUSTION ENGINEERING, INC., CONTROLS DIVISION

99900221 CONSOLIDATED CONTROLS CORPORA 71GN, SUBSIDIARY OFCCC BETHEL CT US

CONDEC CORPOPATION RIS ROCHESTER NY US

99900222 ROCHESTER INSTRUMENT SYSTEMS, INC.

99900224 BAILEY METER COMPANY SUBSIDIARY OF BABCOCK & BMC WICKLIFFE OH US

WILCOX TFC FOXBOR0 MA US

9990022S THE FOXBORO COMPANY. INC. LNC NORTH WALES PA US

99900226 LEEDS & NORTHRUP COMPANY GCC GREENWICH CT US

99900227 GENERAL CABLE COPP0 RATION

99900228 THE KERITE COMPANY SUBSIDIARY OF HARVEY KC SEYMOUR CT USHUBBELL, INC.

USSC WORCESTER MA US

99900229 UNITED STATES STEEL COPPORATION, ELEC. CABLE O!V.ACD MARION IN SS

99900230 THE ANACONDA COMPANY, WIRE & CABLE DIVISIONOC RAMSEY NJ LS

99900231 THE OKONITE COMPANY CP CHICAGO IL US

99900232 CONTROL PRODUCTS CORPOPATION SMC AUROPA OH US

99900233 SAMUEL MOORE AND COMPANY, DEKORON DIVISIONRI TOLEDO OH US

RC MENLO PAPM CA US99900234 ROWE INDUSTRIES

99900235 PAYCHEM CORPORATION, WIRE & CABLE DIVISIONGI COSTA MESA CA US

9990023G GULTON 5.C.D., DIV.0F GULTON INDUSTRIES, INC.SEL FORT LAUDEPDALE FL US

99900237 SYSTEMS ENGINEERING LABORATORIES, INC.

99900240 WESTINGHOUSE ELECTRIC COPP0 RATION,W PITTSBUPGH PA US

INDUSTRY SYSTEMS DIVISION

15

.'n';

.7O.N

Q

OCCOU(iCURRENT CONTRACTOR AND VENDOR LISTINGS (comU.!

VENDOR \TSDOR SFATF COUNTRYNmr P W.:K W VFN M PRODtTT CODF Cli L CODF CODF

39300270 44075 WESTIN340USE ELECTRIC CORPORATION, CONTROL ELECTRIC CABLEPROCUL:S DIVISION & INSTRUMENT W BEAVER PA US

39900271 ;0SEvCLNT, INCCR?0 RATED CEMPONE NTS R1 EDEN PRAIRIE MN US93320272 BELF;3, BA! LEY METER COMPANY (C3NT) BBMC DA7TONA BEACH FL US99900273 WESTI'.SHCLSE ELECTRIC CO., RELAY INSTRUMENT DIV. W NEWARK NJ US99300274 r!:'.EY ENGINEERING COMPANY FEC ADDISON TX US;3900275 CEJTE ST0AES, INCORPORATED RSI CLEVELAND OH US993:C276 SOLID STATE CONTROLS, INCORPORATED SSCI COLUMBUS OH US3??:0277 THE ? CsSESTOS COMPANY, MEMBER OF THE MAPPON GROUP ROCK NEW HAVEN CT US93300273 AUT ?ATI:', INDUSTRIES, VITRO LABORATORIES DIVISION AIV SILVER SPRINGS MD US99900279 G0JL:, '.C., ELECTRICAL APPARATUS DIVISION GCS FINKSBURG MD US99900230 WESTP Gr0USE ELECTRIC COMPANY, COMPUTER &

INSTt MENTATION DIVISION W TEMPE AZ US33900233 SCST:N INS'JLATE3 WIRE & CABLE COMPANY BIWC BOSTON MA US9390C234 SIGMA I'.STRD'ENTS, INC. INTERNATIONAL

I'.STRLMENTS DIVISION SIF ORANGE CT US333002S8 LNITED ELECTRIC CONYROLS COMPANY UECC WATERTOWN MA US93900294 WESTI'.G"OUSE ELECTRIC CORPORATION, MEDIUM MOTOR

5 GEARI'.G DIilSION W BUFFALO NY US99900295 WESTINGHCUSE ELECTRIC CORPORATION, INCJS. RIAL

EQUIPMENT DIVISION W BUFFALO NY US39900296 AMEPACE CORPCRATION, CONTROL PRODUCTS DIVISION AC GRAFTUN WI US39900297 THE TOABORO COMPANY, PANEL OPERATIONS TFCM MANSFIELO MA US99900293 THE F0tB0R0 COMPA'iY, NEPONSET PLANT TFCF FOXBORO MA US99900300 CC'.T I'.DLSTRIES, FAIRB ANKS-MORSE ENGINE DIVISION COLT BELDIT WI US93300310 ITT CANNON ELECTRIC - A DIVISION OF ITT CORP. ICE PHOENIX AR US99300311 GENERAL ELECTRIC COMPANY, SJITCHGEAR DIVISION GESD BURLINGTON IA US39900317 CCOPER SERVICES, INC., C00 PEP ENERGY SERVICES CI MT VERNON OH US37900323 CCNav CORPCRATION CC BUFFALO NY US39300324 WESTINGHOUSE ELECTRIC CORPORATION W HORSEHEADS NY US99920325 SMND-REX COMPANY, A PMT OF AK20NA INC0PPORATED B-RC WILLlMANTIC CT LS39300325

~ 3. O'BRIEN, I'.' DG0 SEABROOK NH US9390032) G0CLC, INC., SWITCHGEAR CPERATIONS DIVISION GI FT. WASHINGTON PA US;))00?;0 WESTI'.Gr0USE ELECTRIC COPPORATION, SWITCHGEAR DIV. W E. PITTSBURGH PA US

*iis0033A :E tr.AL TCPBINE INC., E'4 SINE AND CC*PPESSOR DIV. DLT 0AKLAND CA US '}90I0333 SIEVENS-ALLIS, INC. S-A LITTLE ROCK AR US99}C033; GENE:AL ELECTRIC COM W4V, SMALL AC P: TOR

?:0 DUCTS 2!'.ISICN GE SAN JOSE CA US

16

.

O

i'

CURREtlT CONTRACTOR AND VENDOR LISTINGS (COST)VENDOR VENDOR STATE COUNTRY

TMFFT PROGRA M VFNDOR PRODUCT CODE CITY CODE CODE

99900400 44081 BABC0CK & WiLC0X COMPANY, NUCLEAR POWER NUCLEAR STEAM

GENERATION DIVISION * SYSTEM SUPPLIERS B&W LYNCHBURG VA US

99900401 COMBUSTION ENGINEERING, INCORPORATED * CE WINDSOR CT US

99900404 WESTINGHOUSE ELECTRIC CORPORATION (PWRSD) * WESTH MONROEVILLE PA US

9990^403 44082 GENERAL ELECTRIC COMPANY, NUCLEAR ENERGYGE SAN JOSE CA US

BUSINESS GROUP *

99900402 44083 GENERAL ATOMIC COMPANY GAC LA J0LLA CA US

W MADISON PA US99900405 44084 WESTINGHOUSE (ARD)

AI CANOGA PARK CA US99900406 ATOMICS INTERNATIONAL

GEfRD SUNNYVALE CA US99900407 GE FAST BREEDER REACTOR DEPARTMENT

_

99900500 44090 BECHTEL POWER CORPORATION ARCHITECT BC SAN FRANCISCO CA US

99900502 BROWN & ROOT, INC. ENGINEERS B&R HOUSTON TX US

B& ROE ORADELL NJ US99900503 BURNS & ROE, INC.

EBSCO NEW '0RK NY US99900505 EBASCO SERVICES, INC. *

S&L CHICAGO IL US99900507 SARGENT & LUNDY

S&R DENVER CO US99900508 STEARNS-ROGER CORPORATION

S&W BOSTON MA US99900509 STONE & WEBSTER ENGINEERING CORP.*

UEEC PHILADELPHIA PA US99900510 UNITED ENGINEERS & CONSTRUCTORS. INC. *

SPA ST. LOUIS M0 US9990051B SVERDRUP AND PARCEL ASSOCIATES. INC.99900519 BECHTEL POWER CORPORATION, GAITHERSBURG

BCHTL GAITHERSBURG MD USPOWER DIVISION *

CFB ALHAMBRA CA US99900520 C F BRAUN AND C099500521 BECHTEL POWER CORPORATION, LOS ANGELES POWER

BCHTL NORWALK CA USDIVISION

99900522 BECHTEL POWER CORPORATION, SAN FRANCISCOBCHTL SAN FRANCISCO CA US

POWER DIVISION *FPS CHICAGO IL US

99900523 Fl u0R POWER SERVICES, INC.G&H NEW YORK NY US

99900524 GIBBS & HILL, INC. *CA READING PA US

99900525 GILBERT / COMMONWEALTH COMPANIES

99900526 BLACK & VEATCH CONSULTING ENGINEERS,B&V KANSAS CITY M0 US

POWER DIVISIONRMP PASADENA CA US

99900527 THE R. M. PARSONS COMPANY

(Continued next page)

17

97wdiCf)H

NuO

CURRENT CONTRACTOR AND VENDOR LISTINGS (com L.'.:1LC

SUMMARY OF ORGANIZATIONS BY PRODUCT OR SERVICE

At the time of printing of this issue of the White Book.226 organizations, as identified above, constitute thecurrent contractor and vendor listing. A breakdown ofproduct or service is as follows:

PRODUCT OR SERVICE Arid NUMBER OF ORGANIZATIONS

ELECTRIC CABLE & INSTRUMENT COMPONENTS. .56VALVES. . .40MISCELLANEOUS. . . .33PIPE AND FITTINGS. .22.

ARCHITECT ENGINEERS. .. . . .18STEAM GENERATORS AND PRESSURIZERS. .16PUMPS. . . . .13NUCLEAR STEAM SYSTEM SUPPLIERS. 8CONTAINMENTS AND PENETRATIONS. 7REACTOR PRESSURE VESSELS. ... 7FUEL FABRICATORS. . . . 6 ,

1

* Indicates that this organization has received anIE letter confirmi satisfactory implementationof their corpor6te 411ty assurance program.

18

'.

MF-JQ

- CD- LLJ

CCZO Z- Ol-- -

Q &LLJ QM LLJ

CLMZ-

* .(.:= , wJ> :y q- ,t

C0FGdSTION ENGINEERING, INCORPORATED, WINDSOR, CONNECTICUf 44081- W300401

BACKGROUND INFORMATION INSPECTION T SULIS_ , _

PRif.C n L FR000CT(S) DATI(S) OI INSPICIIDN INSPIC11DN RIPORT NO. OPDAllD ON: 7/7/78

|. N NUCLU2 STEliM SYSTEM SUPPLILAV 6/26-30/78 78-02 | By: J. R. Costello

m-m._ -a tw

. PEJCLEAR INDUSTRY INVOLVEMENT DEVI ATIDN(S) IR0h (OiMITMf NIS'

ACKNOWLE!KLD - IL REVIEld C'ydINUINGN1 CLEAR STEAM SYSTEM SUPPIM RS AND ARJitnFCI ENGINF g

Reactor Units ir. Service. . . . . . . . 7 1 Contrary to CE Topical Pqort CENPD-210-A, one f r-d!vidua? had perf:;r1nc1

Reactor Units Under C-snstruction. . . . 13 audits of NDE processes when his NDt qualificction h d expired.

Reactor Unitr finder Cos.t s act. . . . . . . 13 2. Contra v to CE iopical Report CENPD-210-A, managment ac-fits are notthrough written operating procedures.4doctsner.

3. Contra ry o CE Topical Report CENPD-210-A. Croup Quality $fstems hnl' ctM kACToRS, VEf. DORS, Omee not scheduM any internal audits of Plant Apparatus or Developmnt.'

Contrary to 10 of R 50, Appendix B. Criterion III, the design of high~ 4.Percent of Production Devoted to Nuclear t roduct s . N/A g pressure safety injection header valves t'.s inadequate.5. 2ntrary to 10 Cfk, Appendix B Critet' ion XV, r.o fidd action report

(; AR) was generated for inadequate HPS[ header valves.^ f; Contrary to 10 CFR, Appendix B, Criterion V, certifi%tions of equip-,

tiert with outstanding itras were released for shipment without properORGANIZATIONAL CU; TACT| docisnented approvals.

C. 14. Hoffman, Director, CQA i 1 -

Nare/ Title . . . .. .

1000 Prospect Hill Road UNRESOLVED ITEM (S)Address. . . . . .

city / State / Zip . .. . Windsor, Connecticut 06095 ,

Telephone. . . .... . (203) 688-191I 1. b internal audits art being conducted by either EQA cr GQS pore.onnel i

nlative to the $ctio ties or Licaa&..rno *,cject Management per-r

=-- sonnel 3. - tne Conatrcial Departnent.

2. It is not clear wi. ether ANSI N45.2.6 is glicable to surveillance per-yACCONTACTS sonnel.

Assirned Inspector J. R. Costella 3. It is not clear wnetWr IMOPs (Int (grited Manufacturing Quality Plans)..

C. J. Hale are being approved si. (fd veks p-icr to fabrication.Section chief. . ... ..

Telephone. . . . . . (817) 334-2844COMMENTS

- NONE

INSPECTION95ES Txical Report CENPD-210-A (

-

I _

21'

F7)b.,''':.

bff ,

Mi

ln([:O

GENERAL ELECTRIC COMPANY, NUCLEAR ENERGY BUSINESS GROUP, SAN JOSE. CALIFORNI A 14f4082-99000qo3__ C

BACKGROUND 1*60W10N l'!SPECT10N REStilS

PR[NCIFAL PRO}f N ) DATE(S) OF INsitCTinN IN5PlCTION REPORT NO. ImDAT[D tF4: 8/2/78p NUCLEAR STEAM SUPPLY SYSTEMS7/24-23/78 78 02 ny: J. R. Costello

NUCLEAR INDUSTRY I N'.'CL V E ME N T Df vl ATION(5) F ROM COMMITut td5

N1'Ct F AR STEA.4 SYSTEM St'Pri IE ks AND ARCHITF CT F%:!NFFRS NONE

Reac t or l'n t t s in Service. . . 24Reactor l' nit s l'nder Const ruct ion. . 30

UNRESOLVED ITEM (S)Reactor l' nits l'nder Contract. . .. O

NONECONTRACTORS, VENDORS, OTHERS

Percent of Froduction Devoted to Nuclear Product s N/A COMMENTS

f.0NE

ORGANIZATIONAL CONTACT

A. Breed QA Man.2gerName/ Title . .. .

Address. . . . . . . . . . 175 Curtner AvenueSan Jose. Califomia 95125City / State / Zip . . ..

Telephone. . . . . . (408) 925-2726

NRC CONTACTS

.. . J. R. CostelloAssigned Inspector .C. J. HaleSection Chief. . ......

. . . . .. (817) 334-2844Telephone.

INSPECTION

) NE D0-11209-04 A

22

.

.

WESTINGHOUSE ELECTRIC CORPORATION, PRESSURIZED WATER REACTOR SYSTEMS DIVISION, MONR0EVILLE, PENNSYLVANIA % 081-99900404

BACKGROUNO INFORMTION INSPECTION RESULTS

PRINCIPAL PRODUCT (S) DATE(S) Of INSPECTION INSPECTION REPORT NO. JPDATED CN: 6/13/78

NUCLEAR STEAM SUPPLY SYSTEMS6/6-8/78 78-01 BY: D. G. Anderso,

NUCLEAR INDUSTRY INVOLVEMENT DEVIATION (S) FROM COMMITMfNTS

NUCLEAR STEAM SYSTEM SUPPLIERS AND ARCHITECT FNCINFFRs ACKNOWLEDGED - IE REVIEW COMPLETED

Reactor Units in Service. .. . . 24 1. Contrary to Procedure EFP-t'E-1, " Purchase Orders," a purchase requist-Reactor Units Under Construction. . 47 tion change notice had not been generated on a revision to an equip-

.. ... 7 ment Data Sheet, and Consequently, the new revision had not beenReactor Units Under Contract. incorporated into a Project Infonnation Package.CONTRACTORS, VENDORS, oTHERS

2. Contrary to OPR-110-4, revisions to certain drawings and changesPercent of Production Devoted to Nuclear Products . . N/A affecting design were not subject to design control measures comen-

surate to the original.

UNRESOLVED ITEM (S)

ORGANIZATIONAL CONTACTNONE

. . E. J. Kreh, Mgr., Prod. AssuranceName/ Title . . ..

Box 355Address. . ...

City / State / Zip . . Pittsburgh, Penrsylvania 15230 COPt4ENTS.

. (412) 256-4584Telephone. .... .

NONE

NRC CONTACTS

Assigned Inspector . . . . . D. G. AndersonSection Chief. . . . . . . C. J. Hale

. (817) 334-2844Telephone. ......

INSPECTION Westinghouse Water Reactor DivisionsASES Topical Report No. WCAP-8370

Rev|sion 8-A

23

CO.

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'TJI.?

p.,v)C:Z;J

WESlltG10USE ELECTRIC CORPORAT10N, PRESSURld D WATER RIACIOR SYSilMS DIVISION, MONR0lVILU , PENN5YLVANIA til4081 -49900t40I4O"~

BAntimt:Im im ORMAIION INSPICl10N 91SulISl'R I M. l l' At l'R O:ML I ( S ) llAll (5) 01 IN51'I t I ll)N IN'iPl t:l l0N Ri l'Olti NO. lil't)A l l i) ON: H/14/78h NUCLEAR STIAM SUPPLY SYSTEM 5

H/8-11/78 73-02 fly : !) . G. Anderson

NUCllAR INDU$iHY INVOLVIMINI OfVIA110N(5)IROMLOMMlilblNIS

Ntlf t t AN Sil AM SYS1F'M SLI!'PI I F RS AND ARrill11 LCl FNGINFFHS AC LNOWi l l)C.t !) - 11 ,tt VllW COMPLE TE D

Re.ir t or l'n t t s in Servire. . 24Rext or Unit s Under conut ruc t ion. . . 47 Contrary to lopical Peport WCAP 8370, and OPR 300-5, several computerNeu t or l'n t t s 1:nd.-r contract. . . 7

program abstract forms (55374) were not approved by the inwdiatenunager as required.

CONTRACTOMS, VEf. DORS, OTilFRS

'"l'e r r en t of Produc t ion Devoted to Nierlear !"roduct s N/A - ENONC

"ORGANilATIONAL CONTACT

Name/ Title . . E. J. Kreh, Mgr., Prod. AssuranceAddress. . . . . Box 355City / state / Zip . . Pittsburgh, Pennsylvania 15230Telephone. . .. (412) 256-4581

NRC CONTACTS

Assigned Inspector . . D. G. AndersonSection Chief. . .. . C. J. HaleTelephone. . . . . (817) 334-2844

l','PECTION^g Westinghouse Water Feactor Divisiors

) Topical Report No. WCAP-8370,Revision 8-A

.

2 14-

BECHTEL POWER CORPORATION, LOS ANGELES POWER DIVISION, NORWALK, CALIFORNIA 44090-99900571

BACKGROUND INFORMATION INSPECT 11N RESULTS

PRINCIPAL PRODUCT (5) DATE(S) 0F INSPECTION INSPECTION REPORT NO. UPDATED ON: 7/5/78ARCHITECT ENGINEERING SERVICES

</26-29/78 78-02 BY: R. H. Brickley

NUCLEAR INDUSTRY INVOLVEl1ENT DEVIATION (S) FROM COMMITMENTS

NUCI. EAR STEAM SYSTEM SUPPLIERS AND ARCHITECT ENGINEERS- ACKNOWLEDGED - IE REVIEW COMPLETED

Reactor Units in Service. . . ... . 2 The Palo Verde drawings failed to specify the pipe support fillet weld sizeReactor Units Under Construction. . . . . 5 required by Appendix XVII to Section III of the ASME Boiler and Pressure

2 Vessel Code.Reactor Units Under Contract. . .. ... .

CONTRACTORS, VE!.T) ORS , OTHERS

Percent of Production Devoted to Nuclear Products . . N/ANONE


ONEName/ Title . . . . J. E. Bashore. Division QA Manager. . ..

P. O. Box 60860. Tenninal AnnexAddress. . . . ...

City / State / Zip . . . . . Los Angeles, California 90060.

. . . . (213) 864-6011 Extension 2061Telephone. . . .

NRC CONTACTS

Assi ned Inspector . . . . R. H. Brickley3. . C. J. HaleSection Chief. . . .

. . . (817) 334-2844Telephone. . . ..

INSPECTIONBASES 10 CFR 50, Appendix B, and

) Other Applicable Regulations

07 25

.NOOSfE

C';YC

3U-

BECHTEL POWER CORPORATION, GAITHERSBURG POWER DIVISION, GAITHERSBURG, MARYLAND 44090-99900519


PRINCIPAL PRODUCT (S) DATE(S) Of INSPECTION INSPECTION REPORT NO. UPDATED ON: 5/18/78

) ARCHITECT ENGINEERINu SERVICESS/ 8- '78 78-02 BY: R. H. Brickley

NUCLEAR INDUSTRY INVOLVEMENT DEVIATION (S) FROM COMMITMENTS

NUCI.FAR STEAM SYSTEM SUPP1,IERS AND ARCHITECT ENGINEEPS ACKNOWLEDGED - IE REVIEW COMPLETED

....... .. 12 10 CFR 50, Appendix B, Criterion V - three (3) examples of failure toReactor Units in Service.. . .. - 8 follow procedures in the area of desigh control.Reactor Units Under Construction.

Reactor Units Under Contract. . .. .. 3

CONTRACTORS, VENDORS, OTHERS UNRESOLVED ITDi(S)

Percent of Production Devoted to Nuclear Products . . N/A NONE

Co WENTS

ORGANIZATIONAL CONTACT NONE

Name/ Title .. . . . . . . J. M. Ama ral , QA Ha na ge r15740 Shady Grove RoadAddress. . . . .. .....Gaithersburg, Maryland 20760City / State / Zip . ......

(301) 926-1444Telephone. . . .. .....

NRC CONTACTS

Assigned Inspector . R. H. Brickley....

C. J. HaleSection Chief. . ... ..

(817) 334-2844Telephone. . . . ......

INSPECTIONBASES

10 CFR 50. Appendix B, and


26

.

BECHTEL POWER CORP 0PATION, GAITHERSBURG POWER DIVISION, GAITHERSBURG, fiARYlAND M090-99900519

BACKGROUND INf0RMAll0N INSPECTION RESULTS

PRINCIPAL PRODUCT (S) DATE(S) 0F INSPECTION INSFECTION REPORT NO. UPDATED ON: 7/27/78N ARCHITECT ENGINELRING SERVICESV 7/17-21/78 78-03 BY: R. H. Brickley

NUCLEAR INDUSTRf INVOLVEMENT DEVIATION (S) FROM COP 911TMENTS

NUCI FAR STf AM SYSTEM SUPPI.IERS ANI) ARrHITtCT ENGIhFFRS NONE

Reactor Unit s in Service. . I2Reactor Units Under Construction. . . . 8 UNRESOLVED ITEM (S)Reactor Units Under Contract. .. . . . 3

1. Bechtel's position of not modifying nonconfoming fillet weldCONTRACTORS, VENDORS, OTHERS sizes has been referred to NRR for evaluation.

Percent of Production Devoted to Nuclear Products . . N/A 2. The analysis of containment spray coverage has not been completed.

COMMENTS

ORGANIZATIONAL CONTACT NONE

Name/ Title . . . . . . J. M. Amaral, QA Manager15740 Shady Grove RoadAddress. . . . ... . .

.. . . . Gaithersburg, Maryland 20760City / State / Zip .Telephone. . . . . . . . (801) 926-1444

NRC CONTACTS

R. H. BrickleyAssigned Inspector . . . . .

section chief. . . . . . . C. J. HaleTelephone. . . . . . . . . (817) 334-2844



3 27

C.'O.bCO

v4OO';-'2.

BECHTEL POWER CORPORATION, SAN FRANCISCO POWER DIVISION, SAN FRANCISCO, CALIFORNIA 44090-99900577 20


PRINCIPAL PRODUCT (S) DATE(S) 0F INSPECTION INSPECTION REPORT NO. UPDATED ON: 6/1/78N ARCHITECT ENGINEERING SERVICESV 5/22-25/78 78-02 BY: R. H. Brickley

NUCLEAR INDUSTRY INV0tV[ MENT DEvlATION(S) FROM COPfitTHENTS

Nect ran strAM sysTrx sitrrl IFk% AND ARCit' *W7 FNd!NFFRS ACKNOWLEDGED - IE REVIEW COMPLETED

17 10 CFR 50, Appendix B. Criterion V - Failure to follow procedures in theReactor l'nf ts in service. . ......... .

9 area of QA Records - two (2) examples.Reactor Units Under Construction. ........ .

5Reactor Units UnJer Contract. ...... ....

CONTRACTORS, VENDORS, OTIIERS UNRESOLVED ITEM (S)

Percent of Production Devoted to Nuclear Products . . . N/A It is not clear that the definition of when a document becomes a QArecord, as stated in the Hope Creek Nuclear QA Manual, satisfies theintent of ANSI rs45.2.9.

ORGANIZATIONAL CONTACT COMMENTS

Itsee/ Title . . . . . . . . . S.1. Heisler. QA Manager NONEAddress. . . . . . . . . . Post Office Box 3965city / State / zip . . . . . . . San Francisco, California 94119

(415) 768-0751Telephone. . ........

NRC CCrNTACTS

Assigned Inspector . . . . . R. H. BrickleySection Chief. . . . . . . . C. J. Hale

(B17) 334-2844Telephone. .........

INSPECTIONBASES

10 CFR 50. Appendix B. and


28

,

BLACK s VEATCH CONSULTING ENGINEERS, POWER DIVISION, KANSAS CITY, KANSAS 44090-99900526

BK KGROUND INFORMATION INSPECTION RESULTS

PRINCIPAL PRODUCT (S) DATE(S) 0F INSPECTION INSPECTION R[ PORT NO. UPDATED OM: 8/8/78

Q ARCHITECT ENGINEERING SERVICES7/24-28/78 78-01 BY: C. J. Hale


NoctzAn STEAM sysTrse surr:,lERS AND AF.cHITECT ENCINEERS ACKNOWLEDGED - IE REVIEW CONTINUING

0 1. Contrary to QA Program comitments to ANSI N45.2.9, two qualityseactor Units in service. ...............acactor Units Under construction. . . . . . . . . . O related manual: were found that are not being collected, stored, and..

seactor Units Under contract. 2 maintained in the appropriate Q4 recc.ds system..............

corraAcrotS, VENDORS. OTHERS 2. Contrary to ComitE?nts to ANSI Standards N45.2.12 and N45.2.13,procured services for geotechnical studies were not being audited at

Fercent of Froduction Devoted to Nuclear Froducts . N/A the comitted frequencies and certain elements of the Black & Veatch.

internal QA Program were not being audited in the comitted depth orfrequency.

3. Contrary to comitments in ANSI N45.2.12, internal audits are notORGANIZATIL 'AL CONTACT being consistently conducted and reported in accordance with

comitments,same/ Title . . . . . . . . . R. E. Blaisdell, QA ManagerAddress. . . . . . . . . . . Post Office Box 8405City / State / Zip . . * . - . * Kansas City, Missouri 64114 UNRESOLVED ITEM (S't

(913)967-2113Telephone. .........

NONE

NRC CONT'USCOPttENTS

Assigned Inspector . . . , , R. H. Brickleysectico Chief. . . . . . . . C. J. Hale NOC~Telephone. . . . . . . . . . (817)334-2844

INSPECTIONBASES Black Fox Station PSAR, Appendix 178

29yN''.,

tcN

CO7:OC.

EBASCO SERVICES, INCORPORATED, NEW YORK, NEW YORK 44090-99900505 NQ)


PRINCIPAL PRODUCT (S) DATE(S) 0F INSPECTION INSPECTION REPORT NO. UPDATED ON: 6/26/78

h ARCHITECT ENGINEERING SERVICES6/19-23/78 78-02 BY: D. G. Anderson

N'JCLEAR INDUSTRY INVOLVEMENT DEVIATION (S) FROM COMMITMENTS

NUCLEAR STEAM SYSTEM SUPPt.1ERS AND ARCHITECT ENGINEFRS ACKNOWLEDGED - IE REVIEW COMPLETED

4 1. Contrary to Ebasco Topical Report ETR-1001, Section QA-II-1, revisionsReactor Units in Service. . ... .....

Reactor Units Under Construction. .. . ... 4 to controlled copies of the company procedures manual - administrative,... . . . . 6 certain E-procedures, and the purchasing department procedures manualReactor Units Under Contract.

had not been distributed nor had superseded procedures been destroyedCONTRACTORS, VENDORS, OTHERS or labeled superseded.

Percent of Production Devoted to Nuclear Products . N/A 2. Contrary to Ebasco Topical Report ETR-1001, Section QA-II-1, projectunique p mcedures had not been approved by the manager of standardsand procedures.

_

3. Contrary to Ebasco Topical Report ETR-1001 and Procedure E-61, severalORGANI7ATIONAL CONTACT calculations perfomed by the applied physics department did not have

cover sheets, calculation numbers, index, or tables of contents.

Name/ Title . . . . . . . . B. R. Mazo, Chief QA EngineerAddress. 2 Rector Street..... .....

New York, New York 10006 UNRESOLVED ITEM (S)City / State / Zip . ......

Telephone. (212) 785-4303..... ...

NONE

NRC CONTACTSCOMMENTS

Assigned Inspector . D. G. Anderson....

Section Chief. C. J. Hale NONE.. .. ..

Telephone. (817) 334-2844.. .. ... .

INSPECTIONBASES Topical Report No. ETR-1001

30

SARGENT & LUNDY, CHICAG0, ILLIN0IS 44090-99900507


PRINCIPAL PRODUCT (S) DATE(5) 0F INSPECTION INSPECTION REPORT NO. UPDATED GN: 8/17/78

p ARCHITECT ENGINEERING SERVICES8/7-11/78 78-02 BY: J. R. Costello

NUCLEAR INDUSTRY INVOLVEMENT DEVI ATION(S) FROM C0ffi!TMf NTS

NUCI. EAR STEAM SYSTEM SUPPLIFRS AND ARCHITECT ENGINEFRS ACKNOWLEDGED - IE REVIEW COMPLETED

Reactor Units in Service. . . ... . 8 1. Contrary to 10 CFR 50. Appendix B, Criterion V. coments onReactor Units Under Construction. . . . 13 engineering drawings and design criteria documents were not

2Reactor Urits Under Contract. ... .... SuDplies and/or documented from ali cor1*ntators.

CONTRACTORS, VENDORS, OTHERS 2. Contrary to 10 CFR 50, Appendix B. Criterion XV. S AL does not haveprocedures for review and acceptance, rejection or other disposition

Percent of Production Devoted to Nuclear Products . N/A of vendor f.CRs (nonconformance reports) when they are submitteddirectly by the vendor to S&L.

UNPESOLVE0 ITEM (S)ORGANIZATIOMAL CONTACT

Sargent & Lundy's implementation of Procedure GO 3.12 (Project StatusN / Title J. E. McFarland. Head. 0A Division Peports) does not appear to be meeting the intent of the procedure.Ad ess. . 55 East Monroe StreetCity / State / Zip . Chicago. Illinois 60603Telephone. . . (312) 269-6370 COMMENTS

NONENRC CONTACTS

Aartgned Inspector J. R. CostelloSection Chief. . . C. J. HaleTelephone. . . . (817) 334-2844

.

INSPECTIONBASES Topical Report SL-TR-1A

31GOt ',f.O*

CO,ga

.,

LO7:CU

STONE 4 WEBSTER ENGINEERING CORPORATION, BOSTON MASSACHUSETTS 44090-99900509 (,5

BACKGROUND INFORMATION INSPECIl0N RESULIS

PRINCIPAL PRODUCT (S) DATE(S) Of INSPECTION INSPECTION REPORT NO. UPDATED ON: 7/19/78p ARCHITECT ENGINEERING SERVICES

7/11-14/78 | 78-03 BY: J. R. Costellog


NUCtIAR STEAM SYSTEM SUPPt.1ERS AND ARCHITECT ENGINEERS NONE

..... .. 14Reactor Units in Service.... . .. . 7Reactor Units Under Construction. UNRESOLVED ITEM (5)

Reactor Units l'nder Contract. 13 - - - - -

..........

1. Requirements for identifying the independent objective reviewer'sCONTRACTORS, VENDORS, oTHERS signature by an "1" when signature approval is delegated does not

appear to be well defined.Percent of Production Devoted to Nuclear Products . . . N//.

2. Logic Diagrams, which are key design documents, are being revisedwithout an independent objective review because of a question ofavailability of necessary infonnation.


"Name/ Title . F. B. Baldwin, Assistant QA Manager.... ...

Post Office Box 2325Address. . .... ... NONECity / State / Zip . . . . . . . Boston, Massachusetts 02107Telephone. . . . . . . (617) 973-6566..

NRC CONTACTS

Assigned Inspector . . . . . J. R. CostelloSection Chief. . . . . . . . C. J. Hale

(817) 334-2844Telephone. .........

INSPECTION 10 CFR 50, Appendix B, andBASES ) Other Applicable Regulations

32

COMBUSTION ENGINEERING, INCORPORATED, NUCLEAR PRODUCTS MNUFACTURING, WINDSOR, CONNECTICUT 44010-99900002

BACKGROUND INFORMATION INsrECTION ofSULTS

PR[NCIPAL PRODUCT (5) cATE(S) Cr IN 7fLT10', INSIi CIION PE roRT N9. UPDATED r1: 8/18/78

h NUCLEAR FUEL ASSEMBLIES 8/14-18/78 78-02 By- W. M. McNeill

NUCLEAR INDUSTRY IN/0LVEMENI DEVI ATION(5) F EM COMMITMf NTS

Ni!Cl.F AR STF AM SYSTI M St PPI It PS AND AFrid!II( ? I 9. ! ?.F F P" NONE

Reactor l' nits in Service. N/AReac t or l' nit s l'n f er Const ruc t ion. N/A UNRESOLVED ITEM (5)Reactor l'n i t s l'nde r Cont ract . N/A

NONECONTRACTORS, VENDORS, OTII|.RS

Percent of Produc t ion Devoted to Nuclear Product s 100 CO WENTS

NONE

ORCANIZATIONAL CONTACT

Name/ Title J. E. Wahler, QA ManagerAddress. 1000 Prospect Hill Road

City / State / Zip Windsor, Connecticut 06095Telephone. (203) 688-1911

NRC CONTACTS

Assigned Inspector W. M. McNeillSection Chief. D. E. WhitesellTelephone. (817) 334-2844

INSPECTION 10 CFR 50, Appendix B, andBASES ) O'_her Applicable Pegulations

It

'2 33t. .c.',OLOTs

(uQO, ..7;,x

OD

GENERAL ELECTRIC COP.PANY, WILMINGTON PANUFACTURING DEPARTMENT, WILMINGTON, NORTH CAROLINA 44010-99900003

BACKGROUND INFORMAI10N _INSPECIl0N RESULTSPRINCIPAL PRODUCT (S) DATE(S) 0F INWlCTION INWICTION R[ PORT NO. UPDATED ON: 7/21/78

4 WCLE/R FUEL ASSEMBLIESV | 7/14-21/78 78-02 BY: W. M. McNeill

NUCLEAR !NDUSTRY IN/OtVEM NT orVIAT10N(5) FROM (OMMITMINTS

NertfAR sTtAM SY R T t'M SUI Pt.ll HS AN0 ARCHITi t:T FNGINFERS A[a,*;[%([DG[C . IE PEVIEW COMPLETED

React or l' nit s in Service. 1. Con t ra ry to C e Topical Peport, Sect 3r. 5 and the CA Program measuresReactor Units Under coastr'ntion. t* tc cLntrol packaging did not assure items were packaged in full-

Re.se t or l'ni t s t'nde r Cont ract . N/A accordance with establishod Packaging Data Sheets.

CONTRACTO R s , VF'.W S , OTliF RS ?_ ( c r. t ra ry *o the Topical report, Section e and the QA Programinspection instructions were not properly reviewed prior to release.

Perrent o f I'roduc t ior Devoted t o Nuc lear Produc t s 100'3. Contrary to the Topical Report, Section 7 and Practices and Prt)cedure,

CO-11, some vendors were not on the Survey Approved Vendor List norwere the sJrvej forms on file.

ORGANIZATIONAL CONTACTC. W. rey:e, Pa"acer Sality Audits p.,cESOLVED ITEM (S)

Name/ Title & Cu torer EervicesPost Office Ocx 763 1. Some confusion exists on how AFSI 45.2.2 requirenents on halogenatedAddress. . . .

Wilnirgton, .,rth Ca rolina ?8411 or deleterious content of tapes, desiccants, wraps, etc. are to beCity / State / ZipTelephane. (919) 343-5EM identified in specifications and how the Soecifications are to be

implenented.

NRC CONTACTS 2. Time did not allow far recovery of records which would demonstrateconfcmance of shipping containers to the Certificate of Compliance.

Assigned Inspector W. E TicillSection Chief. C. E W ese!ITelephone. (817 4-2544 CCWENTS

__

N0';E

INSPECTIONBASES Tcpical ec ert NEEC-11209-3A

-

34

-

~.

WESTINGHOUSE ELECTRIC CORPORATION, NUCLEAR FUEL DIVISION, PITTSBURGH, PENNSYLVANIA 44010-99900005

BACKGROUND INFOR"ATION I'ISPECTION 9ESULTS

PPIN:! PAL P;'O ' !(11 DATE'5) 0F IN5PECTION IN5prCTION PEPORT NO. UPDATED ON: 5/26/78N NUCLEAR FUEL ASSEMBLIESV L/22-26/78 78-01 By: W. M. McNeill

NUCLEAR INDU5TRf I NVOL', E ME NT DEVIATION {5)FROMC0"MITMENTS

N:T! F AR $1EAM SYSTEM 91PP!!FRS AND AW HITFFT l''I'JFR' ACKNOWLEDGED - IE PEVIE'4 CGMTINUED

Reactor Units in Service. N/A 1. ANSI N45.2.11 was ret fully followed in the areas of identification ofReactor Units Under constru4 tion. N/A calculations. perfomance of verifications, and documentation ofReactor Units Unde r Cont ract . N/A verification in accordance with the Topictl Peport section.

CONTRACTnRS, VE!. DORS, OTHERS 2. .%dit records did not Contain the Checklist used in aCCordance withTopical Feoort. Section 18. and the Product Assurance Department

Percent of Production Devoted to Nuclear Products 100' g3ngaj, 2,1g,1,

L:N?ESOLVED ITEM (S)

ORGANIZATIONAL CONTACT 1. Full implementation of Procedere E.O.P.4.10 could not be verifiedE. F. Menke, Monager b*cause Westingbouse is currently revising the distribution matrix of

Name/ Title Engineering Product Assurance the design manuals.P. O. Box 355AMress.

citv/ state / Zip Pittsburgh, Pennsylvania 15230 2. Cxpliance of the Mechanical Desigr, Manual to requirements of E.0.P.'s(412) 256-5899 could not be est.blished because of the late delivery of the completetelephone.

documants.

NRC CONTACTS

W. M. McNeillAssigned InspectorD. E. Whitesell NONESection Chief.(817) 334-2844Telephone.

INSPECTIONBASES

Topical Report WCAP 7800

h Revision 4A

35

'O

'.,

e'a.3

y'.,4,

C, ...

NBABC0CK & WILCOX COMPANY, MOUNT VERNON, INDIANA 44040-99300042 00

BAUGROUND INFOR%Il0'4 !!1SPECT10N rISl!LIS._

P R I N:! Pl., fk n'CI(S) DATE(5) 0F IN5Pl. TION INSFECT ION RE PORT NO. LTDATED ON: bf its/ /8REACTCR PRESSURE VESSELSg

8/15-16/78 78-01 BY: Poss L. Brown

NUCLEAR INDUSTRY I% 0LV L ME NT DEVIATION (S) FRCM COMMITMfNTS

NectJAR s II AM sYstrM Serr! li ks AND Ah( Hili t I F 't . I M E R s NON[

heactcr i! nits in Service. N/AFeat t er Unit s Under Constror; ton. N/A UNRESOLVEDITEMS)heat tor Unit s '.' n a t centratt. N/A

-

NONECONTRACTOR 3 VENTORS, OTiiF R S

Pertent of Produc t ien Devot ed t o Naclear Product 9 9 0 '.- C0mENTS

NONE

ORfAN!IATIONAL CONTACT

Name/Iitle C. M. Erynanael , QA ManagerAddrews Highway 69 WestCitv/ state / Zip Mount Vernon, Indiana 47(20Telephone. (812) 833-6071

_

NRC CONTACTS

Assig,ned Inspector V. H. Fanter

Section Chief. D. E. Whitesell

Telept one. (817} 33;-2846

_

INSPECTION10 CFR 50, Appendix B, and

BASES ) Other 4 itable Pegulations

36

BARTON INSTRUMENTS, A Chli UF M L CITY OF INDUSTRY, CALIFORNIA 44075-99900113

.BACKtROUND INFORMAT10N INSPEC110N 9ESULTS,

FRIN' IPAL PRODUCT (S) DATE(S) OF INSPECTION INSFECTION REPORT NO. UPDATED ON: 3/2/78

h INSTRUMENTATION-

2/21-24/78 78-01 BY: W. E. Foster

NUCLEAR INDUSTRY INVOLVEMENT DEVIAT!0N(S) FROM COMMITMENTS

NUC11AR STEAM SYSTEM SUH g ERS AND ARCHITECT ENGINEERS ACKNOWLEDGED - IE REVIEW COMPLETED

Reactor Units in Service. . . N/A 1. Contrary to Barton Instruments' corrective action response letter ofN/A September 7,1977, marked documents had not been removed from use, asReactor Units Under Cnnstructi n. .

N/A evidenced by Manufacturing Instruction and Production Order datedReactor Units Under Contract. .

February 6,1978, for P/N 03b610218. Operations 0200 through 0510 hadCONTRACTORS, VENDORS, OTHERS been lined out. The change 'd not been approved and the document

Percent of Product * on Devoted to Nuclear Product s . 8%

2. Contrary to Barton Instruments' corrective action response letterof September 7,1977, Standard Practices EN-1 and EN-2 had not beenput inta ef*ect. This is evidenced by a Barton memo dated February 23,1978, entitled Implementation of EN-1 thru EN-5 and states in part,

ORGANIZATIONAL CONTACT " Effective this date the above company Standard Practices will beput into use."

Name/ Title .G. R. Welt, QA Director

Address. . .900 South Turnbull Canyon Road 3. Contrary to Criterion VI of Appendix B to 10 CFR 50 and paragraphs 3.4

City / State / Zip . City of Industry California 91749 and 3.4.1 of Standard Practice QU-2, the Manufacturing Department hadTelephone. . . (213) 961-2547 no written procedures or instructions that defined their activities

in design documents and related changes, while the QA Departmenthad no written procedures or instructions that defined their activities

NRC CONTACTS related to the following documents and changes: Proc urer'en t ,Manufacturing Instructions , Procedures , Drawings, and Registers.

Assigned Inspector . W. E. FosterSection Chief. D. M. Hunnicutt 4. Contrary to Criterion VI of Appendix B to 10 CFR 50 and paragraph 2.Telephone. . . . (817) 2 J844 of the Manufacturing Instructions Contrcl Policy for Westint, house

,

P. O. No. S46. AIC-265750-BN, Manufacturing Instruction and Production'

Order dated November 23,1977, for P/N 07640001A had not been reviewedand sie'ed off by the QAE before issuing to the shop.



(Continued next page) |

'

37

.

)J

MQe,'.CN'aBARTON INSTRUMENTS, A UNIT OF ITT, CITY OF INDUSTRY, CALIFORNIA 44075-99900113

'

(continued)INSPECTION RESULTS (Continuation from previous page)

ACKNOWLEDGED - IE REVIEW COMPLETED (continued) 10. Contrary to Criterion II of Appendix B to 10 CFR 50 and para-graphs 3.1, 3.2 and 3.3 of Quality Assarance Instructions 10-04,

5. Lontrary to Criterion VI of Appendix B to 10 CFR 50 and para- one log had not been signed for January 1978. Additionally,graph 3.5 of the Manufacturing Instruction Control Policy for the Chief Inspector does not insure the logs are sigred, butWestinghouse P. O. No. 546-AIC-265750-BN, Manufacturing relies upon the monthly audit to detect failure to sign (hisIr.struction and Production Order dated May 9,1977, for words).P/N 07641003B displayed lined out infomation at OperationNo. 0040. 11. Contrary to Criterion II of Appendix B to 10 CFR 50 and para-

graph 4. cf Quality Assurance Instructions 10-04, this6. Contrary to Criterion VI of Appendir. B to 10 CFR 50 and para- procedure had not been added to the internal audit syst a

graphs 7.1 and 7.2 of Standard Fractice No.1209, the followingmarked-up documents were in use without signature of authoriza- 12. Contrary to Criterion XVII of Appendix B to 10 CFR 50 and para-tion: graph 18. of Westinghouse Quality System Requirements, dates

of inspections had not been entered on the following:Assembly List No. 8070.10138 Revision 1, November 1,1976, forP. C. Board Assembly Mt, del 8070. Part ntsnbers, valves, Manu9cturing Instruction and Production Order dated May 9,1977,additions, and deletions had been made. The document identifies for P/N 07641003B, Operation Nos. 0030, 0040, 0050; andRevision 1 for " Production Release."

Manufacturing Instruction and Production Order dated May 18,Assembly List No. 0655.10438 Revision 1, October 3,1975 for 1977, for P/N 076410608, Operation Nos. 0090, 0100, 0110, 0120Power Supply w/o Pre-Regulator. Part number and value of item and 0130.42 had been changed. The document identifies Revisien 1 for" Production Release." 13. Contrary to the requirements in the Standard Practice Manual

Number 1222, certain internal audits were not performed in7. Contrary to Criterion II of Appendix B to 10 CFR 50 and pars- accordance with the specified 'requency established by the

graph 2.1 of Standard Practice No.1225, the Manufacturing and I Periodic Audit Plan.Engineering Departrnents had not established procedures to definetraining activities, schedules, end records. 14. Contrary to the requirements in Standard Fractice Manual Number

1211, certain subcontractors were used for supply of nuclear8. Contrary to Criterion II of Apper. dix P to 10 CFR 50 and para- orders, even though they were not on the Approved Supplier

graph 3.3 of Standard Practice No.1225, the QA Man 3ger does not list.maintain schedules and records of all training activities.

15. Contrary to the requirements in the Standard Prs:tice Man al9. Contrary to Criterion II of Appendix B to 10 CFR 50 and para- Number 1211, certain vendors had not been resurveyed at the

graphs 4.1 and 4.2 of Standard Practice No.1225, nur, lear specified frequency.inspection personnel and audit personnel nad not been qualifiedper ANSI N45.2.6 and ANSI N45.2.23, respectively. (Cor;tinuad next pace',

38

.

.

%075-99900113BARTON INSTRUMENTS, A UNIT OF ITT, CITY OF INDUSTRY, CALIFORNIA (continued)

INSPECTION RESULTS (Continuation from previous page)

ACKNOWLEDGED - IE REVIEW COMPLETED (continued)

16. Contrary to the requirements in 10 CFR 21, certain procure-ment documents did not specify that provisions of 10 CFR 21apply.

17. Contrary to the requirements in Standard Practice ManualNumber 1203, Rejection Reports were not written even thoughseveral gages were found to be discrepant.

18. Contrary to the requirements in Standard Practice Manual Number1215, Rejection Reports were not initiated for certainpurchase orders containing items that were rejected by receivinginspection.

19. Contrary to the requirements in Standard Practice ManualNumber 1215, certain nonconfoming material was not separatedfrom acceptable material.

20. Contrary to the requirements in Standard Fractice ManualNuriber 1215, inspection had not initiated rejection reports oncertain nonconforming material that was referred to MRB.

21. Contrary to the requirements in the Standard Practice ManualNumber 1215, corrective actions were not recorded on certainrejections reports, as required by the Manual.

UNRESOLVED ITEM (S)

NONE

C0ffENTS

NONE

39

CDI:T.

.CN

COOWs'2

BENJAMIN F. SHAW COMFANY, LAURENS, SOUTH CAROLINA44020-99900250 U

MCKhROUND INF ORMATION INSPECT 10N RESULTS

PRINCIPAL PRODUCT (5) DATE(S) Of INSP[CTION |INSPICTIONREPORTNO. UPDATED ON: 9/14/78N NUCLEAR PIPING ASSEMBLIESV 9/6-7/78 78-02 BY: H. W. Roberdst

N'JCLEAR INDUSTRY INV0lVEMENT DEv!ATION(S) FROM C0tt41TMfNTS

N('rt F AR STEAM SYSTEM SUPPLIERS AND ARCHITECT ENGINFERS NONE

Reactor Units in Service. . N/AHeactor Units Under Construction. . N/A

UNPESOLVED ITEM (S)Reactor Units Under Contract. . . . . N/A

NONECONTRACTORS, VENDORS, OTHFRS

Percent of Production Devoted to Nuclear Product s . . . 30% COMMENTS

NONE


Name/ Title . . J. J. McDemott, Plant ManagerAddress. . . . .. . Post Office Box 285City / State / zip . . . Laurens. South Carolina 29360Telephone. . (803) 682-3231

NRC CONTACTS

Assigned Inspector . . . H. W. RoberdsSection Chief. . . . D. M. HunnicuttTelephone. . . . . (817) 334-2845

5 CHON$S 10 CFR 50, Appendix B, and


40

BERGEN-PATERSON PIPESUPPORT CORPORATION, LACONIA, NEW HAMPSHIRE44070-99900209

BACKGROUND INFORMAT10N INSPECT 10N R.FSULIS

PRINCIPAL PRODUCT (S) DATE(S) Of INSPiCTION INSPECTION REPORT NO. UPDATED ON: 6/15/78g COMPONENT SUPPORTS

6/5-8/78 78-01 BY: L. E. EllershawNUCLFAR INDUSTRY INVOLVEMENT DFVIATION(S) FROM COMMITMENTS

NUCl.FAR STEAM SYSTEM SUPPL.IFRS # 1ARCHITFCT FNGINFFRS ACKNOWLEDGED - IE REVIEW COMPLETED

Reactor Units in service. . . . . . N/A 1.Reactor Units UnJer Construction. . - N/A Contrary to Criterion XVI of Appendix B to 10 CFR 50 and ASME Code,

paragraph NCA-4134.16, the QA Manual does not address corrective actionReac t or Unit s Unde r Cont ract . . . N/A requirements being extended to the performance of a subcontractor'scorrective action measures.CnNTRACTnRS, VEMORS, OTHERS

2.Percent of Production Devoted to Nuclear Producta . . 35% Contrary to Criterion XIII of Appendix B to 10 CFR 50 and ASME Code,

paragraph NCA-4134.13, handling instructions s.. procedures have notbeen estab'Ished to prevent damge of material, equipment, and items.

3. Contrary to Criterion V of Appendix B to 10 CFR 50 and ASME Code,ORGANIZATIONAL CONTACT paragraph NCA-8322, component support drawings designed and prepared

by Bergen-Paterson Pipesupport Corporation customers do not showr.'ameplate locations.

N m / Title H. Noreen, Jr. , [sirector QAAddress. . . . 48 Winnisquam Avenue

4.city / state / zip . . Laconia, New Hampshire 03246 Contrary to Criterion X of Appendix B to 10 CFR 50 and QA Manual,Telephone. . (603) 524-1990 Section M:

Certain hold points were designated and signed off by a persona.

NRC CONTACTS other than the Quality Control Manager.

b.Assigned Inspector . .. L. E. Ellershaw Revisions to Weld Procedure Specifications used were not recordedSectfon Chief. . . . . . D. M. Hunnicutt on Fabrication Records af ter welding was completed.Telephone. . .. . (817) 334-2844 5. Contrary to Criterion VI of Appendix B to 10 CFR 50 and QA Manual,

Sections 0 and 6, the master shop drawing book contained Revision 0,sheet 1 of 1, of a certain drawing while the production planning and

ECTION control department files contained sheet 1 of 2, Revision 1 ar.d sheet10 CFR 50, Appendix B, and of evisi n 0.,


(Continued next nage)

CD 41.

CpC&

BI

N ES R

11 C U P GO N E E2W. R

E C NN E N S T -O N O O I PN T N L O AE S E V N TE

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w

BREDA TERM 0MECCANICA, S.P.A., MILANO, ITALY 44040-99900318

BACKGROUND INFORP.ATION INSPECTION 9ESULTS

PRINCIPAL PRODUCT (S) DATE(S) 0F IN;PECTION INSPECTION REPORT NO. UPDATED ON: 6/2/78N NUCLEAR VESSELSV 5/30-6/2/78 78-01 BY: P. I. Verrios

NUCLEAR INDUSTRY INVOLVfMENT DEVIATION (S) FROM COMMITMENTS

NITI F A R SitAM SYSTFM SUPPI.IFRS AND ARCHITICT FNcINFFRS ACKNOWLEDGED - IE REVIEW COMPLETED

Reactor Units in Service. N/A 1. Contrary to Criterion IV of 10 CFR 50, Appendix B, and Section 6 ofReactor " nit s Under Construction. N/A the QA Manual, paragraph 6.5.1, certain released purchased orders hadReactor L its U, der Contract. N/A not been reviewed and approved by the Design and Engineering Depart-

ment.CONTRACTORS, VENDORS, OTlfERS

2. Contrary to Criterion V ard Criterion XV of 10 CFR 50, Appendix B,*rercent of Production Devoted to Nuclear Products and Section 9 of the QA Manual, paragraph 9.2.1, written procedures

or specifications had not been developed relative to handling of*See Comments nonconformances and corrective action.

3. Contrary to Criterion !! of 10 CFR 50, Appendix B, and Section 19 ofORGAN!1ATIONAL CONTACT the QA Manual, paragraph 19.3.3, training courses for certain groups

had not been scheduled every twelve (12) months.Name/ Title T. 23dino, Manager, QAAddress. Viale Sarca, 336 4. Contrary to Criterion IX of 10 CFR 50 Appendix B, :nd Section IX ofcity / state / zip Milano, 20126 Italy the ASME Code, paragraph QW-322, paragraph 10.3.4.2 in Section 10 ofTeiephone. 69.97 the QA Manual requires verification of process use by a welder on a six

months basis, irrespective of whether the welder was qualified inonly one (1) or more processes.

NRC CONTACTS5. Contrary to Criterion V of 10 CFR 50, Appendix B, and Section 17 of

Assigned Inspector P. I. Verrios the QA Manual, paragraph 17.8.5, a certain manual welding machine wasSection Chief. D. M. Hunnicutt observed to have not been calibrated at the required 120 day interval.Telephone. (817) 334-2844

6. Contrary to Criterion IX of 10 CFR 50, Appendix B, paragraph 10.4.5.1in Section 10 of the 0A Manual and r agraph QW-281.2(d) in Section IXof the ASME Code, a certain welding procedure specification for

INSPECTION shielded metal arc corrosion resistant overlay cladding permittedBASES 10 CFR 50, Appendix B, and welding in a position not qualified by the supporting procedure

[)> Other Applicable Regulations qualification.

_(Continued next page)

.s)(;, 43T.:a.

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ed'".

NCC

BREDA TEPJ,0MECCANICA, S.P.A., MILANO, ITALY 44040-9940031R

(continued)INSPECTION RESULTS (Continuation from previous page)

UNRESOLVED ITEM (S)

1. Criterion XVIII of Apr endix B to 10 CFR 50 states in part." Audit results shall be documented and reviewed by manage-ment having responsibility in the area audited. Followupaction including reaudit of deficient areas, shall be taken whereindicated."

QA Manual, Section 20, paragraph 20.7.1, states in part,"Perioaic OA Department meetings will be held to discuss andrenew recurring and serious problems related to Qualityassurarce. These meetings will nomally be attended by the QAManager and his group leaders. . . ."'

Sect ion 20 of the QA Manual contains subjective wording such aspersodic, nomally, from time to time, etc. Breda managementagreed to review Section 20 of the QA manual and make .equiredc'.a ri fi cations .

2. The QA Manual does not describe either control of bending andfoming special processes, or provide a reference to applicablecontrolling procedures.

3. Breda specifications applicable to the rolling of shell coursesdo mt provide fomalized instructions on the method of achievingcorrect final radious of curvature adjacent to weld joints.

COMMENTS

This infomation unavailable this inspection. To be obtainedduring the next inspection.

44

CONAX CORPORATION, BUFFALO, NEW YORK 44075-99900323

BACKGROUND !NFORMAfl0N INSPECTION RESULTS

PRINCIPAL PRODUCT (S) DATE(S) Of INSPECTION INSPECTION REPORT NO. UPDATED ON: 5/24/78N ELECTRICAL PENETRATION ASSEMBLIESV 5/15-19/78 78-01 By: W. E. Foster

NUCLEAR INDUSTRY INVOLVEMENT DEv!ATION(S) FROM COMMITMENTS

NUCI.FAR STEAM SYSTEM SUPPIIFRS AND ARCHITFCT ENGINFERS ACKNOWLEDGED - IE REVIEW COMPLETED

Reactor Linits in Service. N/# 1. Contrary to Criterion IV of Appendix B to 10 CFR 50 and paragraphReact or l' nit s l'nder Const ruct ion. N/A 4.3.3(b) of Nuclear Quality Assurance Procedure No. 4.3, datedReac t or Unit s Und( r Cont ract . . . N/A June 24, 1977, outgoing Purchase Order (P.O.) No. 51392, dated

January 24, 1978, did not require the supplier to provide a qualityCONTRACTORS, VENDORS, OTifERS # assurance program consistent with 10 CFR 50, Appendix B. The P.O.

"* # *#Percent of Produc t ion Devoted to Nuclear Produc t s . 40%

2. Contrary to Criterion IV of Appendix B to 10 CFR 50 and paragraph4.3.4 of Nuclear Quality Assurance Procedure No. 4.3, dated June 24,1977, the Quality Assurance Manager had not initialed and dated the


a. N . 51392 dated January 24, 1978,R. L. Duroure. QA ManagerName/ Title . .. . . t2. No. 52811 dated May 3, 1978,Address. . . 2300 Walden Avenue c. No. 51806 dated January 31, 1978, andCity / state / zip Buf f alo, New York 14225 d. No. 51881 dated March 1, 1978.Telephone. . . . (716) 684-4500

3. Contrary to Criterion XII of Appendix B to le CFR 50, paragraph12.1.3(c) of Nuclear Quality Assurance Procedure No.12.1. dated

NRC CONTACTS June 24, 1977, and Quality Control Instruction No. 29-2-9, datedMarch 12,1971, the ball micrometer had not t'een calibrated to

Assigned Inspector . . W. E. Foster the established frequency of six (6) months. Last ca'ibrated June 23,Section Chief. . . . D. M. Hunnicutt 1977,Telephone. . (817) 334-2844

Note: The instrument was retrieved and recalibrated while theinspector was still in the Metrology Laboratory. No responseto this deviat. ion is required.



] (Continued next pagr)~D.

c., 45y,e

2).

C.'Oem:::NCC:

CONAX CORPORATION, BUFFALO, NEW YORK 44075-99900323(continued)

INSPECTICR4 RESULIS (Coi.-inuation f rom previous page)


4. Contrary to Crit..rion XV of Appendix B to 10 CFR 50 and paragraph 9. Contrary to Criterion III of Appendix B to 10 CFR 50 and para-15.3.4(a) of Nuclear Quality Assurance Procedure No.15.3, dated graph 5.1.6 of Nuclear Quality Assurance Procedure No. 5.1,June 24, 1977, Material Disposition Reports were not affixed to dated June 24, 1977, the pressure boundary block on thethe following items in the Nuclear Storage Area - Nonconforming: Engineering Order is checked automatically when the hardware

contains pressure boundary material and not af ter a review ofa. Header Plate - Part Number 7320-30002-01, the Stress Report for determination if pressure boundary

b. Header Plate - Part Number 7611-30002-01, documents are affected.c. Header Plate - Part Number 7283-30008-01, and

1. Header Plate - Part Number 7429-30005-02.UNRESOLVED ITEM (S)

5. Contrary to Criterion XVIII of Appendix B to 10 CFR 50 and para-graph 5.2 of Quality Control Instruction No.18.1, Revisien A, Procedures require the Job Engineer, among others, to review, approvedated July 7,1977, records of Lead Auditor - Auditor Qualifi- and initial Purchase Requisitions (PR) for material. Purchasecation dated January 3,1977, January 14, 1977, and March 1 Requisitions are equipped with an " Approved By" space and a1977, had not been updated annually. " Requested By" space. Several PR's had been initialed by Job

Engineers in the " Requested By" space.6. Contrary to Criterion VI of Appendix B to 10 CFR 50 and paragraph

8.4.5 of Nuclear Quality Assurance Procedure No. 8.4, dated The contractor stated steps woJ1d be taken to clarify the meaningJune 24,1977, changes had not been initialed and approved by of these initials.

the Quality Assurance Engineer on Travelers for Part Number7611-1000?-01, S/N 818 and Part Number 7611-10003, S/N 821.

COMMENTS

7. Contrary to Criterion VI of Appendix B to 10 CFR 50 and paragraph <8.2.2.3 and 8.2.2.5 of Engineering Instruction No. 5.1, NONERevision F, dated JJ1y 8,1977, an individual other than theDesign Supervisor had signed the " check" space of E.0, No.N-0694, dated April 5,1978, for P/N 7611-10005.

8. Contrary to Criterion VI of Appendix B to 10 CFR 50 and paragraph5.9.2.4 of Engineering Instruction No. 5.1.1, Revision B, datedJuly 8,1977, approval of the Nuclear Products Manager had notbeen secured for E.O.s Nos. N-0679 dated March 10, 1978, andN-0702 dated April 24, 1978, for IPS documents, Nos. 267 and333, respectively.

4

46

. . .

I

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C0i1SOLIDATED CONTROLS CORPORATION, SUBSIDIARY OF CONDEC CORPORATION, BETHEL CONNECTICUT 44075-99900221

BACKGROUND INFORMAIION INSPECIION RESULTS

PRINCIPAL PRODUCT (S) DATE(5) Of INSPEC!!O1 INSPECTION REPORT N0. UPDATED ON: 6/30/ 78N, ELECTRONIC INSTR'JMENTATION PRODUCTSV i 6/20-22/78 78-01 By: W. E. Foster

NUCLEAR INDUSTRY INVOLVEMENT Ofv!ATION(S) FROM COMMITMENTS

NPr!FAR STIAM SYSTEM SUPPL.tFRS AND AkrHITFCT ENt:INFFRs ACKNOWLEDGED - IE REVIEW CONTINUING

Reacter Units in service. N/A 1. Contrary to Criterion IV of Appendix B to 10 CFR 50 and paragraph 12.1Feactor Units "nder Construction. N/A of Quality Control Manual, QCM No. 2, Revision 3 dated April 15, 1977Reactor tnits t'nder Contract. N/A released Purchase Order No. 56922 7, dated May 12, 1978, and its

attendant order cards had not been reviewed and approved by the QualityCONTRACTORS, VENDORS, OTUERS Control Department inasmuch as Q.C.R. and initials were not ind'.cated

on the purchase order and order cards.Percent of Produc t ion Devot ed to Nuc lear Product s .. 157,

2. Contrary to Consolidated Controls Corporation's corrective actionresponse letter of December 20, 1977, the document entitled," Authorities and Duties of the Quality Control Staff," had not beenidentified as Appendix 1 in Quality Control Manual No. 2.


3. Contrary to Consolidated Controls Corporation's corrective actionName/ Title . . L. E. Goodsell, Jr., QC Manager response letters dated August 25, 1977, and September 22, 1977, TestAddress. 15 Durant Avenue Procedure KGD1315 had not been added to the Manufacturing Routing tocit y/ stat e/ Zip Bethel, Connecticut 06801 ccnduct dielectric and insulation resistance tests on the 9N30 assert >lyT~lephone (203) 743-6721 In addition, Manufacturing Routing, Revision D, dated May 27, 1977,

fer Logic Cabinet Assembly, Part No. 9N28, did not identify the testprocedure for conduct of the dielectric and insulation resistance

hPC CONTACTS tests.

Assigned Inspector W. E. Foster 4. Contrary to Consolidated Controls Corporation's corrective actionSectian Chief. D. M. Hunnicutt response letter dated September 22, 1977, the correct harness boardTelephone. (817) 334-2846 had not been listed by number in the tooling column of Manufacturing

Routing, dated September 15, 19F , for Relay Panel Assembly. TypeNo. 9N38-6, Part No. 7N186-1, -2, -3, -4. Additionally, the harnessboards in use during avembly were incorrectly identified; they were

INSPECTION identified as 9N86-1. -? (Left Side) and 9NS6-2, -4 (Right Side).BASES N 10 CFR 50, Appendix B, and

V Other Applicable Regulations

(Continued next page)@U 47:':u

O

t.WPk?|;

CONSOLIDATED CONTROLS CORPORATION, SUBSIDIARY OF CONDEC CORPORATION, EETHEL, CONNECTICUT 44075-99900221 @9(continued)

INSPECTION RESULTS (Continuation frc' previous pa9e)

ACKNOWI. EDGED - IE REVIEW CONTINUING (continued)

Note: The boards were reidentified as 7N186 prior to completionof this inspection.

5. Contrary to Consolidated Controls Corporation's corrective actionresponse letter dated September 22, 1977, there was no indicationof acceptance of approximately forty (40) relays (Part Nos.KHF431A and KHE431A) located on a shelf ire the assembly / testarea. These items were purchased an Purchase Order No. 42263-3,dated November 17, 1976.

6. Contrary to Criterion XII of Appendix B to 10 CFR 50, measureshad not been established to assure that rented measuring and testequipment, used in activities af fecting quality, were properlycontrolled, calibrated, and adjusted at specified periods.

UNRESOLVED ITEM (S)

NONE

C0rtiENTS

NONE

'

-

48

.-

.

TROSBY VALVE AND GAGE COMPANY, WRENTHAM, MASSACHUSETTS 44060-99900052

PACKf>R0llND INF ORMAIl0N i.*''PfCTION REEUt3S

PRINCIPAL PRODUCT (5) U^ '"q v,- "N" & "NV" CLASS I, h ' 1, 2, & 3 VALVES 7/27-28/78 18-01 BY: Wm. D. Kelley

,- w --

NUCLEAR INDUSTEf INVOLVEMENT Df yl ATION(S) FROP DNMITME NTS _

NUrEEAR STEAM SYSTEM SUPPitr.b AND ARCHITECT ENg NEERS SCKN0!$LEDGED - IE REVIEW CONTINUI %

N, A Criterion V of Appendix B to 10 CFR 50 and paragrapn NCA-4134.5 ofReactor Units in Service. . .

Reactor Units Under Construction. .. . N/A Section III to the ASME Code states in s'rt, "Activf tits affectinq qualityN/A shall be prescribed by documented instructions, procedures or drawingsReactor Units Under Contract. . .. ..

of a type appropriate ', the circurostancer anc _ fill be accomplished inCONTRACTORS, VEF. DORS, OTHERS accordance wi th trese ir,i tructions, cr<coures , or drawings "

Percent of Production Devoted tc Nuclear Product a . 20 ;; C.V. Procedu 2 Q. C.-125 Apprtva) Date Au,sst 24, 1977, paragraph 2.3.1.r

states, " SPA Su;,ervisor shall submit ti e necessary dt cumentation regardingeach individ d .* etin3 tr e requi renents of P. ragro;,M ?. l. and 2.2. .

{ to the emailty /ssarance Manager."!

ORGANIZATIOKit CCNTA(T $ ! Parag m 2. . 4 s'ates, " Quality Assurance Manager shall review the,~

i docume .tition and upon his satisfactory review, ne shall issue a Level IIName/ Title . . . . . M. Heman, QA Manager ard listing applicable exceptions for the individual who satisfied tia

43 Kendrick Street nEcM sary requi v ents."Address. . . ...

' City / State / Zip . Wrentham. Massachusetts 02093. .

I Telephone. . . . . . (617) 384-3121 Contrary to these regarements the SPl Survisor had nci. ser.itted theeducation and experience nualificstbn cocoentation (icq#cd tv nra-graph 2.l.5 and on-the-jcb-t rainins documentat f or (required by paracraph

NRC CONTACTS 2.2.) to the Qualit, Assurance Mea , r, oor had the QA Manager prcs iutd~

the qualified personnel, with the pit.3rt bcd cred(n'f als att? sting toAssigned Inspector . . . 14m. D. Kelley e their qualifications. (Fequi red t y p n : graph - .3.2. )Section Chief. . . . . . . D. E. Whitesell

... . (817) 334-2846Telephone.UNRESOLVED TTiM(S)

Documen" were beir g corrected using "whi te-out" and corr ectices wer" ?

INSPECTION rude to othJr documents without the person's signature and date. !BASES 10 CFR 50, jppendix B, and ?) Other bpl sca9 e Regulation; ,

,l

(Cor.ttnued next page). . .

e

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i.7.pHN

.

to....

. ..;

OCROSLY VALVE AND GAGE COMPANY, WRENTHAM, MASSACHUSETTS 44060-9990005? 'J

(continued) f[]NSPECTION RESULTS (cantinua ion from previous page)

LERESOLVED ITEM (5) (continued)

CV is to discontinue this pract'ce and the inspector will verifythis on a subsequent inspection.

CONENTS

NONE

6

h

. . . _

50

DRAVO CORPORATION, PIPE FABRICATION DIVISION, MARIETTA, OHIO M020-99900017

BACKGROUND INFOR".ATION INSPECTION RE3ULIS

PRINCIPAL PRODUCT (S) DATE(S) 0F INSPECTION INSPECTION REPORT NO. UPDATED ON: 4/18/78NUCLEAR PIPING ASSEMBLIES

,4/10-13/78 78-01 BY: I. 8arties


NUrLFAR STFAM SYSTFM SUPPLIERS AND ARrHITFCT ENGINFERS ACKNOWLEDGED - IE REVIEW COMPLETED

Reactor Units in Service. . N/A 1. Contrary to comitments in a Dravo corrective action response letterReactor Unit s l'nder Construct ion. N/A dated November 23, 1977, the inspector observed that all variables overReact or l' nits Unde r Cont ract . . N/A which a welder can exercise control were not being included by the

welding foreman on Weld Joint Data cards supolied to the welders.CONTRACT 0'IS , VENDORS, OTHERS

2. Contrary to comitmer.ts in a Dravo corrective action response letterPercent of Production Devoted to Nuclear Products 75T dated November 23, 1977, a General Welding Specification pertaining

to tack welding had not been finalized as of April 12, 1978.

3. Contrary to comitments in a Dravo corrective action response letterdated November 23, 1977, a certain finding had not been included in an

ORGANIZATIONAL CONTACT audit check list of production activities as of April 17, 1978.

Name/ Title R. L. Anderson, QA Supervisor 4. Contrary to Criterion IX of 10 CFR 50, Appendix B, and paragraph1115 Gilman StreetAddress. .

Marietta, Ohio 45750NA-4451 in the ASME Section III Code (1974 Edition), measures were not.

City / State / Zip . .. ..

(614) 373-7541 of amperage output with the requirements of applicable weldingestablished with respect to certain power sources to assure confonnance

Telephone. . ... .

procedure specifications.

NRC CONTACTS 5. Contrary to a Dravo correction action response letter dated November 23,1977, a new procedure,ES-DOC-3,to specifically delineate the records

Assigned Inspector . I. BarneS to be presented to the Authorized Inspector for execution of theSection Chief. . . D. M. Hunnicutt code data report was not written and implemented prior to January 1Telephone. . (817) 334-2846 1978.

6. Contrary to a Dravo corrective action response letter dated November 23,1977, a manual revision had not been revised prior March 31, 1978, to

INSPECTION include a requirement for the recording of NDE procedures and revisionBASES 10 CFR 50, Appendix B, and letters on the specific back-up shop documents.) Other Applicable Regulations


'O 51

,

.ae

*..

MW".,,-

M,<

(D

DRAVO CORPORATION, PIPE FABRICATION DIVISION, MARIETTA, OHIO 44020-99900017

(continued)!NSPECTION RESULTS (Continuation from previous page)

ACKNNLEDGED - IE REVIEW COMPLETED

7. Contrary to Cravo corrective action response letter dated similar deviation was previously identified and reported inNovember 23, 1977, a mant.al revision to allow recording of the Report No. 77-02.weld operator identification number and specific weld materialin the appropriate box on the sketch any time prior to final 14. Contrary to the requirements in Section 3 of the QA Manual,inspection to clarify this corritment was not issued prior to certain spool detail sheets for class 2 piping had been releasedMarch 31,1978. for fabrication even thouga prior approval had not been obtained.

This deviation was previously identified and reported in ReportL Contrary to 10 CFR 50, Apptadix B, Criterion V, and NB, NC, and No. 77-02.

ND of the ASME Code, the precedurc used for exanination ofLevel III nendestructive persenrel was not described in a written 15. Contrary to the requirements in Section 14 of the QA Manual,practice. certain nonconformance reports were not presented to the

Authorized Inspector for his review. A similar devietion was7 Contrar/ to 10 CFR S0, Appendix 3. Criterion IX, and Section V, previously identified and reported in Report No. 77-01.

;rticle 6 of the ASPE Code, it could not be verified that thetotal sulfur er halogen content did not exceed l' tg weight for 16. Contrary to the requirements in Section 14 of the QA Manual,penetrant roterials used to examire nickel base alloys certain materials with discrepant CMTR's were not red tagged orand austenitic stainless steels, in that penetrant materials trouble tagged. A similar deviation was previously identifiedv re observed stored in open containers. and reported in Peport No. 77-02.

10. Lontrary to co"riitments in a Dravo corrective action response 17. Contrary tc the requiremen's in Section NCA 4134.12 of the ASMEletter dated '.ovember 23, 1977, the provisico -' the draf t was Code, certain Master gages are not traceable to the Nationalnot being imposed, although the specified prou cure was fou.d Standards in that they have been removed from the calibrationto be in a rou';5 draf t stage. control program.

11. Contrary to the reauirements in Section 17 cf the OA Manual, UNRESOLVED ITEMIS)~

certain intern 31 adits were not ,'erfmed. A similar deviationwas previously identified and reported in Eeport No. 77-01 and Criterion VII of Appendix B to 10 CFR 50 states in part, " . Thein Report No. 77-02. effectiveness of the control of quality by cortractors and sub-

contractors shall be assessed by the applicant or designee at12. Contrary to the requirements in Sectis 17 of the QA Manual, intervals consistent with the importance, complexity, and quantity

certain internal auJit results ,er e % + distriMted to the chief of the pmduct or services."inspector and to the Authorized ins?ectcr.

Section 17 of the Quality Assurance Manual. Revision 3, paragraph 4.1,13- Contrary to the requirements in ection 3 of the QA Manual, states, "When required, the quality assurance manual, procedures,

certain sketches MJ not receiv.1 e indepen:ient review. A


t

52 i

DRAVO CORPORATION, PIPE FABRICATION DIVISION, PARIETTA, OHIO 44020-999non17(continued)

INSPECT:0N RESULTS (Continuation from previous page)

UNRESOLVED ITEM (S) (contin;ed)

operations, facilities, etc. of Dravo vendors shall be auditedto assure that they comply with the ASME III Code, the applicableregulatory requirements and other applicable standards that may beinvoked by customer requirements." Also, same section, paragraph 4.5states, "When a vendor has a valid ASME Certificate issued by theSociety, Dravo may, at its option waive the requirement for anin-plant audit of the vendor."

Based on the subjective wording of Dravo Quality Assurance Manual,the area of vendor audits is ne auditable.

COMMENTS

NONE

53_?>

N*n

,4

'+6

b

is-m..

.J,

DRESSER INDUSTRIES, INCORPORATED, INDUSTRIAL VALVES AND INSTRUMENT DIVISION, ALEXANDr LOUISTANA 40n60 o00n0054 L.,

BACKGROUND INFORMATION l'!SPECT10N RESUllS

PRINCIPAL PRC1UCI(S) DATE(S) Of INSrECTIM IWE CT 10'4 RE POU NO. UPDATED 0*4: 6/8/78p ASME SECTION III VALVES

5/30-6/2/78 78-01 BY: Wm. D. Kelley

NUCLEAR INDUSTRY INVOLVEMENT OfylATION(51 FROM C0'1MITM NTS

NUCLEAR STEAM SYSTFM SUPPLIERS AND ARCHITITT F %:INFFRS ACKNOWLEDGED - IE REVIEW COMPLETED

Reactor Units in Service. N/A Contrary to Criterion V of Appendix B to 10 CFR 50 and DI weldingReactor Units Under Construction. N/A procedures WS-302 dated August 15, 1973, a welder was observed weldingReactor Units Under Contract. N, A part number 516J70SNC008 with amperes above the specified range.

CONTRACTORS, VENDORS, OTilERS_

Percent of Production Devoted to Nuclear Product s 16I

1. OI issued an ir.tcroffice correspondence dated July 21, 1977, stoppingthe practice of r 'g taped correction to reports. There was noevidence that pas. eports had been reviewed for the effect of tapedcorrections. DI will review str ess reports prepared prior to July 21,

ORGANIZATIONAL CONTACT 1977, to determine if tape had been used for corrections.

Name/ Title . . . John W. Richardson, QA Manager 2. DI stores their computer program and design data in the computer, but. . Box 1430Address. they do not identify the ASME Code addition and/or addenda that is

. . Alexandria Louisiana 71301City / state / zip . applicable. DI will review their computer program to determine if(318) 640-2250 the applicable ASME code edition and/or addenda can be identified.Telephone. . .

NRC CONTACTS COMMENTS

Assigned Inspector .Wm. D. Kelley

NONE... . D. E. WhitesellSection Chief.

Telephone. . . . . (817) 334-2846



54

%

%

E-SYSTEMS, INCORPORATED, MONTEK DIVISION, SALT LAKE CITY, UTAH 44070-99900315

BACKGROUND INFOR:1ATION INSPECTION RESllLIS

PRINCIPAL PRODUCT (5) DATl(S) Or INSPfCTION INSPECTION REPORT NO. UPDAT[D ON: 6/1/78

) HYDRAULIC SNUBBERS5/23-26/78 78-01 BY: R. E. Oller

NUCLEAR INDUSTRY INVOLVEMENT DEVI ATION(S) F ROM COMMITME NTS

NtfCLEAR STFAM SYSTEM SI' ppt.lFHS AND ARCHI" 'T LNCINF FRSACKNOWLEDGE 0 - IE REVIEW COMPLETED

Reac t or l'ni t s in Service. N/A Contrary to Criterion IV of Appendix B to 10 CFR 50 and the ASME acceptedReact or l' nit s l'nder Const ruct ion. N/A QA Manual, Section 4.0, the " Traveling Purchase Requisition Card" used forReac t or l' nit s Unde r Cont ract . N/A Part 1520Z8-001 was not same type of purchase requisition as the one

identified in the QA Manual.CONTRACTORS, VENDORS, OTHERS

Percent of Produc t ion Devoted to Nuc lear Product a 10%UNRESOLVE0 ITEM (S)

NONE

ORGANIZATIONAL CONTACT COMMENTS

Name/ Title W. S. Enright, Director of QA NONEAddress. 2268 South, 3F.70 WestCity / State / zip Salt Lake City, Utah 84119TeleP one. . (801) 973-4'300h

NRC CONTACTS

Assigned Inspec:or R. E. OllerSectinn Chief. D. M. HunnicuttTelephone. (817) 334-2846


h Other Applicable Regulations

,l', 55* " ,.

SmP4

W.

)

C.v-

v5.....

.

<-

, , .

*LXCELCD DEVELOPPENIS, INL., SILVER CRitK, NEW YORK 44n7n coonn ul

i.| Pr 'uld l'rWF0101 tiMbN -

iI '* N t T I % '"! I NO. I '' - 3/31/78 -

r ASRICATICN OF SPENT fl'EL SHIIPI',G i( ) i_s l ', 11 'i" I .''

NV 3/27-31/78 7P-01 h fiv : W. M. Mc u i l l

N''!Aa 1% .iE f |NN JLWP M J I All"N( 5 ) l i CM f uMv! TM! NT S

o w si-;Il u i r ri t t i. < AN!gv o l ;! i l l' I '.I I F ' ACKNOWLE DGE D - IE REVIEW COWLE TE Dr ; t .w t

N/A 1. Contrary to Criterion 2 of Appendix E and ALME Code, Section 111,R a, .r coits in erv b e.1" %A 1140, the Code edition includina addenda used us not the c.andttoryke nter Untts 'e r r,~, t r m t i en .

U/Ak. n- r , r i nit- i na r centrait. one.2. Contrary to Criterion C of Appendix C and the GA Marual, Section 2.2 ,

aster Logs and Transmitta' forns were not ust' Corrective and- vn m I RAc m :; 'ct!.13 4s, ointRs

preventive measures were taken concerning thin iation be' ore thee, r ci.t ot F->dm tion Devoted t o Nulcar t r od + r u 40 end of this inspection.

3. Contrary to Criterion 10 of Appendix E and ASME Code, Settien Ill,NA 41. 3 3, travelers did not include ttc revision or documents, andtra.elers were not used to control process or expin3tions to tcperforced.

ORGANilATIONAL CONTACT 4 Contrary to Criterion 5 of Appendix E and ASME Ccde Sectien IX,r;W 201.1, welding procedures did not provide welders with the necessary

N u c/ Tit le L . A. Brook s , Preside' t directions, or were not properly changed.

Aurco Post Office Box 230 5. Contrary to Criterion 5 of Appendix E and A?f Code, Section III,i t . / <. t a r e / z i p Silver Creek, New York 14136 NC-42 31.2, attachment weld s were not renoved and mark ed properly , and<

w ii pnan, (716) 934-2051 rea. es were not in place which would assure WE cf the area.6. Contrary to Criterion 9 of Appendix E and ASYL Code, Section V, T-041(d)

cleaning solvents were not certified. Corrective and preventiseNRC CONTACTS measures were taken concerning this deviation be' ore the end of this

inspection.

Assigned inspector W. M. MC".eillsectiot. n.iet. D. E. Whitesell D. RESOLVE D ITF H S)Telerh"ne. (817) 334-2544

- ~ - ~ '

The asserbly drawing identified in the Certificate of Compliance is not anaccurato description of the cask.

. (OMvfNTSIN5PECTION10 M. M endix E, and

BASES ) Certi ficate of Conformance ygyg(E693)

|

56

.

'EXCELC0 DEVELOPMENTS, INC., SILVER CREEK, NEW YORK 44070-99900331 i

BACKGROUND INFORMA110N INSPECTION RESULTS

PRINCIPAL PRODUCT (S) DATE(5) 0F INSPECTION INSPECTION REPORT N0. UPDATED 0.. 6/30/78p SPENT FUEL SHIPPING CASKS6/26-30/78 78-02 BY: W. M. McNeill


NUCIFAx STEAM SYSTEM SUPPt.!FRS AND ARCHITECT FNGINFERS ACKNOWLEDGED - IE REVIEW CONTINUING

Reactor Units in Service. N/A 1. Contrary to Criterion 2 of Appendix E and ASPE Code NA-4133.2 theReactor Unit s Under Const ruct ion. N/A program did not provide for suitably controlled conditions particular-Reactor Units Under Contract. N/A

ity for control of cutting oils.

CONTRA'' TOR S , VENDORS, OTHERS 2. Contrary to Criterion 5 of Appendix E and the design specification thethreading of parts was not inspected with the appropriate ar.eptance

Percent of Production Devoted to Nuclear Products 40%criteria.

3. Contrary to Criterion 5 of Appendix E and the QA Manual,11.4.1,inspection reports did not record the gages used in inspection.

ORGANIZATIONAL CONTACT 4. Contrary to Criterion 5 of Appendix E of 10 CFR 71 and ASME CodeSection III, paragraph NA 4134.4, Welding was not being perforTned inccManu M NcMum GW.

. . Pos Of Boddcitv/ State / Zip . ..

Silver Creek, New York 141365. Contrary to Criterion 4 of Appendix E and the QA Manual, 3.2.1.5,

Telephone. . (716) 934-2651 subvendors were not required to provide a QA program consistent withAppendix E.

NRC CONTACTS 6. Contrary to Criterion 7 of Appendix E and the QA Manual, 3.2.1.2, 3.3.1

Assigned Inspector . . W. M. McNeill and 3.2.1.1, documentation did not demonstrate purchased materialsconform to procurement documents. In particular vendors used were

Section Chief. . . . D. E. Whitesellnot qualified, there was na evidence that balsa condomed to the

T.-lepho. . .- (817) 331-2844 purchase order, and valve and safety head Purchase Requisitions didnot contain all information necessary.

7. Contrary to Criterion 10 of Appendix E and QC procedure QC-0211,' 'iSPECTION

O UR 71, A m @ E, a d receiving insoection for safety heads, fire valves, etc.was not prescribed by documented instructions.h Certificate of Confomance*

(6698)(Continued next page)

.

TO 57-

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??T.iV:

44070-99900331EXCELC0 DEVELOPMENTS, INC., SILVER CREEK, NEW YORK

INSPECTION RESULTS (Continuation from previous page)

ACKNOWLEDGED - IE REVIEW CONTIhulNG (continued)

8. Contrary to Criterion 18 and the QA Manual 12.1.1 and 12.3.5scheduled audited were not performed nor were there records ofqualification for uns.' < duled audit personnel.

UNkESOLVED ITEN(S)

NONE

COMMENTS

NONE

r58

.

M

' FISHER CONTROLS COMPANY, MARSHALLTOWN DIVISION, MARSHALLTOWN, 10WA4f4060-99900105


PRINCIPAL PRODUCT (S) DATE(S) 0F INSPECTION INSPECTION REPORT h0. UPDATED ON: 6/12/7Cg NUCLEAR VALVES AND VALVE PARTS6/5-9/78 78-01 BY: J. W. Sutton

NUCLEAR INDUSTRY IN/0LVEMENTDEVIATION (S) FROM COMMITMENTS

NUCt. EAR STEAM SYSTEM SUPPLIERS AND ARCHITECT ENGINEERSACKNOWLEDGED - IE REVIEW COMPLETED

Reactor Unita in Service. ... . N/A Contrary to Criterion V of Appendix B to 10 CFR 50 and Paragraph hCA 4134.5Reactor Units Under Construction. . N/A of Section III and Fisher Administrative Practice Procedure 07-14, RevisionReactor Units Under Contract. . . N/A 0. Customer Service is not indicating the current revisions to the drawingused to conduct a receiving inspection of castings.CONTRACTORS, VENDORS, OTHERS

Percent of Production Devoted to Nuclear Producta 5%UNRESOLVED ITEM (S)

NONE

ORGANIZATIONAL CONTACT COM4ENTS

R. Duke, QA . nagerName/ Title . . . .

...... .. 205 South Center Renewed Certificates of Authorization for "N" and "NPT" expireAddress. November 18, 1980.Marshalltown, Iowa 50158City / State / Zip . . . ...

(515) 754-3483Telephone. .. .....

NRC CONTACTS

. .. J. W. SuttonAssigned Inspector .

D. E. WhitesellSection Chief. . .. ..

Telephone. . . . . . (817) 334-2846...


Other Applicable Regulations

59

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V;Ne,L.'

[-

44075-99900274FORNEY ENGINEERING COMDANY, ADDISON, TEXAS


PRINCIPAL PRODUCT (S) DATE(S) 0F INSPffT ON INSPECTION REPORT NO. UPDATED ON: 6/7/78

N ELECTRONICS - CONTROLS PRODUCTS-

V 5/30-6/2/78 78-01 BY: J. R. Agee

DEVIATION (S) FROM COMMITMENTSNUCLEAR INDUSTRY INVOLVEMENT

NONENUCLEAR STEAM SYSTEM SUPPt.lERS AND ARCHITECT ENrlNEERS

Reactor Units in Service. . . . N/A. . . N/A UNRESOLVED ITEM (S)Reactor Units Under Construction.

Reactor Units Under Contract. . N/A1. The QA and QC manuals are being revised to meet Comitments and to

more 8CCurately describe Current quality assurance practices.CONTRACTORS, VENDORS, OTHERS

2. The initial operating procedures, data sheets. and drawings for the

Percent of Production Devoted to Nuclear Products . 5% prototype madules are being red-lined for final revision of therespective and related documents for use in the manufacturing andtesting of the pmduction modules.

COMMENTSORGANIZATIONAL CONTACT

Name/ Title . . . . . . . E. W. Rewerts, Mgr., QC NONE

Address. . . . . . P.O. Box 189, 3405 Wiley Post RoadAddison, Texas 75001City / State / zip .. ..

(214) 233-1871Telephone. . ....

NRC CONTACTS

Assigned Inspector . . . J. R. AgeeD. M. HunnicuttSection Chief. . ..

(817) 334-2846Telephone. . . ..

INSPECTION 10 CrR 50. Appendix B. andBASES h Other Applicable Regulations

60

.t.

'

4

GENERAL ELECTRIC COMPANY, SWITCHGEAR BUSINESS DEPARTMENT, PHILADELPHIA, PENNSYLVANIA %075-99900219

BACKGROUND INFORMATICN INSPECTION RESULTS

PRINCIPAL PRODUCT (S) DATE(S) 0F INSPECTION INSPECil0N REPORT NO. UPDATED ON: 3/21/78* SWITCHGEAR PRnDUCTS

2/13-17/78 78-01 BY: J. R. Aaee

NUCLEAR INDUSTRY INVOLVEMENT DEVIATION (5) FPOM COMMITMENTS

NUCLEAR STEAM SYSTEM SUePLIFRS AND ARCHITECT FNGINFERS ACKNOWLEDGED - IE REVIEW CONTINUING

Reactor Units in Service. . N/A 1. Contrary to comitment, the QA Manual does not identify or controlReactor Units Under Constructio. N/A significant engineering procedures in use.React er Units Under Cont ract . N/A

2. Contrary to comitment, the QA Manual does not accurately describeCONTRACTORS, VENDORS, OTHERS engineering change procedures actually in use.

Percent of Production Devoted to Nuclear Products 5% 3. Contrary to commitment, the OA Manual does not describe engineeringresponsibilities associated with qualification testing activitiesand the contract requisition engineer's responsibilities.

4. Contrary to comitment, test and equipment records for switchgear weraORGANIZATIONAL CONTACT signed-off and dated by quality appraisal personnel releasing the

equipment for packaging and shipment while r,echanical discrepanciesName/ Title . . C. A. Scott, Mgr., Quality Systems had not been repaired.Address. . . 6901 Elmwood AvenueCity / state / Zip . . Philadelphia, Pennsylvania 19142 5. Contrary to comitment, equipment had been released for pad agine:Telephone. . . (215) 726-2540 and shipment while welds were missing or inadequately placed on

horizontal seismic members of switchgear f rames in contras t toapproved drawings.

NRC CONTACTS

Assigned Inspector J. R. Agee UNRESOLVED ITEM (S)Section Chief. D. M. HunnicuttTelephone. (817) 334-2846 1. Design Tests - qualification testing programs to satisfy contractural

requirements and IEEE-323 are in pronress.

2. Equipnent Service Problems - results of investigations and follow-upCTION relatin to relay screw problems require further review.10 CFR 50, Appendix B, and


(Eontinued r e,t pr;e)

U;- 61|r.~!

.

M

A.iu-.m;s

:/f.L

GENERAL ELECTRIC COMPANY, SWITCHGEAR BUSINESS DEPARTMENT, PHIL/sDELPHIA, PENNSYLVAN!A M4075-99900219(continued)

INSPECTION RESULTS (continuation from previous page)

l'NRES01 " 0 ITEM (5) (continued)

3. Equipment Service - the loose pigtail connections may causedegredation cf the breaker contacts and consequently dect easethe life expectancy of the contacts.

ComENT.

NONE

62

%

$

GENERAL ELECTRIC COMPANY, SMALL AC MOTOR PRODUCTS DEPARTMENT, SAN JOSE, CALIFORNIA 44075-99900339


PRINCIPAL PRODUCT (S) DATE(S) DF INSPECTION INSPECTION REPORT NO. UPDATED ON: 5/23/78h ELECTRIC MOTORS

5/15-16, % 78-01 BY: J. R. AgeeNUCLEAR INDUSTRY INVOLVEMENT DEVIATION (S) FROM COMMITMENTS

NUCl.FAR STEAM SYSTFM SUPP1.IFRS AND ARCHITECT ENGINFERS ACKNOWLEDGED - IE REVIEW COMPLETED

Reactor Units in Service. N/A 1. Contrary to QA Manual requirements, the QA Manual has not been reviewedReactor Units Under Construction. . . N/A and revised on an annual basis.Reactor Units Under Contract. . N/A

2. Contrary to 10 CFR 50, Appendix B, audits were performed by auditorsCONTRACTORS , VEMORS, OTHERS that were not independent of the areas audited.

Percent of Production Devoted to Nuclear Product s 15% 3. Contrary to customer specification requirements, certain companies'products had been purchased before their quality assurance programshad be'n approved.

4. Contrary to internal quality control requirements, calibration cardsORGANIZATIONAL CONTACT were no: maintained on certain instrisnents.

Name/ Title . W. A. Carew, QA Manager 5. Contrary to internal quality control requirements, inspection reportsAddress. . . . 2155 South First Street had not been written against certain instruments.city / State / Zip San Jose, California 95112Telephone. . (408) 925-2861 6. Contrary to 10 CFR 50. Appendix B, with the exception of the inspection

department, quality training is not provided in other departments.NRC CONTACTS 7. Contrary to internal quality control requirements. Hold Tags attached

to certain parts and components throughout the manufacturing areaAssigned Inspector . J. R. Agee were not filled out, as required.Section Chief. D. M. HunnicattTelephone. (817) 334-2846 8. Contrary to internal quality requirements, adequate identification

tags, inspection report (cards), or other means of identificationwere not provided for certain materials in the designated receivinginspection rejected material storage area.

INSPECTIONBASES 10 CFR 50 Appendix B, and 9.) Other Applicable Regulations Contrary to 10 CFR 50 Appendix B, with the exception of the receiving

inspection area, no cournitment had been made for the segregation ofmaterials throughout the manufacturing areas.

(Continued next page)i

63

:7).

ts'7.9ha1 V

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.,

CD

SENERAL ELECTRIC COMPANY, SMALL AC MOTOR PRODUCTS DEPARTMENT, SAN JOSE, CALIFORNIA 44079-99900339n ..n t i n .. a

INSFECIl01 RESULIS gontr ation fro , pre c or, sa w )

.

L*2ESOLVED I TEM (S)

1. Contrary to 10 CFR 50, Appendix B, the QA Manual does not addresscorrective action relative to internal audit findings

2. Contrary to the QA Manual, 10 CFR 50, Appendix B, makes noprovisions for allowance of substitution of customer audits forfulfilling quality assurance audit requirements.

COMMENTS

NONE

64

GOULD, INCORPORATED, SWITCHGEAR OPERATIONS DIVISION, FORT WASHINGTON, PENNSYLVANIA 44075-99900329

BACKGROL: INFORMATION INSPECTION RESULTS

PRINCIPAL PRODUCT (S) DATE(5) OT INSPECTION INSPECTION REPORT NO. UPDATED ON: 8/18/78SWITCHGEAR

8/8-11/78 78-02 BY: J. R. Agee,

NUCLEAR INDUSTRY INVOLVEMENT DFVIATION(S) FROM COMMITMENTS

NUCIIAR STEAM SYSTFM SUPPt.IFRS AND ARCHITECT FNGINFERS NONE

Ecactor Units in Service. N/AReactor Units Under Construction. N/A UNRESOLVED ITEM (S)Reactor Units Under Contract. N/A

NONECONTRACTORS, VENDORS, OTitERS

Percent of Production Devoted to Nuclear Product s . 10% COMMENTS

NONE


Name/ Title . . E. W. Rhoads, QA ManagerAddress. . 501 Office Center Drive,

City / State / Zip . . . Fort Washington, Pennsylvania 19034Telephone. . . (215) 628-7660

NRC CONTACTS

Assigned Inspector . J. R. AgeeSection Chief. . . D. M. HunnicuttTelephone. .. . . (817) 334-2846

ON 10 CFR 50, Appendix B, and3 Other Applicable Regulations

09 65:.~

*#

;% 4

G:c:ei

f5HAYWARD TYLER PUMP COMPANY, DIVISION OF STONE PLATT, EURLINGTON, VERMONT 44030-99900345 {

BACKGR0i]ND INFORMAll0N INSPECTION REStLISCENTRIFUGAL C]RCULATING WATER PUMPS FOR I

DATE (S) Of INSPECTION INSPICTION RIPORT NO. UPDAlt0 ON: 9/5/78PRINCIPAL PRODUCI(5) INDUSTRIAL AND UTILITY APPLICATIONS IN-h CLUDING ASME CLASS 2 & 3 NUCLEAR PUMPS. a/31 9/1/78 78-01 BY: R. L. Brown

_ _

NUCLEAR INDUSTRf INVOLVEMENT DEVIATION (S) FROM COMMITMENTS

NUCl. EAR STEAM SYSTEM SUPPL.!!RS AND ARCHITFCT ENGINFFPS NONE

Reactor Units in Service. . N/A

Reactor Units Under Construction. . . N/A UNRESOLVED liLM(S)Reactor Units Under Contract. . . . - N/A

NONE,CONTRACTORS, vet; DORS, OTilERS

Percent of Production Devoted to Nuclear Products . . 60 COMMENTS

NONE

ORCANIZ/ ;10NAL CON 1 ACT

R. Groeschel. 0A ManagerName/ Title . . .

Post Office Boy 492Address. . . .

city / State /Ilp Burlington, Ven:ent 05401..

Telephone. . . . . (802) 863-2351 Ext. 68

NRC CONTACTS

Assigt.ed Inspector . .. Brow

Section Chief. . .

Telephone. . . . . .

INSPECTION 10 CFR CO, Appendix B, andBASES ) Other Applicable Regulations

66.

.

e

HENRY PRATT COMPANY, AURORA, ILLINDIS44060-99900056

EACKGROUND INFOR.MATION INSPECTION RESULTS

PRINCIPAL PRODUCT (5) DATE(S) Of IN5ffCTION IN5PECTION PEPORT N3. UPDATED ON: 7/5/73% FUTTERFLY VALVES6/27-30/7R 78-01 BY: R. E. Oller

N'JCLE AR INDUSTRY INVOLVEMENTDEVIATION (5) FROM COMMITMENTS

N"7F A R Sl t:AM SYSTIP St I PI IF RS AND ARCHITFCT F%; INFERS NONE

Reactor Units in Service. N/AReac t or l'nt t s reder Coi.s ruction. N/A UNRESOLVED ITEM (S)ke.c r er I:n i t s t'nde r cont ract N/A

No certificates were available to show traceability of reference standardsCONTRACTORS, VE!. DORS, OTHERS used for Calibrating weld rod and flux ovens temperature controllers.HPCo has sent a letter requesting this information. This item remainsPercent at Production Devoted t o Nuc lear Produc t s *unresolved pending HPCo's receipt of the certificates and verification of

*See Comments this condition during a subsequent NRC inspection.

LOMMENTSORGANIZATIONAL CONTACT

* This information unavailable this inspection. To be obtained duringName/ Title A. K. Wilson, QA Manager the next inspection.Address. . . 401 S. Highland AvenueCity / state / zip Aurora, Illinois 60507Telephone. . (312) 84;-4000

NRC CONTACTS

Assigned Inspector . R. E. OllerSection Chief. O. M. HunnicuttTelephone. (817) 334-2846

INSPECTIONBASES 10 CFR 50 Appendix B, and


s ,0 67.~

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v4CH'?.

NCO

44060-99900086HOPKINSONS LIMITED, HUDDERSFIELD, ENGLAND

IMSPECT10N of SULTSBACKGROUND INFORMMION

DATE(S) Or INStitt10N INSPECTION REPORT NO. UPDATED ON: 7/5/78PRINCIFAL PRODUCT (S)

N NUCLEAR VALVES6/19-22/78 78-01 BY: 1. Barnes

V

DFVIATION(S) FROM COMMITMENTSNUCLEAR INDUSTRY INVOLVEMENT

ACKNOWLEDGED - IE REVIEW COMPLETEDNI'CI EAR STE AM SYSTFM S11 ppt.t FHS AND ARrHI1FOT FNGIM ERS

N/A 1. Contrary to Criterion IX of 10 CFR 50, Appendix B, Section III, andReact or t' nit s in Service. N/A Section IX of the ASME Code, a hardfacing welding procedure specifica-Reac t or l'n it s l'nder Const r uc t ion. N/A tion was observed to permit a change in torch type and decrease inReac t or Unit s i nds r Cont ract . preheat, outside of the qualified ranges referenced by the supporting

procedure qualification record.CONTRACTORS, VE!m0RS, OTHERS

2. Contrary to Criterion V of 10 CFR 50, Appendix B, and Quality Control*

of Production Devoted to Nuclear Product s Procedure No. N9-3, Revision 2, the required heat treatment timePer(ent See Commentsafter hardf acing in a certain furnace run was exceeded by more than257, without preparation and submittal of a deviation report to theMaterial Review Committee.

ORGANI7ATIONAL CONTACT 3. Contrary to Criterion IX of 10 CFR 50, Appendix B, and Section III ofthe ASME Code, Quality Control Procedure No. N6-1, Revision 3, requiredR. Barrow, QA Manager weld impact test specimens for procedure qualifications to be locatedName/Titic

Address. .Britannia Worts, P. O. Box 827 at the surface of the test assembly.

City / State / zip Huddersfield, EnglandHuddersfield (STD 0484) 22171Telephone. 4. Contrary to Criterion XII of 10 CFR 50, Appendix B, and NA 4133-12 of

the ASME Code, Section III, the calibration procedure for furn3ceinstrumentation did not either define required accuracy limits to

NRC CONTACTS be maintained or make provisions for consideration of effects ofinstrument error on previously heat treated materials.

I . Ba rnesAssigned InspectorSection Chief. D. M. Hunnicutt

5. Contrary to Criterion IX of 10 CFR 50, Appendix B, and Quality Control(817) 334-2846 Procedure No. N9-2, Revision 8, a certain furnace calibration wasTelephone.

performed without using the required worst expected typical furnateload.

INSPECTION 10 CFR Co, Appendix B, and 6. Contrary to Criterion XVIII of 10 CFR 50, Appendix B, and Section 13.0BASES Other rp'icable Regulations of the QA Manual, certain internal audits were not performed at the

specified frequency. (Coritinued next pace)-r

68

HOPKINSONS LIMITED, HUDDERSFIELD, ENGLAND 44060-99900086(continued)

INSPECTION RESULTS (Continuation from presious page)

ACKNOWLEDGED - IE REVIEW COMPLETED (continued) COPt4ENTS

7. Contrary to Criterion VII of 10 CFR 50 Appendix B, and This infonnation unavailable this inspection. To be obtained*

Customer Specification Number 8791-G-QA-1, a control copy of a during the next inspection.lower tier supplier's Quality Assurance Program had not beenrequested, reviewed, or approved.

8. Contrary to Criterion VII of 10 CFR 50, Appendix B, and Section3.0 of the QA Manual, welding material utilized for Code applica-tions was purchased from a vendor who had not been approved.

9. Contrary to Criterion XII of 10 CFR 50 Appendix B, and Section8.0 of the QA Manual, a certain master gage used for calibrationof surface plates had not been calibrated.

10. Contrary to Criterion XVI of 10 CFR 50, Appendix B, andNCA-4134.16 of the ASME Code, Section III, with the exceptionof nonconfonning materials, the required measures relative tocorrective action had not been established.

UNRESOLVED ITEM (S)

1. Use of subjective wording in QA Manual, relative to internalaudits, not consistent with Criterion XVIII of 10 CFR 50,Appendix B, and NCA-4134.18 of the ASME Code Section III.

2. QA Man al definition of equipment scope in calibration programunclear with respect to requirements of Criterion XII of10 CFR 50 Apper 4x B, and NCA-4134.12 of the ASME Code,Section III.

3. Segregation of nonconfonning materials detected duringmanufacturing not addressed by QA Manual, as required byCriterion XV of 10 CFR 50, Apperdix B, and NCA-4134.15 of theASME Code, Section III.

69

Q,.

'np:.aN

M'm.

.

mg.NG3

44070-99900342LAKESIDE BRIDGE AND STEEL COMPANY, MILWAUKEE, WISCONSIN

BACKGROUND INFORMATION INSPECTION RESULTSI

PRINCIPAL PRODUCT (S) CONTAINMENT SYSTEM COMPONENTS DATE(S) 0F INSPECTION INSPECTION REPORT NO. UPDATED ON: 7/11/78

h AND COMPONENT SUPPORTS 6/26-30/78 78-01 BY: L. E. Ellershaw

DEVIATION (S) FROM COMMITMfNTSNUCLEAR INDUSTRY INVOLVEMENT

NUCLEAR STEAM SYSTEM SUPPLIERS AND ARCHITECT ENGINEERSACKNOWLEDGED - IE REVIEW COMPLETED

Reactor Units in Service. - N/A 1. Contrary to 0A Manual, Section 9.0, and Criterion XV of Appenu n 6 taN/A 10 CFR 50, certain nonconforming parts were not identified with hold

Reactor Units Under Construction.Reactor Units Under Contract. .. N/A tags.

2. Contrary to ASME Code NCA-4134.16, and Criterion XVI of Appendix B to10 CFR 50, the QA Manual does not address corrective action program

CONTRACTORS, VENDORS, OTNERS requirements being extended to the performance of a subcontractor's90% corrective action measures.Percent of Production Devoted to Nuclear Product s . 3. Contrary to QA Manual Section 10.0, and Criterion VIII of Appendix B

to 10 CFR 50, a weld rod holding oven contained more than one type ofweld rod and two types of weld rod were intermingled in one section ofthe oven.

4. Contrary to QA Manual, Section 10.0, Weld Procedure Qualification No.ORGANIZATIONAL CONTACT No. 5,4.2. , and Criterion IX of Appendix B to 10 CFR 50, a heat treat

Name/ Title . . .E. Kasdorf, Exec., Vice President chart, which supported the qualification of a SMAW procedure requiring5300 N. 33rd Street PWHT, could not be located.

Address. . . . ..

City / State / Zip . .. Milwaukee, Wisconsin 53209 5. Contrary to QA Manual, Section 7.0, Manufacturing Process Sheet, Proce-

Telephone. . . . . . (414) 462-5900 dure No. 1.15, and Criterion V of Appendix B to 10 CFR 50, revisionnumbers to Weld Procedure Specifications and nondestructive examinationprocedures are not recorded on the manufacturing process sheets eitherbefore or after implementation of the procedur?.

NRC CONTACTS

L. E. Ellershaw UNRESOLVED ITEM (S)Assigned Inspector . .

Section Chief. . . .. D. M. Hunnicutt(817) 334-2844 The QA Manual does not address, nor does it reference procedures which

Telephone. . . . .. address, > scrrective action program as required by ASME, NCA 4134.16, andCriterion XVI of Appendix B to 10 CFR 50. There is an internal procedureaddressing corrective action and the QA Manual is being revised to addressand/or reference that procedure.

CTION 10 CFR 50 Appendix B, and

) Other Applicable Regulations COMMENTS

NONE-

70.

.

LIMITOROUE CORPORATION. LYNCHBURG, VIRGINIA44070-99900100

BACKGROUND INFORMATION INSPECTION RESULISPRINCIPAL PRODUCT (S)

DATE(S) Of INSPECTION INSPECTION REPORT NO. |UPDATEDON: 6/20/78N VALVE OPERATORSV6/13-16/78 78-01 BY: R. E. Oller

NUCLEAR INDUSTRY INVOLVEMENTDEVIATION (S) FROM COMMITMENTS

NUCLEAR STFAM SYSTEM SUPPLIFRS AND ARCHI1FCT ENGINEFRSACKNOWLEDGED - IE REVIEW COMPLETED

Reactor Units in Service. N/A 1.Reactor Units Under Construction. N/A Contrary to Criterion XVIII of Appendix B to 10 CFR 50 and paragraphReactor Units Under Contract. N/A 1.B.6 of the QC Manual, the QC system area K, " calibration system,"

was not audited on a semiannual basis.2.CONTRACTORS, VENDORS, OTHERS Contrary to Criterion XVIII of Appendix B to 10 CFR 50 and procedure

QCP-14, Revision 2, with regard to the report of internal auditconducted on January 9,1978, audit checklist nonconfonning itemsPercent of Production Devoted to Nuclear Products *

A.6, E.3, and E.4 were not submitted to the QC manager, nor wereSee com.See Comments Audit Deficiency Notifications issued by QC for these items.

3. Contrary to Criterion XII of Appendix B to 10 CFR 50 Section 8.Dof the QC Manual, and Procedure QCP-7.D. Revision 2, calibration

ORGANIZATIONAL CONTACT requirements were not fully implemented for five (5) differentmeasuring devices.

Name/ Title .. W. Vignola, QC ManagerAddress. . . 5114 Woodall Road

UNRESOLVEDITEME'City / state / zip Lynchburg, Virginia 24502Telephone. (804) 528-4400

NONE

NRC CONTACTSCOMMENTS

Assigned Inspector R. E. OllerSection Chief. . D. M. Hunnicutt * This informath.. umvailable this inspection. To be obtained duringthe next inspection.Telephone. . (817) 334-2846

" "BAS S 10 CFR 50, Appendix B, and

Other Applicable Regulations

712P;

'n%

4 n,

LO.) 7.:

-,

' :.,.

qCD

44050-99900313MURDOCK, INCORPORATED, COMPTON, CALIFORNIA

BACKGROUND INf0RiiAT10N INSPECTION RESULTS

DATE(S) OF INSPECi10N INSPECTION REPORT NO. UPDATED ON: 9/7/78PRINCIPAL PRODUCT (S)

PERSONNEL / EQUIPMENT AIR LOCKS 8/28-31/78 78-01 BY: V. H. Hunter

DEVI ATION(S) FROM C0tHITMENTSNUCLEAR INDUSTRY INVOLVEMENT

NUC1. EAR STEAM SYSTDI SUPPLIERS AND ARCHITECT ENGINEERS-ACKNOWLEDGED - IE REVIEW COMPLETED

. . .. N/A 1. Contrary to the requirements of Appendix B to 10 CFR 50 and the ASMEReactor Units in Service.

. . . . . N/A accepted QA Manual, an annual inventory / accounting of pressure gagesReactor Units Under Ccnstruction.Reactor Units Under Contract. . . . . N/A and measuring equipment was never performed.

2. Contrary to the requirements of Appendix B to 10 CFR 50 and the ASMECONTRACTORS, VE!@ORJ, OTHERS accepted QA Manual, a sumary report of nonconformities including

30% trend analysis was never prepared and submitted.Percent of Production Devoted to Nuclear Products

UNRESCLVED ITEM (S)

NONEORGANIZATIONAL CONTACT

W. B. Parker, QA ManagerName/ Title . .. .. ..

Address. ........ . 15800 South Avalon Boulevard NTSCompton, California 90220

city / State / Zip . ......

...... .. (213) 770-0220 NONETelephone.

NRC CONTACTS

V. H. HunterAssigned Inspector . . ...

D. E. WhitesellSection Chief. .. ....

(817) 334-2846Telephone. ........

INSPECTIONOtherApplicabendixB,and10 CFR 50, Ap

le RegulationsBASES

;,

72 -

- NL)NDUSTRIES, NUCLEAR DIVISION, Wil21NGTON, DELAWARE 44070-99900090


PRINCIPAL PRODUCT (S) DATE(S) Of INSPECTION INSPECTION REPORT NO. UPDATED ON: 4/28/78

N SPENT FUEL SHIPPING CASKSV 4/24-28/78 78-01 BY: W. M. McNeill


NUrl. EAR STEAM SYSTFM SUPPL.IFRS AND ARCHITECT ENGINFERS ACKNOWLEDGED - IE REVIEW COMPLETED

Reactor Units in Service. . .. N/A 1. Contrary to Criterion II the program did not provide for control ofReactor Units Under Construction. . . N/A components to an extent consistent with their importance to safety.Reac t or Units Under Cont ract. . N/A 2. Contrary to Criterion V and NL QA Manual 06-1 shop welding was not

accomplished in accordance with procedures.CONTRACTORS, VENDORS, OTHERS 3. Contrary to Criterion XII and NL QA Manual 10-1. welding machines

did not have voltage metering properly controlled and calibrated.75% 4. Contrary to Criterion XII and ASME Code. hydrostatic testing gages werePercent of Production Devoted to Nuclear Products . not calibrated prior to testing.

5. Contrary to Criterion V and MIL-STD-7678, water being used for hydro-static tests was not being analyzed to verify that it met Grade Bwater requirements.

ORGANIZATIONAL CONTACT 6. Contrary to Criterion III and the NL QA Manual.1ssuance of documentsand drawings was not controlled.

Naw/ Title . . .G. N. Dixon. QA/QC ManagerFoot of West Street

Address. . . . . . . Wilmington. Delaware 19801 UNRESOLVED ITEM (S)city / state / zip . . .

Telephone. . . . . (302) 656-1661 NL will obtain records that will demonstrate welding gas quality.

NRC CONTACTSCOM ENTS

. .W. M. McNeillAssigned Inspector

Se= tion Chief. . . D. E. Whitesell NONE

Telephone. . . . . (817) 334-2844

" " 10 CFR 50. Appendix B. andBA

% Other Applicable Regulations

73

CD

,._.

&

b

b0:M*s,9

5*)D. G. O'BRIEN, INCORPORATED, SEABROOK, NEW HAMPSHIRE 44075-99900326


PRINCIPAL PRODUCI(S) DATE(S) 0F INSPECTION INSPECTION REPORT NO. UPDATED ON: 6/15/78ELECTRICAL PENETRATION ASSEMBLIES

6/6-9/78 78-01 BY: W. F. Foster

NUCLEAR INDUSTRY INVOLVEMENT DEVIATION (S)FROMCOMMITMENQ

NL!CIFAR STE AM SYSTEM St'PPI.lFRS AND ARCHITECT ENI:INFFRS ACKNOWLEDGED - IE REVIEW COMPLETED

N/A 1. Contrary to Criterion VI of Appendix B to 10 CFR 50 and paragraph 1.Reactor Unit s in Service. . . .

N/A of Engineering Policy and Procedure No. EPP-10. Revision B. datedReactor Units l'nder Const ruct ion. . .

N/A May 16, 1978, Test Procedures had e.ot been distributed to Production,Reactor Units l'nder Contract. .... .

and Glass Sealing Procedures had not been distributed to QualityCONTRACTORS, VENDORS. OTTERS Control, as indicated in the distribution list.

Percent of Production Devoted to Nuclear Products . 40% 2. Contrary to Criterion VI of Appendix B to 10 CFR 50 and paragraph VIII.of Engineering Policy and Procedure No. EPP-3 Revision H datedMarch 24, 1978, the following obsolete procedures had not been removedfrom the reference books and replaced with the revised document:

ORGANIZATIONAL CONTACT a. Marking Procedure No, MP-MK-213. Revision N/C (Revision A had beenR. B. Henderson, Manager released on March 22,1978).

Nase / Title . . ... .. Engineering and Quality AssuranceOne Chase Park b. Test Procedure No. QA-TM-193. Revision A (Revision B had beenAddress. . . . . .

.. . Seabrook, New Hampshire 03874 released in May 1977).City / State / Zip .Telephone. (603) 474-5571. .. .

c. Test Procedure No. TP-LK-114. Revisions B and C (Revision D hadbeen released in November 1977). Note: Revision 0 was also at

NRC CONTACTS the test station.

Assigned Inspector . . . . W. E. Foster 3. Contrary to Criterion VI of Appendix B to 10 CFR 50 and paragraph 1.3Section Chief. . .. D. M. Hunnicutt of Quality Control PMcedure ho. SS-QC-118. Revision D. datedTelephone. . . . . .. (817) 334-2844 February 1.1978. Quality Control had not approved sheets 2 and 3

of Process Sheet No. 233-9. Revision B, dated May 18, 1978, forDrawing No. R31E5029G03. Module and Flange Assembly. S/N 7693E.

INSPECTION 4. Contrary to Criterion VI of Appendix B to 10 CFR 50, paragraph V. A.10BASES 10 CFR 50. Appendix B and of Manufacturing Procedure No. MPP-6, Revision C, dated May 22. 1978,) Other Applicable Regulations and sheet 223. Item 4., of South Carolina Electric and Gas Conpany


74

.

.-

D G. O'BRIEN, INCORPORATED, SEABROOK, NEW HAMPSHIRE 44075-99900326

(continued)INSPECTION RESULTS (Continuation frce previous page)

ACKNOWLEDGED - IF REVIEW COMPLETED (continued)

Purchate Order No. SN-10429-SR, dated October 7, 1977, released Example: Timers, Flowmeters and Regulators in the Glass SealingDG0 Purchase Order No. 69006-20 Revision A, dated February 14 Area.1978, had not been initialed and dated by Quality Assurance.

7. Contrary to Criterion XII of Appendix B to 10 CFR 50 and para-5. Centrary to Criterion XII of Appendix B to 10 CFR 50 and paragraph 4.5 of Quality Assurance Procedure No. QA-CP-100,

graph 4.3 of Quality Assurance Procedure No. QA-CP-100, Revision Revision F, dated April 28, 1978, calibration stickers forF, dated April 28, 1978, a recall system had not been used for two (2) thermometers, located on ovens in the Electrical Assectlycalibration of all Quality Control gages on a fixed frequency, as Area, did not bear date of calibration and date of next cali-

illustrated by the following examples: bration,

a. The Calibration Card for Micrometer, DG0 No. D807 shows a 8. Contrary to Criterion XII of Appendix B to 10 CFR 50 and para-calibration frequency of six (6) months with: " Calibration graph 4.5 of Quality Assurance Procedure No. QA-CP-100,Due: June 7, 1977 Calibration Date: December 1, 1977." Revision F, dated April 28, 1978, in-house calit' ration results

had not been recorded on calibration cards,

b. The Calibration Label on Dial Indicator, No. D80 shows:" Calibration Date: November 4, 1977, Calibration Due: 9. Contrary to Criterion XII of Appendix B to 10 CFR 50 andMay 4, 1978." paragraph 4.10 of Quality Assurance Procedure No. QA-CP-100,

Revision F, dated April 28, 1978, employee owned gages hadc. The Calibration Label on Dial Indicator, No. D34 shows: not been maintained under the calibration system inasmuch as

" Calibration Due: April 4, 1978." Personal Tool Calibration Records indicated past due calibrations

and no results of calittation.

d. The Calibration Label on the case for Micrometer No. D216shows: " Calibration Date: March 3, 1977, Calibration Due: 10. Contrary to Criterion XI of Appendix B to 10 CFR 50, para-September 4, 1977." graph 5.3 of Section 1.0, Revision 0, dated October 24, 1975,

of the Nuclear Quality Assurance Manual, and paragraph 3.1e. The Calibration Label on Surface Plate S/N 130411 (Do All of Quality Assurance Procedure No. SS-QA-144, Revision B.

S/N 1304-1) shows " Calibration Date: August 23, 1972, dated May 24, 1978 Job Order Review Foms had not been pre-Due Date: 1 year.' pared to designate the test doctsnent and revision number to be

used for each test operation for the Duke Power Company and6. Contrary to Criterion XII of Appendix B to 10 CFR 50 and para- South Carolina Electric Gas Company purchase orders.

graph 4.4 of Quality Assurance Procedure No. QA-CP-100, RevisionF, dated April 28, 1978, all gages did not bear either a cali- 11. Contrary to Criterion X of Appendix B to 10 0FR 50, paragraphsbration sticker or a color dot code or a usage calibration card 6.1 and 6.3 of Section 8.0, Revision 0, dated October 24,

designating point of next calibration, RM. only, Manufacturing 1975, of the Nuclear Quality Assurance Manual, the lot numberControl only, etc.


T 75

bs. .

T

0.;,p

D. G. O'BRIEN, ',NCORPORATED, SEABROOK, NEW HAMPSHIRE 44075-99900326 2(continued) d

00INSPECTION RESULTS (Continuation from previous page)


(P/C No.) had not been listed on Process Sheet No. 221-10, datedJanuary 23, 1978, reviewed and accepted by Quality Assurance priorto release for assembly of socket contact springs to the socket.

UNRESOLVED ITEM (S)

Process Sheets do not reference all test procedures applicable to aparticular item. Procedures referenced in Process Sheets, in turn,reference other procedures; however, no infonnation is providedregarding current revisions of these secondary procedures.

COPNENTS

NONE

76.

.

/

.. _

'

FACIFIC PUMPS, DIVISION OF DRESSER INDUSTRIES, HUNTINGTON PARK, CALIFORNIA ifiO30-99900063,


PRINCIPAL PRODUCT (S) DATE(5) Of INSPECTION INSPECTION REPORT NO. UPDATED ON: 8/16/78

N ELE /R PUMPS 8/7-9/78 78-02 '3Y: H. W-:RcLerds-- w .ww-=m-

--- -


NUCLEAR STEAM SYSTEM SUPPLIERS AND ARCHITECT ENGINEERS N0 rte

..... ... . .. N/AReactor Units in Service.Reactor Units Under Construction. . . ... N/A UNPESOLVED ITEM (5)Reactor Units Under Contract. . .. .. . . N/A

ZHECONTRACTORS, VENDORS, OTHERS

Percent of Production Devoted to Nuclear Products . . 05% COPHENTS

'NONE

'f

'

ORGAN!ZATIONAL CONTACT ,

Name/ Title . . . . D. J.;Moyer, QA Manager....

. 1515 Bickett Street _ 'Address. ... ..

City / State / Zip . .. Huntir.gten Park. California 90255

,

.... . (213) 588-220JTelephone. <

. . _

1

NRC CONTACTS|

Assigned Inspector . . . . . H. W. RoberdsSection Chief. P. M. HunniCett......

. . (817) 334-2844Telephone. ......

INSPECTION 10 CFR 50, Appendix 8. andBASES ) Other Applicable Regulations

773

asa's

v.C~~?

PAUL-MUNROE HYDRAULICS, INC., ORANGE, CALIFORNIA 44070-99900337fG3


PRINCIPAL PRODUCT (S) PIPE SUPPORT SNUBBERS, LARGE EQUIPMENT DATE(S) 0F INSPECTION INSPECTION REPORT NO. UPDATED ON: 6/13/78N SNUBBERS, VALVE CPERATORS. FUEL RACKV DAMPERS. 6/5-9/78 78-01 BY: R. L . Brown


NUCLE AR STEAM SYSTD4 St'PPLIERS AND ARCHITECT ENGINFFRS NONE

..... .... . .. N/AReactor Units in Service.N/A UNRESOLVEDITEM(5)Reactor Units Under Construction. . . .....

Reactor Units Under Contract. N/A............


Percent of Production Devoted to Nuclear Products . .. 25% CO* NENTS

NONE


Name/ Title . . . . . . William M. Warner QA Manager...

. . . . . . . . . 1701 W. Sequota AvenueAddress.City / State / zip . . . . .. Orarige, California 92568Telephone. . . . . . . .. (714) 633-9600

NRC CONTACTS

Assigned Inspector . . . . R. L. Brown.

Section Chief. . . . . . . . D. M. Hunnicutt(817) 334-2844Telephone. . . . . . . ...

INSPECTIONBASES

10 CFR 50, Appendix B, and


78

.

I

.

-

PITTSBURG4-DES MOINES STEEL COMPANY, WESTERN DIVISION, PROV0, UTAH 44055-99900242

BACKGROUND INFORMTION INSPECTION RESULTS

PRINCIPAL PRODUCT (S) CLASS 1, 2, 3 AND MC VESSELS AND CtLSS DATE(S) 0F INSPECTION INSFECTION REPORT NO. UPDATED On: 6/28/782 AND 3 TANKS

6/19-23/78 78-01 BY: J. W. Sutton


NUCLEAR STEAM SYSTEM SUPPLIERS AND ARCHITFCT ENGINFERS ACKNCMLEDGED - IE REVIEW COMPLETED

Reactor Units in Service. . . . N/A Contrary to Criterion VI!! of Appendix B to 10 CFR 50, NCA 4134.8 ofReactor Units Under Construction. .. .. . N/A Sectiot- III of the ASME Code, and Paragraph 4.6.5 of the accepted QAReactor Units Under Contract. . .... . N/A Mantal, material identification was not maintained on a Component part,

as required by procedures.CONTRACTORS, VENDORS, OTHERS

Percent of Production Devoted to Nuclear Products . . 50%UNRESOLVED ITEM (S)

NONE

ORGAN!ZATIONAL CONTACT COPHENTS

D. Brown Western Div. QA Manager NONEName/ Title . . . . ...

Address. . . . .. .. Post Office Box 1447. .... Provo Utah 84601City / State / Zip .

(801) 373-8150Telephone. . ......

NRC CONTACTS

Assigned Inspector . J. W. Sutton....

Section Chief. . . . . . . D. E. Whitesell(817) 334-2846Telephone. . . . . ...



*:n 79- -

:;,< . ,

's.2%

3

9

C3m%

PULLMAN PCWER PRODUCTS, DIVISION OF PULLMAN, INCORPORATED, PARAMOUNT, CAllFORNIA I 44020-99900077 $..

BACKGROUND INFORMAll(A INSPECTION RESULTS

PRINCIPAL PRODUCT (S) DATE(S) OF INSPECTION INSPECTION REPORT NO. UPDATED ON: 6/29/78

N NUCLEAR PIPING ASSEMBLIESV 6/19-22/78 78-01 BY: H. W. Roberds


NUCI. EAR STEAM SYSTEM SUPP1.lERS AND ARCHITECT ENCL *:lERS ACKNOWLEDGED - IE REVIEW CEEPLETED

... ..... . . N/A 1. Contrary to Criterion XIII of Appendix B to 10 CFR 50 and Paramountacactor Units in Service.Reactor Units Under Construction. .. . . . N/A Shop Standard VII-12, it could not be ascertained that a grinding

.. .. . . N/A wheel being used on stainless steel had not been previously used onReactor Units Under Contract. carbon steel.CONTRACTORS, VFADORS, oTFERS 2. Contrary to Criterion XII of Appendix B to 10 CFR 50 and Pullman Power

Products Procedure JS-150, a Beckman conductivity rater was not cali-Percent of Production Devoted to Nuclear Products 95% brated, as required...

3. Contrary to Criterion V of Apendix B to 10 CFR 50 and ASME, Section III,Article NA-8419, a stainless steel pipe subassembly had been stampedeven though the data report forins had not been completed.

4. Contrary to 10 CFR 50 Appendix B, and Section X of the QA Manual, aORGANIZATIONAL CONTACT penetrant inspection identified as ' Hold for Co. Inspection' had not

been performed, and the work had proceeded beyond the identifiedName/ Title . . . . . . . . . S. L. Engler, QA Manager t'old points.

14507 South Paramount Boulevard 5. Cor,trary to Criterion V of Appendix B to 10 CFR 50 and subsectionAddress. . . . ......

Paramount, California 90723 NB-4622.1 of ASME, Section III, Pullman Power Products FabricationCity / State / Zip . . . ...

(213) 531-1370 Drawings F-13. F-14 F-15, and F-16 for Job No. 2789 did not specifyTelephone. . . . ...

as preheat or post weld heat treatment for a carbon steel piping sub-assembly with a carbon content greater than 0.30 percent, as required.

NRC CONTACTSUNRESOLVED ITEM (S)

H. W. RoberdsAssigned Inspector . ....

Section Chief. . D. M. Hunnicutt Contrary to 10 CFR 50, Appendix B, and Pullman Power Products Procedure... ..

(B17) 334-2846 X-15P, a code plate had been issued, stamped and attached, and the FinalTelephone. . . . .. ...

Inspector had not signed off the process sheet for the ID&OD weld inspec-tion. This item is unresolved pending the ASME subcomittee III decision.

COPNENTSINSPECTION 10 CFR 50, Appendix B, andBASES ) Other Applicable Regulations NONE

80

PX ENGINEERING COMPANY, INC., WOBURN, PASSACHUSETTS 44070-99900204


PRINCIPAL PRODUCT (5) PRESSURE VESSELS, FUEL RACKS, COMPONENTSDATE(S) 0F INSPECTION INSPECTION REPORT NO. UPDATED ON: 7/17/78SUPPORTS, LINERS AND HEAT EXCHANGERS

7/13-14/78 78-01 SY: R. L. Brown

NUCLEAR INDUSTRY INVOLVEMENT DEVIATION (S) FRGM COMMITMENTS

NUCLFAR STEAM SYSTEM SUPPLIERS AND ARCHITECT ENGINEERS NONE

Reactor Units in Service. .. . N/A.... . . N/A UNRESOLVEC ITEM (S)Reactor Units Under Construction.

Reactor f| nits Under Contract. .... . . N/ANONE

CONTRACTORS, VENDORS. OTHERS

Percent of Production Devoted to Nuclear Products . . 95% COMMENTS

NONE


. . ... Nonnand R. Trudel QA ManagerName/ Title .Address. 225 Merrimac Street. . . .......

city / State / zip . Woburn, Massachusetts 02810......

(617) 935-6900Telephone. . . .......

NRC CONTACTS

Assigned Inspector . R. L. Brown....

Section Chief. . . . . . . . D. M. HunnicuttTelephone. . . . . . . . (817) 334-2844. .

INSPECTIONBASES

10 CFR 50, Appendix 8 and


|

8170:>Du, $~n

r4

1:y.

m

(LRHINE-SCHELDE-VER0LME APPARATENBOUW a,v., ROTTERDAM, THE NETHERLANDS 44040-99900039

BACKGROUND INFORMATION 'NSPECTION RESULIS

! DATE(S) 0F INSPECTION INSPECTION REPORT Na- UPDATED ON: 6/16/78PRINCIPAL PRODUCT (5)

N NUCLEAR VESSEI.SV 6/12-16/78 78-01 BY: 1. Barnes


NUCIFAR STEAM SYSTEM SUPPLIERS AND ARCHITECT ENGINEERS ACKNOWLEDGED - IE REVIEW COMPLETED

N/A 1. Contrary to Criterion V of 10 CFR 50, Appendix B, and Welding ProcedureRe -tor Unit s in Service. . ... ...

.... .. N/A Specification, PS-36.23. Revision 1 shielded metal arc first layerReactor Units Under Construction.Reactor Units Under Contract. ... . ... . N/A overlay cladding was observed being perfomed at an amperage value

above the pemitted range.CONTRACTORS. VENDORS OTHERS

2. Contrary to Criterion IX of 10 CFR 50, Appendix B, and Section IX ofPercent of Production Devoted to Nuclear Products . .. 40% * the ASME Code, two (2) cladding welding procedure specifications were

observed to Demit changes to interpass tenperature and arc voltageoutside of the ranges indicated by the referenced supporting procedurequalification records.

ORGANIZATIONAL CONTACT 3. Contrary to Criterion V of 10 CFR 50, Appendix B, and Quality ProcedureNo. 9.08.03(E), Inconel electodes observed to be present in one (1)

Name/ Title .. . . M. Lodder, Manager, QA holding oven and one (1) baking oven were not identified as beingAddress. . . .. .

P. O. Box 221. Heijplaatstraat 4 present on the outside of the ovens.City / State / Zip -.

.. Rotterdam, The NetherlandsTelephone. . . . . 010-872874 4. Contrary to Criterion IX of 10 CFR 50, Appendix B, and paragraph

4.3.3.1.a. in Customer Specification 21A9477, Revision B, the ferritelevel in two (2) cladding beads was observed to be below the specified

NRC CONTACTS minimum value.

. . I. Barnes 5. Contrary to Criterion IX of 10 CFR 50, Appendix B, and Attachment 1.01,Assigned Inspector .Section Chief. .. . D. M. Hunr.icutt Revision 2 to bending and foming Procedure No. PS-51.21. Revision 2Telephone. . . . .. (817) 334-2846 the required qualiflCation of the foming process had not been

perfomed.

6. Contrary to Criterion XVIII of 10 CFR 50, Appendix B, paragraph NCA-JNSPECTION

4134.18 of the ASME, Section !!! Code, and Chapter 14 of the QA Manual,10 CFR 50, Appendix B, and certain internal audits were not perfomed at the specified frequency.

RASES ) Other Applicable Regulations


82

. _ _ __ ____

.

-

RHINE-SCHEl.DE-VER0lliE APPARATENBOUW s.v., ROTTERDAM, THE NETHERLANDS 44040-99900039(continued)

- INSPECTION RESULTS (Continuation from previous page)


7. Contrary to Criterion II of 10 CFR 50. Appendix B paragraphNCA-4134.2 of the ASME Section III. Code, and Chapter 14 of theQA Manual, the yearly audit of the QA activities of all depart-ments was not performed in the year 1977.

8. Contrary to Criterion VII of 10 CFR 50. Appendix B. paragraphNCA-4134.4 of the ASME. Section III. Code, and Chapter 5 of theQA Manual, the Approved Nuclear Vendors List had not beenupdated to remove vendors no longer considered qualified.

.

9. Contrary to Criterion XV of 10 CFR 50. Appendix B. and paragraphNCA-4134.15 of the ASME. Section III. Code, the QA Manual did notaddress segregation of nonconfoming materials in the receivinginspection area.

UNRESOLVED ITEM (5)

1. Use of subjective wording in Chapter 14 of the QA Manual relativeto corrective action.

,

'2. Instrument calibration control program written in Dutch.

COMMENTS

Rotterdam Nuclear was renamed in November 1977, as RSV Zware (Apparatenbouw b.v. (Rotterdam Heavy Equipment).

Percentage applicable to production devoted to U. S. Nuclear*

vessels..

E

WREhe -

83

,

N:.

.LA

O

{w. , . , -

&,.-WW

Ng~,

ROSEMOUNT, INCORPORATED, EDEN FRAIRIE, MINNESOTA 44075-99900271

EACKOR0!AD i'. 0R'' Ail 01 !NSPECT!tJ, Ti.IS''JE CTION PEFCPT NO. UFDATED ON- 8/4/78FRINCIPAL r- D L i(;; CATE(5) CF : LN .:

% INSl?L"ENTATION A'40 CONTV'L: MOCUCTi-

7 '?4 -2 6 / 7'' 7o-01 BY- J. R. Moe_ _]

N'JCLEAR I W TEY I V.0l V Ewf ST N g:Ar m ,(s) r p ;M yw!TurNT54

P P !.16 8 s'.D A F ' n l i tTT 'I' r ! R C ; ! a m ' f( {[' . '{ ;[ .g ? g w up,[7{gYTl f AF ,IleM !. Y '. ' EM (

| Arpendix B and QA Manual . critical production materials}u/ 't

Ontrs *nR.a c t o r t'n t t < in ce rsinn en e rad intemingled with other production naterials withoutFeactor Units : nir cow r t : a.

N/t . "* 4 fic a ti3n of varialsFeactor Units innt iontra .

ccNTucTon , VU. DOM , ONM U*,;ESCLvtl 1EM)

P.rc ut ;'r doc t ion "evoted to ',ciear Freducts 7; Pesultant from contract chances fnr redesign of line of transmitters.

resision of final test qualifications specification is incomplete.

_F_O P ENTS

ORGANI?ATIONAL CONTACT N0 ale

Nar,e/ Title F. J. Dakley. Quality Assurance "gr.

Address. 12001 West '. tn StrNtCity / state / zip Eden Prairie, "irnesota 55343

Telephone. (612) 941-55f~

NRC CONTACTS

U igned Inspector J. R. AgeeSee len Chief. D. u_ Ho .r.t c att

Te1 shone. (OiI; 334-2646

INSPECTION

h. 10 Cr? t.ppendix B. and

BASES s ,

Other glicable Regulations

:84

. -

-'* **

4 e

......_ _ _ _ _._ _ - _-_ _ _ __ - __

.

,.,

TEXAS PIPE EENDING C0?PANY, SUBSIDIARY OF THE BENDIX CORPORATION, HOUSTON, TEXAS M020-99900066

P>ACMGR0llND INf0RMAfl0N INSPECTION RESULTS

PRINClPAL PRODUCT (S) DATE(5) 0F INSPfCT10N INSP[CTION R[ PORT NO. UPDATED ON: 7/27/78

7/17-21/73 78-02 BY: I. Barnes....x

NUCLEAR INDUSTRY INVOL VEME NT DFVIATION(S) FROM COMMITMfNTS

NUrLFAR STFAM SfSTFM SUPPL.IFRS AND ARrHITECT FNGINFFRS ACKNOWLEDGED - IE REVID4 COMPLETED

Reac t or tinit s in Service. . N/A 1. Contrary to corrective action comitrents, a documented independentReactor Linits L:nder Construction. .. . N/A review of welding material qualifications and resolution of anReict or l' nit s linder Cont ract . . . .. M/A observed qualification data deficiency were not accomplished.

2. Contrary to corrective action comitments, a copy of a certainp , RACTORS, VEMORS , OTilFRf, drawing transmittal retumed by QC was not furnished to the

Engineering Clerk.Percent of Production Devo "d to Nuclear Producta . . 2% 3. Contrary to Criterion IX of 10 CFR 50, Appendix B, and Section 5 of

the OA Mar.ual, a temporary attachment was observed welded to 3certain assembly, which was not identified as to its suitability forwelding and for which the attachment operation had not been docu-mented.

ORGANI7AT' N L CONTACT 4. Contrary to Criterion IX of 10 CFR 50. Appendix B, and correctiveaction comitments, the required maintenance check of a selected

Na m le . . . S. S, th, QA ger welding station was not perfomed at the required frequency.City / State / Zip . Houston, Texas 77012

UNRESOLVED ITEM (S)Telephone. .. - (713) 643-0681

1. Absence of documented evidence of quality management review ofvendor nonconformance files.NRC CONTACTS 2. Vendor audit system does not assure accomplishment of comitted

Assigned Inspector I. Barnes vendor corrective actions with respect to survey findings...

Section Chief. . D. M. HunnicuttTelephone. .. - (817) 334-2846 COMMENTS

Texas Pipe Bending Company has started to manufacture welded pipe toASME Section IIT requirements.



co-

::, 857,.

p

--

_ _ _ . _ .

C;.

#-;

' . . .

L .?VfiTEK, INCORPORATED, SPRINGVILLE, UTAH 44060-99900309 IQ-

BACKGROUND INFrRMATION INSPECTION RESULTS

PRINCIPAL PRODUCT (S) DATE(S) OF INSPECTION INSPECTION REPORT NO. UPDATED ON: 7/5/78NUCLEAR VALVES

6/19-22/78 78-02 BY: V. H. Hunter

NUCLEAR INDUSTRY INVOLVEMENT DEVIATI0H S) FROM COMMITMENTS

NUr!.FAR STFAM SYSTFM SUPPLIFRS AND ARCHITFCT ENGINEFRS ACKNOWLEDGED - IE REVIEW COMPLETED

N/A 1. Contrary to Criterion XII of Appendix B to 10 CFR 50, and paragraphReactor t' nits in Service.N/A NCA-4134.12 Section III, of the ASME Codes, there was no procedureReactor Units Under Construction.

Reactor Units Under Contract. . . N/A for the calibration of hand tools.

CONTRACTORS, VLSDORS, OT11ERS 2. Contrary to Criterion VI of Appendix B to 10 CFR 50 and procedureSPP-200, paragraph 5.0, Engineering Order Number 10078 was not signed

10%Percent of Production Devoted to Nuclear Producta . by the Project Engineer.

3. Contrary to Criterion V of Appendix B to 10 CFR 50 and paragraphNCA-4134.5, there were no documented instructions, procedures, ordrawings that address design verification testing or method of stress

ORGANIZATIONAL CONTACT analysis.

Name/ Title . .. ..- G. C. Clark, QA ManagerAddress. . . . .. . Mountain Springs Parkway UNRESOLVED ITEM (S)

.. . . Springville, Utah 84663City / State / Zip .(801) 489-8611 NONETelephone. . . .. ..

NPC CONTACTS COMMENTS

Assigned Inspector . . . . . V. H. Hunter NONESection Chief. . . . D. E. WhitesellTelephone. . . ... . (817) 334-2846



86 _-.

O

-

VELAN VALVE COMPANY, WILLISTON, VERMONT 44060-99900346

BACKGROUND INFORMMION INSPEC110N RESULTS

DATE(5) 0F INSPECTION INSPECTION REPORT N3. UPDAlED ON: 9/15/78PRINCIPAL PRODUCT (S) ASME SECTION III "N" CLASS 1

h 2, & 3 VALVES AND VALVE PARTS 9/12/78 78-01 1' aY : Wm. D. Kelley-


NUCI. EAR STEAM SYSTEN SUPPLIERS AND ARCHITECT ENGINFERS NONE

Reactor Units in Service. . . ... . N/AReactor Units Under Construction. . ... ... N/A UNRESOLVED ITEM (S)

.... .. ... N/AReactor Units Under Contract.NONE

CONTRACTORS, VEMX)RS, OTHERS

Percent of Production Devoted to Nuclear Products . 5% COMMENTS..

VVC has received ASME Certificate of Authorizatior. Number N-2117 touse the "N" symbol for " Class 1, 2, & 3 Valves & Fluid ConditioningDevices" and ASME Certificate of Authorization humber N-2118 to use

ORGANIZATIONAL CONTACT the "NPT" symbol for " Class 1, 2, & 3 Valve Parts & Appurtenances &Fluid Conditionings Devices." These certificates expire on June 9,

.... . . E.1. Francois, Corp. Mgr . of QA 1981.Name/ Title .Address. Avenue "C" Griswold Industrial Park........

City / State / Zip . . . . . . . Willisten Vennont 05495 The new plant at Williston started production r f commercial valves..... . .. (802) 863-2561 in March 1978 and nuclear valvas followed in August 1978. Presently,Telephone.

the new valves amounts to approximately 5% of production and are 3inch and 4 inch in size and are of the 600# and 1500# class.

NRC CONTACTS

Assigned P ;_ tor . . Wm. D. Kelley..

D. E. WhitesellSection Chief. . . . ..

(817) 334-2846Telephone. . . ......

"10 CFR 50, Appendix B, and


x; 87

biyCTC

y

1.0mf :.']

WALWORTH COMPANY, ALOYC0 PLANT, LINDEN, NEW JERSEY | %060-99900087


DAT M M IN W N WM M CM O NUE NMPRIdIPAL PRODUCT (S) ASME SECTICN III "N" CLASS 1, 2,h AND 3 VALVES 8/7-9/78 78-02 BY: Wm. D. Kelley;

NUCLEAR INDUSTRY INVOLVEMENT DEVIATION (S) FROM COMMITMfNTS

NUCLF.AR STEAM SYSTEM SUPP'.IERS AND ARCHITECT ENGINEERS ACKNOWLEDGED - IE REVIEW COMPLETED

Reactor Units in Service. . N/A 1. Contrary to Criterion V of Appendix B to 10 CFR 50, paragraph NCA-4134.5Reactor Units Under Construction. N/A of Section III to the ASME Code, and paragraph 1.6.3. of WC-AReactor Units Under Contract. . N/A procedure AWP-24, Revision 5, welding interpass temperature was

verified by the use of Tempilstik on a 4" N-2216SP Gate Valve Body,CONTRACTORS, VE!; DORS, OTHERS instead of a contract pyrometer as specified.

Percent of Production Devoted to Nuclear Products 25% 2. The QA engineer stopped the welding operation and instructed the..

welding supervisor that the temperatura must be verified by the useof the contact pyrometer as specified by the procedure. Deviationclosed.

ORGANIZATIONAL CONTACTUNRESOLVEDITEM(S)

F. A. Truppo. QA ManagerName/ Title . .. . . . . 1400 West Elizabeth Avenue NONE

.....

Address. . . .

City / State / Zip . . . . Linden, New Jersey 07036(201) 862-4600Telephone. . . . ......

COMMENTS

NRC CONTACTS Atlantic Richfields' Walworth Company announced on July 11, 1978, thatthey had reached an agreement in principle with Serck Limited of England

Wm. D. Felley for their purchase of the Aloyco plant and product lines.Assigned Inspectot .. ..

D. E. WhitesellSection Chief. . .. ..

Telephone. . . . (817) 334-2846. . . ..

INSPECTION 10 CFR 50, Appendix B, andBASES p Other Applicable Regulations

Ii

88

WELK BROS. METAL PRODUCTS, INC., SPOKANE, WASHINGTON @ 070-99900 % 1

BACKGROUND INFORMATION INSPECIl0N 9ESULTS

PRINCIPAL FR000CT(S) NUCLEA'. CI C A, 2, 3. and MC DATE(S) CF INSPECTION INSPECTION REPORT NO. L'PDATED ON: 8/2/78 ,

h .c.S AND VESSELS*

7/24-28/78 78-01 BY: J. W. Sutton

NUCLEAR INDUSTRY INVOLVEMrNT DFVIATICH S) FROM COMMITMENTS

NUCI. EAR STFAM SYSTEM SUPPI IF RS AND ARrHil E('T D.:TNIFPs ACKNOWLEDGED - IE PEVIEW COMPLETED

Reactor Units in Service. N/A Contrary to Criterion V of Appendix B to 10 CFR 50, NCA 4134.5 of SectionReact or l'ni t s Under Const ruc t ion. N/A III of the ASME Code and paragraph 6.11.6 of the ASME accepted QA manual .Reactor Units Under Contract. N/A Electric perameters for manual arc welding identified in the weld.ng

procedure specification could not be verified during welding activities.CONTRACTORS, VENDORS, OTilERS

Percent of Produc t ion Devoted to Nuclear Produc t s 151 UNRESOLVEDITEMQ)

Clarification of the organizational structure, as described in the QAManual, is required. Presently, the corporate manager of the QualityAssurance office is vacant and the Vice President of Technical Services is

ORGANIZATIONAL CONTACT acting as corporate QA Manager.T. L. Prater, Vice President

Name/ Title Technical ServicesAddress. S. 2504 Hayford Road COMMENTSCity / State / zip Spokane, Washington 99219Telephone. (509) 244-5511 The vendor Certificate of Authorization for ''N- and NPT" expire

November 8, 1979.

NRC CONTACTS

Assigned Inspector J. W. SuttonSectfon Chief. . . U. S. WhitCsellTe:ephone. (817) 334-2846

INSPECTION 10 CFR 50, Appendix B, andBASES ) Other Applicable Pegulations

_

03 89t,7,pblN

CQLosmeN:D

WESTINGHOUSE ELECTRIC CORPORATION, ELECTRO MECHANICAL DIVISION, CHESWICK, PENNSYLVANIA P 930-99900033_

BACKGR0liND INFORMATION INSPECTION RESULIS

PRINCIPAL PRODUCT (S) DATE(S) OF INSPECTION INSPECTION REPORT NO. UPDATED ON: 5/25/7B

NUCLEAP PUMPSp 5/16-19/78 78-01 Bf: L. E. Ellershaw

NUCLEAR IFDUSTRY INVOLVEMENT DEVIATION (S) FRO 1 COMMI''iNTS

NUCLFAR STEAM SYSTEM SUPPLIERS AFP ARCHITECT ENGINFFRS ACKNOWLEDGED - IE RCVIEW COMPLETED

Reactor Unli.: in Service. . .. . N/A 1. Contrary to Criterion XV of Appendix B to 10 CFR 50 and QA Manual.Reactor Units Under Ccostruction. . N/A Section C15.1, certain nonconfaming parts were neither identified,Reactor Units Uader Contract. . N/A segregated from good parts, nor placed in a hold area.

2. Contrary to Criterion XV of Appendix B to 10 CFR 50 and QA Manual,CONTRA" TORS, VENDORS, OTHERS Secticn C15.2, hold tags were not placed on nonconfoming parts after

the expiration of their conditional release, in order to preventPercent of Production Devoted to Nuclear Prod'act s . 70% further work from being performed.

3. Contrary to Criterion XII of Appendix B to 10 CFR 50 and QA Manual,Section C12.1, certain gages were as much as five (5) months overduefor calibration because gage room personnel changed the calibration

~

frequency without obtaining a procedure change.ORGANIZATIO GL CONTACT 4. Contrary to Criterion VIII ?f Appendix B to 10 CFR 50 and QA Manual,

J. F. Phillips* Section C8.1, used and uniuentified weld material had not been scrapped.-

Name/ Title . . .. Product Assurance Manager but was returned to the weld material storage area and mixed in with

Chesw1C. Avenue weld material that was identified.Address. . . . .. ..

City / State / Zip . Cheswick, Pennsylvania 15024 5. Contrary to Criterion IX of Appendix B to 10 CFR 50 and QA Manual....

(412) 363-8700 Section C10.3, the acceptance criteria used in an equivalent visionTelephone. . . ., ,...

test given to personnel perfoming special processes is less than therequired Jaeger I letter.

NRC CONTACTSUNRESOLVED ITEM (S)

L. E. EllershawAssigned Inspector . . ..

Section Chief. . D. M. Hunnicutt NONE....

Telephone. . . . ... . (B17) 334-2844

COMMENTS

INSPECT!CN NONE10 CFR 50, Appendix B, andPASES h Other Applicable Regulations

j

90

WESTINGHOUSE ELECTRIC CORPURATION, TAMPA, FLORIDA 44050-99900047


PRINCIPAL PRODUCT (S) |DATE(S) 0F INSFECTION INSPECTION REPORT NO. UPDATE 0 ON: 8/21/78NUCLE,.s STEAM GENERATCRS

!/26-27/78 78-01 BY: V. H. Hunter

NUCLEAR INDUSTRY INVOLVEM N DFVIAT'ON(S) FROM COMMITMENTS

NUCLEAR STEAM SYSTEM SUPPLIERS AND ARCHITECT ENGINEERS NONE

Reactor Units in Service. . . .. . N/AReactor Units Under Construction. . . . . N/A UNRESOLVED ITEM (S)Reactor Units Under Contract. .... . N/a


Percent of Production Devoted to Nuclear Products . 100% C0f14ENTS

NONE


Name/ Title . R. G. Leckey, deliability Manager........

Address. . . . . . . . . . Post Office Box 19218.

City / State / Zip . . . . . . Tampa , Florida 33616Telephone. (813) 837-7451........

NRC CONTACTS

Assigned Inspector . V. H. Hunter....

Section Chief. D. E. Whitesell.......

relephone. (817) 334-2846. .... ..


h Other Applicable Regulations

91gc.:Cw..

%

LOLQyV.N

WESTINGHOUSE ELECTRIC CORPORATION, POWER SYSTEMS, SWITCHGEAR DIVISION, EAST PITTSBURGH, PEMSYLVANI A %075-99900330 60

BACKGROUND INFOR% TION l'iSPECTION RESULIS

PRINCIPAL PRODUCT (5) DATE(S) Oc INSPECTION INSPECTION REPORT NO. UPDATED ON: 6/21/78

N SWITCHGEAR PRODUCTSV 6/12-1C/78 78-02 BY: J. R. Agee

NUCLEAR INDUSTRY INVOLVEMENT DfvlATION(S) FROM COMMITMENTS

N1'CI FAR STF AM SYSTFM StTP! IERS AND ARCHITECT FNPINEERs ACKN0'4LEDGED - IE PEVIEW COMPLETED

N/A 1. Contrary to comitment to customer contracts, the QA Manual does notReactor Units in Service.N/A comit to compliance to Appendix B.Reactor l' nit s l'nder Const ruct ion.N/A 2. Contrary to comitment by the QA Manual, the QA Manual had not beenReactor l' nits L:nder Cont ract. revised and u N ated since February 20, 1974.

3. Contrary to comitment to Appendix B, QA indoctrination and trainingCONTRACTORS, VESDORS, OTHERS had not been provided for personnel performing activities affectingPercent of Production Devoted to Nuclear Products . 5% quality in certain departments.

4. Contrary to comitment by the QA Manual, all aspects of the QA programhad not been audited nor had adequate records been maintained.

5. Contrary to comitment by the QA Manual, the QA program does notprovide for a system for source evaluation at the supplier's site, nordoes it provide for periodic inspection or audit of the suppliers.

ORGANIZATIONAL CONTACT6. Contrary to comitment by the QA Manual, quality assurance require-

Name/ Title . . . . .H. I. Stahr, QA Manager ments were not passed on to certain suppliers.700 Braddock AvenueAddress. . . . .

E. Pittsburgh, Pennsylvania 15112City / State / Zip ...

(412) 256-2329 UNRESOLVED ITEM (S)Telephone. . . . ... ..

1. The Approved Suppliers List contains the identity of several suppliersthat have been approved by the grandfather's clause, i.e., without

NRC CONTACTS qualification by survey and evaluation. The Approved Suppliers ListJ. R. Agee is being upgraded to more accurately identify current approved

Assigned Inspector . ..

Section Chief. . . . . . . D. M. Hunnicutt suppliers.

. . .. . (817) 334-2846 2. Certain prototype models of switchgear are currently being qualifica-Telephone. tion tested to applicable IEEE standards to qualify the equipment to

customer and regulatory requirements.

COMMENTSINSPECTION 10 CFR 50, Appendix B, andBASES ) Other Applicable Regulations NONE

92

.

WESTINGHOUSE El.ECTRIC CORPORATION, PENSACOLA DIVISIGN, PENSACOLA, FLCRIDA 44050-99 ann]04

BACKGROUND INFOR1ATION INSPECTION RESiiLIS.PRINCIPAL FRCDL',T(S) DATE(5) Of IN5rECTICN INSPECTION REFORT NO. UPDAT[D ON: 3/1/78

REACTOR INTERNALS7/24-25/78 78-01 By: V. H. Hunter

NUCLEAR INDUSTRY INVOLVEMENT riv!ATir'ds) FROM COMMITMfNTS

NUCIFAR SIFAM SYSTE M SUPP!.IF RS AND Akf h1II.CT F3 ',INF FR S NO*,{

Heactir l'n i t s in Service. N/AReactor Units inter construction. N/A t M 50LVED ITEM (S)Beactor l~ nits Under Cont rac t . N/A

NONECONTRACTORS, VF3 DORS , OTHERS

Percent of Production Devoted to Nuclear Products 100T C0t?'E NTS

NONE

ORCANIZATIONAL CONTACT

Name/ Title F. B. Hyland, CA ManagerAddress. Post Office Eox 1313City / State / Zip Pensacola, Florida 325961elephone. (904) 477-0535

NPC CONTACTS

Assigned Inspector V. H. HunterSection Chief. D. L . WhitesellTelephone. (817) 334-2846

INSPECTIONBASES h Action Item H-10046F4

ro 93;%:-,

*2..\

MC

_

b17.:e;

zWESTINGHOUSE ELECTRIC CORPORATION, INDUSTRIAL & GOVERNMENT TUBE DIVISION, HORSEHEADS, NEW YORK 44075-99900324

BALKGROUND INFORMAll0N INSPECTION RESULIS

PRINCIPAL PRUDUCT(S) ELECTRICAL PENETRATION ASSEMBLIES, DATE(5) Of INSPECTION INSPECTION REPORT NO. UPDATED ON: 9/20/78

> AND NUCLEAR DETECTORS 9/12-14/78 78-01 BY: J. R. A9ee,

NUCLEAR INDUSTRY INVOL VI ME NT DtV! ATION(S) FROM COMMITMf NTS

NUCIFAR STEAM SYSTEM SUPPt IFRS AND ARCHITFCT FNt:lNFFRS NON[

Reactor Units in Service. . .. . N/AReactor Units Under Construction. N/A p,.FESOLVED ITEM (S)Heactor Units Under Contract. .. . N/A

Medium voltage electrical penetration assemblies with antitracking materialCONTRACTORS, VENDORS, OTHERS applied require additional testing to COnplete final qualification testing.

Percent of Production Devoted to Nuclear Product s 15%

COMMENTS

NONE


J. B. Kessing Manager, QCName/ Title .

Westinghouse CircleAddress. . . .

City / State / Zip . .. f.orseheads , New York 14845

Telephone. . . . (607) 790-3297

NRC CONTACTS

Assigned Inspector . J. R. Agee

Section Chief. . . D. M. HunnicuttTelephone. . . . (817) 334-2846

INSPECTION 10 CFR 50, Appendix B, andBASES ) Other Applicable Regulations

94

THE WILLIAM POWELL COMPANY, PLANT NO. 2, CINCINNATI, OHIO % 060-99900057

MCKGROUND INFORMTION INSPECTION RESULTS

PRINCIPAL PRODUCT (S) DATE($) Of INSPECTION INSPECTION REPORT NO. UPDATED ON: 7/31/78N NUCLEAR VALVESV 7/25-28/78 78-01 BY: R. E. Oller

NUCLEAR lhDUSTRY INVOLVEMENT DEVI ATION(S) FROM COPNITMENTS

Nuct.EA R STEAM SYSTFM SUPPLIERS AND ARCHITECT ENGINFFRs ACKNOWLEDGED - IE REVIEW COMPLETED

.. . ..... . N/A 1. Contrary to Criterion XII of Appendix B to 10 CFR 50 ar.d paragraphReactor Units in Service...... . .. N/A 6.4.1.1 of the QA Manual, calibration requirements were not fullyReactor Units Under Construction.

......... . N/A implemented for four (4) different types of measuring devices usedReactor Units Under contract.in activities affecting quality.

cowrRACTORS, VENDORS, UTHERs 2. Contrary to Criterion II of Appendix B to 10 CFR 50; ASME Codesubarticle NCA 4134.2(b), and paragraph 8.4 of the QA Manual, the

Percent of Production Devoted to Nuclear Products . .. * inspector training sessions were not documented as required.

*See ComentsUNRESOLVED ITEM (S)

ORGANIZATIONAL CONTACT Powell Specification WPEC 2/103, Revision 0, dated August 1,1977, requiresE. E. Winterfeldt, that each furnace employed for heat treatment, shall be subject to a

Name/ Title . Corporate QA Manager, furnace temperature unifomity survey once every two (2) calendar years.... ..

Address. 3233 Colerain Avenue minimum, by subcontracted outside source. During examination of furnaces..........

City / State /Z1P . .. ... Cincinnati, Ohio 45214 numbers 5550, 5437, 5784, 5533, and 5777 in Plant 2, th( inspector wasTelephone. (513) 852-2967 infomed that temperature surveys had not been run on these furnaces,. but.........

that contracting of this service was in process. Review of Powell

Purchase Order No. 4733-2 showed the work had been awarded. This itemNRC CONTACTS remains unresolved pending completion of the survey and its verification

during a subsequent NRC inspection.Assigned Inspector R. E. Oller....

Section Chief. . . . . . . . D. M. Hunnicutt(817) 334-2846 COMMENTSTelephone. .........

* Percent of ProdJCtion Activity devoted to nuclear was not available atthis time.

" "10 CFR 50, Append!x B, and


CD 95t"7....

')s,

CD

SECTION III

hh " APPROVED PROGRAM" LISTitlG

, C0flFIRMING SATISFACTORY TOPICAL REPORT, OR STAtlDARDIZED PROGRAM, IMPLEMEtlTATI0tD(

Co

'?|:.:,

e

$ CONTRACTORS WITH IE LETTERS CONFIP. MING QA PROGRAM IMPLEMENTATION $3

MAILING DATE OF LETTERS *

NUCLEAR REACTOR REGULATION INSPECTION & ENFORCEMENTCONTRACTOR TOPICAL REPORT REVISION QUALITY ASSURANCE BRANCH LCVIP

Babcock & Wilcox BAW 10096A Revision 1 March 25, 1975 December 30, 1975

Ceneral Electric Co. Chapter 17-CESSAR NA December 1975 December 31, 1975

Stone & Webster SWSQAP 1-74 Revision A July 11, 1975 December 31, 1975

Westinghouse PWRSD WCAP 8370 Revision 7-A December 31, 1974 December 31, 1975

Bechtel-Caithersburg BQ-TOP-1 Revision 1 May 30, 1975 January 7, 1976

Bechtel-San Francisco BQ-TOD-1 Revision 1 May 30, 1975 January 7,19 76

Ebasco Services, Inc. ETR-1001 Revision 0 May 12, 1975 March 19, 1976

Combustion Engineering i Chapter 17-CESSAR NA December 1975 January 5, 1977

Gibbs & Hill Inc. CIESAR 17-A Amendment 2 October 5, 1976 March 31, 1977

United Engineers &Constructors UEC-TR-001-3A Amendment 3 November 10, 1976 March 31, 1977

*See next page which consists of typical wording contained in confirming letters

99

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O

O'De',e A.w

# % UNI TE D ST ATESg p NUrtEAR N EGULATORY COMMISSION; . , =rs t g REGsON IV

4,g ~ ' t M LINGTON. TE X AS 76011c 611 RY A4 PLAZA DRIVE, Sul TE 1000 # j

o, .gj# h (ADC W EE) -2- (DATE

Q [s0)s* ..+ (DATE) W

WI gg( b'Q\

(ADC4ESSEE) f " N t b s ', sQ'd ,)s*

Continuing acceptability of implerrentation of your QA program is contin-("C. 8 % v' gent son your maintaining a continuing satisfactory level of program

* sh inplementation - verified through periodic IE inspection - throughout'

Gentlemen: C '/ all corporate organizaticn units encompassed by your program.

By letter dtted (Date), signed by the Chief, Quality Ass;rance Branch- Ehceld your program nplementation at any time be found unacceptable youthe Of fice of Nuclen Reac tor Regulation, indicated the acceptability will be notified by letter, and required to correct the deficienciesof the descripticn " your quality assurance (GA) pr t:qra'i os set f orth ur mptly. In the event you fail to correct the deficiencies promptly, orin your Topical Report. the event the record of deficiencies is such as to indicate chronic poin

inclen entation, you and the applicants and licensees who have referencedA series of inspections, based an >t:lec ti ve e'minatic o cf precedures, year program will be notified that implementation of your program is norepreu ntative records, interviews w1 * h , ers tnrel, anc , rrations by longer acceptable to the NRC and that the inspection requirements of Cri-.

inspec rs, nave been conducted of yo.c s iementaticn te @ program terion VII, Appandix B, 10 U R 50, must be implemented by the affected apu

,

descrit o in your Tcpical Feport, ide iftel above. 2 e ult cf these olicants or licensees. In such an event, the NRC will reinstate its lettinspections, cand cted through (DATE), - a Office of ' :.tttico and of acceptability of irpler.entatien of your QA program only af ter f urtherEnforcenent (IE) concludes that yose> vo , ra- i , , i v; kul ented sat- demonstration of compliance by you and reinspection by our inspectors.isf3ctorily. Neither this conclusicn not tre rem inder af this Ntterapplies to construction activities or otne' activ ities b- img cerd;c ted If your QA progran requires changes for any reasons such that resubmittalat re*ctor sites, to the Of fice of Nuclear Peactor Regulation for additional evaluation is

req : ired, reinspection for acceptability of implementation of the changesThis letter ray te useJ to deronstrate to y;,r cu,t rs who are WC as aproved also will be necessary.applicants or licensees that current implem ntaticn * your a program,based on IE inn e ticns conducted, is satisfa. 30 tc ee Your The results of our inspections will be published quarterly in the License,

custorers may reference this letter in satisf e' tico of tneir cbligation, Contractor and Vendor Inspection Status Report (LCVISR), which is availabas NFC applicants er licensees, under tre m e' - mt req 2irerents of to NRC facility applicants, licensees, contractors and vendors, and tu thCriterion VII, Appendis ~ 10 U R 5" public.

'\

(,,9It should be noted that tance of this letter as ovicence that your "iSincerely *

QA program is satisfactor j inpleru ted is cptional with NRC applicants p% 5and licensees. The NRC expression cf u tisfaction with the implementation , "s %Mof your QA program dces not assure that t'. quality of a specific product f \'vg V f[77/aw da('q \ \ (or service of fered by you to year customer is of acceptable quality. The v wa4 .oNRC applicant or licensee subject te W requirements still nast assure g\ E. Morris Howard.v \, )gthe quality of specific prodJcts or rvices.

( Q*m, .\hg g Director,

VNs.- .p==..*) j

.a

100

SECTION IV

LICEN5EE EVENT REPORTS (LER'S)

THIS SECTION OF THE LICENSEE, CONTRACTOR AND VENDOR STATUS REPORT, CONTAINS A TABULATIONOF LER'S. DURING REVIEW OF THIS INFORMATION, READERS SHOULD BE AWARE OF THE FOLLOWINGTHREE CONSIDERATIONS:

.,

FIRST: THE NAME OF THE ORGANIZATION APPEARING AT THE HEAD OF THE LEFT HAND BLOCK OF'UTTUIkATION FOR EACH LER ENTRY IS INCLUDED TO IDENTIFY THE LICENSEE CONTRACTOR OR VENDORMOST CLOSELY RELATED TO THE EQUIPMENT, COMPONENT, OR SERVICE ASSOCIATED WITH THE LER.

IDENTIFICATION OF CAUSES OF LERS REFLECTS OPINION ON THE PART OF THE LICENSEE AND INSOFARAS DISSEMINATION OF LICENSEE CONTRACTOR AND VENDOR STATUS REPORT INFORMATION IS CONCERNED,DOES NOT NECESSARILY MEAN THAT THE NAMED ORGANIZATION 15 RESPONSIBLE FOR, OR HAS CAUSED,

THE LER IN QUESTION.

SECONDLY: THE LER TABULATION REFLECTS DATA ACCUMULATED, AND PPOCESSED, DURING ThE CURRENTREPURI PERIOD. ADDITIONAL EVENTS WILL NORMALLY HAVE OCCURRED DURING REPORT PERIODS, BUTWILL NOT APPEAR IN THE REPORT DUE TO PROCESSING DELAY TIMES. THESE LER'S WILL APPEAR INA SUBSEQUENT REPORT.

THIRDLY: THE LER LISTING IN SECTION IV 0F THE WHITE BOOK HAS BEEN ELECiRONICALLY TRAN-SCRIBEU FROM COMPUTER DATA SYSTEMS DIRECTLY ONTO PAGES OF THIS BOOK. THIS ACCOUNTS FORSYNTAX, AS WELL AS MARGINAL INEQUITIES.

_

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*C:.

|-*-v

g

o

LICENSEE EVENT REPORTS

CCMPONENT MANUFACTURER DOCKET NO.

COMPONENT / COMPONENT SUBCODE LER NO.CAUSE CODE /CAUSE SUBCODE CONTROL NO. EVENT DATE

FACILITY / SYSTEM SUPPLIER REPORT DATE EVENT DESCRIPTION

METHOD OF DISCOVERY NSSS / A/E REPORT TYPE CAUSE DESCRIPTION

AGASTAT RELAY CO. 05000338 061478 REVIEW 0F DATA GENERATED BY A START-UP TEST (STATION BLACKDUT) REVEALEDRELAYS 78-051/01T-0 062878 A 3 SECOND DELAY IN THE STARTING OF AN AUXILIARY FEEDWATER PUMP. THE PUTIME DELAY, PNEUMATIC 021667 2-WE2K MP WAS EXPECTED TO START INSTANTANEOUSLY UPON RESZORATION OF EMERGENCY B

DESIGN / FABRICATION ERROR A/E US POWER. NO SAFETY CONSEQUENCES SINCE THE AUX. FEEDWATER PUMPS ARE REQU

DESIGN WEST IRED TO START IN 60 SEC Ok LESS AND THE EMERGENCY DIESEL LOADING SEQUENCNORTH ANNA-1 5+W E WAS NOT ADVERSELY AFFECTED.

COOL SYS FOR REAC AUX + CONTSPECIAL TEST / INSPECTION DELAY IN THE START WAS DUE TO IMPROPER ADJUSTMENT OF INSTANTANEOUS CONTA

CTS ON AN AGASTAT 2400 SERIES RELAY. ADJUSTMENT CORRECTED THE DELAY. FURTHER INVESTIGATION REVEALED CONTACTS NOT CEPTIFIED SEISMICALLY QUAL IFIED. CONTACTS WERE REPLACED BY SEISMICALLY QUALIFIED SPARE CONTACTS.

AGASTAT RiiAY CO. 05000348 i 071878 AT 1330 PERFORMING SURVEILLANCE TEST PROCEDURC FOR DG-1-2A, STEP 5 ON BI

RELAYS 78-050/03L-0 081478 F ESS SEQUENCER FAILED TO PICKUP. T/S 3.8.1.1 REQUIRES TWO SEPARATE INDTIMER, SEQUENCER, T-5 CONTROL 022048 30-DAY EFENDENT DIESEL GENERATOR SETS AND SEQUENCERS TO BE OPERABLE. T/S 3.8.1

COMPONENT FAILURE A/E .1 ACTION STATEMENTS WERE MET. THE BIF SEQUENCER /DG 1-2A RESTORED GPtRAOTHER WEST BLE AT 1845. REQUIRED LOAD COULD HAVE BEEN STARTED MANUALLY. NO EFFECT

JOSEPH M. FARLEY-1 SSC/BECH ON HEALTH / SAFETY OF GENERAL PUBLIC.EMERG GENERATOR SYS + CONTROLSROUTINE TEST / INSPECTION TIMER WAS DISASSEMBLED AND A SPRING WAS FOUND TO HAVE COME OUT OF THE RE

LAY FCR STEP 5 0F THE SEQUENCER. RELAY WAS REPAIRED, AND SEQUENCER SATISFACTORILY TESTED.

ALLIS CHALMERS 05000255 052378 IMMEDIATELY FOLLOWING A PLANT TRIP, 2400 VOLT BUS 1E FAILED TO TRANSFER

CIRCUIT CLOSERS / INTERRUPTERS 78-018/03L-) 062278 FROM STATION POWER TO STARTUP POWER. BECAUSE PCS TEMPERATURE WAS GREATE

CIRCUIT BREAKER 021597 30-DAY R THAN 325 DEGREES CONCURRENT WITH THE BUS BEING DE-ENERGIZED. THE PLAN

COMPONENT FAILURE A/E T WAS IN A DEGRADED MODE PERMITTED BY THE LCO OF T.S.3.7. NO SAFETY REL

ELECTRICAL COMB ATED COMPONENTS ARE POWERED FROM THIS BUS; THEREFORE, NO HAZARD TO PUBLI

PALISADES-1 BECH C HEALTH OR SAFETY EXISTED.AC ONSITE POWER SYS + CONTROLSOPERATIONAL EVENT BECAUSE OF FAILED LIMIT SWITCHES IN THE CHARGING MOTOR CONTROL CIRCUIT.

THE BREAKER CHARGING MOTOR HAD NOT CHARGED THE BREAKER'S CLOSING SPRINGS

) . THE LIMIT SWITCHES WERE REPLACED AND THE BREAKER WAS RETURNED TO SERV-

ICE. THE BREAKER IS AN ALLIS CHALMERS MODEL MA-2508, 2400 VOLT,1200 AM+,

57', P.p.,-e

pj 103

CLC

LICENSEE EVENT REPORTS 77/..

:)COMPONENT MANUFACTURER DOCKET NO. (f",COMPONENT /CDMPONENT SUSCOCE LER NO.CAUSE C0CE/CAUSE SLBCODE CONTROL NO. EVENT DATEFACILITY / SYSTEM SUPPLIER REPORT DATE EVENT DESCRIPTIONMFTHOD OF DIsr0VERY NSSS / A/E REPOPT TYPE CAUSE DFSCRIPTION

AMER WARMING & VENTILATING INC 05000335 06157C DURING IESTING, THE HUMIDITY CONTROL HEATERS ON THE SHIELD BUILDING VENTVALVE OPERATORS 78-023/03L-0 071378 ILATION SYSTEM ("B" TRAIN) TRIPPED ON HIGH TEMPERATURE. ALSO LOW FLOW

ELECTRIC MOTOR - AC 021835 30-DAY ALARMS WERE RECEIVED, AND SHIELD EUILDING VACUUM WAS LESS THAN EXPECTED.COMPONENT FAILURE A/E THIS INDICATED THAT THE "B" TRAIN WAS NOT FULLY OPERABLE AND PEQUIRED A

MECHANICAL COMB CTION IN ACCORCANCE WITH SPECIFICATION 3.6.6.1. THIS IS THE FIRST EVENTST. LUCIE-1 EBASCO CF THIS TYPE.CNTNMNT HEAT REMOV SYS + CONTOPERATIONAL EVENT TFE HEATERS TRIPPED PROPERLY DUE TO HIGH TEMPERATURE CAUSED BY LCW FLOW.

THE ADJUSTMENT ON THE THROTTLED F0 TOR OPERATED OUTLET DAMPER WA S RESETAND FROPER FLOW VEPIFIED ON THE "B" TRAIN (AND THE "A" TRAIN) IN 24 HOU

RS, WHICH WAS WELL WITHIN THE TIME LIMIT.

ANCFCR VALVE CO. 05000331 122777 DURING NORMAL OPERATION REACTOR WATER CLEANLP SYSTEM ISCLATED. WHEN ISOLVALVE OPERATORS 77-097/03L-1 062678 ATION SIGNAL CLEAPED MOV 2700 WAS CYCLED TO THE OPEN POSITION BLT WOULD

ELECTRIC MOTOR - AC 020135 30-DAY NOT INDICATE FULL OPEN. AN ATTEMPT WAS THEN MADE TO CYCLE VALVE CLOSED WCOMPGNENT FAILURE A/E ITH NO SUCCESS. INVESTIGATICN FEVEALED $0 TOR THERMAL CVERLOADS WEPE TRIP

ELECTRICAL GE PED. WHEN RESET THE VALVE WOULD CYCLE CLOSED EUT CVERLOACS WOULD TRIP ACUANE ARNOLD BECH GAIN NEAR END OF OPENING CYCLE. REDUNCANT F0V 2701 OPERABLE. OPE RABILIREAC COOL CLEANUP SYS + CONT TY REQUIREMENTS LISTED IN T.S. TABLE 3.7-3.CPERATIONAL EVENT VALVE WAS INSPECTED AT NEXT OUTAGE. INVESTIGATION REVEALED LIMIT SWITCH

ES WERE OUT OF ACJUSTMENT. ADJUSTED LIVIT SWITCHES AND VALVE TESTED ANDCPERATED SATISFACTORILY. VALVE IS AN ANCHCR VALVE CO. 4 INCH GATE VALV

E. VALVE OPERATOR IS LIMITORQUE TYFE SMB-00.

ANCHOR / DARLING VALVE CO. 05000292 041978 WHILE PERFORMING LEAK RATE PROCEDURE 6.3.1.1, PRIMARY CONTAINMENT PENETRVALVES 78-020/03L-0 051878 ATION X-212 WAS FOUND LEAKING AT GREATER THAN TECH SPEC SECTION 3.7 LIM

CHECK 021617 30-DAY ITS. THERE HAVE BEEN TWO PREVIOUS EVENTS OF A SIMILAR NATURE, 75-22 ANDCOMPONENT FAILURE LIC 77-57. THE PECUNDANT SYSTEM WAS AVAILACLE AND OPERAELE. THERE WAS NO A

METALLURGICAL GE DVERSE EFFECT UPON PUBLIC HEALTH AND SAFETY. THERE WERE NO OTbER SAFETYCOOPER-1 B+R IFPLICATIONS.CNTNMNT ISOLATION SYS + CONTROUTINE TEST / INSPECTION PENETRATION X-212 IS TFE RCIC TURBINE STEAM EXHAUST LINE TO THE SUPPFESS

ION CHAPBER AND IS ISOLATED BY TWO VALVES, RCIC-37 AND RCIC-15CV. RCIC-37 HAD ROUGH SEATING SURFACES AND RCIC-15CV HAD A CRACKED SEAT. THE VALES WERE DISASSEMBLED AND THE SEATS WEFE REPAIRED. THE ISOLATION VOLUMEBETWEEN THE VALVES WAS TESTED FOLLOWING REPAIR & LEAKAGE WAS ACCEPTABLE.

104


'E CCMFCNFNT MANLFACTLFER CCCPET N0.COFFCNENT/CCMFCNENT SLECCCE LER NC.CAUSE CCCE/ CAL 5E SLECCEE CCNTPCL NC. EiENT RATEFACILITY / SYSTEM SLFFLIEP FEFCFT CATE EiENT CESCRIPTICNVETbOD OF DISCO'.EPY LESS / A/E EF?fai TVFF CALSE CE5CPIPTICA

ANCERSCN, GFEENWGCD & CO. CSCC0335 0:207E CLRING LOCAL LEAK FATE TESTING, IT WAS FCL?.D ThAT TFE TOTAL LEAK RATE WAVOLVES 78-Cl?/C3L-0 CE1975 5 EC7,4CC SCCM WHICH EXCEECS THE SPECIFICATICN CF 544,7Ef SCCM (T.S.3.6.CHECK C21524 30-CAY 1.2.8). 96: CF TFE TOTAL LEAFACE WAS ATTRIELTED TO TWO VENTILATICN VALVE

COMPCNENT FAILLPE A/L S (V-25-20 AND FCV-25-3). IN EACH CASE THEFE WAS A FECUNDANT FAIL-CLCSEOTFER CC"S C VALVE WITP LITTLE OP NOT L;AKAGE IN SERIES WITH TFE LEAKING VALVES. S

ST. LLCIE-1 EEkiC0 IMILAR VALVES WEFE SLCCESSFULLY LEAK-TESTED AND FCL*.D TO BE SAT' f4CTCRYCNTNM*.T ISCLATICN SYS + CONTFCUTINE TEST /INSFECTICN k ALVE V-25-20 EAD A CUT IN TLE SEAT WHICH MAY HAVE CCCLRRED WHEN THE LEA

K TEST RIG WAS INSTALLE0. VALVE FCV-25-3 F/C A SMALL CEFRESSION IN THESEAT WWICH MAY FAVE REELLTED FRCM A FCRLIGN CBJECT TFAFFED CLRING CLOSURE. NO OTPEF AFPA;ENT CALSE WAS FCLND. THE VALVES WEFE FEPAIRED AND RETESTED SETISTAFTCRILY. FI'JL TCTAL tEAvASE W5% F6.111 (rtv.

ASCO OtLCC313 C42676 WHILL TESTING FADI ATIGN MUNIiuk FtL-ELO1, A HILM kAUIAIIUN SIGN ISLLAILDINSTRUMENTATICN + CCNTRCLS 7E-013/C3L-0 C52578 CCNTPCL PCCM ANC STCPFEC VENTILATICN SLPFLY FANS, ELT THE EMERGENCY SU

SWITCH C2I416 30-CAY PFLY FAN VSF9 FAILED TO START AUTCMATICALLY. THE SYSTEM WAS IN TEST ANDCCMPCNENT FAILLRE A/E TFE FANS WCLLD START MANUALLY. TFEFEFCRE, TFEFE WAS NO EFFECT LPON THE

ELECTRICAL E+W FLELIC FEALTU & EAFETY. TFERE HAVE CEEN 50 FREVICUS EVENTS CF SIMILARAPrANSAS-1 EECH NATLRE.AIR CCND, HEAT,COCL, VENT SfSTEMPCUTINE TEST /INSFECTICN LCCATED AND PEPAIFED CROUND AT ACTUATING SCLENGID WHICH CE-ACTIVATED TFE

GFEEN CIRCUIT.

ASCO C500031E CE017E CURING FEFFCRMANCE OF SLRVEILLANCE TESTING AT OE47, 21 DIESEL CENERATORVALVE CPERATCRS 78-025/03L-0 OE1778 TRIFFED CN HIGF JACKET CCCLANT TEMPERATURE WhEN IT5 SEkVICE WATER SUPPL

SOLEN 0ID - AC C21991 30-CAY Y VALVE FAILED TO CPEN. PEP THE PECLIRCMENTS OF T.S. 3.8.1.1.1 THE OPERCOMPCNENT FAILLFE 4/E ABILITY CF 12 CIESEL AND HE AVAILAEILITY CF TFE OFFSITE TFAN5 MISSION NE

MECHANICAL CCMC TWCPK WERE DPECI ATELY VEi!FIED. 21 DIESEL GENERATOR WAS RETURNEC TO SECALVERT CLIFFS-2 BECH RVICE AND SUCCESSFLLLY TESTED AT 1015. LER'S 77-91 (U-2) AND 77-101 (U-EMERG GENERATOR SYS + CCNTROLS 1) CESCRIEE SIMILAR EVENTS.ROUTINE TEST /INSFECTION SERVICE FETER ': FFLY VALVE FAILED TO CFEN CUE TO A EACLY WCEN PLUNGER SE

AT WFICH CAUSEL THE SCLEN0!D TO STICK. PLUNGER AND SEAT WEFE REFLACED,VALVE WAS TESTEC SATISFACTORILY, AND RETLRNED TO SERVICE. NO FURTFER C0RFECTIVE ACTION IS CEEMED NECESSARY. ( ASCO MCCEL HPX E32CA2C SCLENGID VALVE.)

Q105c,

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q.-

LICENSEE EVENT REPORTS "jCC

COMPCNENT MANLFACTEPER DOCKET NO.COVPGNENT/C0MF0%ENT SLECOCE LER NO.CAUSE CODE /CAUSE SUECODE CCNTPCL NO. EVENT DATEFACILITY / SYSTEM SUPPLIER REFORT DATE EVENT DESCRIPTIONMETHOD OF DISL'VERY NSSS / A/E ;EPODT TYPE CAUSE DESCRIPTION

ASCO 05000250 070C78 WHILE IN A HOT 7ANDBY CONDITION (N0 STEAM FLOW), THE MAIN STEAM ISOLATIVALVE OPERATORS 7R ^C8/01T-0 072078 ON VALVES (MSIV'S) WEPE TO EE CLOSED TO ALLOW REPAIR OF STEAM LEAKS. TH

SOLEN 0ID - DC vc1916 2-WEEK E 3A AND 3C MSIV'S CLOSED IN RESPONSE TO MANUAL CLOSING SIGNALS FROM THECDFFONENT FAILLRE A/E CONTROL ROOM. THE 3B MSIV ONLY PARTIALLY CLOSED. SINCE THE VALVE PART

ELECTRICAL WEST ! ALLY CLOSED, STE AM FLCW, HAD IT BEEN PPESENT, COULD HAVE ACTED TO CLOSETURKEY POINT-3 9ECH THE VALVE.MAIN STEAM SUPPLY SYS + CCNTOFERATIONAL EVENT THE SCLENGIDS FOR TWO PARALLEL AIR SUPPLY VALVES HAD OPEN CIRCUITS. THI

5 PREVENTED AIR FPOM BEING SUFPLIED TO THE CLOSING SIDE OF THE MSIV OPERATOR. THE PRC%BLE CAUSE WAS EXCESSIVE TEMPERATURE DUE TO STEAM LEAKS IN TFE VICINITY. THE DEFECTIVE SOLEN 0 IDS WERE REPLACED. THE VALVE CLOSE0. A%0 TPE STEEP LEAR 5 PEPAIPED,

ASCO 05000293 071078 WHILE SCRAM IIMING CONIkOL RUD 38-47 ON 7/10/78, THE CONTRUL ROD FAILEDVALVE OPERATCRS 78-032/03L-0 072878 TO INSEPT TO ITS S1% INSERTION POINT IN %/= 7 SECONDS AS REQUIRED BY T.SSCLEN0ID - AC 021963 30-DAY (3.3.C.3.). TECHNICIANS CBSERVED THE CONTROL ROD AT POSITION 48 (FULL

CDMPONENT FAILURE NSSS OUT) FOR SEVERAL SLCONDS PRIOR TO ITS SCRAMMING AFTER BEING GIVEN A SCRFTCH ANICAL GE AM SICiAL. OPERATIONS PERSONNEL IMMEDI ATELY TAGGED OUT THE CONTROL ROD

PILGRIM-1 CECH FOR I&L TNVESTIGATION.REACTOR TRIP SYSTEMSROUTINE TEST /INSFECTION ThE PROELEM WAS A ST.CKY ASCO SOLEN 0ID VALVE ASSOCIATED WITH CONTROL R0D

38-47, WHICH SLOWED inE VENTING OF THE SCRAM PILOT VALVES. BOTH SCRAMSCLENDID VALVES WERE REPLACED IN KIND. (ASCO SOLEN 0ID VALVES, CATALOG #HVA 90z405-2A). THE CONTROL ROD WAS SATISFACTORILY SCRAM TIME TESTED ANO PETthNED TO SERVICE.

ASCO 05000325 051576 vtRING N0kMAL F0nER 0FEkAT10N A CONIkUL OFERATOR SELEllED Ibl 10RUS SAMPVALVES 78-C54/03L-0 06137E LE LINE FOR CAC MONITOR CAC-AT-1263. THE MONITOR THEN TRIPPED OFF ON A

CIAPHRAGM 021491 30-DAY LOW FLOW SIGNAL. (TECH SPEC 3.6.6.4)00MPONENT FAILURE A/E

MECHANICAL GE

BRUNSWICK-1 LEC

CNTNMNT COMBUS GAS CONTROL SYS

ROUTINE TEST / INSPECTION SOLENDID VALVE CAC-SV-1263-1 WAS FCUND IN THE STUCK CLOSED POSITION. THE SOLEN 0ID VALVE WAS DISASSEMBLED AND THE CEFECTIVE PLUNGER REPLACED. THE FAILURE OF THIS SOLEN 0ID VALVE IS NOT A NORMAL OCCUFENCE AND NO FURTHER ACTION 15 REQUIRED.

106

.

LICENSEE EVENT REPORTS-.

COMPONENT MANUFACTURER DOCKET NO.COMPONENT /C0t1PONENT SUCC0DE LER NO.CAUSE CODE /CAUSE SUBCODE CONTROL h0. EVENT DATEFACILITY / SYSTEM SUPPLIER REPORT DATE EVENT CESCRIPTIONPETHOD OF DIsr0VEDY ___ h555 / A/I CEPORT TYPE CAUSE pr5CDIPTIDN

ASCO 05000325 070178 WHILE A CONTROL DPERATOR WAS IAERTING THE CRYWELL, CAC OXYGEN ANALYZER CVALVES 7 8-064/03L-0 073178 AC-AQH-1259 WAS FnUND TO HAVE A HIGHER THAN EXPECTED OXYGEN CONCENTRATIO

PLUG 021840 30-DAY N READING. UPON INVESTIGATION, OXYGEN MONITOR CAC-AQH-1259 WAS FOUND INCCMFONENT FAILURE A/E OPE RABLE. (TECHNICAL SPECIFICATION 3.6.6.4)

Ml'TAL LURGICAL GEBR;NSWiCK-1 UECCN1NMNT COMEUS GAS CONTROL SYSROUTINE TEST / INSPECTION OXYGEN FONITOR CAC-AQH-1259 FAILED DUE TO A DRAIN POT VALVF MALFUNCTION.

VALVE USED TO ISOLATE THE DRAIN POT FROM REMAINDER OF MONITOR DURING DRAIN POT ELOWDOWN. AIR FROM THE REACTOR BUILDING ENTERED THE MONITORINGSYSTEM BECAUSE THE DRAIN POT VALVE DID NOT SEAT COMPLETELY. THE AIR CA

l'<rn THr FM er Hf r# DYYrJN CONerNTP ATinN pranf NG

ASTRO INDUSTRIES INC. 05000316 051978 WHILE IN MODE 1 OPERATION REACTOR COOLANT SYSTEM UNIDENTIFIED LEAKAGE EXVALVES 78-035/03L-0 062178 CEEDED TECH SPEC 3.4.6.2.8 LIMIT. UNIT WAS STARTED DOWN 41/2 HOUDS AFTGATE 021467 30-DAY ER DISCOVERY BUT WAS RETURNED TO ORIGINAL LOADING WHEN LEAKAGE INDICATED

COMPONENT FAILURE NSSS WITHIN LIMITS. LEAKAGE EXCEEDED LIMITS TFE SECOND TIME. TbE UNIT WASOTHER WEST STARTED DOWN 4 HOURS AFTER DISCOVERY AND REMOVED FROM SERVICE 21/2 HOUR

D. C. C00K-2 AEP S LATER. THE REACTOR WAS COOLED DGWN TO MODE 5 IN THE NEX T 17 HOURS.REAC CORE ISOL COOL SYS + CONTROUTINE TEST / INSPECTION ISCLATION intyt BUWEEN RCS AND RHR FOUND TO HAVE EXCESSIVE STEM LEAK 0FF

AND PACKAGE LEAKAGE. VALVE REPACKED AND STEM LEAK 0FF ELIMINATED. RCSCETURNED TO OPERATING PRESS. AND TEMP. AND LEAKAGE WAS STILL EXCESSIVE.3AFETY VALVE ON FAILED FUEL CETECTOR FOUND LEAKING THROUGH. SAFETY VALVE PEPL ACFD AND LE AKAGE WAS PEOUCED TO NDPMAL .

ATWOOD & MORRILL CO., INC. 05000296 062678 WHILE THE UNIT WAS Ik A SHUIDOWN CUNDLIION, A Ptk!UDIC SuktLILLANCL TESTVALVE OPERATORS 78-014/03L-0 071878 WAS PERFORMED ON 1!E MSli'S. AN OUTBOARD MSIV FCV 3-1-38 CLOSED FASTER

HYDRAULIC 021781 30-DAY THAN ALLCWED BY T.S.3.7.D.1. THE RESULTING LC0 WAS OBSERVED AND MSIV FCOMPONENT FAILURE NSSS CY 3-1-37 WAS CLOSED. THERE WAS NO HAZARD TO THE PUBLIC HEAL TH AND SAFE

OTHER GE TY. PREi!OUS EVENT WAS S0-206/7813.BROWNS FERRY-3 0MAIN STEAM ISOL SYS + CONTROLSROUTINE TEST / INSPECTION INVESTIGATION REVEALED AN ATWOOD-MORRILL VALVE'S DASHPOT ASSEMELY WAS LO

W ON FLUID. FLUID WAS ADDED AND THE VALVE WAS SUCCESSFULLY RETESTED WITH TIMED P;5ULTS WITHIN THE 3-5 SEC. T.S. LIi41T. FURTHER ACTION IS TO CHECK THE DASHPOT .LUID LEVEL ONCE PER WEEK UNTIL NEXT REFUELING OUTAGE.AT THAT TIME, THE DASHPOT WILL BE REBUILT.

C/S 107tx;h4T.CD

Ts,r .,tun

esg.C2OLICENSEE EVENT REPORTS

COMPONENT F#.LFACTURER CCCnET '.0.COMPONENT /CCFFCNENT SLECCCE LEF NO.CAUSE C0rE/CALSE SLECCCE CChirnL *.0. EiENT CATE'FeCILITY/ SYSTEM SLFFLIER REFCRT C;'E EVENT [F SCRIPTIONbTTFCD CF CiSCOVERY NSRS / A/F FEPCPT TYrf cal'7F DESCRIPT10N

ATWOOD & MOFRILL CO., INC. CSCC0237 05137E CLRING STEAD) STATE CFERATICN, TORUS TO DRYhELL VACULM BREAKERS 2-1601-3VALVES 7E-C32/C3L-C C00970 E & F LEFE F0LtD INCFERABLL CLRING ROUTINE OPERABILITY SLRVEILLANCE. 2-

CFECK C21512 3C-EA) 160-33F FAP A*. EXCESSIVE CPENING TCRQUE AND BOTH FAILED TO FREELY SWINGCOPPGNENT FAILLRE NSSS CLCSED AS FECLIRED EY T.S. 3.7.A.4 THE VALVES WERE SECURED CLOSED AND

MECFANICAL GE NCR"AL OPEF AT!CN CONTINUED SINCE 10 (9 PEQUIRED) VACLUM EREAKER S WEFE OCFESCEN-2 S+L PERAELE. SIMILAR EVENTS: 77-77, 76-8 AND 74-11 & 27.REACTCR CONTAIN"E',T SYSTEMS

FOLTINE TEST /INSFECTIC!< EI'QING OF 2-1f01-33E & 33F WAS A RESLLT CF SHELLING CF THE TEFLON SHffTE L SF It'GS . EDTF BUSHINGS ON 2-1EC1-33E ANC ONE BUSHING ON 2-1601 33F RE

QUIPED NAChlNING TO INCREASE ThE CLEARANCE FOR PROFER VALVE CPERATION.EFCNZE ELSHINGS WILL BE INSTALLED ON FUTLRE OVERF ALLS OF TCRUS TO EPYhEL

VActtM E;FAvFPS. CN EOTH MNITS 2 & 3'

ATWLUD & N0 KRILL LO., I?L. C50002b4 Cti7;e .FLN $LPFFE5510N CF AFBER IG U.JLLLL Dli f E kthlI AL F hts 5U kl N JANL LifFILUkALVES 78 01E/C3L-0 CE2676 Li TO PAINTAIN, TFE VACULM BREAKERS WERE TESTED. V ACCUM BFtf4ER 1-1E01-3

CFECK C217ES 3C-CAY 3E WOLLD NOT GItE A FULLY CLOSED INDICATICN AND SUPPPESSIG'. CFAPCER TO DCCMPGLENT FAILLRE ESSS 7.iWLLL CIFFEFEiTI AL i cES$URE CDULD 0 LCNGER BE MAINTAINED. TFE UNIT LAS

PECPANICAL GE SHLTCCWN IN ACCCRDANCE WITF TECH SPEC 3 .7. A.4.6. ALL OTFER VACULM BREA

CLAD CITIES-1 5+L KEPS FUNCTIChEC AS CESIGNED.REACTOR CCLTAINCEhT SYSTEMSCPERATICNAL EiENT INSFECTION OF iACULM EREAKER 33E REiE' LEO THAT TnE SHAFT WAS BINDING. D

ISASSEPELY PEtEALED THE PACKING ON CNE SICE CF YhE VALVE WAS BILDING. NEW TEFLON PACKING KAS INSTALLED Ah? A .010 SHIF WAS REMOVED TO PEOPERLYADJUST THE NEW FACKING. AFTER R EASSEMELING TFE k ALVE. IT WAS CHECKED FO

I o Tur ArrFcroIATE TOPCLE AND OPEEATICNALLY TESTED.AUICFATIC SWITCP CO (ASCG L50003C4| 05C.976 i+ILE A TTEMPTING TO STROFE 2FCV-I ACIA. ( CLhl:iu IHL FONTHLT LONTAINMENl I

VALiE OPERATCRS 73-C29/03L-0 C6087E SCLATICN V AltE TEST TT-3CO) THE VALVE FAILED TO CLOSE, PLACING THE CONTSCLE!.CIC - AC '''1451 | 30-CAY AIh"ENT ISCLATION Sv5 TEM IN A CCGRACED MOCE. FPEVICUS SIFILAR EVENTS:

COMFCNEST FAILLFE s/E I ,d-22.17; 77-42, 29, 4. THE HEALTH AND SAFETY OF Thf. FUblIC WERE NOT /FFECMANICAL kEST FECTi; SINCE 1rE PEDLNCANT :0CLATION VALVES 2FCV-IAC1B AND 2PP0170 VERE

ZION-2 5+L GF E RABL E .

Cr NPNT ISCLATICN SYS + CCNTFULTINE TEST /INSFECTION ASCO B320 50LE101D VALVE FAILCD H r TO OIL a., .:.s.TUMENT AIR. OIL LCCGE

S ON SCLEh01D FLL'.GEP WFEFE C0ll WEAT BAKES IT INTL VAF215'., ADHERINGTHE PLLNGER TO ThE FLUNGER SLEEV, THE PLUNGER WAS FRLEC Lc AND THE VALiE LAS PFCVEN CFERAF.LE.

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COMPONENT MANUFACTUPER DOCKET NQ

COMPONENT / COMPONENT SUBCODE LER NO.CAUSE CODE /CAUSE SUBC00E CONTROL NO. EVENT DATE


METHOD OF DISCOVERY NSSS / A/F PEPORT TYpf CAnSE DESCRIPTInN

AUTOMATIC SWITCH C0 (ASCO 05000304 060578 DURING THE MONTHLY CONTAINMENT ISOLATION VALVE TEST TT-300, THE FOLLOWIN

VALVE OPERATORS 78-045/03L-0 070578 G VALVES FAILED TO STROKE: 2FCV-I AA 01A, 2SS-9356A, 2 A0V-B C0007. THIS

SOLEN 0ID - AC 021709 30-DAY PLACED CONTAINMENT ISOLATION SYSTEM IN A DEGRADED MODE IN VIOLATION OF T

COMPONENT FAILURC A/E .S. 3.9.3.A. A REDUNDANT ISOLATION VALVE IN SERIES WITH EACH FAILED VALV

MECHANICAL WEST E WAS OPERABLE. PREVIOUS LER'S: 50-304/78-39, 77-4; 50-295/78-32, 78-1

ZION-2 S+L 7, 77-42, 77-29.CNTNMNT ISulATION SYS + CONTROUTINE 'rqT/ INSPECTION ASCO 8320 SCLEN0ID VALVES FAILED DUE TO OIL IN INSTRUMENT AIR. OIL LODG

ES ON SCLEN0ID PLUNGER WHERE C0!L HEAT BAKES IT TO A VARNISH, ADHERING PLUNGER TO PLUNGER SLEEVE. SOLEN 0ID VALVES WERE REPLACED. OIL TRAPS MAYEE INSTALLED IN THE AIR LINES.

AUTOMATIC (x5C0 05000304 070378 WHILE ATTEMPTING TO STROKE 2FCV-IA018. (DURING THE MONTHLY CONTAINMENT I

VALVE C" - 78-051/03L-0 080278 SOLATION VALVE TEST TT-300), THE VALVE FAILE: TO CLOSE, PLACING THE CONT

SOLEk - AC 021928 30-DAY AINMENT ISCLATION SYSTEM IN A DEGRADED MODE IN VILLATION OF T.S. 3.9.3.ACOMPO4;NT FAiLUFE A/E PREVIOUS SIMILAR EVENTS: 78-39, 32; 77-42, 29, t.. THE HEALTH AND SA

MECM NICAL WEST FETY OF THE PLELIC WAS NOT AFFECTED SINCE THE REDUNDANT ISOLATION VALVE4

Z IC'- 2 S+L ZFCV-I A01A WAS OPERABLE.

CN'tMNT ISOLATION SYS + CONTR'x) TINE TEST /INSFECTION ASCO 8320 SCLEN0ID VALVE FAILED DUE TO OIL IN INSTRUMENT AIR. DIL LODGE

S ON SOLENGID PLUNGER WHERE COIL HEAT BAKES IT INTO A VARNISH, ADHERING

I THE PLUNGER TO THE PLUNGER SLEEVE. THE PLUNGER WAS FREED UP AND TFE VALVE WAS PROVEN CPERABLE. INVESTIGATION CONTINUES.

# AUTDMATIC SWITCH CO (ASCO 05000295 070778 WHILE ATTEMPTING TO STROKE 1FCV-PR24B (DURING MONTHLY CONTAINMENT ISOLAT

VALVE OPERATORS 78-059/03L-0 080478 IGN VALVE TEST TT-300), THE VALVE FAILED TO CLOSE, PLACING THE CONTAINME

SOLEN 0ID - AC 021973 30-DAY NT ISOLATION SYTEM IN A PEGRACED MODE IN VIOLATION OF T.S. 3.9.3. A. PR

| COMPONENT FAILURE A/E EVIOUS SIMILAR EVENTS: 78-51, 39; 77-42, 29, 4. THE HEALTH AND SAFETY

I MECHANICAL WEST OF THE PUBLIC WRE NOT AFFECTED SINCE THE REDUNDANT ISCLATION VALVE 1FCV

ZION-1 S+L -PR24A WAS OPEPABLE.I CNTNMNT ISOLATION SYS + CONT

ROUTINE TEST / INSPECTION A3C0 8320 SCLEN0ID VALVE FAILED DUE TO OIL IN INSTRUMENT AIR. OIL LODGES ON SOLEN 0ID PLUNGER WHERE CGIL HEAT EAKES IT INTO A VARNISH, ADHERINGTHE PLUNGER TO THE PLUNGER SLEEVE. THE PLUNGER WAS FREED UP AND THE VALVE WAS PROVEN OPERABLE. FURTHER INVESTIGATION CONTINUES.

109(7)C,C7;p.

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C)aWU.

LICENSEE EVENT REPORTS hCOMPONENT MANLFACTURER DOCKET N0.COMPONENT / COMPONENT SUBCODE LER NO.CAUSE CODE /CAUSE SUBCODE CONTROL NO. EVENT DATEFACILITY / SYSTEM SUPPLIER REPORT DATE EVENT LESCRIPTIONMETu00 nF DISCOVERY NSSR / A/E CEPOPT TYPE CAUSE DESCPIPTION

AUTOMATIC SWITCH CO (ASCO 05000263 C60578 WHILE PERFORMING SCRAM TEST 0081 DURING PLANT STARTUP SCRAM INSERTION OFVALVE OPERATORS 78-010/03L-0 070578 CRD 06-19 DELAYED FOR INDEFINITE PERIOD OF TIME. 4 HEN R0D DID NOT SCRAMSOLENDID - At 021755 30-DAY AFTER S SECONDS CONTROL ROCM GPERATOR FULLY INSERTED IT. R0D WOULD HAV

CCMPONENT FAILURE *555 E SfRAMMED DURING ACTLAL PLANT SCRAM CUE TO BACFUP SCRAM PILOT VALVES. E.

OTHER GE VENT REPORTABLE PER T.S. 6.7.B.2.B. EVENT HAD NO EFFECT ON PUBLIC HEALTMONTICELLO-1 BECH H AND SAFETY. ALL OTHER RODS OPERABLE. NO SIMILAR PPEVIOUS OCCURRENCE.REACTIVITY CONTROL SYSTEMSROUTINE TEST / INSPECTION BUNA-N DISC IN SCRAM PILOT VALVE SOLEN 0ID PLUNGER BROKE INTO SEVERAL PIE

CES WEDGING & PREVENTING VALVE FROM VENTING AIR ON SCRAM VALVES. DISC WAS BRITTLE. VALVE MFG INVESTIGATING CAUSE OF FAILURE. PLUNGER ON REDUNDANT $0LEN01D INSPECTED & FOUND SATIS. PLUNGER INCL DISC REPLACED. VALVE TEST & POD SCPAMvED SATIS. PPnG INITI ATED TO PEPL PL UNG IN SCPAM P/V.

AUTOMATIC SWITCH C0 (A5CO GSG00263 072876 ULRING REVILW CF SCRAM IN5LR110N IIML5 FULLUWING RLACTOR SCRAM, II WAS DVALVE OPERATORS 78-014/01T-0 081078 ETERMINED THAT CPD 30 47 DELAYED APPk0XIMATELY 1.4 SECONDS BEFORE SCRAMM

SOLEN 0ID - AC 021985 2-WEEK ING. DURING SUCSEQUENT SURVEILLANCE TEST CRD 30-47 FAILED TO SCRAM. R0COMPONENT FAILURE NSSS D SCRAMMED IN ACTUAL PLANT SCRAM CUE TO BACKUP SCRAM PILOT VALVES. EVEN

NATURAL END OF LIFE GE T REPORTAELE PER T.S. 6.7.B.1.I. EVENT HAD NO EFFECT ON PUBLIC HEALTH AMONTICELLO-1 CECH ND SAFETY. ALL RODS OPERABLE. ONE SIMILAR PREVIOUS OCCURRENCE (M-RO-78FEACTIVITY CONTROL SYSTEMS -10).ROUTINE TEST / INSPECTION CUNA-N DISC IN SCRAM DILOT VALVE SCLEN01D PLUNGER BROKLN INTO SEVERAL PI

ECES WEDGING & PREVENTING VALVE FROM VENTING AIR ON SCRAM VALVES. DISCWAS BRITTLE DUE TO NATURAL END OF LIFE. PLUNGER ON THIS & ALL OTHER SCRAM PILOT VALVES REPLACED. 6 ADDITIONAL FAILED PLUNGER DISCS FOUND. ALL VELVES FUNC TESTED SATIS F0P SrPAM OPNS. PM INITL TO REPt PLUNG PERIODirl

AUTOMATIC SWITCH CO (ASCO 050C0249 04247E WHILE UNIT 3 WA5 LOLKED IN Ptf uEL. U3 DIL5EL OIL 510kAGL I ANK WA S DISCOVVALVES 78-G18/03L-0 052278 ERED AT 9000 GAL, WHICH IS BELOW THE 10,000 GAL LIMIT REQUIRED BY T.S.3.

GATE 021461 30-DAY 9.C. THE REDUNDANT DIESEL GENERATOR WAS AVAILAELE AND UNIT 3 WAS NOT ATCCMPCNENT FAILORE A/E POWER. THIS IS TFE FIRST OCCURRENCE OF THIS NATURE.

MECHANICAL GECRESCEN-3 5+LEMERG GENEF.ATOR SYS + CONTROLSOPERATIONAL EVENT il.E EVENT WAS CAUSED BY ?/3 FIRE PUMP DAY TANK LEVEL CONTROL VALVE SEING

STUCK OPEN BY A PIECE OF METAL AND FUEL FLOWING INTO D AY TANK FROM STORAGE TANK. UPON DISCOVERY OF STORAGE TANK LOW LEVEL ALARM, FUEL WAS ORDCRED AND CONTROL VALVE REBUILT. NO ADDITIONAL CORRECTIkE ACTION NECESSARY.

J)


CCMFONENT MANLFACTLRER DOCKET LO.

COMPONENT /COMPCf.ENT SLELCDE LER NC.

CAUSE CCCE/CAUSE Sd C0CE COM RCL NO. EVENT CATE

FACILITY / SYSTEM SUPPLIEP EEPOPT DATE EVENT DESCRIPTIONPETurD rr DISCrVEcy m / A/E :r' N T TvFE CAUSE PESCRIPTICN

BAECOCK & WILCCX CANADA LTD. OSCC0346 061678 PSRFORMING SLRVE!LLANCE TESTING 6/IE/78 HORIZONTAL VIBRATION OF HIGH PREPUMPS 7E-C6C/03L-0 071278 SSURE INJECTION PUMP 1-1 IhECARD AND OUTBOARD EEARINGS WAS 1.6 AND 1.5 M

CENTRIFUGAL C21ESE 30-CAY ILS WHICH IS IN EXCESS OF BASELINE TOLERANCE. UNIT IN VODE 6 AND h0T PLCCMFGNENT FAILUFE hSSS ACED IN ANY ACTION STATEMENT. NO DANGER TO HEALTH AND SAF ETY OF PUBLIC

MECFAhICAL B+W CR UNIT PERSONNEL. THE INCRFASE :N VICRATION SLIGhTLY ABOVE ALLOWED TOLCAVIS-EESSE-1 CECH ERANCE WOULD NOT HAVE PREVENTED PLMP FROM PERFORMING PROPERLY.

EMEFG CORE CCCLING SYS + CONTFLMP MOUNTING CCLTS HAD LOOSENED AND ALLOWED PUMP TO MOVE SLIGHTLY OUT 0PCUTIhE TEST /INSFECTIONF ALIGNMENT. PLMP MOUNTING BCLTS WERE TIGHTENED AND PUMP RE-ALIGNED WITH MOTOR. SURVEILLANCE TEST WAS PERFORFED AND VIERATION LEVELS WERE LESSTFAN 1 MIL. ON E/25/78, FPI PLMP 1-1 LECLARED OPERABLE.

BAECOCV & WILCCX CANADA LTD. 050CC312 OE227E WHILE IN A CSD CONDITIch WITI: THE A DHR SYSTEM IN CPERATION, FREQUENT LE

PUMPS 78-0C7/03L-0 CC2378 VEL CPANGES In THE MAKE-UP TANK WERE OBSERVED. A RESULTANT INVESTIGATIO

CEhTPIFUGAL 021744 30-LAY N FOLND LEAKAGE IN DCESS OF THE 0.63 GPH ALLOWAELE PER T.S. SECTION 4.5

COMPONENT FAILURE A/E .3.1 FFOM THE B DbR PLMP SEAL. THE PUMP WAS VALVED CUT AND PLACED UNDER

VECHANICAL E+W CLEARANCE AND TPE A - DPP SYSTEM CONTIhUED IN CPERATION

PA'.Ch0 SECO-1 EECH

PESIDLAL HEAT REMOV SYS + CONTUEFATIONAL EVENT TPE LEAKING SEAL WAS REPLACED AND SP 203.09 DHR SYSTEM LEAKAGE SURV EILLA

NCE TEST WAS FUN WITH SATISFACTORY RESULTS PRIOR TO DECLA RING THE SYSTEMCPERACLE.

LALCCCF A WILCOX C0f*PANY OSCCO269 042178 CURING h0FMAL OPEPATIOh5 ON APRIL 20. RIA 40 ALARMED IhDICATING A POSSISFEAT EXCFAi,GERS 78-013/0IT-0 CE0578 LE PPIt'ARY-TO-SEC0hDARY LEAK. ON APRIL 21, AFTER REACHING TS LEAVAGE LI

STEAM GENEFATOR C21526 2-WEEK MIT. TFE UNIT W!E SHLT 00WN FOR INVESTIGATION AND REPAIR OF IB OTSG. INICOMFC'.EN7 FAILLFE f>SSS TIAL LYDRO TESTS WEPE INCONCLUSIVE. CONTINUED IhVESTIGATION VERIFIED ON

MECHAhICAL E+W E WELD CRACK, ONE TLEE CRACK, AND TWO OTHER SUSPECT TUBES. A TTEMPTS TO

OCCLEE-I 0/EECH PEMOVE A LANE TLLE FOR EXAMILATION FAILED & IT WAS PLUGGED DURING OUTAG

MAIN STLAM SYSTEMS + C0hTRCLS E. EVENT DID NOT AFFECT PUBLIC HEALTH AND SAFETY.THE LE AKAGE ORIGINATED IN ONE OR MORE OF THE FOUR SUSPECT TUBES. ONLY TWCFEPATIONAL EVENT 0, 69-1 (WELD) AND 74-2 (CRACK), H/D VERIFIED FAILUPES. FIVE TUEES IN ALL WERE PLUGGED, INCLUDING TEE LANE TUBE WHICH COLLD NOT BE REMOVED. INVESTIGATIONS BY LULE AfD E&W ARE CONTINUING.

C 111

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M.L'~HLO

LICENSEE EVENT REPORTS NGJ

COMPONENT MANUFACTURER DOCKET NO.COMPONENT / COMPONENT SUCC00E LER NO.CAUSE CODE /CAUSE SUBC00E CONTROL NO. EVENT DATEFACILITY / SYSTEM SUPPLIER REPORT DATE EVENT DESCRIPTIONMETHOD OF DISCOVERY N5SS / A/E REPORT TYPE CAUSE DESCRIPTION

BABC0CK & WILCOX COMPANY 05000312 0E0478 ON AUGUST 4,1978, B&W REPORTED THAT AS A RESULT OF CHEMICAL ANALYSIS PEVESSELS PRESSURE 78-008/02T-0 081578 RFORMED ON ARCHIVE WELDMENTS THEY DISCOVERED THAT WELD FILLER WIRE ATYPI

REACTOR VESSEL 022007 2-WEEK CAL OF THE WELD FILLER WIRE USED BY B&W IN CONSTRUCTION O F NUCLEAR PRESSDESIGN / FABRICATION ERROR NSSS URE VESSELS WAS UNKNOWINGLY MIXED BY THE SUPPLIER WITH A SHIPMENT TO MN

MANUFACTURING B+W -MO-NI FILLER WRE. THE ATYPICAL WIRE HAS HIGH SILICON AND LOW NICKEL CRANCHO SECO-1 BECH ONTENTS OUTSIDE OF THE TYPICAL RANGE FOR WIRE SPECIFIED BY B&W.REACTOR VES. + APPURTENANCESEXTERNAL SOURCE INADEQUATE Q.A. ON MATERIAL PROCUREMENT BY NSS SUPPLIER. THIS WILL REQU

IRE ADDITIONAL ANALYSIS AND TECHNICAL EVALUATION BY THE NSS SUPPLIER WITH RESULTANT T.S. CHANGES IN THE AREA 0F HEAT UP AND COOL DOWN LIMITS. (T5 3.1.2). THESE CHANGES ARE BEING SUBMITTED AS REV. 1 TO T.S. AMENDMENTNO. 59.

BABCOCK & WILCOX COMPANY 05000289 080778 F11-ED RLCEIVLD NU11FICATION FROM B&W THAT WELD FILLER WIRE ATYPICAL OFVESSELS PRESSURE 78-024/01T-0 082178 WIRE 'PEC;FIED BY B&W MAY HAVE BEEN USED IN CONSTRUCTION OF THE TMI-1 RE

REACTOR VESSEL 022053 2-WEEK ACTOR VESSEL. REPORTABLE PER T.S. 6.9.2.A.(9). THE STR UCTURAL INTEGRITDESIGN / FABRICATION ERROR NSSS Y OF THE VESSEL 15 NOT COMPROMISED AND NO THREAT TO PUBLIC HEALTH AND SA

MANUFACTURING B+W FETY IS INVOLVED.THREE MILE ISLAND-1 GILREACTOR VES. + APPURTENANCESEXTERNAL SOURCE ATYPICAL WELD WIRE WAS UNKNOWINGLY MIXED BY THE SUPPLIER IN A SHIPMENT 0

F WIRE TO B&W. B&W DISCOVERED THIS CONDITION DURING C HEMICAL ANALYSIS 0F ARCHIVE WEL0MENTS. WHILE A REVISED TECH SPEC IS BEING PREPARED, PRELIMINARY INFORMATDN SUPPLIED BY B&W WILL BE USED TO GOVEr,N P-T HEATUP & COCEDOWN

BAILEY INSTRUMLNT CO., INC. 05000316 060378 WHILE IN MODE 1 OPERATION PRESSURIZER PRESSURE STARTED DEC LINING RAPIDLYVALVE OPERATORS 78-043/03L-0 071178 PRESSURIZER SPRAY VALVE CONTROLLERS WERE PLACED IN MANUAL AND GIVEN A

PNEUMATIC / DIAPHRAGM / CYLINDER 021674 30-DAY CLOSE SIGNAL. PRESSURE CONTINUED TO DECLINE AND REACTOR WAS MANUALLY TCOMPONENT FAILURE NSSS RIPPED 8 MIN AFTER START OF EXCURSION. TRIP PRESSURE WAS 2 000 PSIG WHIC

INSTRUMENT WEST H WAS 205 PSI LESS THAN TECH SPEC 3.2.5 EUT 100 PSI GREATER THAN AUTO. TD. C. C00K-2 AEP RIP. NO PROBABLE CONSEQUENCES.OTHER COOLANT SUBSYS + CONTROLOPERATIONAL EVENT INVESTIGATION FOUND ONE OF TWO PRESSURIZER SPRAY VALVES FAILED ONE HALF

OPEN. PROBLEM WAS TRACED TO AN IMPROPERLY INSTALLED GASKET IN THE VALVEPOSITIONER. A NEW GASKET WAS PROPERLY INSTALLED AND THE UNIT RETURNED

TO SERVICE. NO FURTHER ACTIONS ARE PLANNED.

112


COMPONENT MANUFACTURER DOCKET NO.COMPONENT / COMPONENT SUBCODE LER NO.CAUSE CODE /CAUSE SUBCODE CONTROL NO. EVENT DATEFACILITY / SYSTEM SUPPLIER REPORT DATE EVENT CESCRIPTIONMETHOD OF DISCOVERY NSSS / A/E PEPnDT TYPE CAUSE prstpIPTION

BARBER MFG. COMPANY 05000249 060678 DURING MONTHLY SURV. PS3-263-53A TRIPPED AT 1178 PSI (VALUE INCLUJES 10INSTRUMENTATION + CONTROLS 78-024/03L-J 062378 PSTG HEAD CORRECTION). T.S. TABLE 3.2.2 REQUIRES A TRIP TO OCCUR AT 1/

SENSOR / DETECTOR / ELEMENT 021508 30-DAY =1070 PSIG. THE (4) SUSTAINED HIGH RX PRESS. SW'S OPEN ON INLREASING PRCOMPONE 'T FAILURE NSSS ESS. 1065+/- 5 PSIG TO INITIATE ISOLATION COND. AFTER 15 SEC TIME DELAY

INSTRUMENT GE REMAINING SW'S WOULD HAVE PLRFORMED THEIR FLNCTION AT 1064 PSIG. SIMDRESDEN-3 S+L ILAR EVENTS AS REF. IN LER #76-11.EMERG CORE COOLING SYS + CONTROUTINE TEST / INSPECTION CAUSE ATTRIBUTED TO INSTRUMENT DRIFT. PS-3-263-53A WAS PROMPTLY RESET T

0 1066 PSIG AND REPEATABILITY WAS VERIFIED. THE SUSTAINED HIGH REACTORPRESSURE SWITCHES WILL CONTINUE TO BE TESTED MONTHLY.

BARKSDALE COMPANY 05000321 070578 DURING OPERATION WHILE PERFORMING SURVEILLANCE TEST NPI-3414 RCIC TURBININSTRUMENTATION + CONTROLS 78-055/03L-0 072078 E EXHAUST DI APHRAGM PRESSURE SWITCH E 51-N0120 FAILED TO ACTUATE TURBIhESWITCH 021758 30-DAY TRIP LOGIC AT % 10 PSIG PLUS 13.8 PSIG HEAD. AS PER T.S. TABLE 3.2-3 IT

COMPONENT FAILURE NSSS EM 11. idIP POINT WAS 25.4 PSIG REDUNDANT SWITCHES WERE OPERABLE. SIMIINSTRUMENT GE LAR EVENTS ARE 75-23, 75-26, 77-10, 77-96.

EDWIN I. HATCH-1 SSC/BECHREAC CORE ISOL C00L SYS + CONTROUTINE TEST /'NSPECTION EVENT WAS CAUSED BY SETPOINT DRIFT. SWITCH RECALIBRATED AND TESTED SATI

SFACTORILY.

BARKSDALE VALVE COMPANY 05000lb5 051278 DURING ROUTINE TESTING, THE CONTROL R00 DRIVE ACCUMLATOR PR ESSURE SWITCH

INSTRUMENTATION + CONTROLS 78-024/03L-0 061278 FOR DRIVE A-5 kAS FOUND TO OPERATE AT 645 PSIG. THIS IS BELOW THE REQUISWITCH 021438 30-DAY RED SET POINT OF 700 PSIG DESCRIBED IN T/S 6.2.1(A). THE SWITCH WAS IMM

COMPONENT FAILURE A/E EDIATELY READJUSTED AND ALL OTHER 31 ACCUMULATOR PRESSURE SWITCHES WEREOTHER GE FOUND SATISFACTORY; THUS N0 UNDUE HAZARD EXISTED. PREh!OUS SET POINT P

BIG ROCK POINT BECH ROBLEM REPORTED AS R0-10-76 DATED 6/25/76 WAS ON SWITCH FOR DRIVE F-2.ENGNRD SAFETY FEATh ihSTR SYSROUTINE TEST /INSPECTIDN EXACT CAUSE OF FAILURE IS UNKNOWN. PREVIOUS MINOR DRIF T PROBLEMS WITH T

HIS TYPE OF SWITCH f.RE NORMALLY COMPENSATED FOR BY USING A SWITCH SET POINT OF 750 PSIG TO PROVIDE OPERATING MARGIN. SWITCH IS A BARKSDALE MODEL NUMBER 82T-A32SS.

f.4)to 113

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. .q.

(f?LICENSEE EVENT REPORTS N

CCOMPONENT MANUFACTURER C0CKET NO.COMPONENT /COMPGNENT SUECODE LER NO.CAUSE CODE /CAUSE TLECODE CONTROL h0. EVENT DATEFACILITY / SYSTEM SUPPLIER REPCRT DATE EVENT DESCRIPTIONMETu00 0F DISCOVE0Y NSSS / A/E ;rrORT TvrE CAUSE DESCRIPTION

BARKSDALE VALVE COMPANY 05000220 052778 DURING ROUTIhE STARTLP CPEFATIONS PERFORMANCE OF SURVEILLANCE TEST N1-ISINSTRUMENTATION + CONTROLS 78-022/03L-0 061278 P-02-13 FOLND TURBINE ANTICIPATORY TRIP BYPASS REACTOR SCRAM SWITCH 02-

|SWITCH 021440 30-CAY 12A WITH A SETPOINT OF 367 PSIG. THIS EXCEEDS THE 3 SS +/- S PSIG SPECIFl

COMPONENT FAILURE 5555 ED BY PRCCELLFE. THIS CONDITION RESLLTED IN MINIMAL SA FETY IMPLICATIONS,INSTRLMENT GE -

RECUNCANT IhSTRLMENTATION WAS AVAILABLE IN THE CHANNEL.NIhE MILE Point-1 0EhCNRD SAFETY FEATP .NSTR SYSROUTIhE TEST / INSPECTION THE CrANCE IN !EIP if 7 POINT ON THE BARKSDALE MODEL 2T-AISS PRESSURE SWIT

CH WAS << n' INSTPLVENT ORIFT. IT WAS RESET TO 357 PSIG. CURRENT SURiEILLANCE TESMNG SCHEDULES ARE ADEQUATE TO INSUFE EARLY DETECTICN OF FUTLPE INSTRLFEN! 3|FTS.

CARKSDALE VALVE COMPANY 05000259 0S3078 DLRING NORMAL OPERA!!CN WHILE SURVEILLANCE TESTING TURBINE FIRST STAGE PINSTRUMLNTATION + CONTROLS 78-016/03L-0 CE2278 RESSURE PEFMISSIVE, PRESSURE SWITCHES PS-1-81A, PS-1-81E AND PS-1-91B FASWITLH 02 EE0 3C-DAY ILED TO MEET T.S. TABLE 3.1.A. CONTROL VALVE FAST CLOSURE AND TURBINE S

COMPCNENT FAILORE NSSS TOP VALVE CLOSURE SCRAMS WERE BYPASSED AT LESS THAN 30% POWER. THERE WEOTHER GE RE NO REDUNCANT CHANNELS AVAILABLE. THEFE WAS NO POTENTIAL FOR HAZARD T

BROWNS FERRY-1 0 0 THE PUELIC HEALTH OR SAFETY.REACTOR TRIP SYSTEMSROUTINE TEST / INSPECTION SWITCHES WERE FOUND TO HAVE CRIFTED AB0VE T.S. LIMIT. SWITCHES ARE BARK

SDALE MODEL B2T-A12SS. THE SWITCHES WEFE INSPECTED, RECALIERATED, AND FJNCTIONALLY TESTtD SATISFACTORILY. SURVEILLANCE CATA FOR THE PAST 6 M0NTHS VAS REVIEWED, AND N0 GENERIC PROBLEMS WERE INDICATED.

EARKSCALE VALVE COMPANY 0E000293 071778 ON JULY 17, 1978 WHILE PERFORMING A SURVEILLANCE ON P.C.I.S. REACTOR HIGINSTRUMENTATION + CONTROLS 78-031/03L-0 072478 H PRESSURE, THE PRESSURE SWITCHES PS-261-23A&B WERE FOUND TO BE OUTSIDE

SENSOR /DETECTCR/ ELEMENT 021964 30-CAY OF THE ALLOWABLE RANGE. THE REQUIRED SETPOINT IS t/= 110 PSIG. THE PSDESIGN /FABRICA!!CN ERROR NSSS 261-23A ACTIVATED AT 117 PSIG AND THE PS 261-23B ACTIVATED AT 115 PSIG.

MANUFACTURIhG GE

PILGRIM-1 EECHRESIDUAL HEAT U U 3YS + (CNTROUTINE TEST /INSFLCTION THE CAUSE OF THIS EVENT WAS MIh0R SETFulNT ORIFT OF A BARKSDALE, 0-1500

PSIG, MODEL B2T-A12SS PRESSURE SWITCH. THE SWITCHES WERE RECALIBRATED AND TESTED SATISFACTORILY.

114


CCMPONENT MANUFACTURER DOCKET NO.

COMPCNENT/ COMPONENT SUBCODE LER NO.CAUSE CODE /CAUSE SUSCODE CONTRCL NO. EVENT DATE

FACILITY / SYSTEM SUPPLIER REFORT DATE EVENT DESCRIPTION

FETHOD OF DISf0VEPY NSSR / A/F REPORT TYPE CACsr OEstpIPTION

BARTON INSTRU CO., DIV 0F ITT 05000247 021678 DURING PERFORMANCE OF SURV TEST PC-R11 REFUELING H2O STORAGE TANK LEVELINSTRUMENTATICN + CONTR0; - 78-00E/03X-1 063078 TRANSMITTER CALIBRATION, ONE OF THE TWO LOW LEVEL ALARMS WAS FCUND TO B

CONTPOLLER 020741 OTHER E SET BELOW THE MINIMUM LEVEL REQUIRED BY TECH SPEC 3.3. A.I.K. THE REDU

C0MPCNENT FAILURE NSSS SDANT LOW LEVEL ALARM, LT 920 SETPOINT WAS WITHIN THE REQUIRED RANGE.

INSTRUMENT WEST HOWEVER, IT WAS SUBSEQUENTLY FOUND THAT THIS INSTRUMENT, LT-920, HAD BEE

INDIAN POINT-2 UEC N OUT OF SERVICE FOR A PERIOD FROM 1/4/78 TO 2/13/78.ENGNRD SAFETY FEATR INSTR SYSROUTINE TEST / INSPECTION THIS EVENT WAS CAUSED BU ALARM SETPOINT DRIFT OF LEVEL INSTRUMENT CONTRO

LLER LIC-921 (BARTON INSTRUMENT CO, MOD 288). THE LEkEL CONTROLLER WASRESET, THEREBY RETURf'ING THE RWST LEVEL ALARM TO WITHIN i.;MITS. THIS EVENT IS REPORTABLE UNDER THE PROVISIONS Of TECH SPEC 6.9.1.7.2 (A).

BARTON INSTRU CO., DIV 0F ITT 05000220 052778 CURING ROUTINE TARTUP OPERATIONS, PERFORMANCE OF SURVEILLANCE TEST N1-I

INSTRUMENTATION + CONTROLS 78-021/03L-0 061278 SP-RE04, FOUND Rt04A AND RE04B WITH A SETPOINT OF 3.65 PSIG. THE REQU

SWITCH 021441 30-DAY ! RED SETPOINT OF THESE DRYWELL HIGH PRESSURE SWITCHES IS 3.50 PSIG +/-COMPONENT FAILURE NSSS 0.053 PSIG. THIS CONDITION RESULTED IN MINIMAL SAFETY IMPLIC ATIONS.

INSTRUMENT GE

hlNE MILE POINT-1 0ENGNRD SAFETY FEATR INSTR SYSROUTINE TEST / INSPECTION THESE CHANGES IN SETPOINTS EXPERIENCED ON BARTON MODEL 289 PRESSURE IND

ICATING SWITCHES WERE DUE TO INSTRUMENT DRIFT. RE04A WAS RESET AT 3.52PSIG, AND RE04B WAS RESET AT 3.00 PSIG. CURRENT SURVEILLANCL TESTING SCHEDULES ARE ADEQUATE TO ENSURE EARLY DETECTION OF FUTURE INSTRUMENT DRIFTS

UARION INSlRU CO., DIV Uf III U5000220 052678 DURING ROUTINE STARIUP UPERATIONS, PERfUkMANCE OF SURVEILLANCE TEST N1-I

INSTRUMENTATION + CONTROLS 78-020/03L-0 061278 SP-RE18, FOUND REI8A WITH A SETPOINT OF 135 INCHIS WC. REQUIRED SETPOIN

SWITCH 021442 30-DAY T OF RX LO-LO-LO WATER LEVEL IS LESS THAN/= 127.1 INCHES WC +/- 2.6 INCHCOMPONENT FAILURE NSSS ES WC. THIS CONDITION RESULTED IN MINIMAL SAFETY IMPLICATIONS.

INSTRUMENT GE

NINE MILE POINT-1 0

ENGNRD SAFETY FEATR INSTR SYSTHE CHANGE IN SETPOINT EXPERIENCED ON THE CARTON F0 DEL 288 LEVEL INDICATROUTINE TEST / INSPECTIONING SWITCH WAS DUE TO INSTPUMENT DRIFT. IT WAS RESET TO 126.0 INCHES WC

CUPRENT SURVEILLANCE TESTING SCHEDULES ARE ADEQUATE TO ENSURE EAR LYDETECTION OF FUTURE INSTRUMENT DRIFTS.

115CDNfi'.ha-s}ycs

l')[*v5C.9')GO


COMPONENT MANUFACTURER DOCKET NO.COMPONENT / COMPONENT SUBCODE LER NO.CAUSE CODE /CAUSE SUBCODE CONTROL NO. EVENT DATEFACILITY / SYSTEM SUPPLIER REPORT DATE EVENT DESCRIPTIONMETHOD OF DISCOVERY NS$5 / A/F EFPORT TYPF CAUSE DESCRIPTION

BARTON INSTRU CO. , DIV 0F ITT 05000220 062476 DURING STEADY STATE CPERATION, PERFORMANCE OF SURVEILLANCE TEST N1-ISP-RINSTRUMENTATION + CONTROLS 78-025/03L-0 071378 E04, FOUND RE04D WITH A SETPOINT OF 3.70 PSIG. T.S. 3.6.2A REQUIRES THE

SWITCH 021713 30-CAY DRYWELL HIGH PFESSURE SWITCHES T0 HAVE A SETPOINT OF 3.50 PSIG +/- 0.053COMPONENT FAILURE NSSS PSIG. THIS CONDITION RESULTED IN MINIMAL SAFETY IMPLICATIONS. REDUNDA

INSTRUMENT GE NT INSTRLMENTATION WAS AVAILAELE.NINE MILE POINT-1 0ENGNRD SAFETY FEATR INSTR SYSROUTINE TEST / INSPECTION REC 4D, A EARTON MODEL 289 PRESSURE INDICATING SWITCH DRIFTED FROM A SETP

OINT OF 3.54 PSIG. IT WAS RESET TO 3.50 PSIG. CURRENT SURVEILLANCE TF-TING SCHEDULES APE ACEQUATE TO INSURL EARLY LETECTION OF FUTURE INSTRUMLNT DRIFTS.

BARTON INSTRU CO., DIV 0F ITT 05000220 CE3078 DURIt:G STEAD) STATE OFERATION, PERFORMANCE CF SURVEILLANCE TEST N1-ISP-RINSTRUMENTATION + CONTROLS 78-027/03L-0 071378 E22, FOUND R[220 KITH A SETPOINT OF 107 FSID, AND RE22E WITH A SETPOINT

SWITCH 021715 30-CAY OF 106 PSID, T.S. 3.6.2B REQUIFES THESE M AIN STEAM LINE HIGH FLOW INDICACOMPONENT FAILURE NSSS TING SWITCHES HAVE SETPOINTS OF ICS PSID +/- 1 PSID. THIS CONDITION RES

INSTRUMENT CE CLTED IN MINIMAL SAFETY IMPLICATIONS. REDUNCANT INSTRUMENTS WERE OPERATNINE MILE POINT-1 0 ICNAL.ENGNRD SAFETY FEATR INSTR SYSROUTINE TEST / INSPECTION IFE CEVIATIONS IN SETPOINTS EXPERIENCED ON THE TWO EARTON M0 EEL 278 DIFF

EFENTIAL PRESSURE INDICATING SWITCHES WEEE DLE TO INSTRLVENT ERIFT. RE 22D WAS RESET AT 105 PSID AND FE22E AT 1 C5.5 PSID. CURRENT SURVEILLANCETESTING SCHEDULES ARE ACEQUATE TO INSLPE EARLY CETECTIGN OF FUTURE INSTRy r .;T r.o i rTS

BAFTON INSTRU LO., CIV 0F lil USCuCZ201 072276 JURING NORMAL GPLRATIUN, PEhFURMANCE UF SUkklILLANCL IEST N1-ISF-REC 4, FINSTRLMENTATION + CONTROLS 75-029/01T-0 072878 OUND RE04A, RE04B, AND RE04C WITH SETPOINTS LESS CONSERVATIVE THAN ALLOW

SWITCH 021795 2-WEEK ED BY TS 3.6.2. THIS CONDITION PESLLTED IN COTH SENSORS IN CFANNEL 11 0COMPONENT FAILLRE NSSS PEPATING IN A DEGRACED MOCE. THIS CONDITION, FCKEVER, DOES NOT CREATE A

INSTRUMENT GE 7 UNREVIEWED SAFETY QLESTION, AND HAS MINIMAL SAFETY IMPIICA TICNS.NINE MILE POINT-1 0ENGNRD SAFETY FEATR INSTR 50,

ROUTINE TEST / INSPECTION THE HIGH CRiKELL FPESSURE SWITCEES INVOLVED APE EARTON MODEL 289 FRESSURE INDICATING SWITCFES. THE CHANGES IN SETPCINT EXPEFIENCED WERE DUE TOINSTRUMENT DRIFT. RE04A AND B KEPE RESET TO 3.50 PSIC. AND RE04C TO 3.48PSIG. CURRENT SURkEILLANCE TESTING SCHEDULES ARE ADEQUATE TO INSLRE EA

RLY CETECTION OF FUTURE INSTRUMENT DRIFTS.

116

LICENSEE EVENT REPORTS'

COMPONENT MANUFACTURER DOCKET NO.COMPONENT / COMPONENT SUBCODE LER NO.CAUSE CODE /CAUSE SUBCODE CONTROL NO. EVENT DATEFACILITY / SYSTEM SUPPLIER REPORT DATE EVENT DESCRIPTIONMETHOD OF DISCOVERY NSSS / A/E REPORT TYPE CAUSE DESCRIPTION

BARTON INSTRU CO., O!V 0F ITT 05000249 062178 WHILE PERFORMING SURV. MSL FLOW ISOL. SW. DPIS 3-261-2C TRIPPED AT % 119INSTRUMENTATION + JONTROLS 78-027/03L-0 071078 PSID. (T.S. LIMIT %/=115.9 PSID 120% FLOW; TABLE 3.2.1). THE 16 MSL H

SENSOR / DETECTOR / ELEMENT 021684 30-DAY I FLOW ISOL SWITCHES PROVIDE CONTAINMENT ISOLATION PROTECTION WHENEVER PCOMPONENT FAILURE NSSS RIMARY INTEGRITY REQUIRED.BOTH TRIP SYS. WERE OPERABLE AND WOULD HAVE ISOTHER GE OLATED CONTAINMENT AT 111.5 PSID, CONSERVATIVE TO T.S. LIMIT OF 115.9 PS

DRESDEN-3 5+L ID. SIMILAR EVENTS PEF. IN 77-4 & 78-022.ENGNRD SAFETY FEATR INSTR SYSROUTINE TEST / INSPECTION APPARENT CORROSION DEPOSITS IN METER MOVEMENT GEAR TEETH. GEARS CLEANED

AND SWITCH PROMPTLY RESET TO DRESDEN SETPOINT OF 113+ /-2 PSID INCREASING. OTHER SWITCHES CHECKED SATISFACTORILY. THE (16) MSL HI FLOW ISOL. SW'S WILL CONTINUE TO BE TESTED MONTHLY.

BARTON INSTRU C0., DIV 0F ITT 05000249 052178 DURING MONTHLY SURV. MSL HI-FLCW ISCL. SWITCHES DPIS 261-2C, 261-2N & 26INSTRUMENTATION + CONTROLS 78-022/03L-0 060978 1-25 FOUND TO TRIP AT 117.0, 120.0 & 119 PSID RSP. VALUES EXCEED THE 115

SENSOR / DETECTOR / ELEMENT C21510 30-DAY .9 PSID LIMIT IN T.S. 4.2.1 FOR %/- 120% FLOW. MSL HI FLOW ISOL. SW'S ACOMPONENT FAILURE NSSS RE REQUIRED TO PROVIDE A TRIP ON BOTH TRIP SYS. kdENEVER PRIMARY INTEGRI

INSTRUMENT GE TY REQUIRED. BOTH "A" & "B" TRIP S15. WERE OPERABLE & WOULD HAVE SUPPLIDRESDEN-3 S+L ED NECESSARY MSIV CLOSURE & GROUP I ISOL AT 111.0 PSID.MAIN STEAM ISOL SYS + CONTROLSROUTINE TEST / INSPECTION CnUSE ATTRIBUTABLE TO INSTRUMENT DRIFT. SWITCHES WERE IMMEDIATELY RESET

TO WITHIN THE DRESDEN SETPOINT BAND OF 113 + 2 PSID INCREASI NG. THE (16) MSL HIGH FLOW ISOL. SWITCHES WILL CONTINUE TO BE TESTED MONTHLY TO ASCERTAIN COMPLIANCE WITH TECH SPECS.

BARTON INSTRU CO., DIV 0F ITT 05000331 062778 DURING SURVEILLANCE TESTING PRESSURE DIFFERENTIAL SWITCHES 4304 AND 4305INSTRUMENTATION + CONTROLS 78-031/01T-0 071178 WERE FOUND TO HAVE 0UT OF SPECIFICATION SETPOINTS. THESE SWITCHES CONTSWITCH 021863 2-WEEK ROL REACTOR BUILDING TO TORUS VACUUM BREAKERS CV 4304 AND CV 4305. THE

COMPONENT FAILURE A/E SETPOINT OF PDS 4304 WAS FOUND TO BE 1.35 PSID AND THE SEIPOINT OF PDS 4INSTRUMENT GE 305 WAS FOUND TO BE .85 PSID. TECHNICAL SPECIFICATION 3.7.A.3.A REQUIRE

DUANE ARNOLD BECH S THE SETPOINT TO BE .5 PSID. THERE HAVE BEEN TWO PREVIOUS SIMILAR OCCUREACTOR CONTAINMENT SYSTEMS RRENCES (SEE LER 75-33 AND LER 77-55).ROUTINE TEST / INSPECTION INSTRUMENT DRIFT. PDS 4304 AND PDS 4305 ARE BOTH BARTON MODEL 288A PRES

SURE DIFFERENTIAL SWITCHES. THE SWITCHES WERE RECALIBRATED AND FUNCTIONALLY TESTED. A DESIGN REVIEW WILL BE INITIATED TO VERIFY THE ADEQUACY 0F THIS IkSTRUMENT APPLICATION. PENDING COMPLETION OF THIS REVIEW, SURVEILLANCE WILL BE INCREASED TO MONTHLY C.4CE PLANT OPERATION RESUMES.

117

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LICENSEE EVENT REPORTS*C(2

COMPONENT MANUFACTURER DOCKET NO. OCOMPONENT / COMPONENT SUBCODE LER NO.CAUSE CODE /CAUSE SUBCODE CONTROL NO. EVENT CATEFACILITY / SYSTEM SUPPLIER FEPORT DATE EVENT DESCRIPTIONPETUDD OF DI!r0VEpy NSSS / A/F LEpnpT Type cat (E DESCpIPTInN

BARTON INSTPU CO. , DIV 0F ITT 05000304 060973 WHILE PERFORMING MAINTENANCE ACTIVITIES, PRESSURIZER LEVEL CHANNEL 459 WINSTPUMENTAT10N + CONTROLS 78-048/03L-0 070778 AS FOUND LOW BY 41. THIS WAS IN TFE NON-CONSERVATIVE DIPECTION FOR HIGHTRANSMIETEF 021708 30-CAY PRESSURIZER LEVEL REACTOR TRIP AS INCICATED IN TABLE 3.1.10F TECH SPEC

COMPONENT FAILUPE NSSS 5; THE REDUNDANT CHANNELS WERE OPERABLE AND AVAILABLE, S0 THE HEALTH ANDINSTRUMENT WEST SAFETY OF THE PUBLIC WAS NOT AFFECTED.

ZION-2 S+LPEACT0R TRIP SYSTEMSROUTINE TEST / INSPECTION ZERO SHIFT OF BARTON FOCEL 386 TRANSMITTER. THE TRANSMITTER ZERO WAS PE

ADJUSTED BY COMPAPISON WITH THE 2 REDUNDANT CHANNELS. THESE TRANSMITTERS ARE CHECKED BY PERIODIC SLRVEILLANCE TESTING. ZION STATION IS PRESENTLY TFENDING INSTRUMENT LRIFT, NO FURTHER ACTION IS REQUIPED.

BECKMAN INSTRUMENTS, INC. 05000325 061878 A REACTOR OPEPATOR DISCOVEFED THAT THE CRYWELL OXYGEN CONCENTPATION, 15INSTRUMENTATION + CONTROLS 78-C65/03L-0 071778 INDICATED BY CAC MONITOR CAC- ATH-1263, WAS LOWER THAN EXFECTED. UPON IN

SFN50R/ DETECTOR / ELEMENT 021729 30-CAY VESTIGATION, THE CAC MONiiOR WAS FOUND OUT OF CALIBRATION. (TECHNICAL SCOPP0NENT FAILURE NSSS PECIFICATION 3.6.6.4)

ELECTRICAL GE

BRUNSWICK-1 LECCNTNMNT COMBUS GAS CONTROL SYSROUTINE TEST /INSFECTION THE 0xYGEN ANALYZER SECTION OF THE MONITOR WAS CRIFTING. A NEW OXYGEN A

NALYZER SECTION WAS INSTALLED IN THE MONITOR AND THE MONITOR DECLARED OPERATIONAL. A REQUEST FOR A FAILURE ANALYSIS WAS MADE TO THE MANUFACTUREP CF THE OXYGEN ANALYZER SECTION.

BECKMAN INSTRUMENTS, INC. 05000324 06017C DURING POUTINE RTGB PANEL CHECK, A CONTPOL OPERATOR NOTICED THAT CAC 0XYOTHER COMPONENTS 78-045/03L-0 062978 GEN MONITOR CAC-AT-1263 HAD FAILED 00WNSCALE. (TECHNICAL SPECIFICATION

SUBCOMPONENT NOT APPLICABLE 021662 30-CAY 3.6.6.4)COMPONENT FAILURE A/E

ELECTRICAL GE

BRUNSWICK-2 LECCNTNMNT COMBUS GAS CONTROL SYS

ROUTINE TEST / INSPECTION THE MONITOR WAS FClaD WITH A ELOWN FUSE. THIS FUSt IS LOC IN THE POWERSUPFLY WHICH FEEDS THE MONITOR ELECTPONICS. THE 2.5 AMP FUSE WAS REPLACED AND THE f0NITOR PLACED EACK INTO SERVICE. THE ELECTRONICS OF THE P0HER SUPPLY & THE METER CIPCUIT WEPE CHECKED. NO FAULTY COMPONENiS WERE F

-

OUND. | CON'T)

118

LICENSEE EVENT REPORTS!

COMPCNENT VANUFACTURER DCCKET NO.^*FONENT/CCFFCNENT SUECOCE LER NO.

<E LCCE/CALSE SLECCCE CCNTFOL NO. EVENT DATts

FAs TTY / SYSTEM SUFFLIER FEPCRT DATE EVENT DESCRIPTIONvrikt nr risrCVEpv 'X55 / A /r ;trcRT Tyre (v;5E CESto!PTION

!EELL & HOWEL. 050002E5 C61978 CLRING NOFMAL STARTUP FOLLOWING A SCHEDLLED MAINTENANCE OUTAGE, IT WAS NINSTRUMENTATiCN + CONTFOLS 76-019/03L-0 070378 DTLD THAT "B" CHAANEL FOR THE VARIABLE HIGH POWER TRIP WAS NOT INDICATINCOMPUTATION MODULE C21697 3C-CAY G FROFERLY. THt FEMAINING THREE CHANNELS REMAINED OPERABLE THROUGHOUT T

COMPONENT FAILLEE NSSS HIS ELENT. SEE ALLO LER 78-CC9.ELECTRCNIC CC PU

FT. C ALHOLN-I GHTRREACTCR TRIP SYSTEMSOPERATIONAL EVENT THE EELL & HCWELL MODEL 19-502 AMPLITUOE SELECTOR MODULE FAILED. THIS M

CEULE WAS FEFLACED A*.D "B" CFANNEL WAS SATISFACTORILY TESTED BY THE APPLICAFLE SLRiEILLA'.CE TEST AND RETURNED TO NORMAL. THE VARIAELE HIGH FCWER TRIP CHANNELS WILL CONTINUE TO EE MONITORED BY VISUAL INSPECTION AhD 5"?VEILt t'/E TE S T I'm

EthbAN FAIIthtLN UbOLOJtt ;t2J/b L'LWIN6 INillAL FLLL LUADING Of IHL FtALILd, LJNSIRLsIl0N blILLILD ib DLFFANGFRS.5LPFORTS SHCCA.SLPFFSS 70-CC2/ CIT-0 C6307B ICIENCIES WITH FEACTOR B' 'LDING HANGERS WHILE CONDUCTING HANGER SURVEILL

SUFPCFTS C21717 2-WEEK ANCE. OF THE 26 FANGERS, d VSRE NOT INSTALLED AND THE REMAINDER HAD SUCHCESIGN/FAERICATICN EFRGR A/E CEFICIENCIES AS LOOSE DR M.SSING NUTS, MISSING U-BOLTS, ETC. A LISTING

CONSTRLCTION/ INST"LLATICN GE OF SLBJECT HANGERS AND DEFICIENCIES ACCCMPANIES THIS REPORT.E C W "' I. HATCH-2 SSC/EECHCIFER AUX SYSTEMS + CCNTROLSFOLi!NE TEST / INSPECTION CAUSE OF THIS DEVIATION IS CONSTRUCTION DEFECTS IN INSTALLATICN OF THE R

EACiOR BUILDING HANGERS. C0FRECTIVE ACTIONS IMPLEMENTED To CORRECT THEFFOBLEM WAS INSTALLATION OF TFE FIVE MISSING HANGERS ANC REFLACEMENT AND/CR ADDITION OF NECESSARf PARTS ON THE BALANCE CF THE HANGERS. ALL HANGEPS WERE CORDECTED EY 6/23/79

LLFTAN A55ctlAllLN INC. Ot0003C4 051olt JLRINb NOFFAL OFLFAIl0N, THE LNii i SIL AM btNLxAIUR btOnbOWN MGNITOR, 2RINSTRLVENTATION + CONTROLS 76-002/03L-0 C61578 E0019 WAS SPIKING AND ALARMING HIGH. THE RESULTS OF THE MANUAL GRAB SAMFCWER SUFFLY C21543 30-CAY PLES THAT WEFE PULLED IN RESPONSE TO THE HIGH ALARM, DID NOT INDICATE A

COMPONENT FAILLRE 5555 BONAFICE HIGH ALARM CONDITION. THE MONITOR WAS TAKEN 005 AND MANLAL GR'INSTPLMENT WEST '3 SAMPLES WERE TAKEN IN ACCORDANCE WITH T.S.3.14.1.

ZION-2 5+LLIQ RADICACT WS!E MANA NNT SYSOFEPATIONAL IkENT SPURICUS HIGH ALARMS WERE ATTRIBUTED TO A CRIFT IN THE HIGH VOLTAGE POWE

R SUFFLY, EEPTAN ASSOCI ATES MODEL 1110. CF THE WESTINGHOUSE MONITCR. TWE HIGH VOLTAGE WAS ADJUSTED, THE MONITOR FUNCTIONALLY CHECKED AND RESTORED TO SERVICE.

119(?)?

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LICENSEE EVENT REPORTS 9QCOMPONENT MANUFACTURER DOCKET NO.COMPONENT / COMPONENT SUBCODE LER NO.CAUSE CODE /CAUSE SUBCODE CONTROL NO. EVENT DATEFACILITY / SYSTEM SUPPLIER REPORT DATE EVENT DESCRIPTIONPFTHOD OF DISCOVFRY NSSS / A/E REPORT TYPE CAUSE DESCRIPTION

BONNEY FORGE DIV. 05000263 050878 DURING NORMAL OPERATION A STEAM LEAK WAS DISCOVERED IN A 45 DEGREE ELB0WPIPES, FITTINGS 78-007/03L-0 060778 ON THE HPCI STEAM SUPPLY LINE 1" DRAIN LINE TO THE CONDENSER. THIS COLESS THAN 4 INCHES 021422 30-DAY NSTITUTED A DEGRADATION OF A SYSTEM DESIGNED TO CARRY RADI0 ACTIVE MATERI

COMPONENT FAILURE A/E AL RESULTING FROM THE FISSION PROCESS (T.S. 6.7.B.2.D.) SPCI AND REDUNDOTHER GE ANT SYSTEMS WERE AVAILABLE AND OPERABLE. FOUR PREVIOUS SIMILAR OCCURREN

MONTICELLO-1 BECH CES (M-R0-76-01, 16 .24 AND M-R0-77-19). NO EFFECT ON PUBLIC HEALTH OREMERG CORE COOLING SYS + CCNT SAFETY.ROUTINE TEST / INSPECTION LEAK DUE TO EROSION CAUSED BY FLOW 0F STEAM AND WATER THROUGH LEAKING VA

LVE, CV-2045 UPSTREAM OF ELBOW. TEMPORARY CLAMP TYPE REPAIR MADE. VALVE INTERNALS, LEAKING ELBOR, AND ADDITIONAL PIPING AND ELB0WS TO BE INSPECTED AND REPLACED AS REQUIRED DURING FALL, 1978 REFUELING OUTAGE.

BORG-WARNER CORP. 05000320 052078 WHILE PERFORMING SFAS REACTOR BUILDING ISOLATION AND COOLING SURVEILLANCINSTRUMENTATION * CONTROLS 78-040/03L-0 061578 E TESTING ON MAY 20, 1978 CONTROL ROOM CHILLER AH-C-8B FAILED TO OPERAT

SWITCH 021606 30-DAY E. SINCE THE REDUNDANT CONTROL R00M CHILLER WAS OPERABLE, THERE WAS NOCOMPONENT FAILURE A/E EFFECT ON THE HEALTH AND SAFETY OF THE PUBLIC.

MECHANICAL B+WTHREE MILE ISLAND-2 B+RCONT ROOM HABITBLTY SYS + CONTROUTINE TEST / INSPECTION HPON FAILURE OF AH-C-88, ACTION A WAS ENTERED AND CHILLER RETURNED OPERA

BLE STATUS WITHIN REQUIRED TIME. FAILURE OF AH-C-8B CAUSED BY MICR0 SWITCH WITH ROUGH EDGE ON STEM, PREVENTING PROPER OPERATION. ROUGH EDGE REMOVED AND SWITCH RETESTED OK. AH-C-8B RETESTED SATISFACTORILY CN MAY 21

1978.BOSTROM-BERGEN METAL PRODUCTS 05000309 053078 DURING ROUTINE STEADY STATE OPERATIONS, PLANT OPERATORS NOTICED THAT THE

INSTRUMENTATION + CONTROLS 78-012/03L-0 062678 RPS CH. DT POWER INDICATICN WAS FLUCTUTATING SLIGHTLY AND NOT STEADY.SENSOR / DETECTOR / ELEMENT 021651 30-DAY BECAUSE THE DT POWER FUNCTION PROVIDES INPUT TO VARIABLE OVER POWER. SY

COMP 0NENT FAILURE NSSS MMETRIC OFFSET AND THERMAL MARGIN / LOW PRESSbRE TRIP CIRCUITS, VARIATIONSELECTRICAL COMB WERE ALSO NOTICED IN THESE CIRCUITS. TO PREVENT POSSIBLE SPURIOUS TRIP

MAINE YANKEE S+W SIGNALS, ACTUATED BY THE ERRATIC DT POWER SIGNAL, THE TRIP FUNCTIONS WEREACTOR TRIP SYSTEMS RE PLACED TO BYPASS.OPERATIONAL EVENT AN INVESTIGATION WAS PERFORMED BY THL I&C DEPT. IT WAS DETERMINED THAT

THE CDMPENSATING LEADS FOR TWO RTD'S IN THE CH. DT POWER CIRCUIT WERE SHOWING VARYING RESISTANCE. THIS VARI ANCE IN RESISTANCE IS BELIEVED TO BE

INDICATIVE OF A FAILING RTD. BECAUSE THE RTD'S ARE INACCESSIBLE DURINGPOWER OP, AFFECTED TRIP CHANNELS WERE PLACED IN BYPASS.

120

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COMPONENT MANUFACTURER DOCKET N0.COMPONENT / COMPONENT SUBCODE LER NO.CAUSE CODE /CAUSE SUBCODE CONTROL NO. EVENT DATEFACILITY / SYSTEM SUPPLIER REPORT DATE EVENT DESCRIPTIONMETHOD OF DISCOVERY NSSS / A/E PEPORT TYPE CAUSE DESCRIPTION

BUFFALO TANK 05000250 042678 FOR APPROXIMATELY 10 HOURS. THE CONDENSATE STORAGE TANK CONTAINED A VOLUHEAT EXCHANGERS 78-004/03L-0 052678 ME OF WATER LESS THAN THE 185,000 GALLONS REQUIRED BY TECH SPEC 3.8.1.C.OTHER 021507 30-DAY OPERATION IN THIS MODE IS ALLOWED BY TECH SPEC 3.8.3. THE MINIMUM ANK

COMPONENT FAILURE A/E WATER INVENTORY DURING THIS INTERVAL WAS 156,000 GALLONS. IN ADDITION,CAUSE SUBCODE NOT PROVIDED WEST 198,000 GALLONS OF WATER WAS READILY AVAILABLE IN THE UNIT 4 CONCENSATE

TURKEY P0lNT-3 BECH STORAGE TANK.CONDENSATE STORAGE FACILITIESOPERATIONAL EVENT HIGH STEAM GENERATOR BLOWDOWN FLOWS WERE BEING HAINTAINED TO CONTROL SEC

ONDARY WATER CHEMISTRY DURING IDENTIFICATION AND CORRECTION OF A MAIN C0NDENSOR TUBE LEAK. COINCIDENTAL DEPLETION OF THE CATION DEMIN INTERRUPT'"

ED CONDENSATE MAKEUP FLOW WHILE REGENERATION WAS PERFORMED.

BYRON JACKSON PUMPS, INC. 05000318 071478 DURING NORMAL OPERATION THE DAILY RCS LEAK RATE DETERMINATION INDICATEDHEAT EXLHANGERS 78-021/01T-0 072778 THAT THE UNIDENTIFIED RCS LEAKAGE WAS 1.3 GPM A' 0330. PER THE REQUIREMCOOLER 021844 2-WEEK ENTS OF T.S.3.4.6.2. THE REACTOR WAS SHUTDOWN AT v741. AT 0900 A CRACKE

COMPONENT FAILURE NSSS D WELD WAS DISCOVERED ON 21B REACTOR COOLANT PUMP SEAL COOLING HEAT EXCHMECHANICAL COMB ANGER. REACTOR WAS PLACED IN COLD SHUTDOWN TO EFFECT REPAIRS. LER 78-0

CALVERT CLIFFS-2 BECH 19 DESCRIBES A SIMILAR EVENT.COOL SYS FOR REAC AUX + CONTROUTINE TEST / INSPECTION UPON INVESTIGATION IT WAS FOUND THAT REPAIRS ON THE RCP SEAL COOLING HEA

T EXCHANGER (REPORTED UNDER LER 78-19) WERE NADEQUATE. ADDITIONAL WELDREPAIRS WERE PERFORMED ON A CRACK IN THE HEAT AFFECTED ZONE OF THE HEATEXCHANGER PIPING. NO FURTHER ACTION IS REQUIRED AS A RESULT OF THIS EV

ENT.

BYRON JACKSON PUMPS. INC. 05000318 052378 WHILE OPERATING IN MODE 1 THE CONTROL ROOM OPERATOR REPORTED AN INLREASEPIPES, FITTINGS 78-013/03L-0 061578 RATE OF LEVEL LOSS IN THE VOLUME CONTROL TANK. AT 1:00 P.M., THE REAC

LESS THAN 4 INCHES 021530 30-DAY TOR COOLANT SYSTEM UNIDENTIFIED LEAKAGE WAS DETERMINED TO BE 1.184 GPM.COMPONENT FAILURE NSSS THE REACTOR WAS PLACED IN MOCE 3 AT 1:00 P.M. PER T.S.3.4.6., ACTION

METALLURGICAL COMB B. THE LEAK WAS DETERMINED TO BE FROM A CRACKED WELD ON 22A REACTOR C0CALVERT CLIFFS-2 BECH OLANT PUMP UPPER SEAL PRESSURETRANSMITTER SENSING LINE WHICH WAS ISOLACOOLANT RECIRC SYS + CONTROLS TED BY SHUTTING THE ISOLATION VALVES. REF: 77-73 (U-2):77-22 (U-1).OPERATIONAL EVENT CRACKED WELD LOCATED WHERE THE SENSING LINE JOINED FLANGED COUPLING DOW

NSTREAM 0F SEAL ISOLATION VALVES. ;R0BABLE CAUSE OF FAILURE WAS CYCLEFATIGUE FROM PUMP VIBRATION. WELD WAS REPAIRED AND SENSING LINE RETURNED TO SERVICE. RCP VIBRATION DATA HAS BEEN TAKEN UNDER FCR 77-147 ANDAN ENGINEERING STUDY IS BEING PERFORZED TO DETERMINE LONG-TERM SOLUTION

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LICENSEE EVENT REPORTS fjCOMPONENT MANUFACTURER DOCKET NO.COMPONENT / COMPONENT SUBCODE LER NO.CAUSE CODE /CAUSE SUBCODE CONTROL NO. EVENT DATEFACILITY /SYSTLM SUPPLIER REPORT DATE EVENT DESCRIPTIONMETHOD OF DISCOVERY NSSS / A/E RFPORT TYPE CAUSE DESCRIPTION

BYRON JACKSON PUMPS, INC. 05000318 070478 DURING PERFORMANCE OF A PRESTARTUP CONTAINMENT CLOSE0UT INSPECTION AT 12PUMPS 78-019/01X-1 071378 :00 P.M. A CRACKED WELD WAS DISCOVERED ON 218 REACTOR COOLANT PUMP SEAL

CENTRIFUGAL 021059 OTHER AT THE WELD BETWEEN THE PUMP CAP AND SEAL COOLING HEAT EXCHAHGER. PRESSCOMPONENT FAILURE NSSS URE BOUNDARY LEAKAGE ESTIMATED AT 1/4 GPM NECESSITATED PLACING THE REACT

MECHANICAL COMB OR IN COLD SHUTDOWN TO EFFECT RFPAIRS. THIS IS NOT A REPETITIVE OCCURRECALVERT CLIFFS-2 BLCH NCE.COOLANT RECIRC SYS + CONTROLSROUTINE TEST / INSPECTION UPON INVESTIGATION THE WELD CRACK WAS FOUND TO HAVE INITI ATED IN THE HEA

T AFFECTED ZONE OF THE WELD AND PROP.AGATED APPROXIMATELY 130 DEGREES CIRCUMFERENTIALLY AROUND THE SOCKET. THE CRACK WAS GROUND OUT AND WELD REPAIRS MADE. EXACT CAUSE 0F THE WELD FAILURE IS UNKNOWN. NO ADDITIONAL ACTION IS PE0UIPED AS A PESULT OF THIS EVENT.

CAF GOLAIRE ENGINEERING CURP. 05000338 070178 UURING THE PERFORMANCL OF PERIODIC ILSI 1-PT-62.4 LEAKAGE WAS DL1LCILD 0PENETRATIONS.PRIMRY CONTAINMNT 78-058/03L-0 072878 N THE INNER PERSONNEL AIR LOCK DOOR SEALS. THE LEAKAGE DETECTED WAS OF

PERSONNEL ACCESS 021922 30-DAY THE STANDARD TYPE EXPECTED AND WAS CORRECTED BY ROUTINE MAINTENANCE PROCCOMPONENT FAILURE A/E EDURES. NO SIGNIFICANT CONSEQUENCES WERE ANTICIPATED OR ENCOUNTERED.

NATURAL END OF LIFE WESTNORTH ANNA-1 S+WREACTOR CONTAINMENT SYSTEMS

ROUTINE TEST / INSPECTION THE PERMANENT SET IN THE SEAL MATERIAL INCREASED CAUSING THE INNER 000RSEAL TO FAIL. THE SEALS ON THE INNER DOOR WERE REPLACED AND PERIODIC TE

ST 1-PT-62.4 THE PERSONNEL A:R LOCK SEAL LEAKAGE TEST, REPERFORMEC. NOLEAKAGE WAS DETECTED.

CHEM-TROL CORP 05000366 062278 PRIOR TO COMMENCEMENT OF INITIAL FUEL LOAD WHILE REVIEWING FIRE BARRIEROTHER COMPONENTS 78-001/01T-0 070378 PENETRATION WORK, ADDITIONAL BREACHED BARRIERS WERE DISCOVERED. CONDUIT

SUBCOMPONENT NOT APPLICABLE 021718 2-WEEK 5, CONDUIT SLEEVES, VENTILATION DUCT, AND PIPING PENETRATING 3 HOUR RATEDESIGN / FABRICATION ERROR A/E D FIRE WALLS / FLOORS DID NOT HAVE APPROVE AND RATED SEAL',- ALSO, TWO (2

CONSTRUCTION / INSTALLATION GE ) FIRE D0 ORS BETWEEN THE TURBINE AND RADWASTE BUILDINGS DID NOT MEET THEEDWIN 1. HATCH-2 SSC/BECH REQUIRED 3 HOUR RATINGS.

FIRE PROTECTION SYS + CONTOPEkATIONAL EVENT THE CAUSE OF THE PROBLEM WAS DUE TO A LACK OF SPECIFIC FIRE PROTECTION

STANDARDS AT THE TIME OF CONSTRUCTION OR INITIAL INSTALLATION. ALL THEABOVE DEFICIENCIES WERE IMMEDIATELY CORRECTED OR FIRE WATCHES POSTED UNTIL THE DEFICIENCIES WERE CORRECTED.

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COMPONENT MANUFACTURER COCVET NO.COMPONENT / COMPONENT SUBC00E LER NO.CAUSE CODE /CAUSE SUBCODE CONTRCL NO. EVEIT CATEFACILITY / SYSTEM SUPPLIER PEPCRT CATE EVENT CESCRIPTIONMETHOD OF DISr0NFPY NSSS / A'E REPORT TYPF CAUSF DESCRIPTION

CHEMELEX C50002S1 050578 DURING NORMAL OPERATION, POUTINE OBSERVATION REVEALED THE FAILURE OF ONEHEATERS. ELECTRIC 78-016/03L-0 0S2678 CF THE TWO RECUNDANT HEAT-TRACING CIRCUITS PROVIDED ON THE BORON INJECT

SUBCOMPONENT NOT APPLZCABLE C21522 30-DAY ION TANK INLET PIPE. THE EVENT IS CONTRARY TO T.S. 3.3. A.4 AND IS REPORCOMPONrNT FAILLFE A/E TABLE PER T.S. 6.6.2.B(2). THE HEALTH AND SAFETY OF THE GENRAL PUBLIC W

ELECTRICAL WEST ERE NOT AFFECTED.SURRY-2 S+WOTHER ENGNRD SAFETf FEATR SYSOPERATIONAL EVENT A REVIEW OF THE HEAT-TRACING CIRCUIT SHOWED THAT FAILURE WAS CAUSED BY B

ORIC ACID PENETRATION OF THE HEAT-TRACING TAPE CIRCUIT. THE CORRECTIVEACTION IMPLEMENTED WAS TO REPLACE THE HEAT-TRACING TAPE FOR THE ENTIRE CIPCUIT.

CHICAGO BRIDGE & IRON COMPANY 05000338 051478 FOLLOWING A RADIATION SURVEY IN THE CONTAINMENT, THE INNER DOOR DN THE PPENETRATIONS.PRIMRY CONTAINMNT 78-039/03L-0 060978 ERSONNEL AIR LOCK FAILED TO SEAL PROPERLY (T.S. 4.6.1.3.A). THE OUTER D

PERSONNEL ACCESS 021503 30-DAY 00R REMAINED OPERABLE. THERE WAS NO EFFECT UPON PUBLIC HEALTH OR SAFETYCOMPCNEl.T FAILURE A/ENATURA_ END OF LIFE ' TST

NOPTH ANNA-1 5+WREACTOR CONTAINMENT SYSTrv5ROUTINE TEST /INSFECTION SEALS ON PERSONNEL AIR LOCK INNER DOOR FAILED. THE SEALS WERE REPLACEu

ON S/15/78 AND RETESTED SATISFACTORY.

CHICAG0 BRIDGE & IRON COMPANY 05000272 060678 DURING CONTAINMENT ENTRY VI A 100 FT AIR LCCK, EXTERIOR D0OR WOULD NOT CLPENETRATIONS,PRIMRY CONTAINMNT 78-027/03L-0 063078 OSE. INNER DOOR REMAINED CLOSED THROUGH0LT THIS EVENT. ACTION STATEMENOTHER 021650 30-DAY T FOR LC0 3.6.1.3 INITIATED. MAINTENANCE PERSONNEL REPAIRED FAILED WELD

COMPONENT FAILURE LIC ACTION STATEMENT TERMINATED. THIS IS ThE FOURTH OCCURRENCE OF THIS TOTHER WEST YPE.

SALEM-1 C

REACTOR CONTAINMENT SYSTEMSOPERATIONAL EVENT BROKEN PLUG WELD ON INTERLOCK DEVICE CAUSED THE EXTERIOR D60R NOT TO CL0

SE. WELD REPAIP.ED AND AIRLOCK TESTED SATISFACTORY.

[?)e; 123CT.p(23N

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fhLICENSEE EVENT REPORTS

(.OCOMPONENT MANUFACTURER DOCKET NO.COMPONENT / COMPONENT SUBCODE LFR NO.CAUSE CODE /CAUSE SUBCODE LvnfROL NO. EVENT DATE

FACILITY / SYSTEM SUPPLIER REPORT DATE EVENT DESCRIPTION,


CLIMET INSTRUMENTS CO. 05000302 OE 78 AT 0200, 6/12/78 & 6/28/78 THE 175 FT WIND SPEED INDICATION WAS LOST. AINSTRUMENTATION + CONTROLS 78-033/03L-0 07U778 T 0900, 6/21/78 & 0800 6/28/78, THE 33 FT. WIND SPEED INDICATION WAS LOS

SENSOR / DETECTOR / ELEMENT 021776 30-DAY T. CONTRARY TO TECH SPEC 3.3.3.4. WIND SPEED SENSORS WERE RENEWED ANDCOMPONENT FAILURE OTHER RETURNED TO SERVICE IN EACH CASE WITHIN 24 HOURS. N0 HAZARD TO HEALTH A

INSTRUMENT B+W ND SAFETY OF THE PUBLIC. NO GASEOUS RELEASES WERE IN PROGRESS.CRYSTAL RIVER-3 GILOTHR INST SYS REQD FOR SAFETYROUTINE TEST / INSPECTION W ND SPEED SENSOR BEARINGS CONTAMINATED WITH C0AL DUST CAUSING INOPERABI

LITY AT LOW WIND SPEEDS. WIND SPEED SENSORS RENEWED. REQUEST FOR ENGINEERING INFORMATION GENERATED FOR AN EVALUATION OF THESE EVENTS.

COMBUSTION ENGINEERING. INC. 05000255 050978 PRIOR TO A REACTOR START-UP, IT WAS DETERMINED THAT CONTROL R0D NO. 8 C0CONTROL R00 DRIVE MECHANISMS 78-016/0lT-1 071478 ULD NOT BE MOVED BY ITS OPERATOR. AFTER DETERMINING THAT SHUTDOWN MARGI

SUBCOMPONENT NOT APPLICABLE 021324 2-WEEK N REQUIREMENTS COULD BE MET, R0D NO. 8 WAS MANUALLY MOVED TO THE FULL OUCOMPONENT FAILURE NSSS T POSITION AND LOCKED IN THAT POSITION. THIS OCCURRENCE REPORTABLE PER

MECHANICAL COMB SPECIAL T.S. S.5.1. EVENT HAD NO EFFECT ON PUBLIC HEALTH OR SAFETY.PALISADES-1 BECH

REACTIVITY CONTROL SYSTEMSOPERATIONAL EVENT INVESTIGATION SHOWED THAT THE BUFFER PISTON CASTELLATIONS HAD BEEN BENT

OUTWARD SUCH THAT THEY WOULD DIG INTO THE SIDE OF PISTON GUIDE TUEE DURING ATTEMPTED WITHDRAWAL OF THE R00. THE CASTELLATIONS APPEAR TO HAVE BEEN SENT BY THE CONNECTOR NUT LOCKING PAWL Wh!CH WAS NOT FULLY RETRACTEDFROM THE CASTELL ATIONS DURING INSTALLATION OF THE CONNECTOR NUT.

COMBUSTION EhGINEERING, INC. 05000335 062578 DURING PLANT STARTUP FROM A SHORT (16-HOUR) MAINTENANCE SHU1DOWN, DOSE E

FUEL ELEMENTS 78-024/03L-0 072478 QUIVALENT (DEQ) IODINE EXCEEDED THE TECHNICAL SPECIFICATION 3.4.8. A LIMISUBCOMPONENT NOT APPLICABLE 021836 a 30-DAY T OF 1.0 UCI/ GRAM DOSE EQUIVALEhT I-131. THE DEQ 10 DINE WAS FIRST MEASU

COMPONENT FAILURE NSSS I RED ABOVE THIS LIMIT AT 1900 ON 6/25/78 WHILE THE PLANT WAS AT 97% POWEROTHER COMB | A PREVIOUS OCCURRENCE OF THIS TYPE IS DESCRIBED IN LER 335-78-13..

ST. LUCIE-1 EBASCOREAC COOL CLEANUP SYS + CONTOPERATIONAL EVENT AFZER AN EXTENDED PERIOD OF POWER OPERATION WITH A NOMINAL LEVEL OF FUEL

LEAKAGE THE PLANT SHUTDOWN AND SUBSEQUENT STARTUP TRANSIENTS WERE SUFFICIENT TO CAUSE IODINE BUILD UP (IODINE SPIKING PHENOMENON) AhD EXCEED THE PURIFICATION CAPACITY FOR A SHORT PERIOD OF TIME.

124

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.

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COMPONENT MANUFACTURER DOCKET NO.COMPONENT / COMPONENT SUBCODE LER NO.CAUSE CODE /CAUSE SUBCODE CONTROL NO. EVENT DATEFACILITY / SYSTEM SUPPLIER REPORT DATE EVENT CESCRIPTIONMETHOD OF DISCOVERY NSSS / A/E REPORT TYPE CAUSE DESCRIPTION

COMBUSTION ENGINEERING, INC. 05000255 062178 DURING NORMAL PLANT OPERATION, STEAM GENERATOR PH DROPPED TO 8.02. EVENTHEAT EXCHANGERS 78-024/03L' 072078 OCCURRED APPROX 1 HR AFTER CONDENSATE POLISHERS WERE PLACED IN SERVICE.

STEAM GENERATOR 021803 30-DAY OCCURRENCE IS A DEGRADEE MODE PERMITTED BY LC0 0F TS 3.18.3. PH WAS RETUDESIGN / FABRICATION ERROR NSSS RNED TO WITHIN SPECS WITHIN 4 HRS BY CHEMICAL AUDITION, REROUTING OF AFT

MANUFACTURING COMB ER CONDENSATE DRAINS, & REGULATING BLOWDOWN FLOW RATE. EVENT HAL NO ADVPALISADES-1 BECH ERSE EFFECT ON PUBLIC HEALTH OR SAFETY.MAIN STEAM SUPPLY SYS + CONTOPERATIONAL EVENT CONDENSATE POLISHER CATION RESIN HAD 1% OF AVAILABLE TRANSFER SITES IN H

YDROGEN FORM. THIS RESULTED IN REMOVAL OF AMINES FROM CONDENSATE WITH ARESULTANT PH DEPRESSION. RESIN VENDOR HAS BEEN NOTIFIED OF PROBLEM. RE

SINS TO BE USED IN THE FUTURE WILL BE FULLY AMMONIATED IN ORDER TO AVOIDAMINE TPANSFER CUT OF THE CONDENSATE.

LOMBUSTION ENGINEERING, INC. 05000335 053078 DURING A SPEC LOW POWER (ABOUT 3%) ftEDWAIER CONI sys IL5T, A 151 FEEDWAINSTRUMENTATION + CONTROLS 78-019/03L-0 062878 TER BYPASS CONT VALVE INADVERTENTLY OPENED FULLY CAUSING EXCESS COOLINGCONTROLLER 021733 30-DAY OF 1A S/G. REACTOR COOLANT SYS AVERAGE TEMP DROPPED SLIGHTLY BELOW 515F

COMPONENT FAILURE NSSS ( ABOUT IF) RFQ ACTION IN ACCORD WITH SPEC 3.1.1.5. REACTOR WAS TRIPPEDOTHER COMB MANUALLY WHEd THIS OCCURRED. THIS WAS THE FIRST OCCURRENCE OF THIS TYP

ST. LUCIE-1 EBASCO E AT ST. LUCIE.CONDNSATE + FEEDWTR SYS + CONTCPERATIONAL EVENT A VENDOR PRUP MOD OF THE 15% FEEDWATER CONTROL SYS WAS TEMP INSTALLED ON

THE A LOOP FOR FEASIBILITY TESTING (T0 IMPROVE STABILITY OF AUTOMATIC MODE). GAIN SETTINGS BASED ON ANALYTICAL RESULTS PROVED TO BE UNREALISTIC & CAUSED BYPASS \ALVE TO OPEN. SETTINGS WERE CHANGED TO ALLOW COMPLETION OF THE TEST.

COMBUSTION ENGINEERING, INC. 05000335 060678 DURING PUWER A$ TENSION TESTING FULLUWING A RLIULLING OUl AGE, (LA #68 CR0INSTRUMENTATION + CONTROLS 78-021/03L-0 070778 PPED 4 TIMES WITHIN AN 8 1/2 HR TIME SPAN. AFTER EACH OF THE FIRST 3 DRPOWER SUPPLY 021832 30-DAY OPS, CEA 868 WAS RESTORED TO NORMAL POSITION WITHIN THE TIME LIMIT REQUI

COMPONENT FAILURE NSSS RED BY APPLICABLE TECH SPEC 3.1.3.1.E ACTION STATEMENT. AFTER THE 4TH DELECTRONIC COMB R0P CEA #68 WAS CECLARED INOPERABLE. SEVERAL COMPONENTS WERE REPLACED,

ST. LUCIE-1 EBASCO AFTER WHICH CEA a68 WAS OPERATED SATISFACTORILY AND DECLARED OPERABLE.REACTIVITY CONTROL SYSTEMS TQ AND FXY EXCEEDED LIMITS AT TIMES.OPERATIONAL EVENT CEA #68 DROPPED DUE TO FAILURE OF ONE OR MORE OF ITS C0ll POWER PROGRAMM

ER TIMING MODULE, INTEGRAL TIMER, OR 15 VOLT POWER SUPPLIER. SINCE ALLTHREE WERE REPLACED, IT IS NOT KNOWN WHICH WAS THE CAUSE OF THE CEA DROP5. CEA 768 WAS RESTORED TO ITS NCRMAL POSITION AND HAS PERFORMED NORMALLY FOR FOUR WEEKS.

)0)rJ; 125uw(2)r$1

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pLICENSEE EVENT REPORTS ' i-

}-

COMPONENT MANUFACTURER DOCKET N0.COMPONENT / COMPONENT SUBCODE LER NO.CAUSE CODE /CAUSE SUBCODE CONTROL NO. EVENT DATEFACILITY / SYSTEM SUPPLIER REPORT DATE EVENT DESCRIPTIONMETHnD OF DISCOVERY NSSS / A/E RFPORT TYPE CA!'SE DEsrRIPTION

COMBUSTION ENGINEERING, INC. 05000335 041578 (78-11/1T-1) WHEN UPPER GUIDE STRUCTURE (UGS) WAS PEMOVED (REFULLING SHUOTHER COMPONENTS 78 OIT 080878 TDOWN),3 INCORE INSTR. THIMBLES RLMAINED IN CORE. ALL 3 SHOWED EVIDENCE

SUBCOMPONENT NOT APPLICABLE 021899 2-WEEK THAT CLEAN SEPARATION HAD OCCURRED BEFORE PLANT COOLDOWN.EACH SEPARATI0DESIGN / FABRICATION ERROR NSSS N WAS AT THE POINT OF ATTACHMENT TO UGS INSTR. PLATE. THESE THIMGLES AR

CAUSE SUBCODE NOT PROVIDED COMB E NOT PRES. BOUNDARIES; THEY ACT AS " BUSHINGS" TO SLPPORT INCORE DETECT.ST. LUCIE-1 ECASCO

REACTOR VESSEL INTERNALSOFERATIONAL EVENT INVEST. TO DETERMINE THE CAUSE OF THE BR0 KEN THIMELES WAS PERFORMED BY T

HE VENDOR. RESULTS OF THE INVEST. SHOW THAT THE THIMELES FRACTURED BY FATIGUE AT LOCATION WHERE STRESSES WERE CONC. DUE TO THREADING & WELOS.

COMBUSTION ENGINEERING, INC. 05000285 052078 TOP WEL CRACKED ON 90-DEGREE ELBOW ON CHARGING FEADER WELD NUMEER M-4A 0PIPES,F D T INGS 78-014/03L-0 053178 N LINE NUMBER 9-2051-2

LESS THAN 4 INCHES 021529 30-DAYDESIGNFABRICATION ERROR NSSS

DESIGN COMBFT. CALHOUN-1 GHDRCHEM,VOL CONT + LIQ POISN SYSOPERATIONAL EVENT CRACKED WELD WAS DUE TO VIBRATION OF PIPING IN SERVICE, SYSTEM DRAINED.

WELD GROUND OUT & REPAIRED USING CERTIFIED WELD POD & APPROVED PROC. LINE TESTED HYDR 0 STATICALLY TO LINE PRESSURE. VIB. CAMPING MOD. WILL BEINSTALLED WITH NEXT 6 MOS. LPON RECEIPT OF PARTS TO REDUCE VIB. IN SYS.REACTOP WASN'T CPITICEL & ALTEp. CHAPGING PATH WAS AVAIL. Et' PING PEPAIP.

COMBUSTIUN ENGINEERING, INC. 05000285 062078 THE WELD UN IHL ULMINtkAlllLD WAILR INLLI VALVL (th-JL2) FOR CHAKGING FUPIPES FITTINGS 78-021/03L-0 071278 MP CH-1A DEVELOPED A SMALL LEAK ALLOWING LEAKAGE FROM THE SYSTEM INTO TH

LESS THAN 4 INCHES 021738 30-DAY E CHARGING PUMP ROOM. REDUNDANT CHARGING PUMPS CH-1B AND CH-1C WERE OPECOMPONENT FAILURE NSSS RABLE; THEREFORE, TECHNICAL SPECIFICATION 2.2 REQUIREMENTS WERE SATISFIE

METALLURGICAL COMB D.FT. CALHOUN-1 GHDRCHEM, V0L CONT + LIQ POISN SYSCPERATIONAL EVENT THE CRACKED WELD WAS DUE TO VIBRATION OF THE P! PING IN SERVICE. THE CRA

CK WAS GROUND OUT AND REWELDED USING CERTIFIED PROCEDURE. PERMANENT CORRECTIVE ACTION WILL INCLUDE MODIFICATION TO REDUCE PIPING VIBRATION.

126

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COMPONENT MANUFACTURER DOCKET NO.CCMPONENT/COMFCNENT SUECCCE LER NO.CAUSE CODE /CAUSE SUSCODE CONTROL NO. EVENT CATEFACILITY / SYSTEM SUPPLIER FEPCRT DATE EVENT CESCRIPTIONMFTPCD OF DISCOVERY NSSS / A/F PEPrRT TYPF CAtKF f,FSCRIPTiON

CONDE' MILKING MACHINE COMPANY 05000348 07047z AT 1110 AND 1851 7/4/78 AND 0250 7/5/78, CONTAINMENT MONITORS R-11 AND RPUMPS 78-045/01L-0 080378 -12 INOFERASLEZWFEN VACUUM PUMP FAILEC TO RESTART. T/S 3.4.6.1 REQUIRES

POTARY 021973 30-CAY R-11 AND R-12 CR A CONTAINMENT AIR Cr1LER CONDENSATE LEVEL FONITORING SCOMPONENT FAILUPE NSSS YSTEM EE OPERAELE. AT 1946 ON 7/5/78 x 11 AND R-12 TALEN OUT OF SERVICE

MECHANICAL WEST TO REPLACE VACULM PLMP AND MOTCR. EACH TIME R-11 AND R-12 RETURNED TOJOSEPH M. FARLEY-1 SSC/EECH OPEPACLE STATUS WITHIN TIME SPECIFIED IN T/S. HEALTH AND SAFETY OF FUBLAIREOFNE PADICACT MCNITCR SY5 1C WERE NOT AFFECTED.OPERATIONAL EVENT EXCESSIVE VIBRATION DUE TO PUMP / MOTOR COUPLING FAILURE CAUSED RELAY FAIL

URES DUE TO BROKEN WIRE AT H10 7/4/78 AND 0250 7/5/76 AND CAUSED PLUG-1N TYPE RELAY TO VIBPATE DUT OF ITS SOCLET AT If51 7/4/78. RELAYS REFLACED/ REINSERTED. VACUUM PUMP, f0 TOR, AND COUFLING ASSEMELY REPLACED. SEELFP 78-034/03L-0.

LUNSOLIDAILD LUNihULS LUhP. Ot00034b 0605/8 16-MUNIH SFAS SUkktILLANLL IL5T FAILED b/2/ib LLL 10 AN SFA5 SLQLtNLLR fINSTRUMENTATION + CONTROLS 78-055/01T-0 061678 All ING TO PROPEPLY Or'EPATE IN SFAS CHANNEL 1. INVLSTIGATION FEVEALED AOTHER 021574 2-WEEK DES'GN DEFICIE NCY CGMBINED WITH SLICE LINKS INCORRECTLY LEFT CPEN. HAD

DESIGN / FABRICATION ERROR A/E SFAS ACTUATION OCCURRED WITH LOSS OF 0FFSITE F0WER. SEQUENCLR WOULD NOTDESIGN B+W HAVE AUTOMATICALLY SEQUENCED ECCS LOADS ONTO ESSENTIAL EUSSES. OPEPATCR

DAVIS-EESSE-1 BECH S COULD HAVE MANLALLY LOADED EMEFGENCY DIESEL GENERATOR.ENGNPD SAFETY FEATR INSTR SYSROUTINE TEST / INSPECTION DESIGN DEFICIENCY IN A SYSTEM REVISION. FACILITY CHANGE RECUEST 78-263

WRITTEN TO CORRECT CESIGN CEFICIENCY. CORRECTIVE ACTICNS INCLUDE PLVIEWOF ELECTRICAL SLIDE LINK USES, MANAGEMENT CONTROLS FOR SLICE LINKS, ANDTECHNICAL REVIEW OF DESIGN CONTROL FEATURES NERSUS SURVEILLANCE TEST PR

OCEDURES-CON 50LIUATED LUNIFUL5 LUFP. 05000346 0620/o SAFLIY FLATURL5 ALIUAllON SYSTLM LHANNLL 2 LOUIL 10 $EyLtNLER fULNU IU H

INSTRLMENTATION + CONTPOLS 78-073/03L-0 071878 AVE A WIRING ERROR. DISCOVERED AT 0800 06/20/76 WHILE RUNNING SFAS 18 MSWITCH 021854 30-DAY ONTH TEST ST 5031.07. REPORTED IN ACCORDANCE WITH T.S. 3.9.1.9. CHANNE

DESIGN /FAERICATION ERROR A/E L 2 SEQUENCER WOULD HAVE FUNCTIONED PROPERLY FOR ZVERY CONDITION EXCEFTMANUFACTLRING B+W AN SFAS ACTUATION CCCURRING WHILE EMERGFNCY DIESEL GENERATOR WAS SUPPLYI

DAVIS-EESSE-1 EECH NG ESSENTIAL BUS DI.ENGNRD SAFETY FEATR INSTR SYSROUTINE TEST / INSPECTION SEQX RELAY - E64B DRAWING INCORRECTLY WIRED TO RELAY SOCKET. THIS SCCKE

T IS FACTORY WIRED; THUS INCIDENT WAS CAUSED BY A MANUFACTURING DEFECT.AT ABOUT 1600 ON 06/20/78 WIRING WAS CORRECTED AND VERIFIED BY SATISFAC

TORY COMPLETION OF SURVEILLANCE TEST ST 5031.07.

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LICENSEE EVENT REPORTS 'd'2

COMPONENT MANUFACTURER DOCKET NO.COMPONENT / COMPONENT SUBCODE LER NO.CAUSE CODE /CAUSE SUBCODE CONTROL N0. EVENT DATEFACILITY / SYSTEM SUPPLIER REPORT DATE EVENT DESCRIPTIONMETHOD OF DISCOVERY NSSS / A/E REP 0RT TYPE CAUSE DESCRIPTION

CONSOLIDAIED CONTROLS CORP. 05000346 061978 DURING SURVEILLANCE TESTING B0 RATED WATER STORAGE TANK LOW LEVEL TRIP SEINSTRUMENTATION + CONTROLS 78-070/03L-0 071378 TPOINT FOR SFAS CHANNEL 1 FOUND TO HAVE BEEN OUT OF TOLERANCE. UNIT IN

SWITCH 021856 30-DAY MODE 6. BWST LEVEL INSTRUMENT STRINGS FOR SFAS CHANNELS 2, 3 AND 4 WERECOMPONENT FAILURE A/E OPERABLE WHILE INDICATION FOR CHANNEL 1 WAS INOPERABLE.

INSTRUMENT B+WDAVIS-BESSE-1 PECHENGNRD SAFETY FEATR INSTR SYSROUTINE TECT/ INSPECTION COMPONENT FAILURE OF LEVEL TRIP MODULE. SETPOINT ON LIMIT SWITCH LSL-15

25A APPARENTLY DRIFTED. LEVEL TRIP MODULE WAS REPLACED. AFTER SURVEILLANCE TEST SUCCESSFULLY PERFORMED, BWST LEVEL INDICATION FOR SFAS CHANNEL

1 DECLARED OPERABLE.

CONSOLIDATED CONTROLS CORP. 05000346 061878 ON 06/1B/78, 1015 HOURS DURING SURVEILLANCE TESTING, CONTAlhMENT SPRAY PINSTRUMENTATION + CONTROLS 78-071/03L-0 071478 UMP 1-2 FAILED TO START AUTOMATICALLY ON SEQUENCE AND THUS INOPERABLE. T

SWITCH 021855 30-DAY .S. 3.3.2.1 REQUIRES OPERABILITY OF BOTH CS PUMPS IN MODES 1, 2, 3 AND 4COMPONENT FAILURE A/E UNIT IN H0DE 6. NO DANGER TO HEALTH AND SAFETY OF PUBLIC OR UNIT PER

INSTRUMENT B+W SONNEL. THE OTHER CS PUMP WAS OPERABLE.DAVIS-BESSE-1 BECH

OiHR INST SYS REQD FOR SAFETYROUTINE TEST / INSPECTION COMPONENT FAILURE. FAILURE UF A SAFETY FEATURES ACTUATION SYSTEM OUTPUT

MODULE CAUSED FAILURE OF RELAYS TO DE-ENERGIZE. THE OUTPUT MODULE WASREDLACED. CS PUMP 1-2 WAS RETURNED TO OPERABILITY ON JUNE 20, 1978.

CONSOLIDATED VALVE CORP. 05000346 042878 AFTEF PERFORMANCE OF MONTHLY TEST AT 1015 TEST Trio BYPASS SWITCH WAS M0INSTRUMENTATION + CONTROLS 78-043/03L-0 052478 VED FROM REACTOR COOLANT SYSTEM POSITION. RCS PRESSURE INDICATION FELL

SWITCH 021SG6 30-CAY TO ZERO INSTEAD OF RETURNING TO NORMAL. NO DANGER TO HEALTH AhD SAFETYCOMPONENT FAILURE A/E OF PUBLIC OR UNIT PERSONNEL. THREE OTHER RCS LOW PRESSURE INSTRUMENT ST

MECHANICAL B+W RINGS WERE OPERABLE AND SFAS CHANNEL 2 FOR RCS LOW PRESSURE WAS IN THEDAVIS-BESSE-1 BECH TRIPPED (SAFE) CONDITION.ENGNRD SAFETY FEATR INSTR SYSROUTINE TEST / INSPECTION BPOKEN WIRE FOUND ON TEST SWITCH FOR SFAS CHANNEL 2. CAUSE BELIEVED TO

HAVE BEEN MOVEMENT OF SWITCH IN PANEL SINCE SWITCH FOUND SLIGHTLY LOOSE.SWITCH TIGHTENED 4D BROKEN WIRE REPAIRED. CHANNEL DECLARED OPERABLE AT

1442.

128

LICENSEE EVENT REPORTS.

COMPCNENT M.ANUFACTURER COCKET NO.COMPONENT /CCMPONENT SUECODE LER NO.CAUSE C0CE/CAUSE SUECODE CONTRCL NO. EVENT CATEFACILITY / SYSTEM SUPPLIER PEPORT DATE EVENT CESCRIPTIONMETh0D OF DISCOVERY NSSS / A/F REPncT TYPE CAUsF CESCRIPTION

COOPER PENJAX C5CCC295 071776 DURING TESTING, TFE 1A DIESEL GEMir,ATOR WAS FOUND INOPERABLE DUE TO A HIENGINES, INTERNAL COMBUSTION 78-CES/C3L-0 081678 -CELTA-P ACROSS THE LLEE OIL FILTE P. THE AUX. POWER SYSTEM WAS IN A DEG

SUBCCMPONENT NOT APPLICAELE C2196E 3zpzy raded c.ede 9 tech. spec. 3.15.2.C). FREVIOUS LER'S: 50-295/78-9; S0-304COMPONENT FAILLPE A/E /77-67. THE FEALTH AND SAFETY OF THE PLELIC WERE NOT AFFECTED CECAUSE R

CORROSION kEST EDUNDANT SYSTEFS WEFE OPERACLE AS VERIFIZD BY REQUIPED TESTING.ZION-1 S+LEMERG GENERATOR SYS + CONTROLSSPECIAL TEST / INSPECTION CIL COOLER TUCE LEAK ALLOWED WATER INTO OIL CAUSING HI FILTER CELTA-P.

TUEE LEAK CUE TO EROSION FROM HI WATEP VELOCITY INTO COOLER. TUBE PLUGGED. CHANGED OIL AND FILTER. CRANKCASE LEVEL AND OIL SAMPLES WINL BE M0NITORED MCPE CLOSELY. WATER \ELOCITY WILL EE LOWERED. FURTHER CORRECTIVr ccTinq nyrrp r|y E S T ig rJ ICN . COCLEP FFP IS PASCO *12120-OP,

CRANE COMPANY C5000249 030476 JUST PRIOR 10 & DLkING LNIT 3 ktFLELING OUTAGL, SEVERAL LOCAL LLAK RAitVALVES 78-003/01X-1 062378 TESTS IDENTIFIED CONTAINMENT VALVE LEAKAGES IN EXCESS CF TECH SPEC. 4.7OTHER 0207E0 OTHER .1 LIMITS FOR SINGLE \ ALVE LEAKAGE, SINGLE PENETPATION LEAKAGES, AND TOT

COMPONENT FAILURE NSSS AL LEAKAGE FROM ALL TESTALLE FENETRATIONS. SINCE ALL LEAKAGE WAS CONFINMECHANICAL GE ED WITHIN TEE SECCNDARY CONTAINMENT AND NONE OF THE LEAKAGE WAS TO THE E

DRESCEN-3 S+L NVIRCNMENT, THIS EVENT HAS LITTLE SAFETY SIGNIFICANCE.REACTOR CONTAINMENT SYSTEMSROUTINE TEST / INSPECTION LEAKAGE ThROUGH FEEDWATER CHECK VALVES 3-220-58B & 62B CUE TO WORN SEAT /

DISC ASSEMELY PINS. SEAT / DISC ASSEMELIES REFLACED. LEAKAGE FROM AN OFFCENTER DISC IN VALVE 3-1601-21. VALVE WAS REPLACEC. EXCESSIVE LEAKAGE

THROUGH TEST CONNECTION VALVE WHEN MSIV 3-203-2C WAS TESTED. VALVE REPArrED.

CRANL CoMPANf 05L00254 070/76 LN 7/ 7/1976, CURING STEADY STATE POWER UFERT.TIUN LNIT 1 CFERATOR NOTICLDVALVES 78-020/03L-0 080278 A CUAL POSITION INDICATION ON CRYhELL EQUIP SUMP DISCFARGE ISOLATION VAL

GATE 021981 30-DAY VE A0 1-2001-15. THE VALVE WAS GREASED AND EXERCISED 3 TIMES. ON 7/11/COMPONENT FAILURE A/E 78, WHILE FERFORMING SURVEILLANCE PROCECURE 005-005-1, VALVE FAILED TO CMECHANICAL GE LOSE. CONSEQUENCES OF THIS EVENT WERE MINIMIZED BY THE FACT TbAT VALVE

QUAD CITIES-1 5+L A0 1-2001-16 WAS OPERABLE AND PLACED IN THE CLOSED POSITION TO PROVIDE PREACTOR CONTAINMENT SYSTEMS RIFVRY CONTAINMENT ISOLATION.OPERATIONAL EVENT TFE CAUSE OF THIS EVERT IS DLE TO COMPONENT FAILURE. THE VALVE NEEDED M

INOR ADJUSTMENTS TO lee PACKING AND LUERICATION CF THc BUSHINGS. NO OTHER DEFECTS WERE FOUND, AND FOLLOWING ADJUSTMENT OF THE PACKING AND LUBRICATION IT FUNCTIONED PROPERLY.

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CW GNENT/ELFP.Em ' cCCCCE LEP NO.CAUE! COLE /CAUEL M LCTE CONTECL NO. EVENT EATE

F AC '. L IT Y / SY ST E M SLFPLIER REFORT DATE EVENT DESCRIPTION

"cTHM CF n!Cff M ki WC / A/E PFPr&T TYFF f f UU DEV RIPTIfd

! WHILE TESTING THE 2/3 P!FSEL GENERATOR TO ALLOW MONTELY IN3PECTION OF REW NE TELTDYNE CHEM-fiVP CIV CSCCG737 cf3078PLMPS 70-041/ 03 L-l C"C7t ~

DUNDANT DIESEL THE THERMAL OVERLDAD FOR THE 2/3 DIESEL COOLING WATER PUMCENTRIFUGAL 021082 M- M P TPIPFED. THIS DENT HAD MINIMAL SAFETY SIGNIFICANCE BECAUSE BOTH THEJTONENT FAILL _ LIC U.IT 2 AND LNIT 3 ;ELLNCANT DIEEELS WERE AVAILACLE. PREVIOUS PUMP TRIPS

MECHZNICAL D 's OLFORTED P4 ZE-13, 77-29, AND 77- 38.3ESDEN-? 'N LEFERG CENE W CL tr + .NTRGLS;FERAi!G A1 IENT M GP '4EiAGE UF XLING WATER PUMP TRIFFED OVERLCAD FOR EREAKER. FUMP

'AS REPL?'m EUT NFECTION REVEALED '.0 PROBLEM WITH REMOVED PUMP. OVERLOAD TRIF ' t.F N N OVL;EC SET TOO CLOSE TO FUMP RUNNING CURRENT. HEAT LCADS REQU nING tACESSIkE PUMP SERVICE hAVE EEEN RECUCED.

10SEY VALVE & GAGE CO. c COC 2 Ef. 40o7S WhlLE EHLTCGv4 FCR REFUELING, PERFORPNiCE OF FEFUELING SURVEILLANCE TEST

/ALVES 3-013/03L-0 27& 7L , 3PT-R6 SPCWED THE NO. S SAFETY VALVE ON THE NO. 34 STEAM GENEPATOR TO

N0ZZLE C217C? /aY CE OUISIDE 'bE REQUIPED TOLEFANCE.00FPONENT FAILUPE os

MECHANICAL WEST

INDIAN 00lNT-3 UEC

MAIN STEAM SYSTEMS + CONTRULS20CTIt.E TEST /INSPECTICN IFE EQUIPED PRESSUPE SETTING OF 1120 PSIG ON THIS CROSLEY, MODEL HC6SW

VALVE WAS h0T ALHIEVED UNTIL SETTING WAS ADJUSTED.

CUMMINS ENGP.E 'O. , 'NC. O MC'E4 4 041978 THE CIESEL-CRIVEN FIPE PUMP FAILS TO AUTOMATICALLY START ON TWO OCCASIOENGINES.INTE?'AL CCFbCSTICN M-ClE/03L-0 051978 NS (AFRIL 19, 1978. AND MAY 4, 1976).SLBCOMPONENT " APPt ICAEL: 021420 30-CAY

COMPONENT FAILiEE -/EELECTRICAL WEST

TROJAN-1 LECF

FIRE FPOTECTION S' + CON ~

CPERATIONAL EVENT TEE FAILURES TO START WERE CAUSED BY A LOOSE CONNECTION IN THE DIESEL'SFUEL CONTROL CIRCUITRY. THIS CONNECTION ACTED INTERMITTENTLY TO PREVENTTHE DIESEL FROM RECEIVING THE REQUIRED AMOUNT OF FUEL REQUIFED FOR OPERATION.

130


COMPCNENT MANUFACTURER CCCKET No.COMPONENT /CCMPONENT SUECOEE LER f,0.CAUSE C0?E/CAUSE SUBCODE CONTRCL NO. EVENT CATEFACILITY /;YSTEM SUFPLIER REPORT DATE EVENT DESCRIPTIONvrT4ng nF 9fSr0VFPY NSSS / A/F EFPrRT TYPF CAU%F CFSCRIPTION

CUMMINS ENGINF CO., INC. 05000346 C5167E ON 5/18/78, THE DIESEL FIRE PLMP FAILED ITS SURVEILLANCE TEST. EACH OCCENGINES,INTEPNAL COVELSTION 78-054/03L-0 061478 CUhPENCE PLACED ThE UNIT IN TFE ACTION STATEMENT OF T.S.3.7.9.1, WHICH R

SUBLOMFONENT NOT APPLICALLE C21575 30-DAY EQUIPES TWO HICH FRECSLPE PLMPS AT ALL TIMES. NO DANGER TO HEALTH AND SCOMPONEf;T FAILURE A/E AFETY OF PUELIC OR UNIT PERSONNEL. THE ELECTRIC FIRE PLMP WAS OPERALLE

MECHANICAL B+W IF AN INCICENT REQUIRIN' THE FIRE FROTECTION SYSTEM LAD OCCURRED.DAVIS-EESSE-1 LECHFIRE PROTECTION SYS + CONTROUTINE TEST / INSPECTION OCCURRENCE ON 5/18/78 WAS ATTRICUTED TO COMPONENT FAILURE OF RADIATOR H0

SE AND TRIPPING ON FEMOTE START FROM CONTROL ROOM- ON 5/25/78, DIESEL FIRE PUFP FAILED TO START FEMOTELY FROM CONTROL ROOM RESULTING FROM DEFEC,

TIVE STAPTING CONTACTORS. THE RA11ATOR EOSE WIS REPLACED. NEW DIESELPATTTPIFS ann STfpTING frNTArTrp% MVF RFFN INSTcttFD.

LLMMIN5 ENGINL LU., INL. us0003Jd utlt/c IHL NuiUR-URIvth f ikt t LMr 1-fi-kl LLLAML INuPthsbLL UN b-6-76 LLt TO AHEAT EXCMANGERS 78-053/01T-0 062878 STARTER FPOBLEft GN E-IE-78. FRIOR TO THE REPAIR OF 1-FP-P-1. THE DIESE

COOLER 02166C 2-WEEK L CRIVEN FIRE PUMP, 1-FP-P- , EECAME INOPERAELE CUE TO LOSS OF COOLING WCOMPONENT FAILURE A/E ATER. THIS IS REFORTABLE LNCER T.S.3.7.14.1 ACTION STATEMENT B. TWO TEOTHER WEST "PORAFY PUFPS RATED AT 1CCC CFM EACH HAD BEEN ESTABLISHED AS BACLUP PUMP

NCRTH ANNA-1 S+W S. A 750 GPM FIRE TRUCK PUFP WAS ALSO AVAILAELE.FIRE FROTECTION SYS + CONTOPERATIONAL EVENT FOSE SUPPLYING COOLING WATER TO RAI . ATOR ON DIESEL BECAME DISCONNECTED A

FTER ThE FIRE PUMP 55ARTED CAUSING IHE PUMP TO EECOME INCPERATIVE. THETEMPERATURE INDICATOR CONNECTION 0 WATER JACKET ALSO LEAKED. TEMPERATU?E INDICATOR CONNECTION WAS PLUGGE HOSE REPLACED AND THE PUMP PLACEDIN SF PVirF Folt0 WING TF%T.

LLFl!1N5 LNGINL LU. , iNL. USUUu324 001276 UN 6/14/76 Iht DIL5LL LNLINt Lhit N ilnL fLMr ikiEM D GN AN UvtnM LtU INMECHANICAL FUNCTICN UNITS 78-053/03L-0 071178 DICATION DURING PERIODIC TEST 35.7 (FIRE PPOTECTION SYSTEM CHECKS). TEC

SUBCOMPONENT NOT APPLICAELE C21687 30-DAY HNICAL SPECIFICATION 37.7.1)COMPONENT FAILURE A/E

MECHANICAL GELRLNSWICr c UECFbm ,KOTECTION SYS + CONT

ROUTINE TEST / INSPECTION THE DIESEL ENG TACHOMETER, WHICH IS USED TO CONTROL ENG SPEED, WAS FOUNDOUT OF CALIBRATION C%USING THE ENG TO RUN AT 1000 RPM INSTEAD OF 1750 R

PM. ALSO, THE OVERSPEED TRIP SWITCH WAS FOUND INITIATING A TRIP AT A LOWER THAN NORM SET PT. ON 61278 THE TACHOM WAS ADJ SO THE ENG NOULD NOTTRIP ON OVERSPEED.

131Coi,

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;J

LICENSEE EVENT REPORTS yJ-

CCMPONENT var,LFACTLPER C0CKET %0.COMPCNENT/CCMPCNENT SUCCCCE LER NO.CAUSE CCCE/CALSE SLECCCE CONTROL NC. EVENT CATE

FACILITY /SYITEM SLPPLIER REFCRT CATE E'. E NT CESCRIPTICN

vFTurO CF CISCOVFPY N%RS / A/F ;rrr;T Tyrr (Apsr FFsrRIFTION

CLMMINS ENGINE CO., INC. 05CCC267 070378 DLRING ROUTINE SERVEILLANCE TESTING CF TFE IACM CIESEL GENERATCP/PLMP UNCTHER CCMFC%ENTS 7E-02A/03L-C 030278 ITS, ONE OF THE TWC CIESEL ENGINES WOULC TLRN CVER EUT WOLLD NOT START.

SLBCCMACNENT NOT APPLICAELE 0220CA 30-CAY PEPDFTAELE FE9 TECH'.ICAL SFECIFICATIC% AC 7.5.2(B)2 0FERATICS UNCER A DCCMPCNENT FAILLEE N555 EG;ACCD MCCE PE;MITTED EY LCO 4.2.16. NG ACCOMPANYING CCCLPPENCE. NO D

CTFER GGA 2.GE; TO FLELIC "EALTh CP SAFETY. REOLNDANT LNIT AiAILAELE AND OPERAELEFT. ST. V; AIN-1 5+L SIMILIA? PF0ELEY ?EFCFTEC CN FEPORTAELE CCCLFRENCE 7E-15.OTHER SYSTEMSPOLTINE TEST / INSPECTION WATER IN TFE hlL SYSTEM CLE TO CONDEN_ATION IN STCRAGE TANN FRCM ERAINI

NG ANC FILLING FELiENTED CIESEL E'.G*NE FFCM ST APTING. EDTP STCFACE TAMSCRAINED TO REMCVE ANY WATER ACCLFLLATICN CHAIN VAL'.E5 IN5i;LLED ON EO

'TCM CF EACH STCRAGE TAN' SURVEILLA',CE TEST FEYISEE TO INCLLCL CRAININc emc ro r:cv cT-rtct '".c

CUT LE W-F AMPL R CECLCC L etElle .LPING A r0UTINL SLCvEILLANCE TEST A LNIT J E5a FLMP SLFPLf FAN (2Akt0)CIRCUIT CLCSERS/INTEPRUPTEPS 7E-C27/C2L-C CE2E7; FAILEC TO START IN TFE MAN;AL "CCE TFI CCN5T'TLTED CFE;ATIC'. IN TFE D

CONTACTCP C21A99 3C-LAv ESRACEC PCCE AS PE;MITTED EY T.S. :.9.C.A. INVE5'!GATICN CETEFMP.ED TFACCMPONENT FAILL;E A/E ' TFE PPCELEM WAS CAUSEC CY A "ALFLNCTICA P. T'E FA'. 90 TOR STARTING CIPC

MECFANICAL GE w!' TrE FECLNCANT FANS WEPE OFE;AELE AT 'FIS TIME

PEACH BOTTCP-2 EECF

CCCL SYS FCP FEAC AL/ + CCSTROUTINE TEST /U.5FECTION TFE MALFLNCTIC': WAS CALSED EY TFE FAILL;E CF 'FE CVE;LCAC ;ELaf C ;ESET

CLE TO MECHANICAL P;CELEMS. TFE HELAV (TYFE C3CO, SIZL 2, ete:EG LCIL_MEE0 1006) WAS FEFLACEC IN VI'.C.

CUTLER-FAMMEP CSCCCC10 CCCC7E EAtrLP 01ESEL CENEFATCP LOCAL LOW FLEL OIL LEVEL ALAFU LAS CE!E r .EC . C

CIPCUIT CLCSEF5/ ''E;;LFTE 'E-C20/C.L-C C6217E CNTPCL PCCM T:CLELE ALAPM "AC ?.CT 47.NLNCIATEC. IMMECIATE INVESTIGATICNSTARTER C21537 30-CAY ;EkEALED TFE CAY TA%- WAS EMPTY AND TFE FLEL OIL T;ANSFEP FLMF WAS CFF.

CCvFONENT FAILLE OTFER T'E CG FAC EEEN ELCCESSFLLLY CFE;ATEC CN C/S/7E. TRANSFCFMEP 13, TrE EQ

ELECTRICAL CE LIVALE'.T CFFLITE FCWER SCLFCE, WAS Ak AILAELE. TFIS 15 NCT A FEPETITIVE

CPE5 DEN-1 EECH CCCLF;ENCE.

EMEPG GENEPATCR SYS + CCNT;Llf

SPECIAL TEST /INSFECTICN TFA%5FEP PLM0 STCFFED SCE TU A FAILLPE CF TFE STARTEP CCaiPCL TRANSFCEMER. TFE ALA 3 FLNCTIC%ED PPCFEPLY, ELT LCW LEVEL ALARM WAS ACthCWLECGEC AND NCT PESET CLRING CG 5FUTCCWN ON E/5/7E. ThE CFERATOR MI5FEA0 TANK

LEVEL AS FLLL. STAPTEP TRANSFC' {L WAS FEPLACEC ANC TFE SLRV. FPCCECLRE ;EVISED TO ',EFIFY G FANEL ALAFMS APE CLEAR.

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||COMPCNENT MANUFACTURER DOCLET NO.COMF0NENT/CCMPONENT SUSC0CE LER NO.CAUSE COCE/CAUSE SLBC00E CONTROL NO. EVENFACILITY / SYSTEM SUPPLIER PEPCR EVENT DESCRIPTIONMETHOD OF O!!COVERY NSSS / A/E GEPORT CAUSE DEsrpTPTION, . .

DARLING VALVE & MFTG CO. 05000261 050973 AT 2300 HRS, MAY 9. 1978, ANALYSIS OF " BIT" SAMPLE REVEALED BORON CONCENVALVES 78-012/03L-0 060778 TRATICN IN THE TANK OF 19,638 PPM, LESS THAN THE MINIMUM ALLOWED BY TECH

GLOBE 021616 30-DAY NICAL SPECIFICATION 3.3.1.1.B CF 20,000 PPM. " BIT" CONCENTRATION WAS EVCOMPONENT FAIIUFE NSSS ENTUALLY BROUCHT EACK ABONE MINIMLM CONCENTRATION.

MECHANICAL LESTH. B. ROBINSON-2 EBASCOEMERG CORE COOLING SYS + CONTROUTINE TEST / INSPECTION CCCURRENCE WAS CAUSED BY LEAKAGE PAST THE INLET VALVES (S1-867 A&B) ON T

HE " BIT" DURING PERFORMANCE OF THE SI FERICCIC TEST. EIT WAS FECIRCL'LATED WITH THE "A" BAST AFTER ANALYSIS OF A SAMPLE OF BAST REVEALED PROPERCONCENTRATION.

DARLING VALVE & MFTG. CO. 0500C261 C61378 AT 2300 HRS, 6/13/76, ANALYSIS OF BIT SAMPLE REVEALED ECRON CONCENTRATI0VALVES 78-016/03L-0 071878 N IN THE TANK OF 17,268 PPM, LESS THAN TFE MINIMUM ALLOWED BY TECH. SPEC

GLOBE 021748 30-DAY 3.3.1.1.B 0F 20,000 PPM. THIS WAS FOUND DURING SAMPLING AFTER COMPLETCOMPONENT FAILURE A/E IGN CF THE MONTFLY SI SYSTEM CCMPONENT TEST. BIT CONCENTRATION WAS BROU

INSTRUMENT WEST GET BACK ABOVE MINIMUM BY FECIRCULATION WITH "A" BAST. NO ADVERSE CONSEH. B. ROBINSON-2 EBASCO QUENCES RESULTED FROM THIS OCCURRENCE.EMERG CORE COOLING SYS + CONTROUTINE TFST/ INSPECTION OCCURRENCE WAS CALSED BY LLAKAGZ PAST TFE INLET VALVES (S1-667 AaB) ON T

HE BIT DURING PERFORMANCE CF THE SI PERI 0CIC TEST. BIT WAS RECIRCULATEDWITH THE "A" BAST AFTER ANALYSIS OF A SAMPLE OF BAST REVEALED PROPER B0

RON CONCENTRATICN. THE BIT WAS LEFT WITH A CONCENTRATION OF 21,214 PPMAT 0215. JUNE 14 1978

DEARBORh rub 6ER LOkP. 05000295 070676 JLRING NUkPAL OFLRAllGN, lHL LNIl 1 CUNTAINMENT PARTILULATE AND GAS MuNIPIPES, FITTINGS 78-060/03L-0 060778 TOR 1PE0011/1RE0012 REPEATEDLY FAILEC ON LOW FLOW. THE MONITOR WAS TAKELESS THAN 4 INCHE; 021972 30-CAY N 005 AND SURVEILLANCE WAS PERFORNED AS REQUIRED IN TECH SPEC 3.14.1.C.

LOMPONENT F?ILURE NSSS THERE WERE NO SAFETY IMPLICATIONS AND THE HEALTH AND SAFETY OF THE PUBLNATURAL END OF LIFE WEST IC WAS NOT AFFECTED.

ZION-1 S+LAIPBORNE RADICACT MCNITOR SYSOPERATIONAL EVEhi FAILURE OLE TO COLLAPSE OF FLEXIBLE HOSE ON INLET TO FLOWMETER. HOSE WA

S SUPPLIED BY DEARBORN EUBBER CORP. AND THE FAILURE WAS DUE TO NORMAL END OF LIFE. HOSE WAS REPLACED AND MONITOR WAS RESTORLD TO SERVICE. NO FURTHER CORRECTIVE ACTION IS NECESSARY.

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LICENSEE EVENT REPORTS I,ti

ZCOMFONENT MANUFACTURER DOCKET NO.

CCFFONENT/COMPCNENT SUbCCCE LER NO.CAUSE COCL'/CiUSE SUECCCE CONTFCL NO EVENT CATE

FACILITY / SYSTEM SUPPLIER PEPORT CATE EVENT CESCRIPTION

METHOD OF CIsrCVERY NSSS / A/F REPnRT TYPF CAUSF prSCRIPTION

DELPHI INDUSTRIES 05000348 062878 PERFORMING FNP-STP-220.9B. POST ACCIDENT HYCROGEN ANALYZER 1B FUNCTIONALELECTRICAL (CNDUCTORS 78-044/03L-G 071578 TEST, ANALYZER CELL GAVE ERRATIC READINGS. ANALYZER 18 DECLARED INOPER

SLECOMPCNENT NOT APPLICALLE C21979 30-CAY ABLE AT 1340. T/S 3.6.4.1 REQUIRES TWO INDEPENDENT CONTAINMENT HYCROGENCCMPONENT FAILURE A/E ANALYZERS OFERAELE. ANALYZER 1A WAS CFEFAELE. UNIT RETURNED CPERAELE A

ELECTRICAL WEST T 1020 7/12/78, T/S REQUIREMENTS MET. FEALTH/ SAFETY OF PUELIC NOT AFFECJOSEFH M. FARLEY-1 SSC/EECH TED.CNTNMNT COMLUS GAS CONTROL SYSFOUTINE TEST / INSPECT!ON WIRING TO ANALYZER LELL INSIDE HEATED LCMfARTMENT WAS CEGRADEC DUE TO HI

GH CEERATING TEMP. REFLACED WITH WIRE SUITAELE FOR HIGH TEMP USE. ALSOLOW SAMPLE FLOW D/P EWITCH, STATIC-0-RINr NO. A RE-K2YIC, WOULD NOT GIV

E LCW FLOW ALAPM AND WAS REPLACED. ANALYZER 1A NSPECTED; N0 LVIDENCE OF WIRING PEGRADATIrN.

blAMUNU PUWER SELCIAllV L0 r.P . CLOLC270 Ut2//d UN t/9//6, LONikUL MUL t bkULP 4 WA5 ftsNU 10 HAVL A SnLkT 1N irl LkD blCC IPCL RCD DRIVE MECHANISMS 78-009/C3L-0 072878 ATOP WHICH WOULO FPECLUDE NCRMAL POWERED yn"E,htNT. ThE GFCLP WAS FULLY

'tCCCMPONENT NOT APPLICAELE 021902 30-DAY WITHERAWN 50 ThAT NO FAZARD RESLLTED FPCM THE SHCRT. ThE LNIT WAS SHUTtCMPONENT FAILUPE NSSS CCWN FOR REFAIR CN JL'LY 1, 197P. FEPLPTEL E/27 CUE TO SCrECULED SURVEIL

i ELErTRICAL E+W LANCE TEST WHICH COULD NOT EE FEPFCEMED WITnCUT DPCPPING THE ROD. TS AMOCCNEC-2 C/EECH ENDED TO ALLOW CCNTISLEC CPERATICN WITH INCFERAELE ROD.RE*CTIVITY CONTRCL SYSTEMS-UUT'N'_ TEST /;NSFECTION TFE SHORT WAS FRCEAELY C%LSEC BY MCISTLFE INCUCED CCRROSION WHICH HAS CC

CURRED PPEVIOUSLY CN ALL OCCNEE UNITS. CORRECTIVE ACTION WAS TO REPAIRTFE Sh0RTED STATCR

DIAMC'-C PCWER SPECIALTY C0hP. CFOCC259 C61476 SEVEN OF NINE CONTROL PCCS IN G;0LP 3 INADiERTANTLY CRCPFED INTO CORE PE

CONTFDL D00 CRIVE MECHANISMS ;E-020/017-0 CO2878 $ULTING IN CFERATICN WITH "0PE THAN CNE INOPERAELE RCD PER T.S. 4.7.1.2.SL3COMPONENi NOT AFELICAELE C21953 2-WEEK VIOLATION OF T.S. 3.5.2.2.A, AND ROD INDEX LIMITS CF T.S. 3.5.2.5.E.

COMPONENT FAILUPE NSSS CtRING FCLLOWING T7ANSIENT QUACRANT PUWER TILT LIMIT CF T.S. 3.5.2.4.A WELECTRICAL S+W AS EXCEECED EUT RETLENED TO ACCEPTAELE kALLE IN FOUR FOURS. POWER FEDUC

TbfEE MILE 13 LAND-1 Gli ED TU 40 IMMEDIATELY ANC CONTROL FDD ASYMMETRY CLEARED IN CNE FOUR WITHREACTIVITY CCNTPCL SYSTiv" EPUTCCWN MARGIN AL0iE 11 CELT A K/K.FCUTINE TEST /INU 'r?It, CFCFPED POCS CAlSED "Y Sh0RTED DIGCE IN CC PCLD SECCNCARY F0WER SUPFLY.

SFORTEC DIOCE AdC .CWN FUSES CAL 5ED LCW VOLTAGE FRCM SECONCARY SUPPLY.WFEN TRIP EFEAVERS FCR MAIN S!+ FLY TESTEC CURING RPS SURVEILLANCE, RCD

5 CRCFPEC EECAUSE OF LCW VCLTAGE. FUSES AND CICDE REFLACED AND CUTPUT WAVE FORMS ChECEED.

134


C CFFONE*,T 1 v.LFACTL:EP CCC ET NO.,

CCPTG .J.T/CrvFL' c NT SCECCCE L E P *, .Cela c. L t.?. .. / _ e , , n. c ; e s t r. t.- c r '.'. o *l , m' .r .r- ec

v . . r. n. ',- . v r. 'i m~ rFACILITY /5YSTEv SUFFLIEP FEFCFT CATE EVENT DISCFIPTIONvri m er 'c r c vr u . c. c c j zir : r r.n; 7 Tyrr ca c: r Ecc pTI; .

NAou'. VAL't. IL CLC:03:1 Cf 1( 7E C'. 6/IE/7E WITu TFF rE ACTOR IN STA:T-S-PCT STA'i'SY, SURVEILLANCE TESTINk AL VE 5 ' -CAE/CI'-L Cf2678 3 CF EXCESS FLCW C-ECW VALVE (EFCV) E31-FOACA (CFACCN VALVES, A55Y. NO.CEECt 0?l727 2-WEEr. 97CC E A) FEkEALEC A J.0 EEPTAELE LEA G SE CF 4.2 GPF. ACCEPTACLE LEA GCE

CCMFONE".' FAILLE A/E IE 1 GF". In 5 kALiE IC N A I" INSTFLvD.T L ME FFOM Thr 'A" FECIRC PUCTHEF CE v7 51: TIC' lpm ANs 5LFFL N A FECIFC PL"r TRANSMITTEF INDICATOR LOCP.

ELWIN 41C"-1 SSC/EEPCCOL4' FECIK SYS + CNTO <5R."T!t T E S! '" t rE CT . N EXACT CA. CF L E A' AGE ThKL Gn TFE EFCV 15 A5 YET L MN0'aN. TFE iAliE MU*

ST E E '. s' CJ' CF T " LPr TO E X AM P,: ThE SEATI'.3 ELRFACES. THE VALVE HALEE I S OL ,.'' E.1 CLC , CF A'. LFSTREAM ISCL ATION k"LVE. AFTER EXAMIN

ATION CAU: OF W LFiNC'i.GN WILL Ef TF;NSVITTED IN AN LFOATE FEFORT

:%, Ih: C5CCO2E0 CL7; :iPING TFE CCN' J '. T 'S ECTIGN FOLLCW:Tu A FLA*.',ED SnLIE0WN FCR MAI'iTFu.CE- ,SwFLr':,iH O ,9 % :5 7t-0C7/03L-C 07037E J. W E, EVICE'CE ~ Ei E55!VE PCTIC' C r THE 3 P.[F CHARGING LP.: TC TFE

O FORTS C 2191.6 30-CAY 3A CCLE LEG W ; ": _ hie" I'i IFE FC W CF DAMAGEC LAGGING AND INSLLATICN O"L u ./ C - u.TICN E Fh r/L A FCET!Ct LF TrE L..~ FLRib:e l'.5FECTION 5 HOWE D THAT TWO ADJACENT PI

'

J t:GN W: ST FE LLPPORTS WLLE "h-E % LE, WHICH TE MTTED EXCL55IiE PPING "CIION.

'LL Ey rul.*-: Lech_'"Ef Cu te ' ; b545 + CCNT Ecr r vE sij p,: ; E c71c , ssE 5tFFCR' AFFA;[ TLY LC^' FL*.CTICN nFEN TFE NUT ATTACHING IFE CLEVIS,_

FANGED EC: CAMF CFF D E /C3::N' SLFFCR', A U-LCLT TYPE , WAS BFCKE'. PC55IELv CLE TD ' CL;J x P.G FFCV T"E C'EFECTIVE FANCEP. Tr: t-SCLT WAS EEFLACED A: CL E '. ! S F A'.CE ? ;EASSE*TLED USP 3 LC3 NUTS.

. rec- ..m,. ..,m....c 8 1. - , - rc- s,. . t. c ., , , , - > C ,. , C , s n . ., ,,i <+..P,o c,u r~- cA rT.Y .m ".E LIFitD, Cr"e<mi-.as .- r.ai . m a,o .e u a o w m

-

ose,c Tmo Caerm r oo i# lie 5 7s -:: /03L-C C62676 DFCP BELCW EAlf. T/5 3.1.1.5 FEQUIFE; THAT ECS CPERATING LCCP TEMP TAVGOT'EE C21572 30-LAY 5Alf C0 MCFE. ' AVG FESTP- - WIT"!N T/5 LIM IS AT 0405 COCE SAFETY VALV

C LMFO' NT FAILLc /E : FAILEC TO FESEAT ATTEF L*IT E KLCHT 07 LP,: ATTEMPT MACE TO GAG VALVE9 CFANIC AL aEST TO FESEA' IT. T/ 5 3. 7.1.1 P E _ ::: A.t MA:N STE AM L P.E CC:E SAFETv kALV

J d EPF P. FAFLEY-1 VC/EECF E5 CFERACLE. AT CE3{ Odi IFIF FE0 r:Gn 5/G LEiELS COOLED TO PEFLACE '.LVv... c,: y < g m.c..s:< p. a p r , ca J > st,m.

OPE F ATICN-L Et E'.T CECFEA:E IN TAiG PCE TC LIFTING UF CCE SAFETY VAL \E. FEACTCR FCWER INCPEASED TO P.CREASF TAVG WITFP, I/5 LIMIT 5. FAILLRE OF COCF SAFEit iALkE T: RESEAT CLE TO E;0 9 LC,.EE rwJLSTINC . RING LOCKING PIN ALLCWIN3 LCWEP Am s T I . u- y , . ee . . .a, u .c . d, N. . .. ; L ~e a - ,a m

.. s ,. - .wc ..,. FFCu. R m Ai..,.

rec e met - a~< it ic.m.t si;.

;EFLACED.,

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LICENSEE EVENT REPORTS 'nD

COMPONENT MANUFACTURER DUCKIT NO.COMPONENT /CCMPONENT SUBCODE LER NO.CAUSE C0CE/CAUSE SUBCODE CONTROL NO. EVENT DATE

FACILITY / SYSTEM SUPPLIER REPORT DATE EVENT DESCRIPTIONMETHOD OF DISCOVERY NSSS / A/E REPORT TYPE CAUSE DESCRIPTION

DRESSER INDUST. VALVE & INST D 05000312 061178 DURING NORMAL OPERATION WHILE PERFORMING LEAK RATE PROCEDURE SP 207.04 AVALVES 78-006/03L-0 070578 N ACCEPTABLE LtAK RATE OF % 1GPM PRT T. S. 3.1.6.2 COULD BE OBTAIhED. T

PLUG 021746 30-DAY HE LEAK RATE CALCULATIONS INDICATED LEAKAGE VARYING FROM 1.1 TO 1.7 GPM.COMPONENT FAILURE NSSS UNIDENTIFIED.

MECHANICAL B+W

RANCHO SECO-1 BECH

REACTOR VES. + APPURTENANCESROUTINE TEST / INSPECTION THE INCREASED LEAK RATE WAS ATTRIB' FED TO LEAKING PPESSURIZER SAFETY VAL

VES AND AN ASSOCIATED BLOCL VALVL ON THE ELECTRGM.\ TIC RELIEF VALVE. ONESAFETY VALVE AND THE ELECTROMATIC RELIEF VALVE' WERE REPLACED. iHE OTHE

R SAFETY VAtVE WAS REBUILT AND THE ELOCK VALVE REWORKED. ALL VALVES WERE TESTED PPIOR TO PETURN TO P0kEFL ___,

DUNHAM BUSH 05000338 012278 CURING NORMAL OPERATION (MODE 1), CASING COOLING IANK ILMPLRATURL LALLLD

HEAT EXCHANGERS 78-059/03L-0 082178 ED 50 DEGREES F. VIOLATING T.S. 3.6.2.3.C.3. CASING COOLING TANK TEMPER

COOLER 022036 30-CAY ATURE MUST BE MAINTAINED BETWEEN 35 AND 50 F. THE TANK TEMFERATURE WAS

DESIGN / FABRICATION ERROR A/E RETURNED TO ITS LCO WITHIN THE PROVISIONS OF THE ACTION STATEMENT. THEMANUFACTURING WEST PUELIC HEALTH AND SAFETY ARE NOT ENDANGEPED BY THIS EVENT.

NORTH ANNA-1 54W

CNTNMNT HEAT REMOV SYS + CONTCPERATIONAL EVENT A FkE0N LEAK FROM THE TANK CHILLER UNIT IS SUSPECTED TO biVE CAUSED A DE

CREASE IN COOLING CAPACITY. THE HOT GAS BY-PASS VALVE ON THE UNIT WAS CLOSED TO TEMPORARILY CRAW DOWh TANK TEMPERATURC. THE UNIT WAS THEN RE-CHARGED WITH FREON.

EAGLE SIGNAL 05000285 061378 JURING THE PERFORMANCE OF SURVEILLANCE TEST ST-EST-5 SECTION F.1 THE MORELAYS 78-016/03L-0 C62878 NThlY AC SEQUENCL' TIMER TEST , ilMLRS SI-1B AND CH-1B ON SEQUENCER S2-2

TIMER, SEQUENCER, T-S CONTROL 021691 30-DAY FAILED TO TIME OUl WITHIN THE FRESCRIBED LIMIT. THE TIMERS WERE E)ERCISCOMPONENT FAILURE A/E ED AND TESTED WITHIN SPECIFIED LIMITS.

MECHANICAL COMB

FT. CALHOUN-1 GHUR

OTHER ENGNRD SAFETY FEATR SYSROUTINE TEST / INSPECTION THE FAILURE CF THE RELAY TO TIME OUT WITHIN PRESCRIBED LIMIT WAS DUE TO

STICKY OPERATING MECHANISM. THE TIMERS WERE EXERrlSED TO FREE THF MECn

HANISM. THE TIMERS WILL BE TESTED MONTHLY. IF A lIMER SHOULD SUFFER AREPEATED FAILURE, IT WILL BE REPLACED.

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COMPONENT MANUFACTURER DOCKET NO.COMP 0NiNT/CCMPONENT SUBC00E LEP N0.CAUSE CODE /Ca.USE SUBCODE CONTRCL NO. EbENT DATEFACILITY / SYSTEM SUPPLIER REPORT DATE EVENT DESCRIPTIONPETh00 0F DISCOVERY NSSS / A/E REpnpT Tyre CApsr rEstpIPTicN

EDWAR;5 C0 05000213 071178 DURING NORMAL OPERATICN THE DRAIN VALVE ON THE HIGH EIDE OF #4 STEAM LINVALVES 78-015/03L-0 072878 0 ELBCW TAP (STEAN FLOW FRIMARY SENSOR) STARTED L2AKING. THIS CAUSED TH

GLOBE C21906 30-DAY E FLOW INDICATION TO " READ" LOWER THAN AC',uAL. a ,1UF1ER WAS INSTALLED TCOMPONENT FAILURE A/E O PLACE THE CHANNEL IN TRIP //LARM UNTIL A GEPAIR CCULD BE COMPLETED. TH

MECHANICAL WEST IS IS REPORTABLE AS PER TECHNICAL SPECIFICATI0AS. SECTION E.9.2.B.1 ANDHADDAM NECK-1 S+W 2.REACTOR TRIP SYSTEMSOPERATIONAL EVENT THE CAUSE IS DUE TO NATURAL END OF LIFE OFTHE COMP 0NENT WHICH WAS REPLAC

ED IN KIND.

EDWARDS VALVES DIV 05000338 052978 ThE RESULTS OF PERIODIC TE'T 1-PT-52.2 PERFORMED ON MAY ZG.1978 SH0kEDVALVES 78-043/03L-0 C62778 A RCS LEAK RATE OF 1.41 GFM. T.S.3.4.6.2 SFECIFIES A MAU MCM ALLOWABLE

GLOBE 021540 30-DAY UNIDENTIFIED PCS LEAD RATE OF 1 CPM. TWO SMALL RC% VALVE LEs#5 WERE DISCOMPONENT FAILURE NSSS COVERED D"'ING A WALKDOWN OF THE RC5. THE LEAKAL DIC hDt AFFECT RCS OP

DTHER WEST ,E RAT ION . NO RADIDACTIVE GASES OR FLt!!DS WERE RELEASED TO THE ENVIRONMENNORTH ANNA-1 S+W

' T. THE ?UM 'C HE ALTH AND SAFETY WAS NJ LNDANGE RED.COOLANT RECIRC SYS + CONTROLS |

R0HTINE TEST / INSPECTION 'TW6 (ALVES,1-RC-77 AND 1-RC-102, W'..a A COMBINED VALVE PACK!NG LEAKAGERAIE OF APPP0X 1 GPM WERE LOCATED IN CONTAINMENT. VALVES WERE BACK SEATED AND LEAKALE RXDUCED WITHIN ACCEPT *BLE LIMITS. 1-RC-77 AND 1-RC-1022WEPE LEAKihG DOE TO PACKING FAILURL AND WILL BE REPACKED DU9ING NEXT COL0.lb41[CEL -

ELLCI6O-MuTIVE DIV. 05000335 092677 ULR1aG A sb a , ItSI LUNDUCTLD WHILL IN MUDL 5. lA UlLSLL LEN. WAS SIAxitENGINES. INTERNAL COMBUSTION 77-042/03t 051578 3 & SUCCCSSFULLY LOADED TO CARRY FULL EMtRGENCY LOAD. AN ATTEMPT WAS TH

SUBCOMPONENT NOT APPLICACLE 019511 30-DAY EN MADE TO LOAD IT TD FULL DESIGN LOAD. DURING THIS EVOLUTION. SM0KE SECOMPONENT FAILURE A/E CAN ISSUING FP.0F 1A2 12-CYLINDER DIESEL TURB0 CHARGER. DIESEL WAS IMMED

CAUSE SUBCODE NOT PROVICED COMB IATELY STOPPES. PEDUNDANT DIESEL GEN. IB REMAINED OPERABLE. (77-42)ST. LUCIE-1 ECASCOEMERG GENERATOR SYS + CONTROLS

ROUTINE TEST / INSPECTION THE 1A DIESEL GEN. BECAME INOPERABLE DUE TO A FAILED TURBO CHARGER UNIT.CAMAGED TURB0 CHARGER UNIT HAS BEEN ANALYZED BY THE VENDOR & THE LICENS

EE TO DETERMINE THE EXACT CAUSE OF FAILURE.

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COPPCNENT MA'UFACTLFEF DOCLET N0.CCFPONENT/ COT CNEh' SUflGE< LER NO.CAUSE COLE /CAUSE 'LU DDL CONTFOL NO. EVENT CATE

T ACILIT Y /5Y ST EM SUFFLIER REPCRT LATE EVENT DESCRIPTICN

v[Tum rf DIsinvfFY Nsss / A/r PFPOPT TYPf CAUSI DE5IFIPITCN

ELECTRO-MOTIVE DIV. 05300237 C52276 nHILE U-2 WAS LOCKED IN REFLEL DURING AN OUTAGE, A TEST WAS FERFORMED ON

MiCHANICAL FUNCTION UNITS 78-033/03L-0 Ot2178 U-2 D-G TO MEx5URE IT5 OVER5h00T AND OVER5 FLED SETFOINT. THE CIESEL TRSLCCOFPCSENT NCT APFLICAGLE 021538 30-CAY If fE0 FOUR TIMES DURING ST ARTUP DUE TO OVERSFEED. UNIT WAS NOT AT PCWER

CGWe'.ENT F AILLFE A/E EVENT FA5 LITTLE SAFETY SIGNIFICANCE. SIMIL AR EVENTS FAD OCCURPED ON

OTFER GE U2/3 D/G LER 77-024, 77-C25 AND 78-021).LFESPEN-2 5+L

ErfRS CENERATCR SYS + CONTROLSSPECI AL TLST/Ih5FECTION GOV. SFLEC VAS FOUND SET 100 HIGH. TU9THER TEST REVEALED OVEPSPEED TRIF

WCULD OCCUP DLE TO CVERSHOOT IF SFFED WA5 SE T ALOVE E.3 FZ. THE DIESEL

SL'Fv. FROC. CALLS FOR A SETTING CF fl HZ AT END OF TEST. PEAEGN FOR HIGF StTTI M S COUt0 NOT BE FOUND.

ELECT RO-NOT IVE DIV. 050C0010. 050778 T 22A5 FR, ThE TEPPCPAPY DIESEL GENERATC FAILEL TO STAPT DURING AN ATT

FUNPS 7E-02C/03L-C OEC27E 't TO LLLAR A LCL TEF ALALE IN InVESTIGATICA PLVE ALID TFAT Thi CIKi

FUTARY 021517 3C-EAY ;LATINu L LI E OIL FUFP WS N1T PROVIDING EUf flCIE'.T HE AD TO CLEAR TFL ST A

CCMfDNENT FAILUPE CTHER RT-LP 1;if0LCCE An' T ST Thi ASSCCI ATED LCW F PE55 uke ALARM F AILEC. TRAN

"ECHANICAL GE SFCRMER 13, IFE EQUliAllNT Cff5ITE f0WER 50LFCE. WAS AVAllAELE DURING TH

U ESCEN-1 EECH 15 FEPIOD

EFERG GENEFATOR SYS + CCNTROLS IFE CIRCL'L ATING LUEE CIL PLMP COLPLING LAS DAMAGED, TsESULTING IN PUFP INSIECIAL TEST /IN5FECTION

FE F ACIL ITY. PPE55cFE SEh50k HAD FFEVIOU5LY LNCETECTED WIRING ERROR. L'ISTINS WHITE STEEL COUPLING ' FEFLACED WITH STAINLESS STEEL COLPLING.>

WIPISS ERh0R WAS CCLFECTED AND TESTEL. ELPAiR5 MA;f WITHIN 24 HOUR 5.

EXIEE IND'tTRI AL DIV CE000321 Of C478 WITH TFE FE KTCP. IN CCLD SHUTCCe,1 WHILE INSFLCTING THE STATION SERVILE E

FATTEPIES + CHAFGERS 78-04C/ CIT-0 C61278 ATTEPY CtAPSEFS (EXICE F0 Z L LPC L30-3-40C) A hlAT-SENSITIVE TRANSISTCR2-WEEK 4:6 FOLY ON T"E EATTEFY Cl1FGEP5 FIPING MALL CARD. THIS FF0btEF WASSL'LCUFFONE Ni NCT AFF LICALLE 021475| 3RIGI' ?LLY FOLND AND hEPCRTED f f CM FLANI FATCh UNIT II UELP 50.55E. THGTFERCESIGN/FAERICATICN EFPCR

EESIGS GE I ' STAT IGN SE FVICE LATTE RIES WELE AVAIL ACLE A'.D OFEF AELE IF TFE CHAPGEP5

ECWIN I. PAICH-1 SSC/ELCH WERE TC FAIL.

PC ONSITE PCWER SYS + CONTROL 5EXTERNAL SCLLCE THE CAL 5L GF THE FRCELEM WA5 A HEAT-SENSITIVE TRAN51STCR (ETCO TYFE 2N14

79) FPDF Tht FJNUFACTLFEP 04 EXiCE f 0bT EM3f R 101070212 FIRINS MODULE CAPD, IN fxIDE EATi!Ft CHAF CEPS MCCEL 13C-3-400. THE TRAN5I5TGR5 IN ALL C,ESEPS WEFE FEFLACEO WITH A *. .-eEAT-SENSIT!VE TFAh5ISTCR, PCA TYPE 2N1

479. CHALGERS WEFE FUNCTIBALLY TESTED AT 400 AMPS.

138


CCFPONENT MANUFACTURER DOCKET NO.CCMPONENT/COMPCNENT SUECCCE LER NO.CAUSE CODE /CAUSF SLTCCLE CONTRUL NO. EVENT DATEFACILITY / SYSTEM SUPPLIER REPORT DATE EVENT DESCRIPTIONprTHnp 0F nier0VFRY Ns% / A/F REPr,RT TYPF CAny rFsrRTPTION

EXIDE INDUSTRIAL DIV CSCC'0316 C61578 CURING SURVEILLANCE TEST ON A6 PLANT BATTERY, CELL #3 5 WAS FOUND TO HAVEEATTERIES + CHARGERS 78-039/03L-0 063078 A SPECIFIC GRAVITY CF 1.197 WHICH IS BELOW THE 1.200 MINIMUM SPECIFIC GSLECOMPONENT NOT APPLICAELE 021632 30-DAY RAVITY ALLOWED PER T.S.4.8.2.3.2A.2, WHICH CONSTITUTED AN INOFERABLE BATCOMPCNEN' FAILURE A/E TERY. CD BATTERY WAS OPERABLE. DC LOADS WERE SHIFTED TO CD BATTERY FCRELECTRICAL WEST A PERIOD OF 13 MINUTES WHILE CELL #35 WAS JLMPERED. AB BATTERY WAS RETD. C. C00K-2 AEP JRNED TO SERVICE AFTER BEING INOPERABLE FOR 29 MINUTES. REFERENCE SIMilCC ONSITE POWER SYS + CONTROLS AR LER NO. 78-038/03L-0.POUTINE TEST / INSPECTION THE EXACT CAUSE CF THE LOW SPECIFIC GRAVITY COULD NOT BE DETERMINED, A

PROCECURE IS EEING DEVELOPED TO ATTEMPT TO PESTORE THE CELL. ALSO, A REPLACEMENT CELL HAS BEEN ORCERED IN CASE RESTORATION IS NOT PCSSIblE. REGINING CELLS IN AB EATTERY SHOW NO SIMILAR PRCBLEMS.

EXIDE INDUSTRIAL DIV C5000316 OC0778 OURING SURVEILLANCE TEST CN CD PLANT 6ATTERY, CELL #89 WAS FOUND 10 HAVEEATTERIES + CHARGERS 78-038/03L-0 063078 A SPECIFIC GRAVITY OF I.195 WHICH IS BELOW THE I.200 MINIMUM SPECIFIC G

SUECOMPONENT NOT APPLICABLE 021633 30-DAY RAVITY ALLOWED PER T.S.4.8.2.3.2A, 2. WHICH CONSTITUTED AN INOPERABLE BACOMPONENT FAILLRE A/E TIERY. AB BATTERY WAS OPERABLE. CC LOADS WERE SHIFTED TO AB EATTERY FORELECTRICAL HEST A PERICL OF 16 MINUTES WHILE CELL #89 WAS JUMPERED. CD EATTERY WAS RETD. C. CC0K-2 AEP URNED TO SERVICE AFTER BEING INOPERABLE FOR 80 MINUTES.CC ONSITE POWER SYS + CONTROLSFOUTINE TEST / INSPECTION THE EXACT CAUSE CF THE LOW SPECIFIC GRAVITY COULD NOT BE DETERMINED. A

PROCEDURE IS BEING DEVELOPED TO ATTEVPT TO RESTORE THE CELL. ALSO, A REFLACEMENT CELL HAS EEEN ORCERED IN CASE RESTORATION IS NOT POSSIBLE. REYAINING CELLS IN CD BATTERY SHOW NO SIMILAR PROBLEMS.

EXIDE INDUSTRIAL DIV 050003C2| 080278 JNIT 3 WAS NOTIFIED THAT UNIT 1 EATTERY FAILED TO MEET THF CRITERIA CF TBATTERIES + CHAPGE FS 73-028/03L-0 081478 HE WEEKLY BATTE9Y CHECK, SP-SIO, CCNTRARY TO T.S. 3.8.I.2. B DIESEL GEN

SUECCMPONENT NOT APPLICAELE 02:042 30-CAY ERATCR WAS CFERdiLE. NO SAFETY HAZARD TO PLANT OR GENERAL PUBLIC AS NOCOMPONENT FAILLi<E N/A CORE ALTERATIONS OR PEACTIVITY CHANGES WERE IN PROGRESS. SIXTH OCCURREN

ELECTR: CAL B+W CE CF THIS TYPE EVENT.CRYSTAL RIVER-3 GILGFFSITE PCWER SYSTEMS + CC'NTRLFOUTINE TEST / INSPECTION STRATIFICATION CF ELECTROLYTE WHILE EATTERIES ARE UNDER NO LCAD CONDITIO

i. REQUEST FOR ENGINEERING INFORMATION IS UNDER EVALUATICN AND CORRECTIVE ACTIONS WILL BE CASED UPON ENGINEERING RECOMMENDATICNS.

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LICENSEE EVENT REPORTS @,

COMPONENT MANUFACTURER DOCKET NO.

COMPONENT / COMPONENT SUSCODE LER NO.CAUSE CODE /CAUSE SUBCODE CONTROL NO. EVENT DATE

FACILITY / SYSTEM SUPPL 1ER REPORT DATE EVENT DESCRIPTION

MFTN01 0F DISCOVERY NSSS / A/E REPODT TYPE CAUSE DESCRIPTION

EXIDE INDUSTRIAL DIV 05000317 050378 DURING SURVEILLANCE TESTING MAINTENANCE PERSONNEL DETERMINED AT 0830 THA

BATTERIES + CHARGERS 78-024/03L-0 060278 T 125 VDC BATTERY 22 CELL 54 ICV WAS BELOW THE MINIMUM VOLTAGE (2.10V) S

SUBCOMPONENT h0T APPLICABLE 021533 30-DAY PECIFIED BY T.S.4.8.2.3.2.B. THE CELL WAS IMMEDIATELY CHARGED, INCREASI

COMPONENT FAllCRE A/E NG ITS ICV TO 2.16V AT 1320. BATTERY 22 OVERALL VOLTAGE REMAINED ABOVEOTHER CCMB 125 VDC THROUGHOUT THIS EVENT. THIS IS NOT A REPETITIVE EVENT. UNIT 2

CALVERT CLIFFS-1 BECH WAS OPERATING AT 657 POWER THROUGHOUT THIS EVENT.

DNSITE POWEd SYSTEM + CONTROLROUTINE TEST /INEPECTION THE CAUSE OF THE CELL FAILURE IS UNKNOWN. SURVEILLANCE OF THIS PARTICUL

AR CELL (EXIDE FHC-19) WAS INCREASED TO DETERMINE ANY Tk:ND. ON 5/10/78 WITH THE CELL VOLTAGE AT 2.14V AND CONTINUING TO DROP, THE CELL WAS REPLACED.

EXIDE !NDUSTRIAL DIV 05000333 051878 DURING NORMAL OPERATIONS THE LPCI INVERTER / CHARGER TRIPPED RESULTING IN

GENERATORS 78-040/03L-0 061278 LOSS OF "B" LPCI INDEPENDENT POWER. PERFORMED SURVEILLANCE TEST ON "A"

INVERTER 021402 30-DAY LPCI INDEPENDENT POWER SUPPLY BATTERIES, CHARGERS AND INVERTERS IN ACCOR

COMPONENT FAILURE NSSS DANCE WITH TECHNICAL SPECIFICATION 3.9.F REQUIREMENTS.

ELECTRICAL GE

FITZPATRICK-1 S+W

ONSITE PCWER SYSTEM + CONTROLFAILED SCR'S IN THE INVERTER / CHARGER RESULTED IN THE TRIP. THE INVERTEROPERATIONAL EVENT/ CHARGER WAS ISOLATED AND THE LPCI BUS WAS SUPPLIED WITH POWER FROM THEMAINTENANCE BUS. THE FAILED SCR'S WERE REPLACED AND THE INVERTER / CHARGER RETURNED TO SERVICE.

EXIDE INDUSTRIAL DIV 05000271 053078 DURING NORMAL OPERATION A LOSS OF VOLTAGE TO MOTOR CONTROL CENTER (MCC)

GENERATORS 78-012/03L-0 062878 89B OCCURRED. THIS MCC POWERS THE *B" LPCI INJECTION VALVES AND THE *B"

INVERTER 021542 30-CAY RECIRCULATION TST.M DISCHARGE AND DISCHARGE BYPASS VALVES. ALTERNATE

COMPDNENT FAILURE LIC TESTING WAS PERFORMED DURING MAINTENANCE PER T.S. REQUIREMENTS. REDUNDA

ELECTRICAL GE NCY WAS AVAILAELE.

VERMONT YANKEE-1 EBASCO

CNSITE POWER SYSTEM + CCNTRCL AN EXIDE POWER SYSTEM, 250 KVA UNINTERRUPTIBLE POWER SUPPLY, HAD TRIPPEDOPERATIONAL EVENT

BECAUSE CF A BLOWN INVERTER LEG FUSE (2A18F2). TROUBLESHD0 TING OF THEUNIT CID NOT RESULT IN DETERMINING THE CAUSE OF THE FUSE FAILURE. THE REMEDI AL ACTION TAKEN WAS TO REFLACE THE IN0PERABLE COMPONENT AND TEST THE UNIT.

140

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COMPONENT MANUFACTURER COCKET NO.COMP 0hENT/ COMPONENT SLECODE LER NO.CAUSE CODE /CAUSE SUBCODE CCNTROL NO. EtENT CATEFACILITY / SYSTEM SUPPLIER PEFORT CATE EVENT DESCRIPTIONMFTHOD OF DISCOVERY NSSS / A/F OFrrci TYPF rMKE DESCDIPTION

EXIDE INDUSTRIAL DIV 05C00271 CE2978 :LRING CFERATICN, VCLTAGE WAS LOST TO MOTOR CCNTROL CENTER 898 WHICH POWGENERATORS 78-019/03L-0 072578 ERS THE 'E' LFCI INJECTICN VALVES AND THE 'B' RECIRC DISCFARGE AND SYPASINVERTER C21842 30-CAY S VALVES. 'B' L'i!NTERFLPTICLE FCLER SUPPLY PAD TRIFFED, AN ALTERNATE PCOMPONENT FAILUFE LIC

AER FEECER WAS ENERGIZED TO MCCS98. TFE REDUNDANT A UPS SYSTEM WAS ASAELECTRICAL GEILAELE WITH CTFER REOL*. DANT SAFEGUARDS SYSTEMS.VERMONT YANKEE-1 EEASCO

ONSITE POWER SYSTEM + CONTROLCPERATIONAL EVENT ar. EXICE FCWER SYSTEM, 250 KVA UPS, TRIPPED CLE TO AN INVENTGR LEG FUSE

(2A19F2) ELCWING WHEN THE 2A13A4 GATE INTERFACE LOGIC MODULE AND THE 2A13A15 AC FFOTECTION LOGIC MCDULE MALFLNCTICNED. FEPLACED FAILED CCMFONENTS IN KIND AND U*.IT TESTEC SATISFACTCRILY.

EXIDE INDUSTRIAL DIV OECC0366 071778:LRING RX. STARTLP THE CUTFUT BPEAFER FOR STATIC INVERTER (2R44-5002) TRGENERATORS 78-004/03L-C 073178 IFFEC CALSIN3 MCMENTA9Y LCSS OF PCLER TO INJECTION, RHR MIN FLOW. LOOP AINVERTER 022024 30-CAY FECIRC DISCH, AND LOOP A FECIRC SUCTION VALVES (T.S. 3.8.2.1.) TrE CPECOMPONENT FAILURE A/E2 ATOP ATTEMFTEC TO RE-ENEFGIZE ThE INVERTER EUT FAILED TO FFE-CFAPGE THEELECTRONIC GE INVERTER CAPACITCFS.

EDWIN 1. HATCH-2 SSC/EECHONSITE POWER SYSTEM + CCNTROLOPERATICNAL EVENT

IFE INVEM ER QUTPUT BPE ALER TRIFFED CLE TO A FAILUPE CF A FREGLENCY CARD(EC CE PART NO. A13A9). TFE CPERATCR'S FAILLPE TO PPE-CFAPGE TFE CAPAC

ITCRS PEStiiED IN ELCWING FOLR CAFACITCR FUSES. TFE CCMPARTMENTS AND EREAEEFS O'. THE INVERTER LEFE NOT CLEARLY MAFKED. TFE FFEGLENCY CARD WASrriarrn

FAIkeANKS MURSE OL000320 CH076 ;LRING FLH MANLL LF iUMllLLAM.L F NLLLLht 23uj-Mit 'tFtu btNLV UltitLMECHANICAL FUNCTION LNITS 78-039/03L-0 C61578 GENERATCR AND CCCLING LATER \AltE CPERAEILITY TEST", THE "B" CIESEL GENSUBCOMPONENT NOT APPLICAELE 021607 30-CAY

ERATOR FAILED TO START. SINCE TFE FECLNCANT EMEFGENCY CIESEL GET.ERATLRCOMPONENT FAILURE A/E WAS CPEPAELE, TblS CIC NOT HAKE AN ACsERSE EFFECT ON TFE FEALTH AND SAFEME CH ANICAL B+W TY OF TFE PLELIC.

THFEE MILE ISLAND-2 E+REMERG GENERATOR SYS + CONTRCLSROUTINE TEST /INSFECTION

.ERTICAL SFAFT EETWEEN LPFER AND LOWER CRA'.K SPAfiS FAILED DLE TO IMPPCPER MATERI AL. A CCo*FLETE CCLFLI'.G CF FPCFER MATERI AL LAS INSTALLED A' D CF-X-IE PETLRNEC CFEFAELE WITFIN REQUIRED TIVE. CF-x-1A ALSO INSFECTED.UCPEP MATEFIAL LSED IN ITS CCLPLING.

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COMPONENT MANUFACTURER DOCKET N0.



METHOD OF DISCOVFRY NSSS / A/F REPORT TYPE CAUSE DFSrpIPTION

FAIRBANKS MORSE 05000320 052378 WHILE VERIFYING OPERABILITY OF EMERGENCY DIESEL GENERATOR "DF-X-1B" FOLLPIPES, FITTINGS 78-041/03L-0 061578 OWING REPLACEMENT OF VERTICAL SHAFT COUPLING AS IDENTIFIED IN LER 78-39/

LESS THAN 4 INCHES 021605 30-DAY THE DIESEL TRIPPED ON HIGH CRANKCASE PRESSURE. SINCE THE REDUNDANT Dm.

DESIGN /FABRICsTION ERROR A/E IESEL GENERATOR, DF-X-1A WAS OPERABLE. THERE WAS NO EFFECT ON THE HEALT

hANUFACTURING B+W H AND SAFETY OF THE PUBLIC.

THREE MILE ISLAND-2 B+R

EMERG GENERATOR SYS + CONTROLSPARTIALLY PLUGGED ORIFICE PLATE TO CRANKCASE VACUUM EJECTOR RESULTING INROUTINE TEST /INSPE'. TION

REDUCED CRANKCASE VACUUM WHICH HAD BEEN NOTED ON THE DIESEL PRIOR TO TRIP. RESTRICTION REMOVED AND OF-X-1B RERUN TO VERIFY NORMAL CRANKCASE VACUUM AT FULL LOAD AND AT SYNCHRONOUS SPEED. PERIODIC CHECKS WILL BE PER

FORMEO.

FAlkflLLD LNG. LL. 05000267 051076 JURING kuuilNL $UkhtlLLANLL UF THE SILAM FIFL buPILkt UtlLL110N SYSILM,

INSTRUMENTATION + CONTROLS 78-017/03L-0 052678 ONE OF THE THREE BISTABLES FOR ULTRASONIC NOISE GUTSIDE THE PCRV DID NOT

OTHER 021417 30-CAY TRIP, REPORTABLE PER TECHNICAL SPECIFICATION AC 7.5.2(B)2 OPERATION UND

COMPONENT FAILURE NSSS ER A DEGRADED MODE PERMITTED BY LCO 4.4.1. NO ACCOMPANYING OCCURRENCE.

OTHER GGA NO EFFECT ON PUBLIC HEALTH OR SAFETY. REDUNDANT SYSTEM AVAILABLE AND OP

FT. ST. VRAIN-1 S+L ERABLE.

ENGNRD SAFETY FEATR INSTR SYSRCUTINE TEST / INSPECTION 31 STABLE DID NOT TRIP DUE T9 A FAILURE OF AN OFERAT10NAL AMPLIFIER. OPE

RATIONAL AMPLIFIER REPLACED AND SURVEILLANCE TEST SUCCESSFULLY COMPLETED

_

FISCHER & PCRTER CO. 05000335 061578 DURING POWER OPERATION, THE DIGITAL DATA PROCESSINS SYSTEM (DDPS) MALFUN

INSTRUMENTATION + CONTROLS 78-022/03L-0 071378 :TIONED. THIS RESULTED IN LOSS OF CEA BACKUP POSITION INDICATION AND THCOMPUTATICN MODULE 021834 30-CAY E INCORE FLUX DETECTOR SYSTEM USED TO MONITOR FLUX DISTRIBUTION. ACTION

COMPONENT FAILURE NSSS REQUIRED BY SPECIFICATIONS 3.1.3.3 AND 4.2.1.3 WAS INITI ATED AND POWERELECTRONIC COMB 4AS REDUCED. THE DCPS WAS REPAIRED AND PLACED BACK INTO SERVICE IN TWO

ST. LUCIE-1 EBASCO HOURS. THIS WAS THE FIRST OCCURRENCE INVOLVING LOSS OF THE DCPS DUE TOOTbR INST SYS REQD FOR SAFETY THE CAUSE DESCRIBED BELOW IN THE CAUSE DESCRIPTION.

THE CAUSE OF THE DDPS FAILURE WAS A MALFUNCTIONING FULTIPLEXER CARD. THOPERATIONAL EVENTE CARD WAS REPLACED AND THE DDPS RETURNED TO SERVICE IN TWO HOURS.

142


..

CCMFCNE*.T SAN'.FACTLF ER CCCrEi NO.-

COPFCNENT/CCvFONENT SLECOCE LER NO.r4LSE CCCE/ CAL 5E SLBCOCE CCSTPCL NO. E'.ENT CATEFACILITf/ SYSTEM SUFFLIEP EEFCRT CATE EVENT CESCPIPTIONPETFCD CF CISCC\ E EY NSSS / A/E ;EPCOT TWE CAL'SF CFSCRIPTICN

FISCrER & FCRTER CO. CECOC272: CE2378 CURING TRAN5"ITTER CALIERATICN CHECV, NO 11 STEAM GENERATC; FLCW CHAZELINSTRLPENTATION + CC'.TRCLS 78-033/C3L-0 C71278 II WAS FCLND TO EE CUT-CF-SFEC LCW. Act REPAINING CFANNELS WERE CPERAB

EENSCR/CETECTOR/ ELEMENT C21912 30-CAY LE. THIS IS THE THIRD CCCLRRENCE CF 'HIS TYPE.COMPCNENT FAILUPE LIC

OTFEP WESTSALEV-1 0FE*CTOR TRIP SYSTEM 5FCUTINE TEST /I*.SFECTICN TFE CALSE CF THIS CCCURRENCE WAS INSTPLMENT CRIFT IN TPE NCN-CCNSEPVATIV

: CIRECTIC%. TRANSMITTER WAS FECALIERATED TO WITHIN T.S. VALUE.

78-C70/03L-)0FISCFER & FCRTEF CC. CSCC0295 071778 WFILE CPERAi!NG WITF TFE BISTAELE TO STEAM GENERATCR ID LEVEL CFA'.NEL 53

INSikLMENTATICN + CCNTRCLS CEIE7E E TRIFFEC CUE TO A FIGW INCICATED LEVEL AND CHANNEL 537 EEGAN TO INCICATTRANSPITTER C21967 30-CAY E A HIGFER LEkEL TFAN CHANNEL 539. TECH SPEC TABLE 3.1-1 FECUIF<ES A PIN

CCPPC*.E*T FAILUPE NSSS IvuM CF 2 CFEFAELE STEAM GENERATCR LEVEL CHANNELS. UNIT TAkEN TO FOT SHINSTELMENT WEST ;TCOW'. MTHIS A FCURS FER T.S. FEOUIFEM ENTS,

ZICN-1 5+LREACTCR TPIF SYSTEMSOFERATICNAL EiENT :FANNEL 538 INCICATED HIGH CLE TO FAILED TRANSMITTER. FISCFER-FCRTER MCD

EL 13D 2A9Ex ESAEEE-NS. TRANSMITTER WAS REPLACEC. CHANNEL 537 INCICATEC FIGH CUE TO A FACKING LEAK FRCM A ROOT VALkE TO TRANSMITTER. POCT VALVE WAS SEALED WITH FLFPANITE. FOGT iAliES WILL EE REFLACED.

FIELE;. CCNTFCLS CC. CEC 00345 071676 CECAY FEAT COOLER 1-2 CUTLET VAliE CH 14A INCPERAELE AND WCULC NOT CPEN.V AL '. : CPERATCR5 7E-079/C3L-C CS117E FEACTOR COOLANT 56 TEM TEPPERATLRE ON OECAY EEAT LCCP 2 COULD NCT PRCPELECTRIC MOTCR - CC C21957 30-CAY ERLY EE CCNTROLLEC. CH LCOP 2 lEMCVED FROM SERVICE AND Ch LCCP 1 PLACECCivFC.ENT FAILL;E '.555 IN SERVICE. w MNGER TO HE AL'M AND SAFETY CF FLELIC OR UNIT FERSCNNEL"EC"ANICAL E4 LNIT IN MCCE 5.

CeV!S-EESSE-1 EECFFEEIDtAL MEAT FEPCV SYS + CC'.TCFERATICNAL E',E'.T

CTLATCR ARM EAD MOVED WITF RESFECT TO SHAFT. SUSFECTED SET SCREW LOCSE'.EC CLE TO VIEPATION CR FAULTY INSTALLATICN. INSTRUMENT AND CCNTROL TECN!CI AN5 SFIFTED ACTUATOR ArtM TO CCRRECT POSITION AND TICFTENEC SET SCEE

4. VALkE TESTED AND RETLENED CPERAELC.

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[LICENSEE EVENT REPORTS


COMPONEN1/ COMPONENT SUBCODE LER NO.CAUSE CODE /CAUSE SUECODE CONTROL NO. EVENT DATE


PETH00 0F DISCOVEPY NSSS / A/E PEPORT TYPE CAUSE DESCPIPTION

FISHER CONTROLS CO. 05000346 051178 AT 1700 ON 5/11, CONTAINMENT VACUUM RELIEF VALVE CV 5076 HAD EXCESSIVE L

VALVES 78-051/03L-0 C60578 EAKAGE DURING PERFORMANCE OF LOCAL LEAK RATE TEST. NO CANGER TO HEALTH

BUTTERFLY 021578 30-CAY AND SAFETY OF PUBLIC OR UNIT PERSONNEL. UNIT WAS IN SHUTDOWN CONDITION.

DESIGN / FABRICATION ERROR A/E OVERALL ALLOWABLE LEAKAGE FOR CONTAINVENT NOT EXCEEDED. NO COPE ALTERAT

CONSTRUCTION / INSTALLATION B+W ION OR MOVEMENT OF IRRADIATED FUEL WITHIN CONTAINMENT TOOK PLACE WHILE TDAVIS-BESSE-1 BECH HE VALVE WAS IN0PERABLE.

REACT 0' CONTAINMENT SYSTEMSROUTINE TEST / INSPECTION THE VALVE NOT PROPERLY SEAi JG AGAINST VALVE LINER. VALVE PEMOVED FROM

SERVICE AND LINE BLANKED CF.' TO MAINTAIN CONTAINMENT INTEGRITY BY 1830 0N 5/12/78. PRESENTLY REPAIRING VALVE.

FISHER CONTROLS CO. 05000346 050978 AT 1330 ON 5/9/78, CONTAINMENT VACUUM RELIEF VALVF "V 5070 HAD EXCESSIVE

VALVES 78-050/03L-0 060578 LEAKAGE DURING PERFORMANCE OF LOCAL LEAK RATE TEdf. ALSO, ONE VALVE FL

BUTTERFLY 021579 30-CAY ANGE BOLT FOUND LOOSE. NO DANGER TO HEALTH AND SAFETY OF PUBLIC OR UNIT

DESIGN / FABRICATION ERROR A/E PERSONNEL SINCE UNIT WAS SHUT DOWN. OVERALL ALLOWACLE LEAKAGE FOR CONT

CONSTPUCTION/ INSTALLATION d+W AINMENT NOT EXCEEDED. NO CORE ALTERATIONS OR MOVEMENT OF IRRADIATED FUEDAVIS-SESSE-1 BECH L WITHIN CONTAINMENT TOOK PLACE WHILE CV 5070 INOPERABLE.REACTOR CONTAINMENT SYSTEMSROUTINE TEST / INSPECTION CEFECTIVE INITIAL INSTALLATION OF TEST CONNECTION PIPING. WELD HAD BEE

N GROUND DOWN TD0 FAR AND PATCH WELD WAS DEFECTIYE. REMOVED TEST CONNECTION PIPING, INSTALLED NEW ELBOW AND REPLACFC IEST CONNECTION PIPING. VALVE CV 5070 RETESTED. RESULTS ACCEPTACLE AND DECLARED OPERABLE AT 1000ON 5/11/78.

F0xbONO CO., THE 05000266 051278 li WAS FOUND THAT THE OUTFUT OF A SFECI AL SUMMER (1-TM-404v) IN vhE OF FINSTRUMENTATIDN + CONTRDLS 78-009/03L-0 060578 OUR OVERPOWER DELTA T (DELTA T SP2) CHANNELS IN THE REACTOR PROTECTION S

COMPUTATION MODULE 021444 30-CAY YSTEM HAD CRIFTED HIGHER THAN PERMITTED BY T.S.15.2.3.1.B(5). DUTPUT H

COMPONENT FAILURE, NSSS AD DRIFTED TO 62.8 CEGREES F (43.5 MA) COMPARED TO T.S. LIMIT OF 60.975ELECTRONIC WEST DEGREES F (42.52 MA).

POINT BEACH-1 BECH

ENGNRD SAFETY FEATR INSTR SYSOPERATIONAL EVENT

THE AFFECTED POWER DELTA T CHANNEL WAS PLACED IN TPIPPED CONDITION, SUMM

ER WAS REPLACED AND CHANNEL RETURNED TO SERVICE. THE FOXBORO 66RC-OL SPECIAL SUMMER, WHICH DRIFTED HIGH BECAUSE OF A CEFECTIVE ZERO POTENTIOMETER, WAS REPAIRED.

144

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COMPONENT MANUFAL!URER DOCKET NO.COMPONENT / COMPONENT SUBCODE LER NO.CAUSE CODE /CAUSE SUBCODE CONTROL NO. EVENT STEFACILITY / SYSTEM SUPPLIER REPORT DATE EVENT DESCRIPTIONMETHOD OF DISCOVERY NSSS / A/F PFPORT TYPE CAUSE DESCRIPTION

FOXBORO CO., THE 05000346 060278 ON 6/2/78 AT 1910 CHANNEL 2 BORATED WATER STORAGE TANK LEVEL INDICATIONINSTRUMENTATION + CONTROLS 78-059/03L-0 062378 DN SAFETY FEATURES ACTUATION SYSTEM CHANNEL 2 FAILED HIGH. AT 1930 SFASTRANSMITTER 021571 30-DAY CHANNEL 2 WAS PLACED IN TRIPPED CONDITION. T.S.3.3.2.1 PEQUIRES BWST L

COMPONENT FAILURE A/E EVEL INDICATION IN MODES 1,2 AND 3 ONLY. NO DANGER TO HEALTH AND SAFETYINSTRUMENT B+W OF PUB'.IC OR U41T PERSONNEL. THREE OTHER BWST LEVEL INDICATORS WERE OP

CAVIS-BESSE-1 BECH ERACLE. THE UNIT WAS IN MODE 6.ENGNRD SAFETY FEATR INSTR SYSOPERATIONAL EVENT COMPONENT FAILURE OF AMPLIFIER ASStMBLY AND LEVER ASSEMBLY OF LEVEL TRAN

SMITTER. EFFECTIVE PARTS REPLACED, TRANSMITTER CALIBRATED AND STRING CHECK PERFORMED. AFTER TWO SURVEILLANCE TESTS, BWST LEVEL INPUTS TO SFASCHANNEL CALIBRATION AND SFAS MONTHLY BWST LEVEL INDICATION FOR SFAS CHANNFL 2 DECLARED OPERABLE AT 1550 ON 6/4/7R.

F0xBORO CO., THE 05000286 060278 OURING NORMAL UPERAll0N, PLhf 0RMANCL OF PLR10DIC IL5I 3PI-M1 RLVLALLD THINSTRUMENTATION + CONTROLS 78-012/03L-0 070278 AT THE STATIC GAIN UNIT OF THE F(DQ) NO. 41, NIS POWER RANGE CHANNEL WAS

POWER SUPPLY 021652 30-DAY LESS CONSERVATIVE THAN THE VALUE REQUIRED BY THE TECH SPECS. SIMILAR EVCOMPONENT FAILURE NSSS ENTS WERE REPORTED IN R.0.76-3-42(B), R.O.-76-3-46(B) AND R.0.-77-3-16(

INSTRUMENT WEST 3)INDIAN POINT-3 UECREACTOR TRIP "YSTEMSROUTINE TES ~1SPECTION FOXBORO STATIC GAIN UNIT, MODEL DQ, WAS FOUND TO NEED ADJUSTMENT. UNIT

WAS ADJUSTED WITHIN THE TECH SPEC LIMITS.

FOXBORO CO., THE 05000316 07127c DURING NORMAL OPERATION, THE REFUELING WATER STORAGE TANK (RWST) LEVEL IINSTRUMENTATION + CONTROLS 78-047/03L-0 071878 NOICATION FAILED LOW. THIS INDICATION IS REQUIRED BY T.S. 3.3.3.6. THEOTHER 021793 30-DAY APPLICABLE AC:!ON REQUIREMENTS WERE FULFILLED.

COMP 0N:NT FAILURE A/EELECTRONIC WEST

D. C. C00K-2 AEPSAFETY RELATED DISPLAY INSTROPERATIONAL EVENT INVESTIGATION REVEALED THAT A BAD RESISTOR IN THE CURRENT REPEATER WAS T

HE CAUSE OF THE FAILURE. THIS RESULTED ONLY IN A LOSS OF THE RWST LOW LEVEL ALARMS WITHOUT AFFECTING THE AUTOMATIC FEATURES ASSOCIATED WITH THE

RHR PUMPS.

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LICENSEE EVENT REPORTS GJ

COMPONENT MANUFACTURER DOCKET NO.COMPONENT /COMFONENT SUBCODE LER NO.CAUSE CCDE/CAUSE SUut0CE CONTROL NO. EVENT DATEFACILITY / SYSTEM SUPPLIER REPORT DATE EVENT DESCRIPTIONMETh0D OF DISCOVERY NSSS / A/E REPORT TYPE CAUSE DESCRIPTION

GAMMA PROCESS CO., INC. 05000293 070478 AT APPROXIMATELY 1400 HOURS ON JULY 4, 1978 THE MAIN STACK PROCESS RADIPUMPS 78-033/03L-0 073178 ATION MONITOR (MS-PRM) SYSTEM PALFUNCTIONED AS INDICATED BY AN ANNUNCIAT

VANE TYFE 021932 30-DAY OR ALARM ON PANEL 903 IN THE CONTROL ROOM. THE SAMPLE PUMP WAS IMMEDIATCOMPONENT FAILURE NSSS ELY REFLACED. THE MS-PRM WAS RETURNED TO SERVICE WITHIN ONE HOUR, THERE

MECHANICAL GE FORE, INITIATION CF A PLANT SHUTDOWN AS INDICATED BY TECHNICAL SPECIFICAPILGRIM-1 EECH TION 3.8.B.5. WAS NOT REQUIRED.PRCSS + EFF F1DIC1 "0NITCR SYSOFERATIONAL EVENT TPE CAUSE OF ihl3 E'4ENT WAS DETERIORATION CF THE RUEEER SPIDER COUPLING

ON THE INSERVICE UNIT. THE STANDBY PUMP WAS FLACED IN SERVICE. THE DEFECTIVE COLPLINL REPAIRED AND THE REPAIRED UNIT RETURNED TO STANDBY SERVICE.

1AST MANUFACTURING CORPORATION C'.00CO29 053178 DURING STEADY STATE CPERATION, A MECHANICAL FAILURE ALARM FOR THE VAPORPLMPS 78-014/03L-0 C63078 CONTAINEP AIR PARTICULATE MCNITOR OCCURRED. MONITOR WAS INOPERABLE; HOW

VANE TYPE C21625 30-CAY EVER, A DIFFERENT MEANS CF MONITORING MAIN COOLANT LEAKAGE WAS AVAILABLECOMPCNENT FAILURE LIC SIMILAR FAILURES HAVE OCCURRED ON 1/24/75, 1/19/76, 3/9/76, AND 8/5/7

MECHANICAL WEST 6.YANKEE RCWE S+WAIRBORNE RADICACT MONITOR SYSCFERATIONAL EVENT VACUUM PUMP FAILURE DUE TO BROKEN CARBON VANES IN PUMP IMPELLER RESULTIN

G FROM NATURAL END OF LIFE. PUMP MADE BY GAST MFG CORP, MODEL V110. PUMP REPLACED IN KIND WITH A SPARE.

GENERAL ATOMIC CO. CS000267 061378 DURING ROUTINE SURVEILLANCE TESTING OF THE HELIUM CIRCULATOR SPEED TRIPSINSTRUMENTATICN + CONTROLS 78-019/03L-0 071378 , ONE OF THE HIGH SPEED TRIP CHANNELS WOULD NOT TRIP. THIS IS REPORTABL

SWITCH 021942 30-DAY E PER FORT ST. VRAIN TECHNICAL SPECIFICATION AC 7.5.2(B)2. OPERATION UNCOMP 0NENT FAILURE NSSS DER A DEGRADED MODE PERMITTED BY LCO 4.4.1.

INSTRUMENT GGAFT. ST. VRAIN-1 S+LENGNRD SAFETY FEATR INSTR SYSROUTINE TEST /INSFECTION FAILURE OF AN INTEGRATED CIRCUIT. THE INOPERATIVE INSTRUMENT WAS REPLAC

ED WITH A CALIBPATED SPARE AND THE SURVEILLANCE COMPLETED. THE FAULTY !NSTRUMENT WAS REPAIRED.

If46

.

.

LICENSEE EVENT R PORTS

COMPONENT MANUFACTURER DCCKET NO.COMPONENT / COMPONENT SLECODE LER NO.CAUSE CODE /CAUSE SUSCODE CONTFOL NO. EVENT CATEFACILITY / SYSTEM SUPPLIER REPORT DATE EVENT DESCRIPTIONvrThon nr nisroyEpy NSSS / A/F REPORT TYPF r:U(F DESCRIPTION

GENERAL ATOMI CO. 05000285 070378 DURING THE PERFORMANCE CF ST-RPS-3, IT WAS NOTED THAT ThE TRIP AND ACTUAINSTRUMENTATION + CONTROLS 78-020/03L-0 071478 L TRIP SETPOINTS FOR "C" CHANNEL LOW FLOW WERE OUT OF TOLERANCE. THE RECOMPUTATION H0DULE 021800 30-DAY MAINING Tl REE RPS CHANNELS REMAINED GPERABLE THROUGHOUT THIS EVENT. SEE

COMPONENT FAILURE NSSS ALSO LER 74A-4 AND 77-27.ELECTRONIC COMB

FT. CALHOUN-1 GHCRREACTOR TRIP SYSTEMSROUTINE TEST / INSPECTION THE GENERAL ATOMICS MODEL ELD 240-C000-IF BISTABLE TRIP UNIT kAS FOUND TO

HAVE CRIFTED FROM PROPER SETPOINT. THE TRIP UNIT WAS RECALIERATED ANDSATISFACTORILY TESTED AND RETURNED TO SERVICE.

GENERAL ELECTRIC CO. 05000250 070678 CURING LOAD REDUCTION FOR UNIT SHUTDOWN, THE 3C CONDENSATE PUMP MOTOR CICIRCUIT CLOSERS / INTERRUPTERS 78-010/03L-0 CE0478 RCUIT BREAKER WOULO NOT CPEN WhEN THE CONTROL ROOM CONSOLE SWITCH WAS TU

CIRCUIT BREAKER 022C62 30-CAY RNED TO STOP. AN CPERATOR WAS SENT TO THE SWITCHGEAR ROOM WHERE HE MANUCOMPONENT FAILURE A/E ALLY TRIPPED AND PACKED CUT THE BPEAKER. A LOSS OF VOLTAGE WOULD HAVE R

ELECTRICAL WEST EQUIRED MANUALLY CPENING THE BREAKER TO ALLOW THE BUS TO STRIP PRIOR TOTURKEY POINT-3 EECH RE-ENERGIZING THE BUS FROM THE EMERGENCY DIESEL.AC ONSITE POWER SYS + CONTROLSOPERATIONAL EVENT THE TRIP FAILURE OCCURRED EECAUSE THE PIVOT POINT BETWEEN THE TRIP COIL

ARNATURE AND THE TRIP ARM HAD BROKEN OFF THE TRIP ARM. THE TRIP ARM WASREPLACED AND THE BREAKER SUCCESSFULLY TESTED. FIRST REPCRTABLE OCCURRE

NCE CAUSED BY THIS TYPE OF FAILURE. BREAKER IS G.E. 1200 AMP 4160 VOLTWAGNABLAST TYPE BDEAvro

GENERAL ELLCIRIC CO. 05000321 050676 WHILE FtRFORMING INE CORL SPRAY RAILO FLOW SURVLILLANCE IL5T, C0kt SPRAYCIRCUIT CLCSERS/ INTERRUPTERS 78-031/03L-0 060278 PUMP 1A FAILED TO START WITH THE CONTROL SWITCH AS REQUIRED. OPERABILIT

SWITCH (OTHER THAN SENSOR) 021481 30-DAY Y OF THE REDUNDANT CORE SPRAY LOOP, THE LPCI MODE OF RHR, AND THE DIESELCOP.PONENT FAILURE NSSS GENERATORS WAS PROVEN TO COMPLY WITH T.S.3.5.A.2 AND PERMIT CONTINUED S

ELECTRICAL GE AFE OPERATION OF THE REACTOR. THE RHR PUMPS AND ONE CORE SPRAY PUMP PRCEDWIN I. HATCH-1 SSC/BECH VIDED ADEQUATE REDUNDANCY TO ENSURE MAKEUP WATER AVAILABILITY.EMERG CORE COOLING SYS + CONTROUTINE TEST / INSPECTION INVESTIGATION REVEAL.ED THAT THE PUMP'S OVEPCURRENT LOCK 0UT RELAY WAS TRI

PPED AND THAT THE GE SEM CONTROL SWITCH MALFUNCTIONED DUE TO A BROKEN P0SITION STOP. THE SWITCH WAS REPLACED, THE LOCK 0UT RESET AND THE PUMP FUNCTIONALLY TESTED STISFACTORILY. THE PUMP LOCKOUT DOES NOT HAVE ANNUNCIATION IF IT IS TRIPPED.

CO

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LICENSEE EVENT REPORTS 'V.

00




METHOD OF DISCOVERY NSSS / A/F RFPORT TYPF CAUSE DESCRIPTION

GENERAL ELECTRIC CO. 05000296 070678 DURING OPERATION. OPERATIONS PERSONNEL DISCOVERED AN ABNORMAL INDICATIONCIRCUIT CL)SERS/INTERPUPTERS 78-015/03L-0 071878 ON A 4-KV STAND 8Y POWER CIRCUIT BREAKFR. THE CIRCUIT BRLAKER WAS FOUND

CIRCUIT BREAKER 02178D 30-DAY DEFECTIVE AND ONE DIESEL GENERATOR WAS DECLARED IN0PERABLE. REDUNDANTCOMPONENT FAILURE LIC SYSTEMS WERE TESTE9 SATISFACTORILY AS REQUIRED BY TS 3.9.B.2. THERE WAS

E L ECT RIC A'. GE NO HAZARD TO THE PUBLIC HEALTH OR SAFETY.BROWNS FERRY-3 0EMERG GENERATCR SYS + CONTROLSCPERATIONAL EVENT A SHORT IN A WINDING CF A SPRIhG CHARGING MOTOR, GE 105C9393-P3. CAUSED

THE FUSES TO CrtN IN THE CLOSING CIRCUIT OF A CIRCUIT BREAKER WHICH SUPPLIES THE AUXIL 'S<Y STAND-BY POWER TO THE SHUTDOWN BOARD. THE MOTOR WASREPLACED

GENERAL CLECTRIC CO. 05000324(I052678 A ROUTINE SURVEILLANCE OF THE RTG BOARD BY A CONTROL OPERATOR REVEALED TCIRCUIT CLOSERS / INTERRUPTERS 78-046/03L-0 062678 HAT THE " FULL IN' LIGHT FOR ROD 50-19 WAS NOT INDICATING THE ACTUAL FULL

SWITCeGEAR 021659 30-CAf IN CONTROL RCD POSITION. THE FULL IN CONTROL ROD REED SWITCH WAS FOUNDCOMPCNENT FAILURE NSSS INOPERABLE (T.S.3.1.3.7.A2).

ELECTRICAL CE

BRUNSWICK-2 UEC

SAFETY RELATED DISPLAY INSTRROUTINE TEST / INSPECTION THE CONTROL OFERATOR IMMEDI ATELY VERIFIED; ACTUAL CONTROL ROD POSITION,

C0 ERECT POSITION IN THE PROPER SEQUENCE. AND AT LEAST TWO CONTROL CELLSCPERAELE IN ALL DIRECTIONS. THE FULL IN REED SWITCH FOR ROD 50-19 WAS

REPAIRED AND PLACED BACK INTO CPERATION. CATA IS ALSO BEING TAKEN TO DETEPMINE Ir A C[NER!r PPD [L[M EVICTE WITH THFEE TWITCUFR.

~~~

bENERAL LLLLIkit LO. L5uv03E4 U52276 ON 5/42/16 A CONikUL UPLEAICK WAS ELkFURMINu itRICUIC IEST 14.1 CUNIRULCONTPOL ROD ORIVE MECHANISMS 78-017/C2L-0 Oc2078 E00 CPE9 ABILITY CHECK FOR R00 26-11. THE ROD WAS MOVED FROM POSITION 48

SUBCOMPONENT ROT APPLICAELE 021483 30-DAY TO 46 AND THEN COULD NOT BE MOVLD IN OR CUT FROM POSITION 46. APPROXIMCOMPONENT FAILURE NSSS ATELY 9.5 HOURS LATER, A REACTOR SCRAM OCC'JRED WHICH SCRAMED ROD 26-11 T

OTHER GE 0 THE FULL IN POSITION. ON 5/29/78 DURING PERIODIC TEST 14.1 CONTROL R0BRUNSWICK-2 LEC 3 26-11 WOULD NOT MOVE IN OR OUT. (TECHNICAL SPECIFICATIONS 3.1.3.1B)FEACTIVITY CONTkOL SYSTEMSROUTINE TEST / INSPECTION ON 5/22/78 INSERT VALVE V121 AND THE WITHDRAWAL AND INSERT FILTERS WERE

REPLACED ON HCU 26-11. AFTER THE PEACTOR SCRAM THE ROD WAS MOVED NORMALLY, EXERCISED AND WAS OPERATING PROPERLY. ON 5/29/78 CONTROL ROD 26-11WAS ELECTRICALLY DISARMED. THIS DRIVE WAS REBUILT DURING THE JUNE 2 OUTAGE AND PLACED BACK INTO THE VESSEL.

-

148.


COMPONENT MANUFACTURER DOCKET NO.COMPONENT / COMPONENT SUBCODE LER NO.CAUSE CODE /CAUSE SUBC00E CONTROL NO. EVENT DATEFACILITY / SYSTEM SUPPLIER REPORT DATE EVENT DESCRIPTIONMETHOD OF DISCOVERY NS*S / A/E REPORT TYPE CAUSE DFSCRIPTION

GENERAL ELECTRIC CO. 05000155 060678 THE DAILY UNIDENTIFIED PRIMARY SYSTEM LEAKAGE OF 1.36 GPM EXCEEDED THE A .CONTROL R0D DRIVE MECHANISMS 78-029/03L-0 063078 LLOWABLE LIMIT OF 1.0 GPM (T/S 4.1.2(C)1) AT 1630 HRS 09 6/6/78. ANALYS

SUBCOMPONENT NOT APPLICABLE 021791 30-DAY IS OF WATER IN THE R0D DRIVE SUMP WAS ANALYZED AND DEEMED NOT TO BE PRIMCOMPONENT FAILURE NSSS ARY SYSTEM WATER AT 0210 ON 6/7/78. NO HAZARDS EXISTED. THE INCIDENT I

INSTRUMENT GE 5 SIMILAR TO R0-78-16 REPORTED ON 4/19/78.BIG ROCK POINT BECHREACTOR VES. + APPURTENANCESROUTINE TEST /INSPECTi N LEAKAGE IS RELATED TO DRIVE FLANGE "0" RING SEAL DETERIORATION CAUSING L

EAK OF DRIVE COOLING WATER. THIS WILL BE INVESTIGATED AND REPAIRED DURING A FUTURE OUTAGE. REPORTABLE PER T/S 6.9.2.B(2).

GENERAL ELECTRIC CO. 05000322 030178 POTENTI0 METERS IN NGV RELAYS MADE BY G.E. WERE FOUND TO BE DEFECTIVE. FENGINES INTERNAL COMBUSl.?N 78 /02L 040178 AILURE OF THESE POTENTI0 METERS IN THESE RELAYS WOULD PREVENT AUTOMATIC

SUBCOMPONENT NOT APPLICAELE 021809 30-DAY TRANSFER OF EMERGENCY DIESEL GENERATOR EQUIPMENTDESIGN / FABRICATION ERROR * UNS

CAUSE SUBCCDE NOT PROVIDED GE

SHOREHAM-1 S+WEMERG GENERATOR SYS + CONTROLSSPECIAL DOSIMETER REPORTS A VENDOR PROCESS PROBLEM WAS CAUSING FLEXING AND BREAKAGE OF THE POTENTI

OMETER. RELAYS TO BE CHECKED FOR PROBLEM.

GENEFAL ELECTRIC CO. 05000206 060778 DURING NORMAL OPERATION ON 6/7/78, THE DC INPUT FUSE FOR MOV SSOC INVERTGENE RATORS 78-007/03L-0 061278 ER OPENED FOLLOWING FAILURE OF A CAPACITOR AND SILICON CONTROLLED RECTIF

INVERTER 021743 30-CAY IER. TFE POWER SOURCE FOR MOV 850C TRANSFERRED TO ThE BACKUP SUPPLY. TCOMPONENT FAILURE UIHER HE REDUNDANT POWER SUPPLY WAS AVAILAELE.

ELECTRONIC WESTSAN ON0FRE-1 BECH

DC ONSITE POWER SYS + CONTROLSOPERATIONAL EVENT A GENERAL ELECTRIC 28FS108 CAPACITOR IN CAPACITOR BANK C-4 FAILED RESULT

ING IN THE FAILURE OF SILICON CONTROLLED RECTIFIER SCR-2. ALL AFFECTEDCOMPONENTS WERE REPLACED

CD0;

f:[] 149

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NLICENSEE EVENT REPORTS ti-

cab)COMPONENT MANUFACTURER DOCKET NO.

COMPONENT / COMPONENT SUBCODE LER NO.CAUSE CODE /CAUSE SUBCODE CONTROL NO. EVENT DATEFACILITY / SYSTEM SUPPLIER REPORT DATE EVENT DESCRIPTIONMETHOD OF DISCOVERY NSSS / A/F RFPORT TYPF CAUSF DESCRIPTION

GENSRAL ELECTRIC C0. 05000285 071278 DURING THE MONTHLY LOAD TEST OF DIESEL GENERATOR NUMBER 1 THE GENERATORGENERATORS 78-022/03L-0 071978 FIELD WENT TO MAXIMUM EXCITATION & WAS SHUTDOWN TO PREVENT GENERATOR DAOTHER 021799 30-DAY MAGE. THREE PROBLEM AREAS WERE DISCOVERED: THE FIELD BOOST RELAY HAD D

COMPONENT FAILURE A/E RIFTED, THE REFERENCE POTENTIAL TRANSFORMER TAB WAS LOOSE AND THE REGULAELECTPONIC COMB TOR REFERENCE ZENER WAS FOUND DEFECTIVE. THE ITEMS WERE REPAIRED AND TH

FT. CALHOUN-1 GHDR E DIESEL RETESTED AND RETURNED TO SERVICE.EKERG GENERATOR SYS + CONTROLSROUTINE TEST / INSPECTION THE FIELD BOOST RELAY WAS FOUND TO HAVE DRIFTED, THE REFERENCE POTENTIAL

TRANSFORMER TABS WERE LOOSE AND THE REFERENCE ZENER DIODE FOR THE GENERATOR REGULATOR WAS FOUND DEFECTIVE. THE ITEMS WERE REFAIRED. THIS IS THE FIRST FAILURE OF THIS TYPE AND NO FURTHER ACTION IS ANTICIPATED. THEZENER DIODE WAS FRT TO ef THE FAltURE MACHANISM,

GENERAL ELECTRIC 00. 05000259 050476 DURING N0kMAL OFEkATION, OFLRATOR5 fUUND THE 10RUS UXYGEN MONITURING Si5INSTRUMENTATION + CONTROLS 78-014/03L-1 061278 TEM INDICATING HIGH. INVESTIGATIN REVEALED THE SYSTEM WAS INOPERABLE.

SENSOR / DETECTOR / ELEMENT 021351 30-DAY THIS IS CONTRARY TO T.S. 3.7.H.2. THE HYDRDGEN SENSOR WAS OPERABLE WHICCOMPONENT FAILURE NSSS H ALLOWS CONTINUED OPERATION FOR 30 DAYS. THERE WAS NO POTENTIAL FOR HA

ELECTRONIC GE ZARD TO THE PUBLICHEALTH 0R SAFETY. MOST RECENT PREVIOUS OCCURRENCES WEBROWNS FERRY-1 0 RE BFR0'S 50-259/7814, 296/7801, AND 296/7716.CNTNMNT COMBUS GAS CONTROL SYSOPERATIONAL EVENT TORUS OXYGEN SENSOR - GE PART N0. 23991-47C226431-P1 - PRODUCED A HIGH 0

UTPUT WHEN CONNECTED TO NORMAL INPUT AMPLIFIER. INSTALLATION OF AN ISOLATION AMPLIFIER CORRECTED THE PROBLEM, SENSOR WAS CALIBRATED, AND THE RE

ADING CONFIRMED BY COMPARISON TO A GAS CHROMAT0 GRAPH ANALYSIS. THIS ISEN UDDATFD PEPOPT

GENERAL ELECTRIC CO. 05000259 052378 DURING NORMAL OPERATION, LNIT 1 DRVWELL HYDROGEN SENSOR bECAME ERRAill 5INSTRUMENTATION + CONTROLS 78-015/03L-0 061378 HOWING A FALSE HIGH HYDROGEN CONTENT BEYOND REQUIREMENTS OF TECH SPEC 3.

SENSOR / DETECTOR / ELEMENT 021494 30-CAY 7.H/4.7.H. A REDUNDANT DRYWELL HYDRDGEN SYSTEM WAS OPERABLE WHICH ALLOCOMPONENT FAILURE NSSS WS CONTINUED OPERATION FOR 30 DAYS. THERE IS NO POTENTIAL FOR HAZARD TO

ELECTRONIC GE THE PUBLIC HEALTH OR SAFETY. THIS IS A REPETITIVE OCCURRENCE. BFRO-50BROWNS FERRY-1 0 -259/7814, 296/7719CNTNMNT COMBUS GAS CONTROL SYSOPERATIONAL EVENT DRYWELL RDR0 GEN SENSOR - GE PART NO. 47E226411G1 - H2E-76-39 SHOWS ERRA

TIC READINGS NEAR 4% HYDRDGEN. PROBLEM REMAINS UNIDENTIFIED. A FINAL REPORT WILL FOLLOW.

150.

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UCENSEE EVENT REPORTS,

COMPONENT MANUFACTURER DOCKET NO.COMPONENT / COMPONENT SUBCODE LER NO.CAUSE CODE /CAUSE SUSCODE CONTROL NO. EVENT DATEFACILITY / SYSTEM SUPPLIER REPORT DATE EVENT CESCRIPTIONMETHOD OF DISCOVERY NSSS / A/F RFPORT TYPF CAtiSE DESCRIPTION

GENERAL ELECTRIC CO. 05000259 060278 DURING PLANT $UTDOWN, OPERATORS DISCOVERED THE TORUS OXYGEN SENSING CIRINSTRUMENTATION + CONTROLS 78-018/03L-0 062278 :UIT ISOFERABLE AND REQUIREMENTS OF T.S.3.7.H.2 U NSATISFIED. THE TORUS HSENSCR/DETE CTOR/ ELE MENT 021558 30-DAY YDROGEN SENSING CIRCUIT WAS OPERABLE WHICH ALLOWED CONTINUED OPERATION F

COMPONENT FAILURE NSSS OR 30 DAYS. THERE WAS NO POTENTIAL FOR HAZARD TO THE PUBLIC HEALTH ORELECTRONIC GE SAFETY. FFEVIOUS OCCURRENCES WERE BRF0'S 50-259/7814, 50-296/7801, AND

BROWNS FERRY-1 0 50-296/7716.CNTNMNT COMBUS GAS CONTROL SYSOPERATIONAL EVENT TORUS OXYGEN SENER - GE PART NO. 23991-47C226431-P1 SHOWED A LOW OUTPUT

SIGNAL. PROBLEM IS UNICENTIFIED. A FINAL REPORT WILL FOLLOW.

GENERAL ELECTRIC CO. 05000259 062178 DURING NORMAL OPERATION WHILE SURVEILLANCE TESTING. THE HYDROGEN MONITORINSTRUMENTATION + CCNTROLS 78-020/03L-0 071378 ING SENSOR IN THE TORUS FAILED TO MEET T . S . 3 . 7. H . 2. THERE WERE NO SIGNSENSOR /CETECTOR/ ELEMENT 021728 30-CAY IFICANT OCCURRENCES AS A RESULT OF THIS PROBLEM. THERE WERE NO EFFECTS

COMPONENT FAILURE NSSS ON THE PUBLIC HEALTH OR SAFETY. PREVIOUS OCCURRENCE 50-259/7719.INSTRUMENT GE

BROWNS FERRY-1 0CNTNMNT COMBUS GAS CCNTROL SYSROUTINE TEST / INSPECTION GENERAL ELECTRIC HYDROGEN. MODEL 47E226411G1, HAD AN ERRATIC OUTPUT. TH

E CAUSE OF THE PP0BLEM 15 UN KNOWN . THE REACTOR WILL BE SHUTDOWN FOR REPL; CEMENT OF THE DEFECTIVE PART WITHIN 30 DAYS. A NEW SYSTEM WILL BE INSTALLED, WEEN AVAILABLE TO PREVENT RECURRENCE.

GENERAL ELECTRIC C0. 05000324 CE0278 ON f/2/78, DURING PERIODIC TEST 45.3.4 (HPCI INITIATION RESPONSE TEST).INSTRUMENTATION + CONTROLS 78-051/03L-0 062978 IT WAS DISCOVERED THAT THE HPCI TURBINE CONTROL SYSTEM DID NOT NEET THECONTROLLER 021E61 30-CAY RESPONSE TIME ROUIREMENTS OF LESS THAN GR EQUAL TO 30 SECONDS. (TECHNI

COMPONENT FAILURE NSSS CAL SFECIFICATION 3.5.1).ELECTRICAL GE

BRUNSWICK-2 UECEMERG CORE COOLING SYS + CONTROUTINE TEST / INSPECTION TECH REP. EXAM THE TERRY TURBINE EGM (ELECTRONIC SPEED GOVERNOR) EGR (

HYERAULIC ACTUATOR) & THE GEN ELEC FLOW CONTROLLER. THE HPCI FLOW CCNTROLLER (E41-FIC-R6CO) LAS FOUND OUT OF CALIBRATION, ALSO THE EGM UNIT WOULD NOT CALIBRATE. THIS WAS CORR BY CLEAN A DIRTY CONTACT ON THE EGM CARD. THE FLOW CONTROLLER & THE EGM UNIT WERE CALIBRATED.

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.ILICENSEE EVENT REPORTS y

CE2COMP 0NENT MANUFACTURER CCCKET NO.COMPCNENT/COMFONENT SUBCODE LER NO.CAUSE CODE /CAUSE SUECODE CONTROL NO. EVENT DATEFACILITY / SYSTEM SUPPLIER PEPORT DATE EVENT DESCRIPTIONPETHOD OF DISrnVERY NS$$ / A/E PEPODT Type rAUSE DESCRIPTION

_.

GENERAL ELECTRIC CO. 05C00324 062278 A CONTROL CPERATOR WAS PULLING RCDS FOR A NCRMAL POWER INCREASE WHEN THEINSTRUMENTATION + CONTROLS 78-056/03L-0 072178 POD SELECT WAS DEPRESSED FOR SELECTION OF ThE NEXT ROD TO BE PULLED. RSWITCH 021771 30-DAY BM (ROD BLOCK MONITOR) CHANNEL "A" FAILED INDICATING 00WNSCALE. (TECHNI

COMPONENT FAILURE NSSS CAL SPEC 1r1 CATION 3.1 4.3)ELECTRICAL GE

BRUNSWICK-2 UECENGNRD SAFETY FEATR INSTR SYSROUTINE TEST /INSFECTION CEFECTIVE POD SELECT SWITCH, WHICH WOULD NOT RETURN FROM PUSHED-IN POSIT

ION, SHORTED RESISTOR "RS" IN REACTOR MANUAL CCNT RELAY MODULE Pl. THISIN TURN CAUSED RBM CHANNEL A TO FAIL INDICATING DOWNSCALE. CEFECTIVE RODSELECT SWITCH & SHORTED "RS" RESISTOR kERE REPLACED. R0D SELECT SWITCHES PPES IN U<E ON OPER r6NSOLE ARE EEING Pert W/Mr$E RELI AELE (WITrhES.

GtNtkAL LLECTRIC CO. 05000259 0109/6 DURING $URVLILLANLL IL511Nb Wilh THE LNil ShUlbUWN, iHL kOD $LQULNLL LUNISSTRUMENTATION + CONTPOLS 78-021/01T-0 072178 TROL 3 STEM (RSCS) WAS DISCOVERED INOPERACLE BELOW 20% REACTOR POWER (T.OTHER 021783 2-hEEK S.3.3.B.3). CFD'S WERE VERIFIED FULL-IN AND THE CRD SELECT POWER TURNED

COMPONENT FAILURE NSSS CFF. THE FEACTOR REMAINED SHUT DOWN UNTIL REPAIRS WERE MADE. THERE WAELECTRONIC GE S N0 HAZARD TO THE PUBLIC HEALTH OR SAFETY. NO REDUNDANT SYSTEMS WERE A

BROWNS FERRY-1 0 VAILAELE.ENGNRD SAFETY FEATR INSTR SYSROUTINE TEST /INSPEC110N LOGIC CIRCUITS FAILED ON A G.E. PRINTED CIRCUIT BOARD IN SUCH A MANNER A

5 TO PERMIT SELECTION OF MORE THAN ONE RSCS GROUP. CRD MOVEMENT WAS STCPPED. THE PRINTED CIRCUIT BOARD WAS REPAIRED AND RETURNED TO SERVICE. NO PREVIOUS FAILURES OF TI:IS NATURE HAVE EEEN ENCOUNTERED; THEREFCRE. TEE

FAILUPE WAS PANDOM AND NO PECUPPENCE CONTPOL WAS NECESSARY.GENLRAL ELLCIRIC 00. 05000333 072678 DURING N0kMAL SURVEILLANCE IL511NG (F-ISP-19) FULND Of f-GA5 RADI AllUN MU

INSTRUMENTATION + CONTROLS 78-061/03L-0 081178 NITOR 17-RM-150B INDICATING IN A NON-CONSERVATIVE DIRECTION WHICH WOULDOTHER 021944 30-DAY RESULT IN NON-CONSERVATIVE TRIP AND ALARM ACTIONS.

COMPONENT FAILURE NSSS

INSTRUMENT GE

FITZPATRICK-1 S+WPRCSS + EFF RADIOL MONITOR SYSRDUTINE TEST / INSPECTION INSTRUMENT DRIFT. INSTRUMENT RECALIBRATED AND SURVEILLANCE PROCEDURE SA

TISFACTORILY COMPLETED IN ACCOPDt.NCE WITH TECHNICAL SPECIFICATION TABLE3.2-4 REQUIREMENTS.

,

152 .

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LICENSEE EVENT REPORTS-

COMPONENT MANUFACTURER 00CKET NO.COMPCNENT/CCMPONENT SUBCODE LER NO.CAUSE COCE/CAUSE SUSCODE CONTROL NO. EVENT CATEFACILITY / SYSTEM SUPPLIER REPORT CATE EVENT CESCRIPTIONMFThr0 0F DIsr0VFPY NSSS / A/F PEPOPT TYPF CAU<F PFSCRIPTir.N

GENERAL ELECTRIC CO. 05000237 072678 CURING UNIT START-LP, WHILE PULLING CRD'S TO CRITICALITY ON SEQUENCE "A"INSTRUMENTATION + CONTROLS 78-043/03L-0 082578 THE RWM MALFLNCTIONED CAUSING E00 INSERT AND WITHCRAW BLOCKS. BECAUSE

COMPUTATION MODULE 022070 30-CAY FWM INCFERABILITY OCCLRRED DLRING FIRST 12 RCD WITHCRAWALS, FURTHER WITHCOMPONENT FAILURE NSSS CRAWALS WERE NOT PERMITTED BY TS 3.3.B.3.B. NO SAFETY SICNIFICANCE EECAELECTRICAL GE USE THE RWM FAILUPE LIGHT ANNUNCIATED AND ADDITIONAL RCD PULLS WERE SUSPCRESCEN-2 5+L ENCED. FIRST REPORT OF THIS TYPE.REACTIVITY CONTRCL SYSTEMSOPERATIONAL EVENT

ThE FAILURE OF THE RWM LAS CAUSED BY A DEFECTIVE DIGITAL OUTPUT RELAY B0ARD. INSERT /WITHCRAW BLOCKS WERE ELIMINATED WhEN THE RWM WAS BYPASSED AND THE 5 WITHDRAWN CONTROL RODS WERE FULLY INSERTED. TbE DEFECTIVE E0ARD WAS REPLACED AND NORMAL UNIT STARiLP BEGAN.

GENERAL ELECTRIC CO. 05C00249 052078 DURING STARTUP OPERABILITY SURV. TESTING IN REFUEL MODE SRM'S #24 AND 21INSTRUMENTfTICN + CONTROLS 78-023/01T-0 060278 WERE CECLARED INOPERABLE. TECH SPEC 3.2.C.2. TABLE 3.2.3 ALLOWS ONLY 0GTHER 021509 | 2-WEEK NE SRM TO BE INOPERABLE WHILE IN THE STARTUP CONDITION. SAFETY SIGNIFIC

COMPONEN~. /AILURE NSSS ANCE MINIMAL BECAUSE THE CEFICIENCIES WERE DETECTED BEFORE CONTROL RCD DMECHANICAL GE RIVE WITHCRAWAL WAS INITIATED. NO PREVIOUS REPORTABLE EVENTS OF THIS TYCRESCEN-3 S+L FE HAVE OCCURRED.

REACTOR TRIP SYSTEMSROUTINE TEST / INSPECTION FAILURE OF SRM 24 TO INSERT TO ITS PFCPER STARTUP POSITION WAS ATTRIBUTE

D TO A FAULTY DRIVE CABLE. THE CABLE WAS REPLACED AND THE SRM WAS SUCCESSFULLY INSERTED. CAUSE Or FAILURE OF SRM 21 WAS DUE TO A BAD SIGNAL CABLE. THE SIGNAL CABLE WAS REPLACED.

GENERAL ELECTRIC CO. 05000010 060278 WHILE PERFORMING INCORE CALIBRATION, INCORE MONITOR AMP 113C WAS FOUND TINSTRUMENTATION + CONTROLS 78-023/03L-0 061678 0 TRIP AT 12E%. T.S. 2.1.A.1 REQUIRES A LIMIT OF %/= 125% FULL SCALE INOTHER 021514 30-DAY DICATION. SUFFICIENT ADJACENT MONITORS WERE OPERABLE TO CETECT A HIGH F

COMPONENT FAILURE NSSS LUX CONDITION. PREVIOUS EVENTS OF SIMILAR NATURE ARE REF. IN LER'S 76-INSTRUMENT GE 17, 77-3 & 13, 78-016 & 78-022 78-022.

DRESDEN-1 BECHREACTOR TRIP SYSTEMS

ROUTINE TEST / INSPECTION THE CAUSE IS ATTRIBUTED TO DRIFT OF THE APPLIED BIASING VOLTAGE VIA THETRIP ADJUSTING 25K OHM RESISTOR OR CHANGING RESISTOR CHARACTERISTICS. THE HIGH TRIP WAS PROMPTLY ADJUSTED TO 116%. INCORE FLUX AMPLIFIERS WIll

CONTINUE TO BE TESTED MONTHLY.

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CQWN

LICENSEE EVENT REPORTS (CiN1.

COMPONENT MANUFACTURER COCKET N0.COMPONENT / COMPONENT SUBC00E LER NO.CAUSE CODE /CAUSE SUBCODE CONTROL NO. EVENT DATE


METHOD OF DISCOVEPY NS$5 / A/E REPODT TYPE CAUSE DESCRIPTION

GENERAL ELECTRIC CO. 05000010 052578 WHILE PERFORMING INCORE CAllBRATION, INCORE MONITOR AMPLIFIER 109A WAS

INSTRUMENTATION + CONTROLS 78-022/03L-0 061678 FOUND TO TRIP AT 1311. T.S. 2.1.A.1 REQUIRES A LIMIT OF %/= 125% FULLOTHER 021515 30-DAY SCALE INDICATION. SUFFICIENT ADJACENT MONITORS WERE OPERABli TO DETECT

COMPONENT FA? LURE NSSS A HIGH FLUX CONDITION. PPEVIOUS EVENTS OF SIMILAR NATURE ARE REF. IN LEINSTRL"AENT GE R'S 76-17, 77-3 & 13, 78-016.

DRESDCN-1 BECH

REACIOR TRIP SYSTEMSRDUTINE TEST / INSPECT 10N THE CAUSE IS ATTRIBUTED TO DRIFT OF THE TRIP ADJUSTING BIASING VOLTAGE 2

SK OHM RESISTOR OR CHANGING RESISTOR CHARACTERISTICS. THE HIGH TRIP WASPROMPTLY ADJUSTED TO 116%. INC0nE FLUX AMPLIFIERS WILL CONTINUE TO BE

TESTED MONTHLY.

GENERAL ELECTRIC CO. 05000277 070578 WHILE AT POWER, DURING PERFORMANCE OF SURVEILLANCE TESTING ON THE APRM'S

INSTRUMENTATION + CONTROLS 78-032/03L-0 071378 IT WAS OBSERVED THAT THE SCRAM CLAMP TRIP SETPOINT WAS 121 ON THE "A" AP

SWITCH 021707 30-DAY - RM. THIS VALUE EXCEEDED THE 120 PERCENT LIMIT OF TECHNICAL SPECIFICATI0COMPONENT FAILURE NSSS N 2.1. A.1. ALL OTHER APRMS WERE SATISFACTORY AND THE 100 PERCENT FLOW H

INSTRUMENT GE I-HI TRIP POINT ON THE "A" APRM WAS WITHIN SPECIFICATIONS. THUS REDUCING

PE..H BOTTDM-2 BECH SAFETY SIGNIFICANCE TO A MINIMUM.REACTOR TRIP SYSTEMSROUTINE TEST /INSPECTIDN THE "A" APRM SCRAM CLAMP TRIP SETPOINT HAD DRIFTED 1 PERCENT ADOVE THE V

ALUE PERMITTED EY TECH SPECS. THE INSTRUMENT WAS IMMEDIATELY RECALIBRATED. PERFORMANCE OF FUTURE SURVEILLANCE TEST ON THIS EQUIPMENT WILL BE CLOSELY MONITORED FOR INDICATION OF DRIFTING PROBLEMS.

GENERAL ELECTRIC CO. 05000237 062678 DURING APRM SETDOWN FUNCTIONAL TEST (DIS 700-5), APRM CHANNEL #4 ROD BLO

INSTRUMENTATION + CONTROLS 7E-040/03L-0 081878 CK TRIPPED AT 12.5% EXCEEDING T.S. SECT 3.2 LIMIT: APRM ROD BLOCK %/=12SENSOR / DETECTOR / ELEMENT 021B61 30-CAY % OF RATED PWR. ONE OR MORE OPERABLE APRM'S PER CHANNEL REMAINED AVAILA

COMPONENT FAILURE NSSS BLE AS REQUIRED BY T.S.3.2 WHEN APRM *4 WAS BYPASSED. SIMILAR EVENT REFINSTRUMENT GE IN LER #78-029.

DRESDEN-2 5+L

REACTOR TRIP SYSTEMSROUTINE TEST / INSPECTION SETPOINT CRIFT OF R-25 ON MODULE BOARD Z34 UPON DISCOVERY, APRM #4 PLA

CED IN " BYPASS" APRM 44 ROD BLOCK SETDOWN REFERENCE PROMPTLY PESET TO

11.5" (DRESDEN SETPOINT IS 11.5+/ .5%). APRM SCRAN ROD BLOCK SETDOWN F

UNCTIONAL TESTS WILL CONTINUE TO BE COMPLETED AS REQUIRED AND DURING REFUELING OUTAGES.

154

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LICENSEE FVENT REPORTS

CCMFCNENT MANLFACTLRER COC8ET NO.CCMPONENT/CCMPCNENT SLECCCE LER NO.CAUSE CODE /CAUSE SvECODE CONTROL NO. EVENT DATEFACILITY / SYSTEM SLFFLIER LEPORT LATE E'sENT DESCRIPTIONVETpr'D OF Disr0kf RY N es / A/F pfPCPT TYFF

CAUSF FFsrRIPTIONGENERAL ELECTRIC CO, CS000249 060378

WHILE FERFORMING DOS 500-3. APRM e6 ROD CLOCK TRIPPED AT 12.5%. THIS EXINSTRUPENTATICN + CCNTROLS 7E-029/03L-0 072678CEECED T.S. SECT. 3.2 LIMIT - APRM RCD ELCCK i/= 12: FATED PhR. ONE ORSENSOR /CETECTOR/ ELEMENT C21663 30-CAYPORE OPERAELE APFM'S PER CHANNEL PEMAINED AVAILAblE AS FEQUIPCD BY T.S.CCPPGNENT FAILUPE GIFER3.2 AFTER APRM e6 WAS BYPASSED. THIS IS THE FIRST REPORTAELE OCCURRENCEINSTPUMENT GE CF THIS TYFE.DRESDEN-3 S+L

FEACTOR TRIP SYSTEMSROUTINE TEST / INSPECTION

CAUSE ATTRIBUTActE TO SETPCINT DRIFT OF R-25 CN MODULE BOARD 234. UPON DISCOVERY, AFEM e6 PLACED IN "EYPASS" DIS 700-5 WAS PERFORMED & APRM #6

POD Et0CK SETDOWN PEFERENCE PROPPTLY PESET TO 11.5% (CRESDEN SETPOINT IS11.5 +/ .5%) APRM SCRAM & RCD BLOCK SETDOW'. FUNCTIONAL TESTS WILL CONTI

S'T To rE invPt ETEn et cent'IPEn 5 nr* PING PErUELINr, otjTArEsutNteAL tLLCTRit tv. LtuvuJJJ 010)lbf0LNU APhM U LFKM LULNI IklP LLS$ LUNhlhbATIVE IHAN ILLHNILAL 5FttiflLAIINSTRLVENTATION + CONTROLS 78-050/03L-0 CC2478ION TAELE 3.1-1 REQUIREMENTS. TESTED OTHER APRM CHANNELS IMMEDIATELf.CCMPUTATICN MCCULE 022031 3C-CAY

COMFCNENT FAILLFE NSSSELECTRONIC GE

FITZFATRICK-1 5+WREACTOR TRIP SYSTEMSROUTINE TEST / INSPECTION

TRIP CIRCUIT HAD CRIFTED. ADJUSTED COLNT TRIP CIRCUITS TO TRIP WITHIN TECHNICAL SFECIFICATION LIMITS. PEPORT SUDMITTED LATE DUE TO ADMINISTRATIVE ERROR.

GENERAL ELECTRIC C0. C50C0325- 2678DURING NCRMAL PUPER CPERATICN A CONTROL OPERATOR WAS WITHDRAWING CONTR0LINSTRUMENTATICN + CCNTROLS 78-CCC/03' x2678R0D 12-23 AND DISCOVERED THAT TFE RCD HAD NO POSITICN INDICATION AT POSSWITCH 021SE6 30-CAY ITION 48. (T.S.3.1.3.7) TFE POSITION CF ROD WAS VERIFIED BY MOVING RODCOMPONENT FAILURE NSSS | TO POSITION 46.

ELECTRICAL GEBRUNSWICK-1 LECSAFETY RELATED DISPLAY INSTRFOUTINE TES7/INSFECTION

IT WAS CETERMINED THAT THE LOSS OF POSITION INDICATION WAS DUE TO A FallURE OF THE ROD POSITION INDICATION SYSTEM REED SWITCH FOR POSITION 48.THIS SWITCH WILL EE REPLACED DURING THE NEXT REACTOR SHUTDOWN WHICH PERMITS ACCESS TO THE CONTROL FDD DRIVES.

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t! 155, . , .

r&

thv-;

LICENSEE EVENT REPORTS g(0;Q

COMPONENT MANUFACTURER DOCKET NO. ggyCOMPONENT / COMPONENT SUBCODE LER NO.

CAUSE CODE /CAUSE SUBCODE CONTROL NO. EVENT DATE

FACILITY / SYSTEM SUPPLIER REPORT DATE EVENT DESCRIPTION(AIKF DFSrpf pTTON

urTHnD OF DYSCOVroy Nsss / A/r orpopT TYPr

GENERAL ELECTRIC CO. 05000271 062572 DURING STEADY STATE OPERATION, DRYWELL ATMOSPHERIC TEMP RECC9 DER TR-1-1

INSTRUMENTATION + CONTROLS 78-016/03L-0 072473 49. INOPERABLE. THIS IS 1 0F 2 REDUNDANT DRYWELL TEMP RECORDLxS CLASSIFRECORDER 021773 30-DAY IED AS POST-ACCIDENT INSTRUMENTATION BY TECH SPEC TABLE 3.2.6 & REQUIRED

COMPONENT FAILURE NSSSFOR POWER OPERATION. REDUNDANT TEMP RECORDER, WAS AVAILABLE & OPERABLE

A SIMILAR OCCURRENCE WAS REPORTED AS R0 76-30.MECHANICAL GE

VERMONT YANKEE-1 EBASCO

SAFETY RELATED DISPLAY INSTR A GENERAL ELECTRIC COMPANY MODEL BHGIA02011 RECORDER FAILED TO OPERATE DOPERATIONAL EVENT UE TO A BROKEN CORD ON THE CHART DRIVE MECHANISM. THE DRIVE CORD WAS RE

PLACED AND THE RXORDER WAS RETURNED TO SERVICE ON 6/26/78.

GENERAL ELECTRIC CO. 05000271 061278 DURING STEADY STATE OPERATION, DRYWELL ATMOSPHERIC TEMP RECORDER TR-1-1

INSTRUMENTATION + CONTROLS 78-021/03L-0 072478 49, INOFERABLE. THIS 1510F 2 REDUNDANT DRYWELL TEMP RECORDERS CLASS 1FI

RECORDER 021810 30-DAY ED AS POST-ACCIDENT INSTRUMENTATION & 15 REQUIRED FOR POWER OPERATION.REDUNDANT TEMP RECORDER, WAS AVAILABLE & OPERABLE. THIS EVENT WAS IDENTI

COMPONENT FAILURE NSSSFIED ON 7/5/78 DURING A REVIEW OF SAFETY CLASS MAINTENANCE. SIMILAR EVEMECHANICAL GE

VERMONT YANKEE-1 EBASCO NTS WERE REPORTED AS R0 76-30 AND R0 78-16.

SAFETY RELATED DISPLAY INSTR A GENERAL ELECTRIC CCMPANY MODEL 8HG1A02011 RECORDER FAILED TO OPERATE DOPERATIONAL EVENT UE TO A FAILED IDLER ASSEMBLY. THE MAIN IDLER SHAFT AhD GEAR WERE REPLA

CED. THE RECORDER WILL BE REN ACED AT THE NEXT OPPORTUNITY WITH ONE OFA MORE RELIABLE DESIGN.

GENERAL ELECTRIC CO. 05000265 061478 WHILE PERFORMING MONTHLY HPCI PUMP OPERABILITY SURVEILLANCE PROCEDURE 00

MECHANICAL FUNCTION UNITS 78-026/0lT-0 062878 5 2300-2. THE REQUIRED HPCI TURBINE SPEED COULD NOT BE OBTAINED. DURINGSUBCOMPONENT NOT APPLICABLE 021790 2-WEE K THE SURVEILLANCE T ST THE LINKAGE TO THE SECONDARY OPERATING CYLINDER

PILOT VALVE BECAME DISCONNECTED WHICH IN TURN CAUSED HPCI TURBINE CONTROCOMPONENT FAILURE NSSS

MECHANICAL GE L VALVES TO GO CLOSED. PLANT RELIABILITY WAS NOT ADVEPSELY AFFECTED A3

QUAD CITIES-2 S+L CORE SPRAY, LPCI, RCIC, AND APR WERE OPERABLE.

EMERG CORE COOLING SYS + CONT INVESTIGATION DETERMINED THAT A JAM NUT ON AN END R0D HAD CCME LOOSE ALLROUTINE TEST / INSPECTION CWING THE END R0D TO UNSCREW FROM ITS CONNECTING ROD. THE END ROD WAS R

EPOSITIONED AND THE J AM NUT WAS TIGHTENED.

156


COMPONENT MANUFACTURER DOCKET NO.COMPONENT / COMPONENT SUBCODE LER NO.CAUSE CODE /CAUSE SUBCODE CONTROL NO. EVENT DATEFACILITY / SYSTEM SUPPLIER REPORT DATE EVENT DESCRIPTIONMETHOD OF DISCOVERY NSSS / A/E PEPORT TYPE CAUSE DESCRIPTION

,

GENERAL ELECTRIC CO. 05000315 071478 UPON UNIT TRIP, THE TURBINE DRIVEN AUXILIARY FEED PUMP DID NOT START ASMECHANICAL FUNCTION UNITS 78-044/03X-1 081478 REQUIRED UPON RECEIPT OF THE AUTOMATIC START SIGNAL. THE PUMP WAS DECLA

-

SUBCOMPONENT NOT APPLICABLE 021939 OTHER RED INOPERABLE PURSUANT TO ThE ACTION IMPOSED BY T.S. 3.7.1.2 AND UPON RCOMPONENT FAILURE A/E EPAIR WAS RETURNED TO SERVICE WITHIN APPROXIMATELY FIVE HOURS FROM THE S

ELECTRICAL WEST TART OF THE EVENT. SIMILAR OCCURRENCES OF THIS TYPE WERE REPORTED UNDERD. C. C00K-1 AEP R0-050-315/76-35 AND 47.FEEDWATER SYSTEMS + CONTRCLSOPERATIONAL EVENT THE SOLEN 0ID WHICH OPERATES THE TRIP THROTTLE VALVE WAS FOUND BURNED OUT

RENDERING MECHANISM INOPERABLE. IT APPEARED THAT A SHORT EXISTED BETWEEN SOLEN 0ID LUGS & THE CASE ITSELF WHICH CAUSED THE PROBLEM, ALTHOUGH ENTIRE MECHANISM (CE#CR95038/AG-51) WAS REPLACED T's ASSURE THAT ANY ADDITIONAL UNDETECTED PP09tEMS WEDE CORDECTED.

GENERAL ELLLTRIC CU. 05000216 052/16 UUFING A PoullNt SLRbElLLANLL ILSI A LNil 3 LSW FUMr RuGM SUrFLv FAN 3bvMOTORS 78-011/03L-0 062678 60 FAILED TO START IN MANUAL CONTROL. THIS CONSTITUTED GPERATION IN THE

SUBCOMPONENT NOT APPLICABLE 021498 30-DAY DEGRADED MODE AS ALLOWED BY TECH SPEC 3.9.C.4. INVESTIGATION TRACED THCOMPONENT FAILURE A/E E PROBLCM TO A FAILURE IN THE FAN MOTOR. THE REDLNDANT FANS WERE AVAILA

ELECTRICAL GE BLE. SAFETY SIGNIFICANCE IS MINIMAL.PEACH BOTTOM-3 BECHCOOL SYS FOR REAC AUX + CONTRCUTINE TEST / INSPECTION THE FAN MOTOR (480 V., E PHASE, 60 HRTZ, 20 HORSEPOWER) DEVELOPED AN OPE

N CIRCUIT IN A WINDING. THE MOTOR HAS BEEN REMOVED AND WILL BE REWOUNDAND RETURNED TO SERVICE.

GENERAL ELECTRIC CO. 05000237 053078 DURING PRE-INSTALLATION INSPECTION OF RECENTLY PURCHASED SFENT FUEL STOROTHER COMPONENTS 78-035/01T-0 06097 AGE RACKS, CRACKS THROUGH WELD METAL IN ALUMINUM CHANNEL TO BASE PLATE F

SUBCOMPONENT NOT APPLICABLE 021511 2-WEEK ILLET WELDS WERE FOUND IN 8 0F 18 RACKS. EIGHT OTHER RACKS FR0*' SAME SHDESIGN / FABRICATION ERROR NSSS IPMENT WERE PREVIOUSLY INSTALLED BEFORE LAST DRS-3 REFUELING OU~IAGE. TH

MANUFACTURING GE E 8 INSTALLED RACKS WERE NOT SPECIFICALLY INSPECTED FOR CRACKS BUT DID PDRESDEN-2 S+L ASS SIMILAR PRE-INSTALLATION INSPECTION. FUEL WAS NOT STORED IN ANY RACSPENT FUEL STORAGE FACILITIES KS KNOWN TO HAVE WELD CRACKS.EXTERNAL SOURCE UNKNOWN - ALL FUEL REMOVED FROM 8 INSTALLED RACKS IN DRS-3. INVESTIGATI

ON BEING CONDUCTED BY G.E. TO DETERMINE CAUSE OF WELD CPACKS, FORMULATEA REPAIR PROGRAM AND AN INSPECTION PROGRAM FOR THE 8 INSTALLED RACKS AN

D REMAINING WELDS ON THE 18 RACKS NOT INSTALLED.

[ND 157

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is,e;N

LICENSEE EVENT REPORTS 10;J

COMPONENT MANUFACTURER DOCKET NO. 00CCMPONENT/CDMPONENT SUBCODE LER NO.CAUSE CODE /CAUSE SUBCODE CONTROL NO. EVENT DATEFACILITY / SYSTEM SUPPLIER REPORT CATE EVENT DESCRIPTIONMETung er DISCOVEDY NSE$ / A/E P[pODT Typ{ (Agg{ nr$(p}pTION

I WHILE PERFORMING FUNCTION TEST "HPCI STEAM LINE AP", RELAY E41-K36 IN THGENERAL ELECTRIC CO. 05000321 063078RELAYS 78-052/03L-0 071978 E HPCI ISOLATION TRIP SIGNAL "A" CHANNEL FAILED T0 INITIATE THE HPCI TUR

CCNTROL, GENERAL PURPOSE 021778 30-DAY BINE TRIP SOLEN 0ID ALARM. THE FAILURE DID NOT PREVENT THE "A" ISOLATIONCOMPONENT FAILURE NSSS SIGNAL FROM ISOLATING THE TURBINE. AT THE TIME CF THE iAILURE, ISOLATIO

ELECTidCAL GE N TRIP SIGNAL *B" WAS OFERABLE.ECWIN 1. HATCH-1 SSC/EECHEMERG CORE COOLING SYS + CONTROUTINE TEST / INSPECTION THE RELAY FAILED TO OPERATE EECAUSE THE MOVASLE AND STATIONARY CONTACTS

WERE STUCK TOGEThER DUE TO MISALIGNMENT. THE CONTACTS WERE SEPARATED AND ALIGNED. THE SYSTEM FUNCTIONAL TEST WAS PERFORMED SATISFACT0kiLY. RELAY TYPE CR120 (PN CR120CC4242AA).

GENERAL ELECTRIC CO. 05000285 060378 DURING THE MONTHLY TESTING OF VI AS FROM THE STATION PROCESS RADIATION M0RELAYS 78-015/03L-0 062678 NITORING SYSTEM, 66A VIAS LOCKOUT RELAY FAILED TO TRIP ON ACTUATION OF 8OTHER 021739 30-DAY 6A CRHS. THIS ALSO RESULTED IN THE FAILUPE OF THE DERIVED SIGNAL 86B1 V

COMPONENT FAILURE A/E I AS TO ACTUATE. THE REDUNDANT CHANNELS SEB VI AS AND E6Al VI AS WERE OPERAMECHANICAL COMB BLE AND DID ACTUATE AT THE TIME OF THE FAILURE OF 86A VIAS.

FT. CALHOUN-1 GHDR

ENGNRD SAFETY FEATR INSTR SYSROUTINE TEST / INSPECTION ONE OF THE TWO COIL WIRE LUG SCREWS WAS FOUND TO HAVE FALLEN OFF. THE S

CREW WAS REPLACED AND T'.E RELAY RETESTED. FIVE OF THE EIGHT OTHER RELAYS WITH A HIGH OPERATIMd FREQUENCY WERE INSPECTED WITH NO OTHER INDICATIONS OF TROUBLE.

GENERAL ELECTRIC CO. 05000331 061778 DURING WEEKLY CONTROL VALVF TESTING AN AUTOMATIC REACTOR SCRAM OCCURRED.RELAYS 78-031/01T-0 063078 SUBSEQUENT INVESTIGATION REVEALED THE SCRAM HAD DCCURRED DUE TO SEVEN

CONTROL, GENERAL PURPOSE 021E62 2-WEEK REACTOR PROTECTICN SYSTEM RELAY AUXILIARY SWITCHES BECOMING LOOSE ON THECOMPONENT FAILURE NSSS RELAY AND RESULTING IN THE BACK UP SCRAM VALVES BEING ENERGIZED. THE PL

INSTRUMENT GE RNT WAS LEFT IN THE SHUTDOWN CONDITION FOR REPAIRS. THE OPERATION OF THDUANE ARNOLD BECH E REACTOR PROTECTION SYSTEM RELAYS WAS NOT AFFECTED BY THE PROBLEM WITHREACTIVITY CONTROL SYSTEMS THE AUXILIARY SWITCHES.

ROUTINE TEST / INSPECTION THE CAUSE OF SWITCH PROBLEMS WAS TRACED TO SCFEW WHICH RETAINS OPERATINGARM OF AUXILIARY SWITCH BECOMING *.00SE AND BACKING OUT. THIS CAUSED MI

SCPERATION AND N 1 CASE ALLOM:0 THE ARM TO FALL OFF. THE RETAINING SCREWS AND GPERATING ARMS WERE REINSTALLED AND TIGHTENED. ENGINEERING EVALUATION IN PROGRESS TO DETERMINE A BETTER SCREW RETAINING METHOD.

158


COMPONENT MANUFACTURER DOCKET NO.COMPONENT / COMPONENT SUBCOCE LER NO.CAUSE CODE /CAUSE SUBCCCE CONTROL NO. EVENT CATEFACILITY / SYSTEM SUPPLIER REPCRT DATE EVENT CESCRIPTIONwETwe0 rf DI<covEcy Nsts / A/F ;rtrroT TycE rsecE rreroIpTInN

GENERAL RAILWAY SIGNAL 05000338 || 052978 DURING HOT STANCBY OPNS DN 5/29. 5/30 AND 5/a1 AND POWER OPNS ON 5/31, SOTHER COMPONENTS 78-044/03L-0 062878IX CONTAINMENT BULK AVG TEMP EXCURSIONS IN EXCESS OF THE 105 CEGREE F TESUBCCMPONENT NOT APPLICACLE 021637 30-CAYCH SPEC LIMIT OCCURRED. CONSEQUENCE LIMITED DUE TO TFE AYAILABILITY OFCOMPONENT FAILURE A/EUNIT 82 CHILLED H2O SYSTEMS TO PRO *.'?)E C00 LING H2O FOR THE COOLING SYSTEOTHER bEST MS CF UNIT #1. TFE HEALTH AND SAFELY OF THE GENERAL PUBLIC WERE NOT AFFNORTH ANNA-1 S+W ECTED.

CNTNMNT HEAT REMOV SYS + CONTGPERATIONAL EVENT

THE STEAM VACUUM REFRIGERATION UNIT OF THE CHILLED WATER SYSTEM LOST VACUUM CUE TO CLOGGED CHILLED CONDENSER TUBES. MAINTENANCE (CLEANING) WASPEPFORMED.

GOULDS PUMPS INC. 05000346 071078 CURING SURVEILLANCE TESTIN3, COMPONENT CD0 LING WATER PUMP 1-1 VIBRATIONPUMPS 78-077/03L-0 080478READINGS EXCEECED ALLOWAELE I.5 MILS MAX BY .1 MIL. NO DANGER TO HEALTHCENTRIFUGAL 021959 30-CAYAND SAFETY OF PUELIC OR UNIT PERSONNEL. UNIT WAS IN MODE 5. STANDBY CCOMPONENT FAILURE A/E

CW PUMP PLACED IN SERVICE PRIOR TO FAILURE OF CCW PUMP 1-1.MECHANICAL B+WCAVIS-BESSE-1 BECHCOOL SYS FOR REAC AUX + CONTROUTINE TEST / INSPECTION

COMPONENT FAILLRE. PUMP BEARINGS EXAMINED AND THRUST BEARING FOUND FAILING. FURTHER INVESTIGATION REVEALED EEARING TO SHELL CLEARANCE NOT ADEQUATE AND BEARING JOINT NOT SMOOTH. MAINTENANCE PERSONNEL INCREASED BEARING TO SHELL CLEARANCE, SMOOTHED BEARING JOINTS, AND REPLACED PUMP BEARING

GOULUd PLMPd INL. U5000c93 Ot217e UN JUNE 21, 1976 "D" dALI StkvlCL WAlik FLMr wad RtMUnLD FRuM S ERVILL TOPUMPS 78-029/03L-0 071478INVESTICATE THE CAUSE FOR HIGH VIBRATION. THE INVESTIGATION DISCLOSEDCENTRIFUGAL 021763 30-CAY EXCESSIVE WEAR ON THE SCREW, PACKING SLEEVE, MOTOR AND SPACER BEARINGS.CESIGN/ FABRICATION ERROR A/ETHE REDUNDANT SLT SERVICE WATER PUMPS AND ASSOCIATED SYSTEMS WERE OPERDESIGN GE ABLE AS REQUIRED.PILGRIM-1 EECH

STATION SERV WATER SYS + CONTOPERATIONAL EVENT

THE CAUSE OF THIS EVENT IS ATTRIBUTE) TO INADEQUATE CESIGN OF THE PUMP BOWL ASSEMBLIES FOR THE APPLIED USE AND TO UNFORESEEN HiCRAULIC FORCES ACTING ON THE PUMP COLUMNS. PDCRS HAVE BEEN GENERATED AND PARTIALLY IMPLEMENTED TO CORRECT THE BOWL DESIGN AND TO REDUCE THE HYDRAULIC FORCES. THESE ARE GOULD MODEL VIT/SD PUMPS.

Cf:C' 159'7;.

toH00

Ce#'d,. s

UCENSEE EVENT REPORTS 5.s

C$2COMPCNENT MANUFACTURER C0CKET NO.COMPONENT / COMPONENT SUECOCE LER NO.CAUSE CODE /CAUSE SLECODE CONTROL NO. EVENT CATE

FACILITY / SYSTEM SUPPLIER REPORT CATE EVENT DESCRIPTIONMETune Or Disr0VEoy Ness / A/F PFrepT TYPF CAUSF CFsepIPTION

GRAHAM MANUFACTURING 0500033E| 051978 ThE CONTAINMENT EULK AVERAGE TEMPERATURE EXCEEDED THE TECH SPEC F 105 CEOTHER COMPONENTS 78-037/03L-0 CE0578 GREES F FOR 75 MINUTES, REACHING A MAXIMUM CF 107.96 CEGREES F. THE CCN

SUBCOMPONENT NOT APPLICASLE 021505 30-DAY SEQUENCES WERE LIMITED DUE TO THE AVAILABILITY OF UNIT 2 CHILLED WATER SCCMPONENT FAILURE A/E YSTEM TO PROVICE COOLING WATER FOR THE CONTAINMENT COOLING SYSTEM OF UNIOTHER WEST T 1.

NORTH ANNA-1 5+W

CNTNFNT HEAT REMOV SYS + CCNTOPERATIONAL EVENT TFE STEAM (VACUUM) REFRIGERATION UNIT OF TFE CHILLED WATER SYSTEM LAST V

ACULM DUE TO CLOGGED STEAM N0ZZLES AND STRAINERS IN THE STEAM EJECTORS.VINTENANCE (CLEANING) WAS PERFORMED.

GREER HYCRAULICS, INC. 05000317 072178 AT 0700, WITH REACTOR IN HOT STANCBY, NO.12 MSIV ACCUMULATOPS WERE FOUN

VALVE OPERATCRS 78-037/03L-0 081778 D TO BE DEPRESSURIZED AND THE VALVE WAS DECLARED INOPERABLE. EXTENSliEHYDRAULIC 021994 30-CAY OIL LEAKAGE FROM THE VALVE OPERATOR WAS EVIDENT. PER THE REQUIREM ENTS 0

COMPONENT FAILURE A/E F T.S. 3.7.1.5, 11 AND 12 MSIV WERE SHUT AT 1600. CORRECTIVE ACTION WASMECHANICAL COMB COMPLETED AND 12 MSIV WAS SUCCESSFULLY TESTED AT 1455 DN 7/22/76. THIS

CALVERT CLIFFS-1 BECH IS NOT A REPETITIVE OCCURRENCE.MAIN STEAM SYSTEMS + CONTROLSOPERATIONAL EVENT UPON INVESTIGATION THE MSIV ACTUATOR CAP AND SEAL (ITEM #7 0F VENDOR PRI

NT A72533-200) WAS FOUND TO HAVE FAILED. THE CAUSE OF FAILURE COULD NOTBE DETERMINED. THE SEAL WAS REPLACED AND THE MSIV RETURNED TO SERVICE.

NO FURTHER ACTION IS REQUIRED AS A RESULT OF THIS EVENT.

GRINNELL CORP. 05000247 062678 DURING NORMAL OPERATION, A SLIGHT LEAK WAS CBSERVED AT A VALVE IN A LEVE

VALVES 78-018/03L-0 072678 L INSTRUMENTATION LINE FOR THE E0RON INJECTION TANK. THE LEAK EMANATEDCI AFFRAGM 0219C8 30-CAY FROM A CRACK IN THE VALVE BONNET, VI A A RUPTURED DI APHRAGM. TEMPORARY R

COMPONENT FAILURE NSSS EPAIRS WERE ACCOMPLISHED, AND THE LEVEL INSTRUMENTATION REMAINED IN SERV

METALLURGICAL WEST ICE PENDING PERMANENT REPAIRS. THIS EVENT IS REPORTABLE UNDER THE PROVIINDIAN FOINT-2 UEC SIONS OF TECH SPEC 6.9.1.7.2.D.EMERG CORE C00 LING SYS + CONTOPERATIONAL EVENT THE DIAPHRAGM OF A 2-INCH CRINNELL-SAUNDERS DIAPHRAGM VALVE (PLANT DESIG

NATION 1823D), RUPTERED, AND LEAKAGE ThPOUGH A SMALL CRACK IN THE BONNETRESULTED. A STEEL BOX WAS PLACED ARDUND THE VALVE AND WAS FILLED WITH

FURMANITE TO EFFECT TEMPORARY REPAIRS. PEPFANENT REPAIRS WILL BE ACCOMPLISHED AT THE NEXT DUTAGE OF SLFFICIENT DLRATION.

160

UCENSFE EVENT REPORTS

COMPONENT MANUFACTURER DOCKET NO.COMPCNENT/ COMPONENT SUBC0CE LER NO.CAUSE CODE /CAUSE SUBCOCE CONTROL NO. EVENT DATEFACILITY / SYSTEM SUPPLIER REPCRT DATE EVENT CESCRIPTIONMETHOD OF DISCOVERY NSSS / A/E PEPORT TYFE CM'sr frSCRIPTION

GRINNELL CORP. 05000251|| 053178 ALTHOUGH THE FRESSURIZER RELIEF TANK (DRT) DRAIN VALVE INDICATED CFEN, TVALVES 78-006/03L-0 C63078 HE FRT WAS NOT DRAINING. NITROGEN FFESSURE IN THE TANK WAS INCREASED TO

DI AFFRAGM 021917 30-CAY AFPROX 80 FSIG P FACILITATE nRAINING. THIS LED TO FAILURE OF ONE OR B0COMPONENT FAILLRE NSSS TH OF THE PRESSLRE PELIEF RUPTURE DISCS. IN THIS CONFIGURATION FLUID EN

MECHANICAL WIST TERING THE TANK FLOW THROLGH THE DISC CPENING TO THE CCNTAINMENT SUMP, ATURKEY POINT-4 BECH N ALTERNATE TO THE NORMAL DRAIN.OTHER COCLANT SUBSYS + CONTROLCPEFATICNAL EVENT TROUELESH00 TING EFFORTS TO DETERMINE WHY ThE PRT WAS NOT CRAINING LED TO

RUPTURE DISC FAILURE. THE FAILURE OCCURRED AT A FRESSURE BELOW THE NORMAL DESIGN RUPTURE PRESSURE.

GRINNELL INDUSTRIAL PIPING IN 0500G213 361878 DURING ROUTINE CHECK, OFERATOR OBSERVED ONE OF THE HYCRAULIC SH0CK SUPPRHANGERS. SUPPORTS, SHOCK.SUPPRSS 78-011/0IT-0 062178 ESSORS ATTACHED TO #4 STEAM GENERATOR FEECWATER PIPING WAS LNCOUPLED WhESNUBBERS 021655 2-WEEK RE THE ATTACHING EYE-BOLT IS TFREACED INTO THE HYCRAULIC PISTON F03. TH

COMPCNENT FAILURE A/E E FEEDLINE IS RESTRAINED BY ONE OTHER hYCRAULIC AND SEVERAL RIGID SUFFORMECHANICAL WEST TS WHICH COULD PROVIDE ADEQUATE MARGIN TO MAXIMUM CALCULATED STRESS DCCU

HADDAM NECK-1 5+W RRING DURING POSTUL/TED EVENTS. FUNCT. LOSS OF ONE RESTRAINT SHOLLD NOTFEECWATER SYSTEMS + CONTROLS RESULT IN SIGNIFICANT INCREASE IN RISK TO PUBLIC HE ALTH CR SAFETY.POUTINE TEST / INSPECTION MINOR DAMAGE INDICATED ONLY THE LAST TWO THREADS ON THE EYE-BOLT WEFE PR

OVIDING COUPLING AT THE TIME OF SEPARATION. NORMALLY THE THREALED FORTION OF THE EYE-BOLT IS SCREWED INTO THE PISTON ROD AND JAM-LOCKED AT A 5HOULDER. NO REASON CAN BE DETERMINED AS TO WHY ONLY TWO THREADS WERE INSERTED. THIS SUPPPESSnP WAS PEPlaCEn AND ALL OTHERS CHECK Or.

HAGAN CORPORATION 0$000295 060976 ' HILL FikFORMING INSIku. SLkWilLLAhlt, fELDnATER FL0n CHANEL, IF-511, SQa

INSTRUMENTATICN + CONTROLS 78-048/03L-0 000878 UARE ROOT EX"RACTOR WAS FOUND OUT OF TOL HIGH BY 6.9 PERCENT. THIS IS NCOMPUTATION MODULE 021449 30-DAY ON-CONSERVAllkE AS PRESENTED IN TABLE 3.1.1 0F THE TECH SPECS FOR LOW 5

COMPONENT FAILURE NSSS EDUNDANT CHANNEL WAS OPERABLE. PREVIDUS LER'S 50-304/77-6,7; 75-7,20; 7ELECTRONIC WEST 4-53.

ZION-1 5+L 74-53.FEACTOR TRIP SYSTEMSROUTINE TEST / INSPECTION DRIFT OF THE CLDCK PULSE FOR THE SQUARL x00T EXTRACTOR, HAGEN S/N FD-221

, WAS THE CAUSE OF THIL DISCREPANCY. THE CLDCK PULSE WAS RECALIBRATED AND THE CHANNEL WAS RETURNED TO SERVICE. INSTRUMENT DRIFTS ARE BEING TRENCED AT ZION STATION. NO FURTHER ACTION IS REQUIRED.

161C0c:.<7'?U?QO

yc.2.310t. 2

LICENSFF EVENT PFPORTS (D

COMP 0NENT MANUFACTURER 00CKIT NO.COMPONENT / COMPONENT SUSC00E LER h0.CAUSE C00E/CAUSE SUBCODE CONTROL NO. EVENT DALE

FACILITY / SYSTEM SUPPLIER REPORT DATE EVEhT DESCRIPTION

METWOD OF Of(COVroy $sss i A/E cfP0kT TYPr ecusE OrsCol' ,

HAMMEL DAHL 05000315 062178 WHILE PERFORMING THE TYPE C LEAK RATE TESi 1HE AS FOUND DATA 0F VARIOUS

VALVES 78-037/03L-0 072178 VALVES INDICATED LEAKACE IN EXCESS OF ACCEPTABLE LIMITS AS IDENTIFIED BY,

GTHER 021769 30-CAY T.S. 3.6.1.2. PREVIOUS OCCURRENCES OF THIS TYPE WERE REPORTED UNDER R0

COMPCNENT FAILURE A/E 050-315-76/23 AND R0 050-0315-77/11.MECHANICAL WEST

D. C. COOK . AEP

CNTNMNT 1 CLATION SYS + CONT THE MA;N 50CRCE CF LEAKAGE CAN BE ATTRIEUTEP TO THE NESW AND CONTAINMENTROUTINE TEST /INSFECTIUN A.fECTED VALVES ON E0TH SYSTEMS WERE REPAIFED WITH SATISPURGE VALVES.

FACTORY PESL1TS, ALTFOUGH A DESIGN CHANGE HAS CEEN SUBMITTED ON THE CONT

AINMENT PURGE VALVES (BUTTERFLY TYPE) REQUESTING REPLACEMENT.

FCRTON PROCESS DIV. 05000220 062878 9URING STE ADY STATE OPERATION, AN INSPECTION OF THE WASTE CONCENTRATOR E

PIPES, FITTINGS 76-026/03L-0 071378 QUIFMENT FOUND NLMEROUS SKALL LEAKS IN SMALL SAMPLE AND INSTRUMENT PIPESLESS THAN 4 INCHES 021714 30-CAY THIS CCNDITION RESULTED IN MINIMAL SAFETY IMPLICATIONS EUT IS REPORTE

CCMPONENT FAILURE LIC 3 PER T.S. 6.9.2S(4).CORROSIGN GE

NINE MILE POINT-1 0

LIQ RAD!0ACT WSTE MANAGMNT SYS THE WASTE CONCENTRATOR SYSTEM, MANUFACTURED BY HPD, INC., USES 304 S.S.SPECIAL TEST / INSPECTION

PORTIONS OF THE SYSTEM EXPOSED TO LOW FLOW AFFEAR TO EXPERIENCE ACCELERATED CORROSION. IDENTIFIED LEAKS WERE REPAIRED AND PLANS ARE CEING MADE

TO PERIODICALLY FLUSH THE CEACLEG PORTIONS OF THE SYSTEM.

IBM CORP C50C0335 N 053078 DLRING STEADY-STATE CFN, THE PLNr COMPUTER EXPER A MALFUNC IN TH2 PROG A

INSTRUMENTATICN + CONTROLS 78-012/03L-0 062778 DDRESS FUNC & WAS TANEN OUT 0F SERV. THIS FESULTED IN CEA PULSE CGUNTIZG POSITION BEING INOPERABLE. IN ACCORDANCE W/ TECH SPEC ACTION STATEMENT

COMPUTATION MCCULE 021E41|30-DAY 3.1.3.3D, OPERATIONS CONTD AND COMPUTER FAILURE WAS CORRECTED. COMPUTE

COMPONENT FAI1URE A/E

ELECTRONIC CEMS R & THE CEA PULSE COUNTING POSITION INDICATION SYS WERE RESTORED TO OPER

MILLSTONE-2 0/EECH ABLE W/IN 3 1/2 HRS. SIMILAR EVENTS WEPE REPORTEC IN LER 77-41/3L. 9/26

CTHR IhST SYS NOT RECD FP .FTf /77.THE COMPUTER DIAGNOSTIC TESTS WERE RUN, BUT THE CAUSE OF THE COMPUTER FA

OPERATICNAL EVENT ILURE COULD NOT BE TRACED TO A SPEC COMP 0NENT. W/THE COMPUTER OUT OF CERVICE, LINEAR FEAT RATE SURV. WAS DONE IN ACCORCANCE W/ TECH SPEC 4.2.1.2UTILIZING THE EXCORE DETECTOR SYS. THE COMPUTER DISK PACKS WERE REPLAC

ED AND NORMAL CGMPUTER OPERATICN WAS RESTORED. I

162


COMPONENT MANUFACTURER DOCKET NO.COMPONENT / COMPONENT SUBCODE LEP. NO.CAUSr CODE /CAUSE SUBCODE CONTROL NO. EVENT CATEFACILITY / SYSTEM SUPPLIER REPORT DATE EVENT CESCRIPTIONMETHOD OF DISCOVERY NSSS / A/E REPORT TYPE CAUSE DESCRIPTION

INGERSOLL-RAND C0 05000315 062078 WHILE FEEDING STEAM GENERATORS DURING UNIT STARTUP, #1 MOTCR DRIVEN * AUX.PUMPS 78-036/03L-0 071278 FEECPLMP FAILED TO ACHIEVE THE MINIMUM DISCHARGE PRESSURE DELINEATED IN

CENTRIFUGAL 021673 30-CAY TECH SPEC 3.7.1.2. ALTHOUGH THIS CCNSTITUTED AN INOP 'EECLATER SOURCE.DESIGN / FABRICATION ERROR NSSS THE TURBINE DRIbEN AND #2 MOTOR CRIVEN AUX FEEDPUMPS WERE OFERAbtl LURI

DESIGN WEST NG REPAIRS TO #1 AUX FEEEPUMP.D. C. C00K-1 AEPFEEDWATER SYSTEMS 4 CONTROLSOPERATIONAL EVENT THE AUX FEEDPUMP FIRST STAGE IMPELLER RING HAD SEPARATED FROM ITS IMPELL

ER. THE FAILED ASSEMBLY WAS SENT TO INGERSOLL-RAND FOR ANALYSIS. ANALYSIS SHOWED CAMAGE IN OTHER STAGES CAUSED BY THE FIRST STAGE SEPARATICN,BLT THE ULTIMATE CAUSE CF FAILURE COULD NOT BE CETEkMINEC. OPE RATIONALRETEST OF THE PFPt ArfwrNT POTATING ASSY. WAS S ATISFACTORY.

INGERSOLL-kAND C0 05000336 032276 DuxlNG noi STA?.Dby, Knx ftMe 1-Rn-F-1A LittL0iED A LEAN AI ini CGhNECTIvPUMPS 78-015/03L-1 081078 N BETWEEN THE SEAL VENT LINE AND THE SEAL CAVITY. PROBASLE CONSEQUENCES

CENTRIFUGAL 020955 30-CAY WERE VERY LIMITED SINCE RHR PUMP 1-PH-.'-1B WAS OPERABLE AT ALL TIMES ANDESIGN / FABRICATION ERROR NSSS D THERE WAS NO REACTOR CORE HEAT THAT WOLED REQUIRE DISSIPATION.

CONSTRUCTION / INSTALLATION WESTNORTH ANNA-1 5+WRESIDUAL HEAT REMOV SYS + CONTROUTINE TEST / INSPECTION THE LEAKAGE WAS DUE TO AN IMPPOPERLY PREPARED THREADED CONNECTION. TFE

CONNECTION WAS REMOVED, CLEANED, THREAD. SEALANT APPLIED AND REPLACED.NO FU9THER LEAKAGE HAS GCCURRED.

INGERSOLL-RAND C0 05000251 052378 THE IN-SERVICE SPENT FUEL PIT COOLING PUMP SHAFT FAILED. SHAFT FAILUREPUMPS 78-005/03L-0 062278 CAUSED THE PUMP MECHANICAL SEAL FACES TO PARTI ALLY OPEN RESULTING IN WAT

CENTRIFUGAL 022063I' 30-D/Y

ER LEAKAGE. ABOUT 50 GALLONS CF WATER HAD LEAKED BEFORE IT COULD EE ISOCOMPONENT FAILURE A/E LATED. THIS WATER CONTAMINATED THE TWO OPERATORS WSO ISOLATED THE PUMP

MECHANICAL WEST AND A SMALL AREA ADJACENT TO THE PUMP R00M. NO OFF-SITE RELEASES OF RADTURKEY POINT-4 BECH 10 ACTIVITY ASSOCIATED WITH THE SPILL.SPENT FUEL P0OL COOL + CLEANUPOPERATIONAL EVENT SPECIFIC CAUSE OF THE SHAFT FAILURE COULD N01 BE CETERMINED BECAUSE BOTH

THE PUMP SHAFT AND BEARINGS SUSTAINED MAJOR DAMAGE. PUMP SHAFT AND BEARINGS REPLACED AND PUMP REBUILT AND TESTED SATISFACTORILY. THE INSTALLED REDUNDANT PUMP PLACED IN SERVICE AND UPERATORS AND AREA SUCCESSFULLY DECONTAMINATED.

163CDt)

';.,

4

N

CT)NN(.1N

LICENSEE EVENT REPORTS m

COMPCNENT MANUFACTURER DOCKET NC.

COMPONENT /CCMPONENT SUECCDE LER NO.CAUSE CODE /CAUSE SUECODE CONTROL NJ. EVENT DATE


PETHOD CF DISCOVERY NSSS / A/F REPrET TYPE rAUSF DF<fRIPTION

ITE IMPERIAL CORPORATICN 050C0338 060678 AN ATTEMPT TO MANUALLY START QUENCH SPRAY FUMP 1-05-P-1A RWST RFCIRCULAT

CIRCUIT CLOSERS /INTEPRUPTERS 78-047/03L-0 CE2878 ION FAILED. T.S.3.6.2.1 REQUIRES TWO INDEPENDENT CONTAINMENT QLENCH SPR

CIRCUIT BREAKER 021665 3D-CAY AY .LE5YSTEMS TO EE OPERABLE.1-05-0-1B WAS AVAILABLE FOR CONTAINMENT QU

COMFONENT FAILURE A/E ENCH SP?AY AND 1-05-P-1A COULD PAVE BEEN STARTED IF ITS EREAkER WAS MANU

OTHER WEST ALEY CLGSED RATFER TNAN REMOTE CLOSED. THE PUELIC HEALTH AND 58 WER

NORTH ANNA-1 5+W E NGT A F F E CT E D.

CNTNMNT HEAT PEMLN SY5 + CONTCPERATIONAL EVENT

A teG3E SibiW, whilGN TO THE QUENCH 5 FRAY FUMP 1A BFEAKER (14H PREV

EFTED TLE -EAk!R FPOM CLOSING PEMOTELY. THE SCFEW WAS PEMOVED . SUBS

ESUtNT TEi! '.G FRONED THAT TuE EFEAkER WUULD CLOSE FE*0TELY CAUSING QUENCH SPPAY i M? 1-CS-P-1A TO 5 TART. TOTAL CCWN TIME FOR 1-QS-P-1A WAS 7.5

WrcasMu i tMr 1-FP-i-1 EECAME INUFERAELE Utt TO TARTER FRCotEM

Is.TCR-vRIvENFIEtCF PCCUREMENT FLOSL EMS,1-FP-P-1 REMAINED INOFERAELE FOR 12IIE IMEERIAL CUEECRAIICN C50C0336 C6Cc76EECAUSECI;CUIT CLOSERS /INTERRLPTE:5 78-CA8/03L-C C71278

DAYS 3 hDLRS 30 MINLTES. INCFERAEILITY GPEATER THAN 7 DAYS 15 GEPORTABSTARTER C21892 || 30-E AY LE LNDER T.5. ICTION STATEMENT 3.7.14.1.A TO SFEC 6.9.2.1. ALTERNATE 50

CCMPCN"NT FAILLRE A/E

iLEC1kICAL WEST LRCES CF FLMPING CAF ACITY WERE AV AIL AELE AT ALL TIMES.

90RTH ANNA-1 5+W

FIRi FROTECTION SYS + CONT TFE CCN'rst CI;(LIT CF tee EFEAKER FAILEC 10 LEENEEGIZE AFTEP CLOSING THOFERATICNAL EVENT E T";tE FrASE CONTACTS CF THE FIPE FUMP MOTOR CAUSING TrE CONTROL CIPCUI

TRY TO CiEELCAD. CEFECTIVE CONTPOL CIRCUIT PART5 WEPE FEPLACEL, THE BPLAVER TESTED, *ND 1-FP-P-1 FEiLFNED TO CEEEAELE STAILS.

--

IlE IMPERIAL CCRFOPATICN CE 7:033 ' s1978 WHILE THE FEATING LNIT FCR THE TPAIN B IGDINE FILIER EANr 1-PV-FL-3B WAS

RELAYS 7 b- C f.E / 02 L - 0 071278 EEING FLACED IN CFEFATIGN, ire FLSE FCR TPE FE ATING LNIT FAILEC, CAUSIN5 AN OFEN CIPCUIT. TECH SPEC STATEMENT J.7.6.1 REQUIRES TbAT TWO SAFEGU

P{ 3C-CAYCCNTPOL, bi,tPAL FLRPOSE C21 CE

ARDS APE A VENTILATION SYSTEMS (5;ss) El CPEPAELE. WITH TFAIN A ELING OPCOMFONENT FAILLPE A/E

ELECTRICAL WEET EFAELE AND CAPASLE OF FANDLING BOTH TPAIN A AND B LOADS, NO DEGPACATION

NCRTH ANNA-1 5+L OF TPE %ENTILATION SYSTEMS FLNCTICN5 WEPE ExFECTED.

AIR CCND. HEAT.Ctet ENT Sv5'E!-FU5E ON TFE FEATING UNIT FAILING WAS THE POWER FELAY'S CEFCALSE FCR ittOPERATICNAL EVENT

ECTIVE C0IL. FLOW OIVERTED FROM T RAIN B TO TRAIN A WITH A MAINTENANCE PEPCRT SUEMITTED TO EEPLACE TFE POWER RELAY ALCNG VITH TML RELAY COIL ANDTFE FEATER FUSE. NO SCHEDULED GP PREVENTIVE ACT!GNS ARE FEQUIGED FOR TFE

F0LE R PLLAY C01' .^

=.~

164

LICENSEE EVENT REPORTS6 I

\'COMPONENT MANUFACTURER DOCKET NO.

COMPONENT / COMPONENT SUBCODE LCR NO.CAUSE CODE /CAUSE SUBCODE CONTROL NO. EVENT DATEFACILITY / SYSTEM SUPPLIER REPORT DATE EVENT DESCRIPi!ONMFTH00 0F DISCOVERY NSSS / A/E PEPORT TYPE CAUSF DESCRIPTION

ITE IMPERIAL CORPORATION 05000267 073178 DURING NORMAL OPERATION THE 4160/480 VOLT, DRY TYPE, TRANSFORMER FEEDINGTRANSFORMERS 78-028/01T-0 081478 480 VOLT ESSENTIAL BUS 1A, FAILED AND CAUGHT FIRE. INTERRHPTABLE INSTRU

SUBCOMPONENT NOT APPLICABLE 022002 2-WEEK MENT POWER BUS IC LOST POWER AND THE MAIN TZRBINE GENERATOR TRIPPED. THECOMPONENT FAILURE NSSS REACTOR WAS MANUALLY SCRAMMED. REPORTABLE PER FORT ST. VRAIN TECHNICAL

ELECTRICAL GGA SPECIFICATION AC 7.5.2(A)7.FT. ST. VRAIN-1 S+LONSITE POWER SYSTEM + CONTROLOPERATIONAL EVENT THE DRY TYPE ITE 4160/480 VOLT SHORTED TURN-TO-TURN IN ONE PHASE OF THE

LOW VOLTAGE WINDINGS. RESULTING FIRE EXTINGUISHED BY PLANT PERSONNEL 05ING PORTABLE FIRE EXTINGUISHERS. TRANSFORMER REPLACED IN KIND.

ITT GRINNELL 05000338 062178 AN INFORMAL VISUAL INSPECTION OF SNUBBER SAE-HSS-252 (LOCATEU ON STEAM DHANGERS, SUPPORTS. SHOCK,5UPPRSS 78-056/03L-0 071278 RIVEN AUX. FEED RJMP EXHAUST PIPING) REVEALED THAT IT WAS INVERTED WITHSNUBBERS 021887 30-DAY HYDRAULIC OIL DRAINED FROM ITS FTSERV0IR. AS PER T.S. 3.7.10, ALL SNUBB

DESILN/ FABRICATION ERROR A/E ERS MUST BE OPERABLE WITH RESERVOIRS AT FUNCTIONAL LEVELS.CONSTRUCTION / INSTALLATION WEST

NORTH ANNA-1 S+WCONDNSATE + FEEDWTR SYS + CONTMETHOD OF DISC. NOT APPLICABLE THE LOCK NUT ON THIS GRINNELL TYPE 201 SNUBBER STRUT EXTENSION BECAME LO

OSE ALLOWING THE SNUBBER TO ROTATE 180 DOWNWARD, THEREBY DRAINING THE RESERVOIR OF HYDRAULIC OIL. THE INOPERABLE SNUBBER WAS REPLACED WITH f.N OPERABLE SPARE UNIT.

.

ITT GRINNELL 05000304 031578 DURING SNUBBER REPLACEMENT FOUND TEN HYDRAULIC SNUBBERS LOCATED INSIDE THANGER 5, SUPPORTS. SHOCK,5UPPRSS 78-040/03L-0 060878 HE PRESSURIZER ENCLOSURE EMPTY OF FLUID. THE $NUBBERS WERE ATTACHED TO

SNUBBERS 021450 30-DAY PRESSURIZER SPRAY AND RELIEF LINES. THESE FAILURES DID NOT CAUSL THE SCOMPONENT FAILURE A/E YSTEMS TO BE IN0PERABLE. THE SNUBBERS ARE DESIGNED FOR SEISMIC AND SEVE

MFCHANICAL WEST RE TRANSIENT EVENT PROTECTION ONLY. PREVIOUS SIMILAR EVENTS (50-295/77-ZION-2 S+L 92).C00LANT RECIRC SYS + CONTROLSROUTINE TEST / INSPECTION HYDRAULIC FLUID PROBABLY LEAKED PAST SEALS DUE TO THE HlCH TEMPERATURE E

NVIRONMENT. ALL SNUBBERS (TWELVE) IN THIS AREA HAVE BEEN REPLACED WITHMECHANICAL (NON-HYDRAULIC) SNUBBEZS. NO FURTHER CORRECTIVE ACTION IS DEEMED NECESSARY.

Cl3 165N" 7;,

N$>E*

(,7NN2N

LICENSEE EVENT REPORTS OI

COMPONCNT MANUFACTURER DOCKET NO.

COMPONENT / COMPONENT SUBCODE LER NO.CAUSE CODE /CAUSE SUBCODE CONTPOL NO. EVENT L./EFACILITY / SYSTEM SUPPLIER REPORT DATE EVENT DESCRIPTION

METHOD OF DISCOVFRY NSSS / A/F PFPORT TYPF CAUSE DESCRIPTION

ITT GRINNELL 05000338 071978 AN INFORMAL VISUAL INSPECTION OF SNUSCER SHP-HSS-472 (LOCATED ON MAIN STHANGERS, SUPPORTS SH0CK,SUPPRSS 78-C64/03L-0 081078 REAM TRIP VALVE TV-MS-101C 3 IN. BY-PASS L?NE) REVEALEC A LOW RESERV0IRSNUBBERS 922059 30-DAY LEVEL. AS PER T.S. 3.7.10, ALL SNUBBERS MUST BE OPERABLE WITH RESERkOI

EESIGN/ FABRICATION ERROR A/E RS AT FUNCTIONAL LE\ELS.MANUFACTURING WEST

NORTH ANNA-1 S+W

MAIN STEAM SUPPLY SYS + CONTSPECIAL TEST / INSPECTION THE FILL PORT PLUG ON THE SNUBBER BODY WAS LOOSE ALLOWING HYDRAULIC OIL

TO LEAK OUT. TEE INOPERABLE SNUBBER WAS REPLACED WITH AN OPERABLE SPAREUNIT.

,

ITT GRINNELL 05000I05 051878 DURING REFUELING, VISUAL INSPECTION OF SNUEBERS PER SURVEILLANCE TEST RE

F ANGERS, SUPPORTS, SHOCK,5UPPRSS 78-020/03L-0 061478 QUIREMENTS REVEALED 2 SNUEBERS WHOSE OPERABILITY WAS QUESTIONED. TFESE SSNUBBERS 021466 30-CAY NUBBERS WERE FUNCTIONALLY TESTE: AND ONE WAS FOUND TO BE INCPERABLE. TH

COMPONENT FAILURE A/E IS PLACED THE FACILITY UNCER LCO TS 3.14.B. THE FAILED SNUBBER WAS ON A

MECHANICAL WEST MAIN STEAM LINE, THEREFCPE, THE ABILITY TO MAINTAIN SAFE SHUTDOWN WOULD

KEWAUNEE-1 PSE NOT HAVE BEEN AFFECTED IF A PIFE FAILLPE HAD OCCURRED DURING A SEISMIC

OTHER ENGNRD SAFETY F ATR SYS EVENT.

ROUTINE TEST / INSPECTION CEGRADED SEALS PERMITTED THE HiCRALLIC FLUID TO LEAK AND DRAIN THE RESERVOIR. THE SEALS WERE REPLACED AND ThE SNUEBER WAS TESTED AND RETURNED T0 SERVICE. TFE VISUAL INSPECTION INTERVAL OF SNLEBERS IN IFE ACCESSIBLE

CATEGORY WILL BE SHORTENED TO 1E-MONTH +/- 255 FER T.S. 4.14.A WITH ONESTEEFP FOUND INffEPATIVE.

III GRIaNELL 05000;05 1 Of0876 ULkING F LsN1 ST AkIUF f kUM ktf LLLIbb A MAIN SILAM SYblLM SNLebth WAb FUUNHANGERS , SUPPORT S ,SH0rv .SLPFRSS 78-C23/03L.0 063078 0 TO BE INOPERARE, PLACING THE F AC. LNDER LCO TS.3.14.E. CCFRECTIVE ACT

SNUBEERS 02If ?S 30-CAY EE INOPERABLE, PLACING THE FACILITY LNEER LCO TS.3.14.B. COPRECTIkE ACT

CGMPONENT FAILLPE A/E ICN VAS COMPLETED WITPIN TbE ALLCWED 72 POURS. SINCE TFE FAILED SNUEBER

MECHANICAL WEST WAS ON A MAIN 7EAM LINE , NO SAFEGUARES FLNCTICNS LOLLD Hair BEEN AFFEC

LEW AUNE E-1 PSE TED IF A PIFE AILUFE FAD OCCLRhiD CLRING A SEISMIC EVENT. TEEFE WAS NOTHER ENGNRD SAFETY FEATR SfS 0 AFFECT GN PLANT CFERATION GR PLPLIC SAFETY.

FAILED SEALS PERMITTED TFE LOSS OF HYERAULIC FLUIC WSICH EPAINED THE EESOPERATIONAL EVENTE R V O I R'. TFF SNUEBER WAS FEPLACEC WITH AN CFERAELE SFAFE. TFE EEMCVED 5'LEEER WILL Ed FEFAIFED. THE INTEFVAL FCF VISUAL INSFECTICN fJ ACCESSIBLE S* UEBERS WILL LE SFORTENED TO 6 MONTHS +/- 15; FEF T.S.4.14. A WITH TWD SNLEBERS FOLND INOFERATIVE DLPING AN INSFECTION INTERVAL.

166 ;


COMPONENT MANUFACTURER DOCKET NO.CUMPONENT/CCMPONENT SUCC00E LER NO.CAUSL CODE /CAUSE SLBCODE CONTROL N0. fVENT DATEFACILITY / SYSTEM SUPPLIER FIPORT DATE EVENT DESCRIPTIONMETHOD OF DISCOVERY NS(S_/,A/E RTPORT TYPE CAUSE DESCRIPTION

ITT GRINNELL 0500028C 070678 DN 7/6/78. DURING ZERO POWER PHYSICS TESTING. WHILE PERFORMING PT-39A, SH)NGIRS. SUPPORTS. SHOCK,5UPPRSS 78-0?0/03L-0 072778 NUBBER l-RH-HSS-10 WAS OBSERVED WITH A 1R BUBBLES SUSPENDED IN RESERVOIR

SNiTBERS 021797 30-PAY FLUID. CLOSE INVESTIGATION REVEALED THAT THE BUBBLES APPEARED TO BE COMIC0ff0NENT FAILURE NSSS ING OUT OF FLUID LINE CONNEC IHE RESERVOIR TO VALVE BLOCK. SINCE UNIT WA

MECHANICAL WEST S NOT AT POWER HEALTH AND SAFETY Of PUBLIC WERE NOT AFFECTED. THIS ISSURRY-1 5+W REPORTABLE IN ACCORDANCE WITH TECH SPEC 6.6.2.B.(2 ).RESIDUAL HEAT REMOV SYS + CONTROUTINE TEST / INSPECTION THE AIR BUBBLES MAY HAVE APPEARED DUE TO THE REDUCED PRESSURE IN CONTAIN

ME NT. HOWEVER, THE SNUBBER WAS REPLACED AS A CONSERVATIVE AND PRUDENT HAINTENANCE PRACTICE.

ITT GRINNELL 0$000281 052278 COMPARISON OF STATION PRINTS WITH "AS BulLT" CONDITION INDICATED THAT TWHANGERS. SUPPORTS SHOCK.SUPPRSS 78-018/03L-0 062178 0 SNUBCERS REQUIRED ON STEAM GENERATOR BLOWDOWN PIPING HAD NEVER BEEN IN

SNUBBERS 021603 30-DAY STALLED. CONDITION REQUIRES REPORT PER T.S.6.6.2.B(2). EXISTING INSTALLDESIGN / FABRICATION ERROR A/E ATION PROVIDED REASONABLE ASSURANCE OF PIPING INTEGRITY S0 THAT HEALTH A

CONSTRUCTION /INSTALATION WEST ND SAFETY OF THE PUBLIC WERE NOT AFFECTED.SURRY-2 S+WSTEAM GEN BLOWDOWN SYS + CONTSPECIAL TEST / INSPECTION FIELD DESIGNED 11SMIC RESTRAINT REQUIREMENTS WERE IDENTIFIED AT THE EN

D OF CONSTRUCTION AND NOT CARRIED OUT TO INSTALLA!!0N. UPON DISCOVERY.THE ARCHITECT ENCINEER PROVIDED DESIGN TEAM TO PROVIDE CORRECTIVE DESIGN

SNUB 3ERS WERE INSTALLED AS REQUIRED.

ITT GRINNELL 05000318 050978 WHILE PERE 0RMING ROUTINE SURVEILLANCE TESTING ON HYDRAULIC SNUBBERS, SAFHANGERS SUPPORTS, SHOCK SUPPRSS 78-012/03L-0 052578 ETY INJECTION $UBBER 2-52-7 WAS FOUND TO HAVE A DRY RESERVOIR DUE TO A '

SNUBBERS 021534 30-DAY LE AK AND WAS DECL ARED INOPERABLE AT 10:00 A.M. , S/9/78, PER T.S.3.7.8.1.COMPONENT FAILURE A/E THE C4UBBER AND RESERVOIR WERE REPLACED WITH TESTED SPARES. THE SNUBBOTHER COMB ER WAS RETURNED TO SERVICE AT 10:15 A.M., S/11/78. LER 77-74 DESCRIBES

CALVERT CLIFFS-2 BECH A SIMILAR LVENT.SYSTEM CODE NOT APPLICABLEROUTINE TEST / INSPECTION THE LEAK WAS APPARENTLY FROM A FAILED 0-RING IN THE CONNECTION BETWEEN T

HE INTEGRAL RESERVOIR AND SNUBBER BLOCK. THE $NUBBER WAS R EPLACED WITHA SPARE AS DESCRIBED AB0VE.

167(?)(S'0,

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COMPONENT MANUFACTURER DOCKET N0.COMPONENT / COMPONENT SUBCODE LER NO.CAUSE CODE /CAUSE SUBCODE CONTROL NO. EVENZ DATEFACILITY / SYSTEM SUPPLIER REPORT DATE EVENT DESCRIPTIONMETHOD OF DISCOVERY NSSS / A/' _ Efr0RT TYPF :AUSE DESCDIPTION

ITT GRINNELL 05000281| 052278 DURING THE COURSE OF VISUAL SNUBBER INSPECTION AT COLD SHUTDOWN ON 4-7-7HANGERS. SUPPORTS, SHOCK,5UPPR55 78-017/03L-0 062178 8. TWO SNUEBERS WERE JUDGED INOPERABLE DU E TO EMPTY RESERVOIRS. THE C0h

SNUBBERS 021604 30-DAY DITION WAS CORRECTED BY REPLACEMENT OF THE UNITS. A RE-REVIEW OF THE TECOMPONENT FAILURE A/E ST DOCUMENT ON 5-22-78 INDICATED THAT THE SNUBBERS SHOULD HAVE BEEN REPO

MECHANICAL WEST RTED AS ITEMS UNDER A LCO. THIS FAILURE TO REPORT IS IN ITSELF REPORTABSURRY-2 5+W LE PER T.S.6.6.2.B(3). THE HEALTH AND SAZETY OF THE GENERAL PUBLIC WERESYSTiM CODE NOT APPLICABLE NOT AFFECTED.ROUTINE TEST / INSPECTION THE CAUSE OF THE INOPERABLE SNUBBERS WAS OIL LEAKAGE. WHILE THE FAILUR

E WAS DOCUMENTED F WAS NOT REPORTED DUE TO ERROR IN REVIEW AND REPORTING PROCEDURES. THE SNUBBERS WERE REPLACED WITH REBUILT UNITS. THE TESTDOCUMENTATION HAS BEEN REWRITTEN TO PROVIDE CLEAR GUIDANCE.

ITT GRINNELL 05000280 060678 DURING REFUELING SiUTDOWN, A SECOND SEQUENCE OF SNUBBER FUNCTIONAL TESTIHANGERS. SUPPORTS. SHOCK,5UPPRSS 78-013/03L-0 070678 IN CARRIED OUT K COMPANY CHOICE RESULTED IN TESTING OF 70 SNUBBERS. SIXSNUBBERS 021694 30-DAY OF WHICH DID NOT MEET "AS FOUND" TEST CRITERI A. THE CONDIDION OF ALL S

COMPONENT FAILURE A/E IX SNUBBERS APPEARED TO HAVE NO EFFECT ON UNITY SAFETY AND ON THE HEALTHMECHANICAL WEST AND SAFETY OF THE PUBLIC. THIS IS REPORTED PER T.S.6.6.2.B(2).

SURRY-1 S+WSYSTEM CODE NOT APPLICABLEROUTINE TEST / INSPECTION THE CAUSE IS ATTRIBUTED TO DRIFT OF THE SETTINGS DUTING UNIT OPERATION.

ALL SNUBBERS WERE ADJUSTED AND PASSED TESTING TO MORE STRINGENT "AS LEFT" CRITERIA.

ITT GRINNELL 05000281 071878 CONDUCT OF VISUL INSPECTION (PT-39) RESULTf D IN 7 SNUBBERS EVALUATED ASHANGERS, SUPPORTS , SHOCK,5UPPRSS 78-027/03L-0 081478 NOT MEETING INSPECTION CRITERIA. THE CONDITION I A DETERMINANT OF FUT

SNUBBERS 021992 30-DAY URE INSPECTION INTERVALS PER T.S. 4.17A AND IS REPORTABLE PER T.S. 6.6.2COMPONENT FAILURE A/E .B(2). THE HEZLTH AND SAFETY OF THE GENERAL PUBLIC WERE NOT AFFECTED.

MECHANICAL WESTSURRY-2 S+WSYSTEM CODE NOT APPLICABLEROUTINE TEST / INSPECTION THE CAUSE IS EVALUATED AS INHERENT TO HYDRAULIC INSTALLATIONS AND AS THE

RESULT OF MORE STRINGENT INSPECTION CRITERIA. ALL DISCREPANCIES FROM THE INSPECTION WERE CORRECTED. THE NEXT INSPECTION INTERVAL IS 62 DAYS PER T.S. 4.17.A.

.

168 .



JOHNSON CONTROLS, INC. 05000305 052278 ON TWO OCCASIONS DURING REFUELING. TRAIN A 0F SHIELD BUILDING VENT (SBV)INSTRUMENTATION + CONTROLS 78-021/03L-0 062178 WOULD NOT DRAW A MEASURABLE VACUUM IN THE ANNULUS WHEN STARTED FOR VARIO

SWITCH 021421 30-DAY US SURVEILLANCE TESTING. THIS PLACED THE FACILITY UNDER LC0 TS 3.6.B.1.COMPONENT FAILURE A/E IN EACH EVENT THE OTHER TRAIN OF SBV WAS OPERATING SATISFACTORILY; THE

OTHER WEST REFORE, THERE WAS NO EFFECT ON PLANT OPERATION OR PUBLIC SAFETY. THIS ISKEWAUNEE-1 PSE THE FIRST SBV FAILURE DUE TO TPE IDENTIFIED CAUSE.OTHER ENGNRD SAFETY FEATR SYSROUTINE TEST / INSPECTION RECIRCULATION FAN EXHAUST CHECK DAMPER FAILED TO OPEN IN EACH CASE. FIR

ST FAILURE DUE TO BROKEN CONNECTOR TO LIGHT BULB 0F PHOTOELECTRIC SWITCHIN STATIC PRESSURE CONTROLLER. SECOND FAILURE RESULTED WHEN PHOT 0 ELECT

RIC SWITCH LIGHT WLB BURNED OUT. CONNECTOR REPAIR / BULB REPLACEMENT CORRFCTFD Tpr poopt FM

JOHNSON CONTROLS, INC. 05000293 061378 ON 6/13/18. BECAUSE OF NRC CONCERNS ON WHY THE STANDBY DILUTION FAN AT lfVALVES 78-026/01T-0 062278 HE MAIN STACK WAS OFF, AN INVESTIGATION WAS CONDUCTED. THIS INVESTIGAT

BUTTERFLY 021639 2-WEEK ION REVEALED THAT BOTH DILUTION FAN BACK DRAFT DAMPERS WERE CLOSED AND TCOMPONENT FAILURE A/E HAT THE STANDBY FAN STARTED WHEN THE CONTROLLER LAS PLACED IN STANDBY. A

MECHANICAL GE REVIEW 0F STATION RECORDS INDICATES THAT THERE HAD BEEN DILUTION FLOW PPILGRIM-1 BECH RIOR TO THIS EVENT (BACK DRAFT DAMPERS NOT POSITIVE SEALING). EFFECTS 0GAS RADI0ACT WSTE MANAGMNT SYS N PUBLIC HEALTH AND SAFETY MINIMAL.OPERATIONAL EVENT THE CAUSE OF THIS EVENT WAS A LOOSE SET SCREW IN THE ACTUATOR LINKAGE ON

THE B DAMPER AND A BLOWN CONTROL FUSE. THE LINKAGE WAS DRILLED AND RETAPED AND THE CONTROL FUSE REPLACED. THE DILUTION FANS WERE CYCLED AND DAMPER OPERABILITY VERIFIED. APPROPRIATE PERSONNEL WILL RECEIVE ADDITIONAL TP_AINING ON DESIPED FLOW INDICATIONS.

JOHNSON SERVICE CO. 05000338 042978 STEAM FLOW TRANSMITIER, PL-1475, WAS ISOLAIED (T.S.3.3.2.1) AND THE CHANPIPES, FITTINGS 78-032/03L-0 052578 NEL, F-1475 PLACED IN THE TRIPPED CONDITION AS PERMITTED BY ACTION STATLESS THAN 4 INCHES 021460 30-DAY EMENT OF TABLE 3.3-3 IN ORDER TO REPAIR A LEAK IN THE INSTRUMENT LINE.

COMPONENT FAILURE A/E THE REDUNDANT CHANNEL, F-1474 WAS OPERABLE.METALLURGICAL WEST

NORTH ANNA-1 5+WMAIN STEAM SUPPLY SYS + CONTROUTINE TEST / INSPECTION ISOLATION OF THE FLOW TRANSMITTER PT-1475 WAS REQUIRED TO REPAIR A LEAK

IN THE INSTRUMENT LINE. THE LINE WAS ISOLATED, REPAIRED (WELDED) AND RETURNED TO SEVICE ON 4-29-78 AT 2200.

4

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COMPONENT / COMPONENT SUBCODE LER NO.




JOHNSON SERVICE CO. 05000338 052978 STEAM FLOW TRANSMIT 1ER, FT-1495, WAS ISOLATED (TS 3.3.2.1) AND THE CHANN

PIPES, FITTINGS 78-042/03L-0 061678 EL, F-1495, PLACED N THE TRIPPED CONDITION AS PERMITTED BY ACTION STATE

LESS THAN 4 INCHES 021501 30-DAY MENT 14 0F TABLE 3.3-3 IN ORDER TO REPAIR A LEAK IN THE INSTRUMENT LINECOMPONENT FAILURE Z/E . SIMILAR OCCURENCE ON 4/29/78 FOR FT-1475. THE REDUNDANT CHANNEL, F-1

METALLURGICAL WEST 494, WAS OPERABLE.

NORTH ANNA-1 S+W

TURBINE BYPASS SYS + CONTROUTINE TEST / INSPECTION ISOLATION OF FLOW TRANSMITTER FT-1495 WAZ REQUIRED TO REPAIR A LEAK IN 1

HE IMST9AMES(T LINE. THE LINE WAS ISOLATED, REPAIRED AND RETURNED TO SER

VICE ON 5/29/78 AT 1527.

L N D, INC. 05000321 060978 WHILE IN COLD SRJTDOWN, A REFUELING FLOOR VENT EXHAUST SENSOR (011-N012A

INSTRUMENTATION + CONTROLS 78-045/03L-0 062978 ) GAVE A FALSE HIGH AND ERRATIC INDICATION DURING THE PERFORMANCE OF REFSENSOR / DETECTOR / ELEMENT 021724 30-DAY UELING F'_00R FXHAUST VENT RADIATION MONITOR SYSTEM CALIBRATION. AT THE

COMPONENT FAILURE NSSS TIME GF THE ERR 0NEOUS SIGNAL IN CHANNEL "A", CHANNEL "B" WAS AVAILABLE A

ELECTRONIC GE ND OPERABLE.

EDWIN I. HATCH-1 SSC/BECHAIRBORNE RADI0ACT MONITOR SYSROUTINE TEST / INSPECTION THE SENSOR WAS CAUSING A FALSE HIGH AND ERRATIC INDICATION BECAUSE THE G

-M TUBE FAILED. THE G-M TUBE WAS REPLACED AND THE SYSTEM CAllBRATION WA5 PERFORMED SATISFACTORILY. THE TUBE WAS A G011 G-M TUBE (P.N.167A2554G001)

LAMBDA ELECTRONICS 05000336 052078 DURING ROUTINE SURVL TESTING OF CEA'S, CEA #8 FAILED TO MOVE FROM THE F

INSTRUMENTAT. a + CONTROLS 78-011/03L-U 061978 ULLY WITHDRAWN 10 SIT 10N & WAS SUBSEQUENTLY DECLARED INOPERABLE. REPAIRS

POWER SUPPLY 021642 30-DAY WERE MADE TO TE CEA DRIVE SYS & THE CEA WAS RESTORED TO OPERABLE. STA

COMPONENT FAILURE LIC TUS W/A TOTAL INOPERABLE f!ME OF 30 MIN. THERE ARE NO PROBABLE CONSEQ 0

ELECTRICAL COMB F THIS EVENT SINCE THE PLANT WAS OPERATED IN ACCORDANCE WITH ACTION STAT

MILLSTONE-2 0/BECH EMENT C OF SEC 3.1.3.1 0F THE TECH SPEC & CEA NUMBER 8 WAS CAPABLE OF BE

REACTIVITY CONTROL SYSTEMS ING TRIPPED.CEA #8 FAILED TO MOVE BECAUSE ITS CEA DRIVE SYS TIMER MODULE HAD BEEN DAROUTINE TEST / INSPECTION MAGEZ BY HIGH VOLTG FROM THE TIMER POWER SUPPLY, A LAMBDA UNIT MODEL LCD

-A-22. BOTH TIMER MODULE & POWER SUPPLY WERE REPLACED. THE CAUSE OF THE HIGH VOLTAGE FROM THE POWER SUPPLY 15 UNKNOWN, BUT EACH Of THE REMAINI

|NGUNITSWASCHECKEDFORSIMILARPOTENTIALFAILURESW/NEGRESULTS.

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COMPONENT MANUFACTURER DOCKET NO.COMPONENT / COMPONENT SUBCODE LER NO.CAUSE CODE /CAUSE SUBCODE CONTROL NO. EVENT DATEFACILITY / SYSTEM SUPPLIE? REPORT DATE EVENT DESCR IPTIONMETHOD OF DISCOVERY NSS$ / A/r PEPORT TYPE CAUSE DESCRIPTION

LAYNE-BOWLER INC 05000331 062278 DURING SURVEILLANCE TESTING "A" RHR SERVICE WATER SYSTEM PUMPS 1P-22A ANPUMPS 78-034/03L-0 072178 D IP-22C DID NOT DEVELOP THE REQUIRED DISCHARGE PRESSURE AT RATED FLOW.

CENTRIFUGAL 021865 30-DAY THE "B" RHR SERVICE WATER SYSTEN WAS TESTED WITH SATISFACTORY RESULTS.COMPONENT FAILURE A/E OPERABILITY REQUIREMENTS ARE LISTED IN TECHNICAL SPECIFICATION SECTION

MECHANICAL GE 3.5.C.I.DUANE ARNOLD BECHRESIDUAL HEAT REMOV SYS + CONTROUTINE TEST / INSPECTION NORMAL PUMP WEAR HAD CAUSED EXCESSIVE CLEARANCES TO DEVELOP BETWEEN THE

PUMP IMPELLER AND CASING WEAR RINGS. IP-22A AND 1P-22C ARE LAYNE-BOWIER MODEL 16EHH CENTRIFUGAL PUMPS. THE PUMP IMPELLORS WERE ADJUSTED AND THE PUMPS TESTED WITH SATISFACTORY RESULTS. NO FURTHER CORRECTIVE ACTION

PLANNED.LEEDS & NORTHRUP CO. 05000325 052378 DURING A ROUTINE CHECK OF CHLORIDE INTRUSION MONITOR CO-CIS-3075-1 THE

INSTRUMENTATION + CONTROLS 78-058/03L-0 062178 MONITOR WAS FOUND TO BE OUT OF ALLOWABLE CALIBRATION LIMITS. WHEN THEINDICATOR 021487 30-DAY CELL WAS REMOVED FOR CHANNEL CALIBRATION, THE MONITOR WAS FOUND DEFECTIV

COMPONENT FAILURE A/E E AND COULD NOT BE REPAIRED BEFORE THE CONDENSATE SYSTEM WAS PRESSURIZEDELECTRONIC GE FOR A REACTOR STARTUP. (TECH SPEC ALLOWS STARTUP UNDER THESE CONDITION

BRUNSWICK-1 UEC S). TECH SPEC 3.15.6CONDNSATE + FEEDWTR SYS , CONT

ROUTINE TEST / INSPECTION A PRINTED WIRING BOARD IN THE MONITOR WAS DEFECTIVE CAUSING THE UNIT TOBE OUT OF CALIBETION. THE WIRING BOARD WAS REPLACED AND THE MONITOR WASCALIBRATED SUCCESSFULLY WITH A KNOWN CHLORIDE SOLUT'ON. THE CONDUCTIVI

TY CELL WILL BE PLACED BACK INTO THE CONDENSATE DISCH/.RGE HEADER, & THECHANNEL DECLARED OPEPATIONAL.

LIMITORQUE CORP. 05000254 050478 AT APPROXIMATELY 2100 HOURS ON MAY 4, 19 % , WHILE PERFORMIhG THE HIGH FRCIRCUIT CLOSERS / INTERRUPTERS 78-017/03L-0 060278 ESSURE COOLANT NJECTION (HPCI) MONTHLY VALVE OPERABILITY SURVEILLANCE T

SWITCH (OTHER THAN SENSOR) 021436 30-DAY EST ZOS 2300-3 THE IPCI PUMP SUCTION VALVE FROM THE CONTAMINATED CONDENCOMPONENT FAILURE NSSS SATE STORAGE TANK (CCST) M0-1-2301-6 WOULD NOT CLOSE. THE VALVE COULD B

NATURAL END OF LIFE GE E OPENED. HPCI WAS NOT RENDERED INOPERABLE SINCE THIS VALVE IS NORMALLYQUAD CITIES-1 S+L OPEN DURING REACTOR OPERATION, AND CHECK VALVE 1-2301-20 PROVIDES ISOLAEMERG CORE COOLING SYS + CONT TION OF THE SUPPRESSION CHAMBER FROM THE CCST.ROUTINE TEST / INSPECTION THE HPCI MO 1-2301-6 VALVE FAILED DUE TO IMPROPER OPERATION OF THE TORQ

UE SWITCH. THE TORQUE SWITCH WAS FOU ND TO BE WORN OUT. THE HPCI VALVEOPERATOR IS A IIMITORQUE MODEL SMB-0. THE CORRECTIVE ACTION TAKEN TO REPAIR THE HPCI MO 1-2301-6 VALVE WAS TO INSTALL A NEW TORQUE SWITCH AND

GPERATE THE VALVE 3 TIMES AS DOCUMENTED BY WORK REQUEST 2283-78.

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LICENSEE EVENT REPORTS NWL




PFTHOD OF DYSCOVFRY N999 / A/F DFPORT TYPE CAUSF DFSCPIPTION

LIMITORQUE CORP. 05000249 060678 DURING NORM OPNS WHILE PERFORMING LPCI VALVE OPERABILITY SURV, M03-1501-

VALVE OPERATORS 78-026/03L-0 063078 28B VALVE WAS BEING CYCLED. BOTH INDICATING LIGHTS WENT Ol' AND THE MOTELECTRIC MOTOR - AC 021679 30-DAY OR STOPPED. NO SAFETY SIGNIFICANCE, SINCE THE A LPCI CONTAINMENT SPRAYS

COMPONENT FAILURE NSSS WERE OPERABLE, AND TECH SPEC 3.5. A.6 STATES ONE LOOP MAY BE INOPERABLE

MECHANICAL GE FOR 30 DAYS. NO PREVIOUS REPORTABLE EVENTS OF THIS TYPE.DRESDEN-3 5+LCNTNMNT HEAT REMOV SYS + CONTROUTINE TEST / INSPECTION A DEFECTIVE SHAFT PIN ON THE TORQUE SWITCH WAS THE CAUSE OF FAILURE OF Z

03-1501-288. SHAFT PIN WAS REPLACED.

LIMITORQUE CORP. 05000301 061678 FOLLOWING VALVE CYCLING DURING AN INSERVICE TEST. THE STARTER BREAKER OVVALVE OPERATORS 78-007/03L-0 071478 ERLOADS FOR 1 0F 2 CONTAINMENT SPRAY VALVES (2-MOV-860C) IN 1 0F 2 TRAIN

ELECTRIC MOTOR - AC 021766 30-DAY S TRIPPED. TECH. SPEC. 15.3.3.B.2.C, PERMITS ONE VALVE IN THE CONTAINME

COMPONENT FAILURE NSSS NT COOLING SYSTEM TO BE INOPERABLE FOR UP TO 24 HOURS. EVENT MAY BE RELMECHANICAL WEST ATED TO LER NO. 78-005/03L-0.

POINT BEACH-2 SECH

CNTNMNT HEAT RLMOV SYS + CONTROUTINE TEST' INSPECTION THE STARTER OVERLOADS LERE IMMEDIATELY RESET. THE VALVE WAS RECYCLED WI

TH THE OVERLOADS TRIPPING AGAll. THE CAUSE WAS A FAULTY LIMITORQUE MODEL SMB-00 TORQUE SWITCH WHICH W15 REPLACED.

LIMITORQUE CORP. 05000333 072278 WHILE PERFORMINC ROUTINE TESTING ON CORE SPRAY OUTBOARD INJECTION VALVE

VALVE OPERATORS 78-056/03L-0 080478 14-MOV-11B, THE VALVE WOULD NOT CLOSE WHEN GIVEN A '' CLOSED" SIGNAL.

ELECTRIC MOTOR - AC 021924 30-]AYCOMPONENT FAILURE NSSS

ELECTRICAL GE

FITZPATRICK-1 5+W

EMERG CORE COOLING SYS + CONTRDUTINE TEST / INSPECTION LIMITORQUE SETTING NEEDED TO BE ADJUSTED ON VALVE 14-MOV-118. INBOARD V

ALVE 14-MOV-12B WAS VERIFIED OPERABLE AND SHUT. THE POSITION WILL BE CHECKED ON A DAILY BASIS.

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COMPONENT MANUFACTURER DOCKET NO.COMPONENT /CCMPONENT SUBCODE LER NO.CAUSE CODE /CAUSE SUBCODE CONTROL NO. EVENT DATEFACILITY / SYSTEM SUPPLIER REPORT DATE EVENT DESCRIPTIONMETHOD OF DISCOVERY NSSS / A/E REPORT TYPE CAUSF DESCRIPTION

LIMITORQUE CORP. 05002770061278 DURING STARTUP OPERATIONS INBOARD MAIN STEAM LINE DRAIN ISOLATION VALVEVALVE OPERATORS 78-030/03L-0 062378 (MO-2-74) FAILED TO RESPOND TO A CLOSE SIGNAL FROM THE CONTROL R00M HAND

ELECTRIC MOTOR - AC 021482 30-DAY SWITCH. THE REDUNDANT OUTBOARD ISOLATION VALVE WAS PLACED IN THE CLOSEDCOMPONENT FAILURE NSSS POSIT 0N. DAILY VERIFICATION AND RECORDING OF THE OUTBOARD VALVE POSITI

ELECTRICAL GE ON WAS 'NTTIATED IN ACCORDANCE WITH THE REQUIREMENTS OF TECH SPECS 3.7.0PEACH BOTTOM-2 BECH 2 AND 4.7.D.2. SAFETY SIGNIFICANCE IS MINIMAL.MAIN STEAM ISOL SYS + CONTROLSOPERATIONAL EVENT ELECTRICAL CHECKS INDICATED THAT LIMITORQUE SMB-000 TORQUE SWITCH ON ISO

LATION VALVE MO-2-74 WAS DEFECTIVE. THE VALVE WAS ELECTRICALLY CLOSED FROM THE MOTOR CONTROL CENTER BY BYPASSING THE TORQUE SWITCH. THE DEFECTIVE TORQUE SWITCH WILL BE REPLACED DURING THE NEXT SCHEDULED OUTAGE.

LIMITORQUE CO,.P. 05000333 061678 AT APPROXIMATELY NOON THIS DATE, ARCHITECT ENGINEER INFORMED THE AUTH0RVALVE OPERATORS 78-043/01T-0 062378 ITY THAT THREE MOTORS ON MOTOR-OPERATED ISOLATION VALVES LOCATED WITHINOTHER 021495 2-WEEK THE CONTAINMENT MAY BE ENVIRONMENTALLY QUALIFIED TO 250 DEGREES F FOR OP

DESIGN / FABRICATION ERROR A/E ERATION INSTEAD OF THE APPR0XIMATE 295 DEGREES F MAXIMUM WHICH COULD OCCDESIGN GE UR DURING A DESIGN BASIS LOSS OF COOLANT ACCIDENT (LOCA). DURING A RESE

FITZPATRICK-1 S+W ARCH OF ENGINEERING DATA CONCERNING MOTOR-0PERATED VALVES THESE WERE THEREAC CORE ISOL COOL SYS + CONT ONLY THREE IDENTIFIED AS BEING QUALIFIED TO THE LOWER TEMPERATURE.EXTERNAL SOURCE THE CAUSE HAS NOT YET BEEN DEFINED. EQUIPMENT WILL BE REPLACED OR MODIF

IED AS REQUIRED.

LIMITORQUE CORP. 05000331 121577 DURING A ROUTINE PLANT INSPECTION, IT WAS DETERMINED THAT THE RHR CROSSVALVE OPERATORS 77-094/01T-1 062778 TIE VALVE WAS IN THE CLOSED POSITION WHEN THE VALVE POSITION LIGHTS INDI

ELECTRIC MOTOR - AC 019967 2-WEEK CATED OPEN IN THE CONTROL ROOM. SUBSEQUENT INVESTIGATION DETERMINED THADESIGN / FABRICATION ERROR NSSS T MOTOR OPERATED PROPERLY BUT VALVE DID NOT MOVE. MANUAL HAND WHEEL ALS

MANUFACTURING CE O TURNED FREELY. VALVE IS NORMALLY OPEN AND REQUIRED FOR LPCI INJECTIONDUANE ARNOLD BECH CAPABILITY TO EITHER RECIRC LOOP. VALVE WAS MANUALLY LOCKED IN OPEN POSRESIDUAL HEAT REMOV SYS + CONT ITION PENDING RECEIPT OF REPLACEMENT PARTS.OPERATIONAL EVENT INSPECTION OF OPERATOR INTERNALS REVEALED FRACTURED TEETH ON WORM & WORM

GEAR. VENDOR DETERMINED BRITTLE FAILURE DUE TO OVERHARDENING DURING MANUFRACTURE. METALLURGICAL ANALYSIS DETERMINED WORM OVER-CARBURIZED. RESULT

OF CARBURIZING FURNACE OPERATOR ERROR. PER VENDOR, RANDOM PROBLEM. AUTO

PROCESS NOW 'JSEU. WORM & WORM GEAR REPLACED. LIMITORQUE TYPE SMB-1.

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COMPONENT MANUFACTURER 00CKET N0.COMPONENT / COMPONENT SUBCODE LER NO.CAUSE CODE /CAUSE SUBCODE CCNTROL NO. EVENT DATE'FACILITY / SYSTEM SUPPLIER REPORT DATE EVENT DESCRIPTION

METHOD OF DISCOVERY NSSS / A/E PEPORT TYPE CAUSE DESCDIPTION

LUNKENHEIMER CO., THE 05000267 050278 "A" INSTRUMENT AIR RECEIVER WAS TAKEN OUT OF SERVICE TO REPAIR 2 VALVESVALVES 78-014/03L-0 060178 THAT LEAKED PAST THEIR SEATS. THIS CONSTITUTES OPERATION UNDER A DEGRAGATE 021415 30-DAY DED MODE PERMITTED BY LC0 4.3.6 AND IS REPORTABLE PER FORT ST. VRAIN TEC

COMPONENT FAILURE NSSS HNICAL SPECIFICATION AC 7.5.2(B)2. THERE WERE NO SIGNIFICANT OCCURRENC

OTHER GGA ES AS A RESULT OF THIS ACTION. THERE WAS NO ADVERSE AFFECT ON THE PUBLIFT. ST. VRAIN-1 5+L C HEALTH OR SAFETY.COMPRESSED AIR SYSTEMS + CONTOBSERVATION / EVALUATION RESIDUE BUILDUP ON THE SEATS OF NORMALLY OPEN, MANUAL VALVES V-82493 AND

V-8235. V-82493 IS A 3", 150 PSI, STEEL, GATE, MODEL T 1150 WA MANUFACTURED BY LUNKENHEIMER COMPANY. V-8235 IS A 3", 150 PSI, STEEL, GATE MODE

L 31-1-BW MANUFACTURED BY WALWORTH COMPANY. THE VALVE SEATS WERE CLEANF0 AND REFINISHED. AND THE VALVES TESTED SATISFACTORILY. I

LUNKENHLIMER CO., THE 05000267 062278 1B IN5TRUMENT AIR RECEIVER WAS TAKEN OUT OF SERVICE TU REFAls Tw0 kALVE5VALVES 78-023/03L-D 072178 THAT LEAKED RST THEIR SEATS. THIS CONSTITUTES OPERATION UNDER A DEGRAGATE 021895 30-DAY DED MODE PERMITTED BYC0 4.3.6 AND IS REPORTABLE PER FORT ST. VRAIN TEC

COMPONENT FAILURE NSSS HNICAL SPECIFICATION AC 7.5.2(B)2. THERE WERE NO SIGNIFICANT OCCURRENCEOTHER GGA 5 AS A RESULT OF THIS ACTION. THERE WAS NO ADVERSE EFFECT ON THE PUBLIC

FT. ST. VRAIN-1 S+L HEALTH OR SAFETY.

CCMPRESSED AIR SYSTEMS + CONTROUTINE TEST /INSPErT vN RESIDUE BUILDUP ON SEATS OF NORMALLY OPEN, MANUAL VALVES V-82492 & V-824

45. V-82492 IS A 4", 150 PSI, STEEL GATE, MODEL 1503C-63-004, MFG BY LUNKENHEIMER CO. V-82445 IS A 3",150 PSI, STEEL GATE, MODEL 5202-WE. MFG BY WALWORTH CO. VALVE SEATS WERE CLEANED & REFINISHED, & VALVES TESTED 5ATf(FACTODffY

MANNING-MAXWELL-M0 ORE 05000285 040878 UPDATE REPORT - PREVIOUS REPORT DATED MAY 8,1978. TAE WELD ON THE SUCT

VALVES 78-011/03L-1 052278 ION HEADER RELIEF VALVE (CH-219) ON HEADER FOR THE CHARGING PUMPS DEVEOTHER 021118 30-DAY LOPED A SMALL LEAK ALLOWING LEf KAGE FROM THE SYSTEM INTO ROOM 7. THE CH

DESIGN / FABRICATION ERROR A/E ARGING SYSTEM IS OPERABLE, THEREFORE TECH SPEC 2.2 REQUIRES ARE SATISF1

DESIGN COMB ED. LEAKAGE E DROP-WISE, WELL WITHIN LEAKAGE SPECIFICATIONS AND PRESEN

FT. CALHOUN-1 GHDR TS NO ABNORMAL AIRBORNE ACTIVITY PROBLEM.CHEM, VOL CONT + LIQ POISN SYSOPERATIONAL EVENT THE WELD CRACKED DUE TO VIBRATION OF THE PIPING IN SERVICE. THE HEADER

WAS FREEZE-SEALED, THE WELD GROUND OUT AND REWELDED USING CERTIFIED WELD

PROCEDURES AND MATERIAL. THE WELD WAS itYDR0 STATICALLY TESTED AND RETURNED TO FULL SERVICE.

174

UCENSEE EVENT REPORTS

COMPONENT MANUFACTURER DOCKET N0.COMPONENT / COMPONENT SUBCODE LER NO.CAUSE CODE /CAUSE SUBCODE CONTROL NO. EVENT DATEFACILITY / SYSTEM SUPPLIER REPORT DATE EVENT DESCRIPTIONMETHOD OF DISCOVERY NSSS / A/E PEPORT TYPE CAUSE DESCRIPTION

MARATHON ELEC MFG 05000263 052578 WHILE PERFORMING WEEKLY SURVEILLANCE TEST ON #11 SBGT, THE INLET AIR HEACIRCUIT CLOSERS / INTERRUPTERS 78-008/03L-0 062378 TER WAS FOUND TO BE OPERATING AT REDUCED CAPACITY DUE TO FUSE FAILURE.OTHER 021753 30-DAY 15KW OR GEATER HEATER CAPACITY REQUIRED BY TECHNICAL SPECIFICATION 3.7.

COMP 0NENT FAILURE A/E B. SIMILAR OCCURRENCE EXPERIENCED WITH #12 SBGT, SEPT. 29, 1973, A0 REPELECTRICAL GE ORT r37. #12 SET WAS OPERABLE AT TIME OF OCCURRENCE. NO EFFECT ON HEA

MONTICELLO-1 BECH LTH OR SAFETY OF FUBLIC.CNTNMNT AIR PURI + CLEANUP SYSROUTINE TEST / INSPECTION INVESTIGATION REVEALED THAT BUSS NOS 30 AMP CARTRIDGE TYPE FUSE FAILED D

UE TO OVERHEATING CAUSED BY HIGH CONTACT RESISTANCE AT FUSE CLIP. MARATHON TYPE 6F30A38, 600 VOLT, 30 AMP, FUSE BLOCK. FUSE BLOCK AND FU",ES REPLACED IN KIND. CLIP CLAMPS WILL BE INSTALLED ON BOTH TRAINS TO PREVEN

T PECURRENCE OF PP0ELEM.MAROTTA SCIENTIFIC CONTROLS IN 05000298 042378 DURING ROL ;1NE SURVLILLANCE TEST 6.3.10.2, MARR0TTA FVL-16D EXCESS FLOW

%ALVES 78-021/03L-0 051778 CHECK VALVE FAILED TO FUNCTION CORECTLY. TECHNICAL SPECIFICATIONS, SECHECK 021620 30-CAY CTION 3.7.D. REQUIRES MARKED DECREASE IN OBSERVED FLOW RATE DURING TEST

COMPONENT FAILURE LIC ING TO BE ACCEPTABLE. EVENT 77-57 IS OF A SIMILAR NATURE. THERE WAS NOMECHANICAL GE EFFECT UPON PUBLIC HEALTH OR SAFETY. THE REDUNDANT RESTRICTING ORIFICE

C00PER-1 B+R WAS OPERABLE. THERE WERE NO OTHER SAFETY IMPLICATIONS.CNTNMNT ISOLATION SYS + CONTROUTINE TEST / INSPECTION THE CAUSE OF THE VALVE'S FAILURE TO CHECK FLOJ HAS BEEN ATTRIBUTED TO CR

UD BUILDUP ON THF POPPET ASSEMBLY. THE EXCESS FLOW VALVE IS L" MARR0TTAMODEL FVL-16D. THE VALVE POPPET ASSEMBLY WAS REPLACED AT THE TIME THE

EVENT WAS NOTED. TINCE THIS SENSING LI'c 15 M LONGER USED THE ROOTVALVE NAS BFEN LOCVED TO

MICR0 SWITCH 05000293 050678 ON MAY 8,1978 WHLE h 'F0kMING SURVEILLANCE 8.7.4.5 (PRIMARY CONTAINMEINSTRUMENTATION + CONTROLS 78-024/03L-0 060678 NT ISOLATION VALVES),1FE FOLLOWING VALVE'S OPERABILITY COULD NOT BE VER

SWITCH 021424 30-DAY IFIED BECAUSE OF LACK OF IW'ATION: OXYGEN ANALYZER VALVES CV-5065-10,COMPONENT FAILURE A/E 15, 16 AND 17: "" ACTOR WATok SAMPLE VALVES A0-220-44 AND 45; AND PRIMCORROSION GE ARY CONTAINMENT EXtAUST VALVE 5044B. A MAINTENANCE REQUEST WAS ISSUED T

PILGRIM-1 BECH 0 INVESTIGATE AND REPAIR AND AT LEAST ONE VALVE IN EACH LINE HAVING AN ICNTNMNT ISOLATION SYS + CONT NOPERABLE VALVE WAS VERIFIED TO BE IN THE ISOLATED CONDITION.ROUTINE TEST / INSPECTION CORROSION BUILDUP ON THE OXYGEN ANALYZER VALVE STEMS CAUSED SLUGGISH OPE

RATION AND CYCLING FREED THEM AND OPERABILITY REQUIREMENTS WERE MET. AMONTHLY TEST FREQUENCY WILL BE ESTABLISHED TO EVALUATE THESE VALVES. ABROKEN LIMIT SWITCH ARM WAS FOUND UN A0-5042b and replacez. ao-220-44 AND 45 ARE INACCESSIBLE AND WILL BE CHECKED DURING NEXT SCHEDULED OUTAGE.

._

m 175

NON4

i.D

LQc:Nt.tiN

LKENSEE EVENT REPORTS m

COMPONENT MANUFACTURER DOCKET NO.COMPONENT / COMPONENT SUBCODE LER NO.CAUSE CODE /CAUSE SUBCODE CONTROL NO. EVENT DATE

FACILITY / SYSTEM SUPPLIER REPORT DATE EVENT DESCRIPTIONMETHOD OF DISCOVERY NSSS / A/F REPORT TYPE CAUSE DESCRIPTION

MICR0 SWICH 05000293 071178 ON JULY 11, 1978 WHILE PERFORMING STANDBY GAS TREATMENT INITI ATION ANDINSTRUMENTATION + CONTROLS 78-036/03L-0 080978 REACTOR BUILDING ISOLATION LOGIC TESTING, SUPPRESSION CHAMBER PURGE EXHA

INDICATOR 021930 30-DAY UST VALVE A0-5042A CID NOT CLOSE COMPLETELY AS INDICATED BY THE POSITIONCOMPONENT FAILURE A/E INDICATION LIGHTS IN THE CONTROL R0]M. THE REDUNDANT VALVE (AO-5042B) D

ELECTRICAL GE ID FUNCTION PROPERLY AND CONTAINM'.NT ISOLATION WOULD HAVE OCCURRED IF REPILGRIM-z BECH QUIRED.CNTNMNT ISOLATION SYS + CONTROUTINE TEST / INSPECTION SUBSEQUENT INVESTIGATION REkEALED NO APPARENT CAUSE FOR THIS EVENT. ON

AUGUST 7,1978. DURING OPERABILITY TESTING OF PCIS VALVES, A0-5042A WASOBSERVED TO STROKE FULLY WITHIN THE ALLOWABLE TIME INTERVAL. THE STANDBY GAS TREATMENT INITIATION AND REACTOR BUILDING ISOLATION TESTING WAS RLSCHEDUtFD TO VERIFY ACCEPTANCE WITH NO UNE XPL AINED DESCRIPANCIE S.

NAMCO CONTROLS 05000298 042578 DURING PERf 0RMANCL OF MSIV SURVLILLANLL IL51 6.2.2.7.1, LIMll $WilLHL$ AINSTRUMENTATION + CONTROLS 78-022/03L-0 052378 . C, AND D DID NOT FUNCTION AS PER TECH. SPEC. TABLE 3.1.1. THE REACTOR

SWITCH 021618 30 CAY M0CE SWITCH WAS IN SHUTDOWN. THEREFORE THE SCRAM ASSOCI ATED WITH THECOMPONENT FAILURE NSSS SUBJECT SWITCHES WAS BYPASSED. THIS IS CONSIDERED AN OPLRABLE SYSTLM.

MECHANICAL GE THERE WAS NO AFFECT ON THE PUBLIC HEALTH AND SAFETY.C00PER-1 B+R

MAIN STEAM ISOL 3YS + CONTROLSROUTINE TEST / INSPECTION THREE NAMCO SL3MLZ LIMIT SWITCHES MALFUNCTIONED. IT IS BELIEV.D AN ACTU

ATING SPRING IN THE SWITCHES TOOK A SET AND WOULD NOT TOTALLY CTUATE THE SWITCHES INITIALLY IN A COLD CONDITION WITHIN THE PRESCRIBED TECH. SPEC

. LIMITS. IDENTICAL SWITCHES INSTALLED. NEW DESIGN SWITCH IS UNDER EVALUATION.

NELSON ELECTRIC 05000338 021618 DURING COLD SHUTDOWN CONSTRUC10N PLRSONNEL Dl5LOVERLD lhL Ab5LNLL OF 00HANGERS. SUPPORTS SHOCK,5UPPRSS 7E-007/01T-1 061478 ORWAY AND SEISMIC EkACING ON NINE UNIT NO.1 HE AT TRACING CONTROLLER CAB

OTHER 020605 2-WEEK INETS.DESIGN / FABRICATION ERROR A/E

CONSTRUCTION / INSTALLATION WESTNORTH ANNA-1 5+WOTHER ENGNRD SAFETY FEATR SYSEXTERNAL SOURCE DUE TO AN OVERSIGHT BY CONSTRUCTION PERSON 2 L, THE BRACES WEREN'T ATTACH

ED AFTER CABINET INSTALLATION. CORRECTIVE ACTION WILL CONSIST OF PLACEMENT OF THE BRACES, AS REQUIRED.

I

175

,

4


COMPONENT MANUFACTURER DOCKET NO.COMPONENT / COMPONENT SUBCODE LER NO.CAUSE CODE /CAUSE SUBCODE CONTROL NO. EVENT DATEFACILITY / SYSTEM SUPPLIER REPORT DATE EVENT DESCRIPTIONMFTHOD OF DISCOVERY NSSS / A/E RFPORT TYPF CAUSF DFSCRIPTION

E C LABORATORIES 05000318 070478 AT 0440 CHANNEL C OF THE REACTOR PROTECTION SYSTEM (RPS) STARTED ISSUINGI!!STRUMERTATION + CONTROLS 78-020/03L-0 072078 SMOKE FROM THE RPSCIP PANEL AND TRIPS APPEARED ON SEVERAL TRIP CIRCUITS

INDICAT01 021846 30-DAY THE TRIPS FOR CHANNEL B WERE BYPASSED FOR CALIBRATION. UPON DISCOVERCOMPONENT FAILURE NSSS Y OF SMOKE THE OPERATOR UNBYPASSED CHANNEL B AND PLACED ALL CHANNEL C TR

ELECTRON K COMB IPS IN BYPASS PER T.S.3.3.1.1. RPS CHANNELS A AND D RIMA!NED IN OPERATICALVERT CLIFFS-2 BECH ON. TFIS IS NOT A REPETITIVE OCCURRENCE.ENGNRP SAFETY FEATR INSTR SYSOPERATIONAL EVENT ZENER DIODE FAILED IN THE REGULATING CIRCUIT FOR THE CHANNEL C RPSCIP DV

M RESULTING IN A FAILURE OF A 120/28V TRANSFORMER. THE DIODE AND iRASFORMER WERE REPLACED AND RPSCIP WAS RETURNED TO SERVICE. NO FUPTnER CORRECTIVE ACTION IS NECESSARY.

NUCLEAR MEASUREMENTS CORP. 05000295 052078 DURING NORMAL OPERATION, THE AREA RADIATION MONITOR FOR THE 579' ELEVATIINSZRUMENTATION + CONTROLS 78-049/03L-0 061978 ON OF THE AUX. BLDG., ORTAR09, FAILED LOW. THE MONITOR WAS TAKEN 005 ANCOMPUTATION MODULE 021546 30-DAY D SHIFTLY SURVEILLANCE WAS PERFORMED IN A'CORDfNCE WITH T.S.3.14.1.C. T

COMPONENT FAILURE A/E HEREZERE NO SAFETY IMPLICATIONS INVOLVED,.?' IHE HEALTH AND SAFETY OFELECTRONIC WEST THE PZ)LIC WERE NOT AFFECTED.

ZION-1 S+LAREA MONITORING SYSTEMS '

OPERATIONAL EVENT THE CAUSE OF THE FAILURE WAS ATTkIPUTED TO DIRTY CLECTRICAL CONTACTS ONTHE ALARM / AMPLIFIER PRINTED CIRCUIT CARD (PART NO. AA-70) IN THE NMC RAD

MONITOR. THE CONTACTS OF ALL PC CARDS IN THE MONITOR WERE CLE ANED. THE MONtTOR WAS FUNCTONALLY CHECKED AND RESTORED TO SERVICE.

NUCLEAR MEASUREMENTS CORP. 05z0295 042773 DURDM NORMAL OPERATION, CLASS 1 PIPE TUNNEL IODINE MONITOR IRTPR07B, FINSTRUMENTATION + CONTROLS 78-054/03L-0 063078 AILLD. MONITOR TAKEN 005 AND SHIFTLY MANUAL GRAB SAMPLES TAKEN IN ZCCOR

POWER SUPPLY 021710 30-DAY DANCE WITH T.S. 3.14.1.C. THERE WERE NO SAFETY IMPLICATIONS INVOLVED ANCOMPONENT FAILURE A/E D THE HEALTH AND SAFETY OF THE PUBLIC WAS NOT AFFECTED. FAILURE DUE TO

CORROSION WEST RTY ELECTRICAL CONTACTS ON NMC SUPPLIED HIGH VOLTAGE PRINTED CIPCulT CZION-1 S+L ARD (P/N HVS 14).PRCSS + EFF RADIOL MONITOR SYSOPERATIONAL EVENT CONTACTS WERE CLE ANED AND MONITOR FUNCTIONALLY CHECKED AND RESTORED TO 5

D ERVICE. REPLACEMENT OF PCC MOTHER BOARDS WITH ONES LESS SUSCEPTIBLE 10CONTACT CORROSION IS BEINGG IMPLEMENTED.

3 177

m'M.Q

beh

LICENSEE EVENT REPORTS D:o

COMPONlNT MANUFACTURER DOC KE T NO .

COMPONENT /COMPONINT SUBCODE liR NO.CAUSL CODE /CAUSL SUUC0bt CONTROL NO. IVINT DAllF AtlLIT Y /5YSTE M SUPPLILR RJPORT DAll EVENT DISCRIPTION

METHOD OF D1500VI RY H555 / A/[ RilORT TYPI CAU5I DESCRIPTION_

NUCLE AR ME ASURIMI NT S CORP. 05000295 071278 ' LURING NORMAL OPIfttsTION, Till UNIT 1, CLASS 1, IPPL TUNNEL RADIATION MON!

INSTRUMLNTATION + CONTROLS 78-061/03L-0 081078 IOR, IRTPR07B, FAILLD LOW. Tlif DETLCl'UR WOULD NOT RESPOND TO THE CHECK

LEN50R/DLTECTOR/LLIMENT 021971 30-UAY SOURCL AND WAS TAKIN OUT OF 5[RVICL. SHlf1LY SURVLILL ANCE WAS PERFORMEDCOMPONINT FAILURL A/I A5 Pf R T E CH. SPEC. 3.14.1.C. THERL Wikt NO SAFLTY IMPLICATIONS INVOLVE

INSTRUMENT WL ST D AND THE HL ALTH AND SAFLTY Of Till PubLIC WA5 NOT AF F LCTLD.IlON-1 5+LPRC55 + Eff RADIOL MONITOR SYSOPERATIONAL EVLNT TH[ CAU51 Of THE FAILUP[ WAS DUE TO A F AILED GAMMA SZINTILIATION DLTECTO

R A55[ Mbl Y , NMC SUP PL IL D , P ART 0. SC-2-ISL . A NEW DETLCTOR ASSLMBLY WA5 INSTALLlD, THE MONITOR WAS CAtlBRATLD, FUNCTIONALLY CHECirLD AND RLSTOktD TO $1RVlt!.

PAClflC PUMPS 05000247 000278 DURING THL PIRI Of tuRV T[5T PTM-17, SAFETY INJLCTION PUMP FUNCTIONAL TE

PUMPS 78-015/03L-0 063078 ST, LXCf5tIVE 10L WAS NOTLD COMING FROM A BLARING HOUSING VENT ON NO. 22

CENTRIFUGAL 021706 10-BAY SAFETY INJICTION PUMP. Till PUMP WAS SHUIDOWN FOR INVESTICATION AND RLP

COMPONENT FAILURE N555 AIR. THI klMAINING TWO 5AFLTYINJLCT10N PUMPS WERE OPLRABLE AT THE TIME.MECHANICAL WEST FOLLOWING klPAIR5, NO. 22 SAFETY INJ[C TION PUMP WAS RLTURNED TO AN OPL

INDIAN POINT-2 U[ L RABLI STATUS WITHIN THL IIMl LIMIT PIPMITTE D bY TLCH $PEC 3.3. A.2(A).LMIPG CORE COOLING SYS + CONTPOUTINT TEST / INSPECTION

A PACIf!C PUMPS, H0kil0NTAL CLNTklf06AL MULTISTAGL PUMP, MODLL JTCH, BLCAML INOPLRALLE WlN 115 THRUST BL ARikG F AllID. THE THkUST COLLAR AND THPUST SHuf 5 WLRL FLPL ACLD, AND THI PUMP WI SUCCESSFULLY TISTED PRIOR TOITS RETURN TO AN OPE PABL[ STATUS.

PACIFIC PUMPS 05000338 071778 CHARGlHG PUMP IC BICAMI INOPLkABL L DUE 10 INBOAFD SL AL LL ArAGE . CHARG!N

PUMPS 78-005/03L-3 081678 G PUMP 1A BECAME Tll Oll kAT ING PUMP- LilARGING PUMP IB WAS NOT MALL OPlR

CENTRIFUGAL 022033 3C-DAY ABLL UNTil 3 HRS. 11 MIN. ATTE R THI SI AL FAILukt Of CilAkGING PUMP 10. TDESIGN / FABRICATION ERROR N555 .S. 3.1.2.4 AND 3.5.2. A RE QUlkf 2 OPi kABLt CitARGING PUMPL ONLY ONI CHA

CONSTRUCT ION / INST ALL AT ION WE ST kGING PUMP 15 PEQtIPlu IOR NORMAL OPI PATING AND IMLPGINCY CONDITIONS.

NORTH ANNA-1 5+W

[MERG COPE COOLING SYS + CONTOPERAT!0NAL LVlNT 5tAL FAILUPI WA5 DUL TO AN IMP 90PLPLY ASSIMBLLD St AL A551MblY. CHAPGING

PUMP IB COULD NOT bl ClCLAPID OPf RABLE UNTIL 5[ AL LI AVAGE PLDUC[D. CHAPGING PUMP IB D[CL APlb OPLRABLE WITHIN 7 2 HR. LIMIT SPLC'FilD BY THl ACTION ST Al[ MINTS Of T.S. 3.1:2.4 AND 3.5.2.A. THL SLAL 01 CHARGING PUMP 1C 15 CUkklNTLY tiling PPGPlPLY A5SIMBLlD.

178

LIU NSEE FVfNT REPORTS

COMPONINT MANUFACTURER DOCKFT NO.CCMPONLNT/ COMPONENT SLDCOCf LER NO.CAUSL CODL/CAUSE SUBCODE CONTROL NO. LVINT DAllFAClllIY/SYSTLM SUPPLifR RlPORT DATL tvlNI Dl5CRIPIl0NMf Til0D OF DIS (OVfRY NSSS / A/F RIPORT TYPI CAust Di st HIP 110N

PACIFIC VALVLS INC. 05000010 102377 DURING NORMAL OPERA 110NS of RADWASIt . NE UTRAllllR WAS Bi!NG PUMPLD 10 BVALVLS 77-041/03X-1 081878 SSG WASil 00ltlC10R. Alvl 5 V3 AND V45 LLAALD 7000 GAL Of H2O 10 IMPTY

CHECK 019647 01HER C ll0L DUP T ANA. WORN GASktI UN A MANHL AD Att OWL D APPROX 12 gal Of 1120 C0COMPONENT FAILURE NSSS NTAINING 2.5 E-4 Cl 10 tlAA 10 GROUND. 50ML LLAKACl WA5 COLLECILD & RET

MICHANICAL Gl UkNID TO NIUTRAL1/IR. NO LI AKAGE R[ ACHl0 UNCONTROLLLD ARI AS. LLAKAGL IDRLSDEN-1 U[CH N10 CONTR0ttlD Akl A5 WAS Cll ANLD. MINOR SPILLS OCCURRLD PRLVIOUSLY 76-1LIQ RAD 10ACT WSTE MANAGMNT SYS AND 7 7-1.OPLRATIONAL LVlNT VAL VL SLA15 IN VALVES V3 AND V45 WI R[ SCRA1CHED, CAUSING LI AKAGE 10 C HO

LDUP TANK Al;0VL THE L owl R MANiil AD. THE VALVLZ SLA15 WLRL LAPPLD. 1HL MANillAD G"5KLT WZ5 RIPLACIO AND litt HA1Cil IIGHTlNLD.

PARKER HANNiflN COFP. 05000325 1 201078 DURING NORMAL POWI R OPL RATION * CONTROL OPL RATOR RECllVLD THL LOW FLOW APIPIS flTTINGS 78-046/03L-0 060878 L ARM (f 0R CAC MON 110R CAC-Al-1259), WHl'. SUtil0N PATHS WLRL CilANGLD FROM

LESS THAN 4 IZCHES 021492 30-DAY THE DRYWE LL 10 THf 10RUS. (IL(ll ZLC .6.6.4)DESIGN / FABRICATION [RROR A/l

ULSIGN GlBRUNSWICK-1 UE C

CNTNMNT COMBUS GAS CONTROL SYSOPLRATIONAL [VLNT Wall R IN THL TORUS SUCTION LINT CAU Sl0 THE LOW FLOW CCNDIT10N. THE LINL

WAS DLOWN DOWN WITH AIR TO RlMOVf THE WAllR AND TLt. h0N!10R PL ACLU DACKINTO OP[ RATION. INGINEERING WORK klQUl5T (LWR 78-249) SutM111LD 10 [LE

VAIL TORUS SUCIl0N LINE 50 LIN[ IS ABl[ 10 SL LF-DRAIN :D IN10/IORUS.MODiflCATION E WLCTLD 10 BL COMPLLTLD AT LND Of NXT ZNii ONL RLfUlllNG

PLL RLL S5 PUMP LO 05000346 0$0H/H ON 5/H/18, Pi kl0RMING lill llRL PRulLL! ION SYSTIM LLLCTRIC PUMP WLLALY SUINSlRUMINI ATION + CONikutS 78-04H/03l-0 000178 RVilLL ANCE TlS1 ATT[MPTING 10 START ilkE PUMP, STARTER CONTACTS ARCLD, C

SWITCH 021581 30-DAY AUSING FIRE INSIDL STARTER CABINt T. THE ILECTRIC FIRE PUMP DLCLARLD INOCOMPONLNT F AllURL A/l PfRABil PLACING UNIT IN ACT!GN STAllMINT Of T.S.3.7.9.lA. NO DANGL TO

[LECTRICAL IHW HlALTH AND SAFETY OF PUBLil UR UNIT PERSONNEL.DAVIS-BLSSI-l I;t CH

flRL PROT [CTION sis CONTROUTINt TLST/INSPlCTION COMP 0NENT FAILURL Of TIIL STARl[R CONTACTS. f!RL BRIGADE SUMMIN[D. THLY

PUT OUT SMAll f!RL IN bRLAKIR. DLFLCTIVI CONTACTS WLRL R[PLAC[D AND CABINL1 Ctf ANLD UP. ELECTRIC F IRE PUMP WAS TLSTED AND RLTURNLD TO SERV'.LAT 1630 HOURS ON 5/10/78. UNIT REMOVLD FR01 ACTION STAT [ MENT Of T

CD 179:,7,

bg

(f)F.;N''

()LICENSEE EVENT REPORTS E.

COMPONENT MANUFACTURER LOCKET h0.CCFPONENT/ COMPONENT SUBCODE LER NO.CAUSE CODE /CAUSL SUBCODE CONTROL NO. EVENT DATE

FACItiTY/ SYSTEM SUPPLIER REPORT DATE _|ENT CESCRIPTIONPETHOD OF DISCOVEPY NSSS / A/E REPORT TYPE rAUSE DESCRIPTION

PERFEX, INC. 05000237 110477 WHILE UNIT 2 WAS SHUT DOWN FCR REFUELING, SERVICE WATER SAMPLES WERE TAK

HEAT EXCHANGERS 77-056/03X-2 081879 EN AT ALL CCNTAINVENT COOLING HEAT EXCHANGERS (CCHX). ThE SAMPLE FROM 2COOLER 019654 OTHER A CCHZ WAS FOUNC CONTAMINATED. IT WAS IMMEDIATELY ISOLATED. BECAUSE TH

COMPONENT FAILURE NSSS IS SYSTEM IS NOT RECUIRED DURING THE PERIOD IT WAS OUT OF SERVICE, SAFECORROSION GE PLANT OPERATICN WAS NOT IMPAIRED. THIS EVENT OCCURRED PREVIOU SLY ON THE

DRESCEN-2 5+L bE CCHX (LER 77-20).EMERG CORE COGLING SYS + CONTSPECIAL TEST /INSFECTIGN CONTAMI W ED ' M LE FROM 2A CCHX SERV. H2O SI?E INDICATED POSSIBLE TUBE

LEAKS. 12 MES PLUGGED AFTER HYDRO. ACTIVITY RELEASES CELOW LIMITS.MONTHL( TEST hlTIATED TO VEPIFY NO ADDITIONAL LEAKS REVEALED TUBE INTERNALS CONTAMINATED. HX CLEANED. CONTAMINATIOh LEVELS REDUCED, SURV. FREn INrPEAM D.

FERFEX, INC. 050002 % C6s NE WHILL Rhf LRMihG LPL1 AND LCSW $URVLILLANLL UN UNIT 3 f kl0K IU tar,1NG THHEAT EXCHANGERS 78-0:5/037 ' CHIEi8 E U-3 D/G OUT CF SERVICE, A SPIKE WAS FOUND CN THE LIQUID PROCESS RADIATCCOLER 0:19 % OTHEF ION MONITOR FOR THE SERVICE WATER DISCHARGE. THE SAVPLE FROM 3B-1503 CC

COMPONENT FAILUFE NSSS HX 45 FOLN' CONTAMINATED. IT WAS IMMEDIATELi ISOLATED. THE OTHER REDUCORROSICN GE NCANT CONTAINMENT COOLING HEAT EXCHANGER LOOP WAS OPERACLE. THIS EVENT

DRESCEN-3 S+L OCCLRRED TWICE FPEVIOUSLY ON 2A CCHX. (LER 77-20 AND 77-56)EMERG COFE C00LIhG SYS + CONTROUTINE TEST / INSPECTION CONTAMINATED SAMPLE TAKEN AT 3B CCHX SERVICE WATER SICE INDICATED POSSIB

LE TUEE LEM. HYDRO TEST INDICATED THAT ONE TUBE WAS LEAKING. IT WAS SUBSEQUENTLY PLUGGED.

.

PERFEX, INC. 05000259 071578 DURING A SCHEDULED OUTAGE ON UNIT 1. REACTOR COOLANT LEAKED FROM AN RHRHEAT EXCHANGERS 78-023/01T-0 072578 HEAT EXCHANGER INTO RHR SERVICE H2O SYSTEM WHICH DISCHARGES TO WHEELER R

OTHER 021837 2-WEEK ESERVOIR. CONCENTRATION IN DISCHARGE H2O RELE ASED WAS IN EXCESS OF T.S.3COMPONENT Fall'.7c hSSS .8.A.1 LIMITS. HEAT EXCHANGER WAS IMMED ISCLATED. AS REQUIRED, EMERGENCY

MECHANICAL GE PLAN WAS INITIATED. PEDUNDANT HE AT EXCHANCERS WEPE AVAILABLE. THE HEALBROWNS FEFRY-1 0 TH AND SAFETY OF THE PUELIC WAS NOT AFFECTED. PREVIOUS CCCURRENCE: 259RESIDUAL HEAT REMOV SYS & C hi /773.OPERATIONAL EVENT INSPECTION DISCLOSED THAT VIBRATION HAD LOOSENED FULL SIZED LOCKING NUTS

ALLOWING FLOATING iFAD GASKET TO LEAK. ALL FULL SIZED LOCKING NUTS WILL EE REPLACED. MORE SENSITIVE PP0 CESS MONITOF5 ARE BEIhG INSTALLED. OTHER HEAT EXCHANGERS WILL EE CHECKED FOR LEAKACE & SELECTED HEAT EXCHMGERSWILL IE INSPECTED TO PREVENT FURTHER OCCURFENCES.

180


COMPONENT MANUFACTURER DOCKET NO.COMPONENT /CCMPONENT SUBCODE LER NO.CAUSE CODE /CAUSE SUECODE CONTROL NO. EVENT DATE

FACILITY / SYSTEM SUPPLIER REFORT DATE EVENT DESCRIPTIONMETHOD OF DISCOVERY NSRS / A/F REPORT TYFF CAMF DESCRIPTION

PORTER PEERLESS MOTDRS 0500325 052778 A CONTROL OPERATOR WAS ATTEMPTING TO STROKE RCIC CST (CONDENSATE STORAGEVALVE OPERATORS 78-059/03L-0 062678 TANK) SUCTION VALVE E51-F010 FROM THE CONTROL ROOM. THIS VALVE WOULD NELECTRIC MOTOR - DC 021557 30-DAY OT MOVE FROM THE CZDSED POSITION. (T.S.3.7.4)

DESIGN / FABRICATION ERROR A/EMANUFACTURING GE

BRUNSWICK-1 UEC

ZAC CORE ISOL COOL SYS + CONTROUTINE TEST / INSPECTION THE VALVE OPERATOR MOTOR FOR VALVE E51-F010 WAS FOUND INOPERABLE. THE M

OTZR DID NOT HAVE A SPACE HEATER. AN EXAMINATION OF THE MOTOR INSULATION DAMAGE SUGGESTED M OIS19RE INTRUSION. A NEW MOTOR AND SPACE HEATER WAS

INSTALLED INTO THE OPERATOR AND THE VALVE WAS RETURNED TO SERVICE.

POTTER & BRUMFIELD 05000348 061378 AT 1150 CONTAIMENT ATMOSPHERE PARTICULATE RADI0 ACTIVITY MONITORING SYSTPUMPS 78-037/03L-0 062678 EM *R-11% 8 GASEOUS MONITORING SYSTEM ;R-12% WERE DECLARED INOPERABLE TO

ROTARY 021873 30-DAY REPLACE VACUUM EUMP AFTER PUMP KEPT TRIPPING ON LOW FLOW. TECH SPEC 3.4COMPONENT FAILURE NSSS .6.1 REQUIRES R-11 & EITHER R-12 OR A CONTAINMENT AIR COOLER CONDENSATE

MECHANICAL WEST LEVEL MONITORING SYSTEM TO BE OPERABLF. R-11 AND R-12 WERE RETURNED OPEJOSEPH M. FAPLEY-1 SSC/BECH RABLE AT 1540 ON 6/13/78. HEALTH AND SAFETY OF PUBLIC NOT AFFECTED.AIRBORNE RAD 10ACT MONITOR SYSOFRATIONAL EVENT PUMP FLOW RATE DEGRADED. FLOW RATES WERE ADJUSTED AFTFR INITI AL TRIPPING

OF PUMP. WHEN PUMP CONTINUED TO TRIP ON LOW FLOW IT WAS RLZLACED. FLOWTRIP SETPOINT WAS NOT ADJUSTED. DESIGN CHANGE TO ADD SECOND VACUUM IN P

ARALLEL BEING EVELUATED BY PLANT STAFF. (SIMILAR OCCURRENCE REPORTED INfFD 7 P- 03 5 / 031_ -0)

PUTTER & BRUMFIELD 05000348 060478 AT 1055 CUNIAINMLN1 ATMUSPHERL PARIILULAIL RAulUACIIVilY MONiluRING SY$1PUMPS 78-036/03L-0 062678 EM iR-11% AND GASE0US MONITURING SYSTEM 1R-12% WERE DECLARED INOPERABLEROTARY 021874 30-DAY FOLLOWING LOW FLOW PUMP TRIP WHEN THE PUMP WOULD NOT RESTART IMMEDIATELY

COMPONENT FAILURE NSSS TECH SPEC 3.4.6.1 REQUIRES R-11 AND FITHER R-12 OR A CONTAINMENT AIRMECHANICAL WEST COOLER CONDENSATE LEVEL MONITORING SYSTEM TO BE OPERABLE. R-11 AND R-12

JOSEPH M. FARLEY-1 SSC/BECH WERE RETURNED OPERABLE AT 1150 ON 6/4/78. HEALTH AND SAFETY OF PUBLICAIRBORNE RADIGACT MONITOR SYS NOT AFFECTED.

OPERATIONAL EVENT PUMP FLOW WAS OSCILLATING BETWEEN 8 AND 10 CFM. STEADY STATE FLOW APPROX. 9 CFM. AIR FLOW LOW FLOW SWITCH ADJUSTED TO CLEAR LOW F LOW TRIP. FILTER PAPER ALSO CHANGED. PUMP OSCILLATIONS WERE WITHIN SPEC BUT AFPARENTLY LOW FLOW PUMP CUTOUT SWITCH WAS SET SLIGHTLY HIGH.

181--

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NLO

Weyns--

g'2LICENSEE FNENT REPORTS

COMPONENT MANUFACTURER 00CKET NO.COMPONENT / COMPONENT SUBCODE LER NO.CAUSE CODE /CAUSE SUCC0DE CONTROL N0. EVENT DATE

FACILITY / SYSTEM SUPFLILR REPORT DATE EVENT CESCRIPTIONMFTHOD OF DISCOVFRY NSSS / A/F RFFORT TYPT CAUST DFSCRIPTION

POTTER & BRUMFIELD 05000348 052678 AT 0940 CUNTAINMENT ATMOSPHERE PARTICULATE RADIDACTIVITY MONITORING YSTPUMPS 78-035/031-0 00:678 EM R-11% AhD GASEOUS MONITORING SYSTEM iR-121 WERE DECLARED INOPERABLE

ROTARY 021875 30-DAY TO REPL ACE VACUUM PLMP AFTLR PLMP TRIPPED AND COULD N01 BE RESTARTED. TECOMPONENT FAILURE NSSS CH SPEC 3.4.6.1 REQUIRED R-11 ANJ EITHER R-12 OR A CONTAINMENT AIR COOLE

MECHANICAL WEST P CONDENSATE LEVEL MONITORING SYSTEM OPERABLE. R-11 AND R-12 WERE RETURJOSEPH M. FARLEY-1 SSC/BECH NED OPERABLE AT 1250 CN 5/26/78. PLALTH/ SAFETY OF PUBLIC WERE NOT AFTECAIRBORNE RADIDACT MONITOR SYS TED.OPERATIONAL EVEZT PUMP WAS REPLACED WEN A LOW FLOW CONDITION COULD NOT BE CORRECTED. THE

SYSTEM WAS SATISFACTORILY TESTLD AFTER PEPLACEMENT OF ThE PUMP.

POTTER & BRUMFIELD 05000348 051878 AT 2350 CONTAINMNT ATMOSPHERE PARTIClLATE RADICACTIVITY MONITORING SYSTPELAYS 78-034/03L-0 C61678 EM R-11 AND CONTAINMENT ATFOSPHER E GASECUS RACI0 ACTIVITY MONITORING SYST

CONTROL, GENERAL PURPOSE 021589 30-DAY EM R-12 DECLARED INOPERABLE AFTE R VACUUM PUMP TRIPPED ON APPARENT HIGH FCOMPONENT FAILURE NSSS LOW. T.S.3.4.6.1 REQUIRES R-11 AND R-12 OR CONTAINMENT AIR COOLER CONDEN

MECHANICAL WEST SATE LEVEL MONITORING SYSTEM OPERACLE. TECH SPEC REQUIREMENTS WERE MET.JCSEPH M. FARLEY-1 SSC/BECH R-11 AND R-12 CPERAELE AT 0150 5/19/78. HEALTH AND SAFETY OF PUBLIC NAIRBORNE RADICACT MONITOR SYS OT AFFECTED.OPERATIONAL EVZNT CR0 KEN WIRE IN HIGH FLOW RELAY (FOTTER AND BRUMFIELD P/N KAP 11AG) CAUSED

EY VICRATION IN UNIT. 1FE RELAY WAS REPLACED AND THE SYSTEM WAS SATISFACTORILY TESTED IN ACCORDANCE WITH FNP-1-STP-227.2B.

POWER SYSTEMS 05000010 051178 WHIL! ATTEMPTING TO DEMONSTRATE OPERABILITY OF U-1 BACKUP DIESEL GENERATCIRCUIT CLOSERS / INTERRUPTERS 78-021/01T-0 052278 OR, ThE TEMFORARY D/G FAILED TO START AS A RES'JLT OF BLOWN FUSES IN THECONTACTOR 021516 2-WEEK FEED TO THE CONTROL LOGIC PANEL. UNIT 1 WAS IN HOT SHUTDOWN WITHIN 24 H

COMPONENT FAILURE OTHER DURS. TRANSFORMER #13 (EQUIVALENT OFFSITE POWER SOURCE) WAS AVAILABLE DELECTRONIC GE URING THIS EVENT. THIS IS THE SECOND FAILURE RESULTING FROM A CONTROL L

DRESDEN-1 CECH OGIC MALFUNCTION AS REF. IN LER #78-013.AC ONSITE POWER SYS + CONTROLSSPECIAL TEST / INSPECTION CAUSE WAS DUE TO A SHORT CIRCUIT IN THE DIODE ACROSS THE FUEL PRIMING PU

MP CONTRACTOR. SYSTEM DESIGN NEGATES THE POSSIBILITY THAT THE DIODE FAILURE COULD HAVE CCCURRED PRIOR TO THIS START ATTEMPT. ALL DEFECTIVE COM

PONENTS WERE REPLACEC.

182

.

4





METHOD OF DISCOVERY NSSS / A/F REPORT TYPE CAUSF DESCRIPTION

POWER SYSTEMS 05000346 060478 PERFCRMING SURVEILLANCE TFSTING, D IESEL GENERATOR 1-1 FAILED TO OPERATE

GENERATORS 78-062/03L-0 062878 WITH PROPER FREQJENCY AND VOLTAGE. TE5T SUSPENDED AND DG 1-1 DECLARED IGENERATOR 021BS2 30-DAY NOPERABLE. UNIT IN MODE 6. NO DANGER TO HEALTH AND SAFETY OF PUBLIC OR'

COMPONENT FAILURE A/E UNIT PERSONNEL. DG 1-2 WAS OPERABLE HAD EMERGENCY POWER BEEN REQUIRED.ELECTRICAL B+W

DAVIS-BESSE-1 BECH

AC ONSITE POWER SYS + CONTROLSROUTINE TEST / INSPECTION ATTRIBUTED TO COMPONENT FAILURE OF PRIMARY POTENTIAL FUSE FOR DIESEL GEN

ERATOR. THE FUSE FOR DG 1-1 WAS PEPLACED. DIESEL GENERATOR MONTHLY TEST WAS COMPLETED AND DG DECLARED OPERABLE.

POWER TRONICS 05000317 072478 DURING NORMAL OPERATION CEA 60 DROPPED TO THE BOTTOM 0F THE CORE AT 1840CONTROL R0D DRIVE MECHANISMS 78-038/03L-0 081778 POWER WAS REDUCED TO 70% IN ACCORDANCE WITH T.S. 3.1.3.1 UNTIL CEA 60

SUBCOMPONENT NOT APPLICABLE 021996 30-DAY WAS FULLY WITHDRAWN AT 1940. AT 0055 ON 7/25/78 CEA 60 AGAIN DROPfED ICOMPONENT FAILURE NSSS NTO THE CORE. POWER WAS REDUCED TO 70% UNTIL CEA 60 WAS FULLY WITHDRAWN

ELECTRICAL COMB AT 0220. LER 78-29 (U-1) AND 78-22 (U-2) DESCRIBE SIMILAR EVENTS.CALVERT CLIFFS-1 BECH ,

REACTIVITY CONTROL SYSTEMSOPERATIONAL EZENT SINCE CEA #60 WAS IMMEDIATELY RETURNED TO SERVICE, NO FURTHER MAINTENANC

E ACTION WAS DEEMED NECESSARY.

POWER-MATE 05000318 | 052878 WHILE AT STEADY POWER LEVEL CONTROL ELEMENT ASSEMBLY (CEA) 5 DROPPED TO

CONTROL R0D DRIVE MECHANISMS 78-014/03L-0 060678 THE BOTTOM OF THE CORE WHEN IT WAS EXERCISED PER T.SZ$.!.W.l.0. THIS P

SUECOMPONENT NOT APPLICABLE 021532 30-DAY LACED THE UNIT IN A DEGRADED MODE DEFINED IN T.S.3.1.3.1.F. THE CEA WAS

COMPONENT FAILURE NSSS IMMEDIATELY WITHDRAWN AND BROUGHT BACK INTO ALIGNMENT WITHIN 20 MINUTESELECTRICAL COMB A SIMILAR OCCURRENCE WAS REPORTED IN LER 78-9/3L.

CALVERT CLIFFS-2 BECH

REACTIVITY CONTROL SYSTEMSOPERATIONAL EVENT SINCE CEA OPERABILITY WAS IMMEDIATELY RE-ESTAEllSHED, N0 M AINTENANCE ACT

ION WAS DEEMED NECESSARY.

183ccNQN4N

Cv;I2(L

[JLICENSEE EVENT REPORTS

COMPONENT MANUFACTURER DOCKET NO.COMPONENT / COMPONENT SUBCODE LER NO.CAUSE CODE /CAUSE SUBCODt CONTROL NO. EVENT DATEFACILITY / SYSTEM SUPPL.IER REPORT DATE EVENT DESCRIPTIONMETHOD OF DISCOVEPY NSSS / A/F PEPORT TYPE CAUSF DFSCRIPTION

POWER-MATE 05000318 072378 DURING PERFORMANCE OF MONTHLY SURVEILLANCE TESTING CEA #5 DROPPED TO THECONTROL ROD DRIVE MECHANISMS 78-022/03L-0 080778 BOTTOM 0F THE CORE AT 0514z POWER WAS REDUCED TO 70% IN ACCORDANCE WIT

SUBCOMPONENT NOT APPLICABLE 021995 30-DAY H T.S. 3.3.3.1 UNTIL CEA 5 WAS RESTORED TO ITS GROUP POSITION AT 0627.COMPONENT FAILURE NSSS LER 78-14 (U-2) AND 7849 (U-1) DESCRIBE SIMILAR EVENTS.

ELECTRICAL COMBCALVZRT CLIFFS-2 BECHREACTIVIZY CONTROL SYSTEMSROUTINE TEST / INSPECTION SINCE CEA #5 WAS IMMEDIATELY RETURNED TO SERVICE. NO FURTHER MAINTENANCE

ACTION WAS DEEMED NECESSARY.

POWER-MATE 05000335 032678 (78-10/3L-1) 1 CHANNEL OF STEAM GEN. LOW PRESSURE MEASU. FOR THE MAI ST.NSTRUMENTATION + CZNTROLS 78 03L 071478 EAM ISOL. SIGNAL FAIED, REQUIRING ACTION IN ACCORD. WITH SPEC. 3.3.2.1.NO SUBCOMP0NENT PROVIDED 021114 30-DAY B. CHANNEL WAS BYPZSSED, REPAIRED & RETURNED TO SERVICE IN 3-1/2 HRS.

COMPONENT FAILURE NSSS WHICH IS WELL WITHIN THE 48-HR. LIMIT FOR BYPASS OPER. A DESIGN CHANGECAUSE SUBCODE NOT PROVICED COMB HAS BEEN INITIATED TO IMPROVE RELIABILITY & REDUCE MAINT. FOR POER SUP.

ST. LUCIE-1 EBASCOMAIN STEAM ISOL SYS + CONTROLSOPERATIONAL EVENT POWER SUPPLY (POWER MATE ISV, 300 MA DC) FAILED, APPARENTLY AT END OF IT

S NORMAL SERVICE LIFE. IT WAS REPLACED & CHANNEL CALIBRATED PROPERLY. POWER SUPPLY UNITS FOR ALL OTHER CHAN. WERE CHECKED & SEV ERAL REPLACED.

POWER-MATE 05000317 053078 CONTROL ELEMENT ASSEMBLY (CEA) 20 DROPPED TO THE BOTTOM OF THE CORE AT 0INSTRUMENTATION + CONTROLS 78-029/03L-0 062278 040 ON 5/30/78 AND 0022, 0910 AND 1145 ON 6/3/78, WHILE REACTOR POWER WAPOWER SUPPLY 021598 30-DAY S AT 89%, 90%, 90% AND 90%, RESPECTIVELY. THE REQUIREMENTS OF T.S.3.1.3

COMPONENT FAILURE NSSS .1.F WERE FOLLOWED AND CEA 20 BROUGHT BACK INTO ALIGNMENT WITHIN 58, 52,ELECTRICAL COMB 60, AND 75 MINUTES RESPECTIVELY. SIMILAT OCCURRENCES WERE REPORTED IN

CALVERT CLIFFS-1 EECH LER 78-2 (U-1) AND 78-14 (U-2).REACTIVITY CONTROL SYSTEMSOPERATIONAL EVENT INITIAL ROD DROP DETERMINED TO BE RESULT OF SURGE IN POWER TIMER. THE S

ERIES OF ROD DROPS ON THE SECOND DATE WAS THE RESULT OF A FAILURE OF THECEDS 15 VOLT POWER SUPPLY (POWER MATE CORP MODEL UNI-83). THIS POWER S

UPPLY WAS REPLACED. A DESIGN MODIFICATION (FCR 78-72) IS UNDER REVIEW T0 IMPROVE THE RELIABILITY OF ZHE SYSTEM.

.

184 '

.


COMPONENT MANUFACTURER DOCKET NO.COMPONENT / COMPONENT SURCODE LER NO.CAUSE CODE /CAUSE SUBCODE CONTROL NO. EVENT DATEFACILITY / SYSTEM SUPPLIER PEPORT DATE EVENT DESCRIPTIONMETH00 0F DISCOVERY NSSS / A/E REPORT TYPE CAllSE DESCRIPTION

POWER-MATE 05000285 071278CURING NORMAL POWER OPERATION WHILE PEZFORMING SURVEILLANCE TEST ST-RPS-INSTRUMENTATION + CONTROLS 78-023/03-0 071978 7 IT WAS NOTED THAT THE "A" CHANNEL OF THE REACTOR PROTECTIVE SYSTEM (RPOWER SUPPLY 021801 30-CAY PS) FOR STEAM GENERATOR PRESSURE TRIP SETPOINT WAS OUT OF TOLERANCE. THCOMPCNENT FAILURE NSZS E REMAINING THREE RPS CHANNELS REMK!VZZEDZ@ EVENT.ELECTRONIC COMB

FT. CALHOUN-1 GHDRREACTOR TRIP SYSTEMSROUTINE TEST / INSPECTION

THE PCWER MATE MODEL DRA 15 .750/15 .750 15 V0LT POWER SUPPLY FAILED ALLOWING THE STEAM GENERATOR SETPOINT TO G0 OUT OF TOLERANCE. THIS POWER SUPPLY WAS REPLACED. THE "A" CHANNEL RECALIBRATED AND TESTED SATISFACTORILY. THE "A" CHANNEL WAS THEN RETURNED TO NORMAL.

RAMCON CORP. 050002821 051678 #14 FAN COIL UNIT DISCHARGE-TO-00MC DAMPER FAILED TO OPER AS REQ ON DEMAVALVE OPERATORS &* )]#7)#L-0 061678 ND. AFTER REPLACEMENT OF THE ACTUATORS THE DAMPER OPER CORRECTLY. SINCPNEUMATIC / DIAPHRAGM / CYLINDER 621640

|30-DAY E ALL REDUNDANT EQUIP WAS OPERABLE, THERE WAS NO EFFECT ON PUB HEALTH &

COMPONENT FAILURE A/E SAFETY. TECH SPEC 3/3/B/1/E APPLIES. SIM OCC REPORTED AS R0 77-29, 77-MECHANICAL WEST 26, 76-06, AND 75-38.

PRAIRIE ISLAND-1 PSECNTNMNT HEAT REMOV SYS + CONTOPERATIONAL EVENT

ACTUATOR FAIZED: BOTH ACTUATORS WERE REPLACED. PACIFIC AIR PRODUCTS DAMPER WITH RAMCON NO. R-260 ACTUATORS. SEARCH FOR A MORE EFFECTIVE LUBRICANT IS UNDERWAY. INVESTIGATION OF THE FAILURE IS CONTINUING.

-

RAYMOND CONTROLS 05000295, 071378 THE UNIT 1 PASSIVE GAS MONITOR (IRT PRIS) WAS FOUND TURNED OFF BY A RADIINSTRUMENTATION + CONTROLS 78-063/03L-0 081178 ATION CHEMISTRY TECHNICIAN DURING ROUTINE SURVEILLANCE. WHEN THE SWITCHOTHER 021969 30-DAY WAS TURNED ON IT EMITTED SPARKS. THE MONITOR WAS TAKEN OUT OF SERVICECOMPONENT FAILURE A/E AND SHIFTLY GAS GRAB SAMPLES OF THE PIPE TUNNEL WERE INITIATED PER TECH.ELECTRICAL WEST SPEC. 3.14.10. THERE WERE N0 SAFETY IMPLICATIONS INVOLVED AND THE PUBLZION-1 5+L IC HEALTH AND SAFETY WAS NOT AFFECTED.AIRBORNE RAD 10ACT MONITOR SYSROUTINE TEST / INSPECTION

TWO ACTUATING VALVE MOTORS OF SEQUENCER WERE FOUND BURNT OUT (NO. 4 BYPASS MOTOR AND NO. 3 INTAKE MOTOR). THE MOTORS WERE, MODEL MA-8-2 (1.40 A

MP) MANUFACTURED BY RAYM0ND CONTROL SYSTEMS AND USED IN THE NMC MONITOR1RT PRIS. MOTORS WERE REPLACED. MONITOR TESTED AND RETURNED TO SERVICE

'op;

185QNAf.

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(4-N

LICENSEE EVENT REPORTSQ,





METHOD OF DISCOVERY NSSS / A/E PEPORT TYPE CAUSE DESCRIPTION

RELIANCE ELECTRIC COMPANY 05000245 I 061378 ON JUNE 13, 1978, AT 1740 HOURS. OPERATION IN A DEGRADED MODE PERMITTED

INSTRUMENTATION + CONTROLS 78-014/03L-3 071278 BY A LIMITING CONDITION FOR OPERATION OCCURRED WHEN THE GAS TURBINE GENE

ZWITCH 021730 30-DAY RATOR BECAME INOPERABLE. A GAS GENERATOR OVERSPEED ALARM AND A LOSS OF

COMPONENT FAILURE NSSS THE READY TO START LIGHT OCCURRED. THE DIESEL GENERATOR WAS DEMDNSTRATE

ELECTRONIC GE D TO BE OPERABLE.

MILLSTONE-1 EBASCO

EMERG GENERATOR SYS + CONTROLS INVESTIGATION OF THE EVENT REVCALED THAT THE SPEZD SWITCH CHANNEL WHICHOPERATIONAL EVENT PROVIDES THE OVERSPEED TRIP SIGNAL HAD SPURIOUSLY TRIPPED. A SPARE SWITCH CHANNEL WAS CONNECTED TO THE CIRCUIT. THE GAS TURBINE WAS DECLARED 0PERABLE AT 2130 HRS 6/13/78. ON 7/6/78, THE SPEED SWITCH ASSEMBLY WAS RE

& REMOVED UNIT SFNT TO MFG FOR DETERM F FAILUREr

PLACED WITH A SPARE3.1.11P, SUPPRESSION POOL HIGH WZTER LEVEL , LE'.2L lI"

ROBLRISHAW CUNTROLS CO. 05000324 050976 DURING PERIODIC TEST

INSTRUMENTATION + CON.'OLS 78-042/03L-0 060778 WITCH E41-LSH-N01SB FAILED TO ACTUATE AT THE DESIRED WATER LEVEL. (TECH

SWITCH 021486 30-DAY SPEC 3.3.3-1, 3D)


MECHAN 1 CAL GE

BRUNSWICK-2 UEC

EMERG CORE COOLING SYS + CONT THE INSTRUMENT MICROSWITCH WAS FOUND DUT OF CALIBRATION DUE TO WEAR.T

ROUTINE TEST / INSPECTION-

HE SWITCHES WERE RECALIBRATED TO THE PROPER SET POINT AND WORK REQUEST 2-E-1277 WAS WRITTEN TO REPLACE THE SWITCHES WHEN NEW ONES ARE RECEIVED.

DURING NORMAL OPERATION WHILE PEZFORMING SURVEILLANCE PROCEDURE HNP-1-32ROBER'.SHAW CONTROLS CO. 05000321 071478

INSTRUMENTATION CONTROLS 78-056/03L-0 072778 02. (CORE TRAY DISCH. LINE LEVEL INSTRU. #T&C), CORE SPRAY LINE LEVEL 5

SWITCH 022014 30-DAY W.'TCH E21-N010B FAILED TO ACTUATE THE LOW LEVEL ALAZM. THIS SWITCH ALAR

COMPONENT FAILURE NSSS LS ONLY. TECH. SPE. 4.5.h.4. SIMILAR LER 76-48, 49,62,65.

INSTRUMENT GE

EDWIN 1. HATCH-1 SSC/BECH

EMERG CCRE COOLING SYS + CONT SWITCH WAS REMOVED AND EVALUATION Cc FAILURE IS IN PROGRESS. THE LINE IROUTINE TEST / INSPECTION S BEING VENTED ONCE ASHIFT TO ENSUti THE LINE IS FILLED. A FOLLOW UP R

EPORT WILL BE SUBMITTED WHEN EXACT ;AUSE OF FAILURE HAS BEEN DETERMINED.

186


COMPONENT MANUFACTURER DOCKET NO.COMPONENT / COMPONENT SUBCODE LER NO.CAUSE CODE /CAUSE SUBCODE CONTROL NO. EVENT DATEFACILITY / SYSTEM SUPPLIER REPCOT DATE EVENT DESCRIPTIONMETHOD OF DISCOVERY NSSS / A/E RFPC1T TYPE CAUSE DFSCRIPTION

ROCKWELL MANUFACTURING CO. 05000213 060578 A ROUTINE IZZPECTION FOR LEAKS ITHIN THE REACTOR CONTAINMENT LED TO THEVALVES 78-009/01T-0 061278 DISCOVERY OF A PIN HOLE LEAK IN THE PRESSURIZER SPRA Y ISOLATION VALVE.GLOBE 021903 ! 2-WEEK THE LEAK WAS AT THE BODY TO BONNET SEAL WELD. SINE THE LEAK WAS ISOLACOMPONENZZZAILURE A/E BLE AND LOCATED WITHIN THE REACTOR CONTAINMENT, THE HEALTH AND SAFETY OFMETALLURGICAL WEST THE PUBLIC WAS NOT AFFECTED.

HADDAM NECK-1 S+WOTHER COOLANT SUBSYS + CONTROLROUTINE TEST / INSPECTION ALTHOUGH THE EXACT FAILURE MECHANISM IS UNKNOWN, IT APPEARS THAT A SMALL

PIN H0LE DEFECT IN THE BODY TO BONNET SEAL WELD PROVIDED THE LEAKAGE PATH. THE VALVE WAS ISOLATED AFD THE WELD REPAIRED.

ROSEMONT ENGINEERING CO. 050C0331 052578 DURING SURVEILLANCE TESTING MAIN STEAM LINE TUNNEL HIGH TEMPER /TURE TISINSTRUMENTATION + CONTROLS 78-028/03L-0 062378 4444 WAS FOUND D TRIP AT GREATER THAN 204 DEGREES F ON ALL 4 SUBCHANNELSWITCH 021860 30-DAY S. THE REQUIRED SETPOINT IS %/= 200 DEGREES F. SFTPOINT REQUIREMENTS LCOMPONENT FAILURE A/E ISTED IN TECH SPEC TABLE 3.2. A. REDUNDANT TEMPERA:URE SWITCH SET POINTSINSTRUMENT GE WERE WITHIN SPECIFICATIONS. THERE HAVE BEEN TWO PREVIOUS SIMILAR OCCURRDUANE ARNOLD BECH ENCES (SEE LER 78-09).CNTNMNT ISOLATION SYS + CONTROUTINE TEST / INSPECTION INSTRUMENT DRIFT. TIS 4444 IS A ROSEMOUNT MODEL 3000A TEMPERATURE INDIC

ATING SWITCH. THE SWITCH WAS RECALIBRATED AZD FUNCTIONALLY TESTED. NOFURTHER CORRECTIVE ACTION PLANNED.

ROSEMONT ENGINEERING CO. 05000285 06197z DURING STARTUP ACTIVITIES FOLLOWING A SCHEDULED MAlhTENANCE OUTAGE IT WAINSTRUMENTATION + CZNTROLS 78-018/03L-0 070378 5 NOTED THAT "B" CHANNEL REACTOR COOLANT SYSTEM COLD LEG TEMPERATURE INE

SENSOR / DETECTOR / ELEMENT 021698 30-DAY ICATOR B/122C WAS READING 0FF SCALE HIGH. THE THREE REMAIZING COLD LEGCOMPONENT FAILURE NSSS TEMPERATURE INDICATORS READ NORMAL AND WERE CONSIDERED OPERABLE.

INSTRUMENT COMBFT. CALHOUN-1 GHDRENGNRD SAFETY FEATR INSTR SYSOPERATIONAL EVENT THE ROSEMOUNT MODEL 104VC RTD APPARENTLY OPEN CIRCUITED AND WAS REPLACED

THE TEMPERATURE LOOP WAS THEN RECALIBRATED AND PROPER COLD LEG TEMPERATURE WAS RESTORED FOR CHANNEL "B" ALL FOUR CHANNELS OF REACTOR C00LANT SYSTEM COLD LEG TEMPERATURE WILL CONTINUE TO BE MONITORED. VISUALLY AND BY SURVEILLANCE TESTING.

187

(06)ZBJ-L.@

[w:~

(\dC:.

LICENSEE EVENT REPORTS hCOMPONENT MANUFACTURER DOCKET NO.

COMPONENT /ZOMPONENT SUBCODE LER NO.CAUSE CODE /CAUSE SUBCODE CONTROL N0. EVENT DATE

FACILITY / SYSTEM SUPPLIER REPORT DATE EVENT DESCRioTr N

METHOD OF DISCOVERY NSSS / A/E REPORT TYPE CAUSE DEY .PTION

ROSEMOUNT, INC. 05000331 122977 DURING SURVEILLANCE TESTING MAIN STEAM LitL TUNNEL HIGH AMBIENT TEMPERAT

INSTRUMENTATION + CONTROLS 77-098/03L-1 062678 URE TIS 4443 WAS OBSERVED TO HAVE UNEXPECTEDLY LOW INDICATION ON CHANNELPOWER SUPPLY 020134 30-DAY S 2. 3 AND 4. REDUNDANT TEMPERATURE INDICATING SWITCHES WERE READING NO

COMPONENT FAILURE A/E RMALLY. TIS 4443 IS PART OF A LOGIC WHICH INITIATES PRIMARY CONTAINMENT

ELECTRONIC GE ISOLTION. OPERABILITY REQUIREMENTS LISTED IN T.S. TABLE 3.2-A.

DUANE ARNOLD BECH

CNTNMNT ISOLATION SYS + CONTROUTINE TEST / INSPECTION INITIAL INVESTIGATION INDICATED TE4443A HAD FAILED . HOWEVER WHEN IT WAS

REMOVED FOR REPLACEMENT, INVESTIGATION REVEALED NO PROBLEMS WITH TE. F

URTHER INVESTIGATION REVEALED A FAULTY CAPACITOR IN THE POWER SUPPLY. THE CAPACITOR SS REPLACED AND ALL CHANNELS NOW FUNCTION PP,0PERLY. POWER

SUPPLY IS PART OF RS3EroVNT MODEL 3000A TEMPERATURE MONITOR.

SANDVIK STEEL INC. 05000318 043078 DURING NORMAL FUWER OPERA 110N PLANT OPERATOR DISCOVERED A CRACKED WELD 2PIPES, FITTINGS 78-011/03L-0 052578 1 CHARGING PUMP SUCTION HEADER. THE PUMP WAS DECLARED INOPERABLE AND IS

LESS THAN 4 INCHES 021535 30-DAY OLATED. THE TWO OTHER CHARGING PUMPS REMAINED OPERABLE.Z LER 78-5 REFORCOMPONENT FAILURE A/E TED A SIMILAR OCCURRENCE.

METALLURGICAL COMB

CALVERT CZIFFS-2 BECH

CHEM, V0L CONT + LIQ POISN SYSCRACKED WELD WAS LOCATED ON A HALF-COUPLING UPSTREAM OF THE SUCTION RELIOPERATIONAL EVENT

THE FAILURE WAS PROBABLY THE RESULT OF PIPING VIBRATION STRESEF VALVE.S. FCR 78-73 HAS BEEN SWMITTED TO PROVIDE AN ADDITIONAL SUPPORT ON THE

RELIEF VALVE DISCHARGE PIPING. CRACKED WELD .HAS BEEN REPAIRED.

SANDVIK STEEL INC. 05000317 053178 DURING NORMAL OPERATION A PINHOLE LEAK WAS DISCOVERED ON THE WELDED FLANPIPES, FITTINGS 78-031/03L-0 062978 GE TO 11 REACTOR COOLANT CHARGING PUMP DISCHARGE RELIEF AT 1430. 11 CHA

LESS THAN 4 INCHES 021701 30-DAY RGING PUMP WAS RETURNED TO SERVICE AT 2020. 12 AND 13 CHARGING PUMPS RE

COMPONENT FAILURE A/E MAINED OPERABLE THROUGHOUT THE EVENT. LER 73-16 (U-1) AND LER 78-11 (U-METALLURGICAL COMB 2) DESCRIBE SIMILAR EVENTS.

CALVERT CLIFFS-1 BECH

CHEM, V0L CONT + LIQ POISN SYSTO CRACKED SOCKET WELD AT FLANGED CONNECTION ON INLET

OPERATIONAL EVENT LEAK OCCURRED DbTO RELIEF VALVE. CRACKED WEL WAS PEPAIRED. FATIGUE FROM PUMP OPERATIO

N DURING HEATUP Aho CDOLDOWN AND/0R VIBRATION OF LINE APPEARS TO HAVE BEEN CAUSE OF THE LEAK. ADDITIONAL ACTION TO PREVENT RECURRENCE IS NOT DEEMED NECESSARY.

188


COMPONENT MANUFACTURER DOCKET NO.COMIONENT/ COMPONENT SUBCODE LER NO.CAUSE CODE /CAUSE SUBCODE CONTROL NO. EVENT DATEFACILITY / SYSTEM SUPPLIER REPORT DATE' EVENT DESCRIPTIONMETHnD OF DISCOVERY NsSS / A/E RFPORT TYPE CAllSE DESCRIPTION

SANDVIK STEEL INC. 05000318| 062578 DURING NORMAL OPERATION PLANT OPERATOR DISCOVERED A CRACKED WELD ON THEPIPES, FITTINGS 78-018/03L-0 071378 CHARGING PUMP SUCTION HEADER DOWNSTREAM OF THE VOLUME CONTROL TANK OUTLE

4 TO 6 INCHES 021740 30-DAY T ISOLATION VALVE. THE OPERABILITY OF THE CHARGING PUMPS WAS NOT AFFECT'

COMPONENT FAILURE A/E ED BY THE PINHOLE LEAK. LER 78-31 (U-1) AND 78-11 (U-2) DESCRIBE SIMILAMETALLURGICAL COMS R EVENTS.

CALVERT CLIFFS-2 BECHCHEM, VOL CONT + LIQ P0 dN SYSOPERATIONAL EVENT LEAK OCCURRED DUE TO A CRACKED WEL AT A Y-CONNECTION DOWNSTREAM 0F THE

VCT DISCHARGE ISOLATION VALVE. CRACKED WELD WAS REPAIRED. FATIGUE FROMPUMP OPERATION DURING HEATUP AND C00LDOWN AND/0R VIBRATION OF THE LINE A

PriARS TO HAVE BEEN THE CAUSE OF THE LEAK. ADDITIONAL ACTION TO PREVENTRFr0RRENff TS NOT PFFMFD NFCFSSARY.

SCHOUNMAKLR, A.G. 05000250 1 0601zb DURING ROUTINE dLHEUULED TLSI of THE ' r EMLRGENCY DIESLL GENERATOK, AhINSTRUMENTZTION + CONTROLS 78-006/03L-0 070378 IGH LEVEL CONDITION OCCURRED IN THE ENGINE MOUNTED FUEL TANK. HIGH LEVE

SWITCH 021919 30-DAY L WAS INDICATED BY AN ANNUNCIATOR ALARM AND CONFIRMED BY OBSERVATION. TCOMPONENT FAILORE A/E EST WAS TERMINATED AND THE ENGINE WAS DECLARED OUT OF SERVICE WHILE TROU

ELECTRICAL WEST BLESH00 TING CONDUCTED.TURKEY POINT-3 BECH

MERG GENERATOR SYS + CONTROLSROUTINE TEST / INSPECTION INVESTIGATION SiOWED THAT A LEVEL SWITCH WHICH OPERATES ON INCREASING LE

VEL IN THE ENGINE MOUNTED TANK HAD MALFUNCTIONED. THE DEFECTIVE LEVEL *WITCH WAS REPLACED, AND THE TEST PERFORMED STAISFACTORILY.

SENTRY EQUIPMENT CORP. 0500033G 060978 THE DEGASIFIER, A COMPONENT IN THE CLEAN LIQUID RADWASTE SYSTEM WHICH GAHEAT EXCHANGERS 78-013/03L-0 071278 5 STRIPS PRIMARY COOLANT, WAS DISCOVERED TO HAVE FIVE TUBE LEAKS IN /N I

OTHER 021702 30-CAY NTERNAL HEAT EXCHANGER. THE SHELL SIDE IS THE BOUNDARY FOR THE PRIMARYCOMPONENT FAILURE A/E COOLANT AND THE TUBE SIDE CONTAINING STEAM FROM THE PLANT'S AUXILIARY ST

CORROSION COMB EAM SYSTEM. THE TUBE LEAKS ALLOWED RADI0 ACTIVE PRIMARY COOL /NT TO CONTAMILLSTONE-2 0/BECH MINATE THE CLEAN AUXILIARY STEAM CONDENSATE RETURN SYSTEM.LIQ RADIDACT WSTE MANAGMNT SYSPOUTINE TEST / INSPECTION THE CAUSE OF TUBE FAILURES IS UNKNOWN. THE LEAKING TUBES WERE PLUGGED A

ND THE DEGASIFIER WAS RETURNED TO SERVICE. THE CONDENSATE RETURN IS PERIODICALLY MONITORED FOR POTENTIAL LEAKS. MFG. SENTRY EQUIPMENT CORP., CAPACITY 132 GPM, TUBE DESCRIPTION: 3/4" 00 X .042" WALL SA-213-TP30 '

COVI7) 189NQ@

W1VaN:4CJ






METHOD OF DISCOVERY NSSS / A/F RFPORT TYPE CAUSE DESCRIPTION .

05000285| 061978 DURING THE REQUIRED TEN SECOND START AND FULL LOAD TEST OF DIESEL GENERASHAWMUT CDCIRCUIT CLOSERS / INTERRUPTERS 78-017/03L-0 070378 TOR #1 PRIOR TO PLANT STARTUP, THE GENERATOR FIELD FAILED TO REACH RATED

OTHER 021692 30-CAY 4.16 KV TERMINAL VOLTAGE. AT THE TIME OF FAILURE. DIESEL GENERATOR #2,

COMPONENT FAILURE A/E THE 161 KV SUPPLY AND 345 KV SUPPLY WERE ALL AVAILABLE.NATURAL END OF LIFE COMB

FT. CALHOUN-1 GHCR

EMERG GENERATOR SYS + CONTROLSROUTINE TEST / INSPECTION ONE OF THE SHOWMUT 100 FUSES SUPPLYING THE GENERATOR FIELD WAS FOUND

TO HAVE FAILED. Tht ,E WAS REPLACED AND THE DIESEL TESTED SATISFACTO

RILY.<

SINGER CO., THE 05000325 06U778 WHILE PERFORMING PERIODIC TEST 2.3.1 (DRYWELL TO TORUS MCUUM BREAKER OP

INSTRUMENTATION + CONTROLS 78-061/03L-0 070678 ERABILITY). A CONTROL OPERATOR DISCOVERED THAT CAC VACUUM BREAKER CAC-XSWITCH 021688 30-DAY 18G WOULD NOT INDICATE FULL OPEN. (TECHNICAL SPECIFICATION 3.6.4.1)


ELECTRICAL GE

BRUNSWICK-1 UEC

REACTOR CONTAINMENT SYSTEMSROUTINE TEST /INSFECTION EVH VACUUM BREAKER HAS 2 OPEN & 2 CLOSE SWITCHEF. NOTMALLY ONE OF EACH

dlTCH IS USED. IT WES DETERMINED THAT THE FULL CLOSED SWITCH HAD FallFD. THE SPARE FULL CLOSED SWITCH WAS ELECTRICALLY CONNECTED & OPERABLE

OF THE VACUUM BREAKER WAS V ERIFIED. THE FAILED FULL CLOSED SWITCH WILLpr pEppipEp.

SMllH, A. O. 05000338 080216 A RLVILW UF lHL SERVILL WAILR RLSLRVOIR RLVLALS THAI SEVLPAL GUY WlRLS UHANGERS. SUPPORTS.SH0CK,5UPPRSS 78-074/01T-0 081678 SED TO SUPPORT THE SPRAY RISERS HAVE FAILED ON UNIT 1 SPRAY ARRAYS. ALLOTHER 022034 2-WEEK SPRAY RISERS ARE UPRIGHT AND FUNCTIONAL AND CONSEQUENCES OF THE EVENT

DESIGN / FABRICATION ERROR A/E ARE MINIMAL. THE HEALTH AND SAFETY OF THE GENERAL PUBLIC WERE NOT AFFEC

DESIGN WEST TED.

NORTH ANNA-1 5+W.

STATION SERV WATER SYS + CONTSPECIAL TEST / INSPECTION THE GALVANIZED SEEL GUY WIRES OX1DIZED AND FAILED. ALL BROKEN GALVANIZ

ED STEEL GUY WIRES WILL BE REPLACED WITH STAINLESS GUY WIRES.

190

.1

llCENSEE EVENT REPORTS

COPPCNENT FANUFACTURER COCLET NO.COPPCNENT/C0fTONENT SCECODE LE R NO.CAUSE CODE /CAUSE SUF, CODE CONTROL NO. EVLNT DATEFACILITY / SYSTEM SUPPLIER REPCRT DATE EVENT DESCRIPTIONMETHOD OF DISCOVFRY N5ss / A/F GIFORT TYPE CAlfSE DESCRIPTION

SOLID STATE CONTROLS, INC. 05000320 032978 1N MODE 2 VITAL BUS 2-IV BECAME DE-ENERGIZED REQUIRING OPERATION IN ACT!INSTRUPENTATION + CONTROLS 78-021/03L-0 050178 ON STATEMENT TO T.S. 3.8.2.1, 3.3.2.1 (TABLE 3.3-3 ITEMS 3A AND 3B), 3.3

CONTROLLER 021952 30-CAY .3.5, AND 3.3.3.6. NO ADVERSE SAFETY CONCERNS, REACTOR TRIPPED, ECCS FU'

COMPONENT FAILLRE A/E 7CTIONED PER DESIGN, AND VITAL BUS WAS RE-ENERGIZED WITHIN TIME FRAME OFELECTRONIC B+W APPLICACLE ACTION STATEMENTS RETURNING AFFECTED EQUIPMENT TO OPERABLE S

THREE MILE ISLAND-2 B+R TATUS.AC ONSITE POWER SYS + CONTROLSPOUTINE TEST /INSPE CTION VITAL CUS INVERTER FAILED TO FUNCTI0'4 PROPERLY IN FREE RUNNING MODE. WH

EN ALTERNATE (AC) SOURCE TRIPPED OURING SFAS TESTING RESULTING IN BLOWNFUSE ON DC INPUT. ALTERNATE SOURCE AC BREAKER WAS CLOSED, ENERGIZING VITAL EUS AND FAULTY INVENTER CONTROL MODULE AND FUSE WERE REPLACED.

STATIC-0-RING 05000366 081078 ON AUGUST 10, 1978 WHILE IMPLEMENTING MAINTENANCE REQUEST 2-79-2964 TECHINSTRUMENTATION + CONTROLS 78-010/01T-0 081778 NICIANS DISCOVERED THAT THE TORUS TO RX BUILDING DIFFERENTIAL PRESS'JRE

SWITCH 022019 2-WEEK SWITCHES (2T48-N210 AND 2T48-N211) WERE INOPERABLE. AN ORDERLY SHUTDOWNDESIGN / FABRICATION ERROR NSSS WAS INITIATED.

CONSTRUCTION / INSTALLATION GE

ECWIN 1. HATCH-2 SSC/BECHCNTNMNT ISOLATION SYS + CONTMETHOD OF DISC. NOT APPLICACLE THE PIPING TO EACH STATIC *0" RING SWITCH (SERIAL NUMBERS 70-5-2741 AND

76-5-2742) WAS TUBED UP BACKWARDS APPLYING PRESSURE TO THE WRONG SIDE OFTHE SWITCH ALSO SWITCH 2T48-N211 WAS WIRED WRONG. THE PIPING TO EACHSWITCH WAS REROUTED AND THE CONTACTS REWIRED AS NEEDED.

STATIC-0-RING 05000237 050978 WHILE PERFORMING MONTHLY SURV. PS-2-1430-1466C FAILED TO OPERATE. T.S 4INSTRUMENTATION + CONTROLS 78-031/03L-0 060278 .5.A AND TABLE 3.2.2 REQUIRE A TRIP TO OCCUR BETWEEN 50 PSIG AND 100 PSISENSCR/DETEC10R/ ELEMENT 021513 30-DAY G. (DRESDEN SETPOINT 13 95 +/- 5 PSIG INCREASING.) 3 REDUNDANT CORE 5

COMPONENT FAILURE NSSS PRAY PUMP DISCHARGE PRESSURE SWITCHES WERE OPERABLE WITHIN TECH SPEC. NINSTRUMENT GE OT A REPETITIVE OCCURRENCE. PRESSURE SWITCH IS MFD. BY STATIC-0-RING, M

ORESnrN-2 5+L ODEL #5N-113.EMERG CORE COOLING SYS + CONTROUTINE TEST / INSPECTION EXCESS SCALE BUILDUP WTHIN SWITCH INTERNALS PREVENTED SWITCH FROM CLOSI

NG. SWITCH WAS CLEANED AND RE-TESTED WITH NO FURTHER ADJUSTMENTS NECESSARY. ALL SIMILAR MODEL PRESSURE WITCH INTERNALS EXAMINED AND FOUND SATISFACTORY. CORE SPRAY PUMP AUTO BLOWDOWN PERMISSIVE PRESSURE SWITCHES WILL CONTINUE TO BE TESTED MONTHLY.

191gN7,Nc1O

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NLICENSEE EVENT REPORTS 00

COMFONENT MANUFACTURER DOCKET NO.

COMPONENT / COMPONENT SUBCODE LER NJ.CAUSE r0DE/CAUSE SUBCODE CONTROL NO. EVENT DATEFACILITY / SYSTEM SUPPLIER REPORT DATE EVENT DESCRIPTIONVETHOD Or DISr0VERY NSSS / A/E PEPORT TYPE CAU(E DESCRIPTInN

STATIC-0-RING 05000366 080378 HIGH DRYWELL PRESSURE INSTRUMENTS 2E11-N011A-D WERE FOUND TO EXCEED TECHINSTRUMENTATION + CONTROLS 78-008/01T-0 060978 SPECS (T.S. 3.3.3) DURING REGULAP SCHEDULED SURVEILLANCE. THE SETPOINT

SWITCH 022020 2-WEEK S WERE BETWEEN 2.2 PSIG AND 3.1 PSIG, THE INSTRUMENT FUNCTIONS: HPCI &COMPCNENT FAILURE NSSS RCIC ISOLATIONS: HPCI, RCIC, LPCI & ADS ACTUATIONS.

INSTRUMENT GEEDWIN I. HATCH-2 SSC/BECHEMERG CORE COOLING SYS + CONTROUTINE TEST / INSPECTION CAUSE OF EVENT WAS INSTRUMENT ] RIFT. INSTRUMENTS v'L?E RECALIBRATED, PET

ESTED SATISFACTORILY, AND RCTURNED TO SERVICE.

STATIC-0-RING 05000265 052478 WF Kr PERFORMING RHR PUFP DISCHARGE PRESSURE f.ALIBRATION PROCEDURE QIS 2,

INSTRUMENTATION + CONTROLS 78-024/03L-0 062378 2-1, PRESSURE SWITCH PS-2-1053D FAILED TO GPERATE. THE REMAINING SEVENEVITCH 021789 30-DAY RHR PRESSURE SWITCHES WERE OPERABLE AND WOLLD HAVE PROVIDED INPUT TO THE

C0FPONENT FAILURE A/E AUTOMArJr PRESShr.E DELIEF INITIATION TGIC id VERIFY TPAT A LOW PRESSURINSTRUMENT GE t ECCS PbhP WAS EUNNING. THEREFORE, _ ?E PLANT OPERATION WAS UNAFFECTED

QUAD CITIES-2 5+L BY THIS EVENT.RESIDUAL HEAT REMOV SYS + CONT ,

ROUTINE TEST / INSPECTION THE CAUSE OF THIS OCCURRENCE LAS ATTRIBUTED TO EQUIPMENT FAILURE. THE INTERNAL MECHANISM WAS FOUND TO BE DIRTY AND THUS RESTRICTING PROPER SWI;CH OPERATION. THE ORIGINAL BOURDON TUBE PPESSURE SWITCH WAS REPLAiTn WI

TH A DIAPHRAGM TYPE SWITCH. ,

STEARNS-ROGER CORP. 05000333 071377 DURING REFUELING OPERATIONS, 600V AC WAS INTRODUCED INTO THE 115V AC REF

ELECTRICAL CONDUCTORS 77-043/03X . 060978 UELING INTERLOCK CIRCUIT & THE ROD MANUAL CON 1 POL SYSTEM (RMCS) CAUSINGSUBCOMPONENT NOT APPLICABLE 018479 ' OTHER 19 RELAYS IN THE RMCS TO BURN OUT, RENDERING BOTH CIRCUITS INOPEPABLE.

COMPONENT FAILURE NSSS THE REFUELING INTERLOCKS FAILED IN THE SAFE CONDITION. ALL REFUELIFG 0ELECTRICAL GE PERATIONS WERE HALTED UNTIL IhTERLOCKS WERE REPAIRED. THE ROC WORTH MIN

FITZPATRICK-1 5+W IMIZER AND THE R00 SEQUENCE CONTROL SYSTEMS WERE CHECKED FOR DA' AGE.FUEL HANDLING SYSTtMS i

OPERATIONAL EVENT THE 600V AC AND TEE 115V AC ARE LOCATED IN THE SAM: CABLE. THE CABLE StGUTED INTERNALLY AT THE POINT WHERE IT FLEXES EAST AND WEST 'dTH BRIDGE

-

MGTION OVE6 THE "5RE. FLANT MODIFICATION F1-78-10 WID - M0]IF1 CABLE FEED ARRANGEMSki /WD USE A MORE FLEXIBLE CABLE.

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192 -

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COMPONENT MANUFACTURER DOCKET NO.COMPONENT / COMPONENT SUSCODE LER NO.CAUSE CODE /CAUSE SLBCODE CONTROL NO. EVENT CATEFACILITY / SYSTEM SUPPLIER ;EPCRT DATE EVENT EESCRIPTIONMETpnD OF DISCOVFRY NSSS / A/E ;EPOPT TYrF CO N rrSrRIPTION

STONE & WEBSTER ENG. CORP. CSC00213 061378 DURING ELECTRICAL PENETRATION QUALIFICATION TESTING LNDER SIMULATED LOCAPENETRATIONS.PRIMRY CONTAINMNT 78-010/01T-0 C62378 CCNDITIONS. THE P0kER SOURCE TRIPPED 25 MINUTES INTO A 7-DAY TEST FROGRELECTRICAL 021LS6 2-WEEK AM. FEGGER READINGS INDICATED PHASE TO PHASE FAILURE BETWEEN TWO CONDUCDESIGN / FABRICATION ERROR A/E TCRS. SLESEQUENTLY OThER FAILURES CCCURRED. ALTh0LGH THEPE WEPE NO IPMCONSTRUCTION / INSTALLATION WEST EDIATE EFFECTS ON PLANT OPERATION, FAILURE OF ELECTRIZAL PENETRATION QUAHADDAM NECK-1 5+W

L. TEST INCICATED POSSIBILITY THAT FUNCTIONAL CPERATION CF SAFETY-RELATEREACTOR CONTAINMENT SYSTEMSD EQUIPMEN! COULD BE COMPROMISED AFTER 25 MINS. LNDER LOCA CONDITIONS.

SPECIAL TEST /INSFECTIONCESTRUCTIVE EXAMINATICN OF THE FAILED ELECTRICAL PENETRATION DISCLOSED A

N INADECCATELY SEALED MI CAELE END POT CAUSED EY VOIDS IN THE FIELD INSTALLED SEALING PATERIAL & INTRUSION OF MOISTURE. MODIFIED SEALING ARRANGEMENT USING RAY CHEM HEAT *HRINK SLEEVES SUCCESSFULLY PASSED A 48-HOUR Ql' AL . TEST. ALL RAFETyartf.TED PENETPATIONS (781 W DIFIED TIultarLY

TARGET ROCK CORPukA110N UbULO321 0609/6 WITH ThL KtACiUK IN LLLD $bulLU M HNP-1-h 02, A "$ArLIV ktLILF (SkV) FLNVALVE OPERATORS 78-043/03L-0 063078 CTIONAL TEST," kAS ATTEMPTED ON B21-F013C AND B21-F013L. THE (SRV'S) AROTHER 021723 30-CAY E NOT REQUIRED TO EE C.ZRABLE WHILE THF REACTOR 15 IN COLD SHUTDOWL ALCOMPONENT FAILURE NSSS L ELEVEN SRV 5)LEN0ID VALVES ','ERE REMCVE0 A?.D DI'ASSEPELED $0 THAT ThEYELECTRICAL GE

COULD EE INSFECTED. THE SOLEN 0 IDS WERE PART 0F A MODIFICATION TO THE SREDWIN I. HATCH-1 SSC/BECH V's THAT kAS NOT CPEPATIONAL AT THE TIME OF THE INCIDENT.CNTNMNT HEAT PEMOV SYS + CONTSPEC?AL TEST /INSFECTION

THr JGET ROCK D.C. ACTUATED SOLENOID VALVES FAILED DUE TO THEIR ASSOCIATED PLUNCERS BEING CUT OF ADJUSTMENT, DIRTY, AND/0R PARTIALLY DAMAGED DURING hANPLING. ALL ELEVEN SRV SOLEN 0ID VALVES WERE ADJUSTED, CLEANED,OR PEPLACED AS DEEMED NECESSARY. THE SRV SCLENCID VALVES WERE BENCH-TESTfD. Dc W NTED. AND PETESTED SATISFACTrrILY

IdRGET ROCK CCRT A110N 0500U259 OZI4/u [URING UNIT 1 RLf LLLING OUTAGL WHILL P hfukMING NUL Uf f blIL, LINLAR INDIVALVES 78-006/01T-2 CC0578 CATIONS WERE FOUND IN MSRV BODY CASTINGS. DURING UNIT 2 REFUELING OUTAGEOTHER 020493 2-WEEK CHLCKS ON THE LNIT 2 MSRV'S SHOWED TWO MORE VALVES WITH INDICATIONS. TDESIGN / FABRICATION ERROR NSSS FESE CEFECTS DO NOT RESULT IN DEGRADATION OF VALVE DESIG'i CRITERI A. NOMANUFACTURING GE ETFECT ON PUCLIC HEALTH OR SAFETY WAS CREATED. THERE IS NO REDUNDANCY.BROWNS FERRY-1 0MAIN STEAM SYSTEMS + CONTROLSOPERATIONAL EVENT

CASTING CEFECTS REPRE. CASTING SHRINKS OR NONFETALIC INCLUSIONS THAT WERE VASKED DLRING SHOP CASTING SURFACE EXAMS. THERMAL CYCLES DLRING GPER

RESULEED IN THESE DEFECTS BECOMING APPARENT. VALVES WERE TARGET ROCK!CDEL 67F. SN'S 61 & 246 ON ONIT 2, & SN'S 72 & 59 CN UNIT I. SURFACEINCLUSIONS WERE GROUND OUT & WELD REPAIRED CN SN'S 59, 61 & 246.

@ts, 193GN

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{LICENSEE EVENT REPORTS

COMPCNENT MANUFACTURER DOCKET NO.

COMPONENT / COMPONENT SUBCODE LER NO.CAUSE CODE /CAUSE SUBCODE CON 1ROL NO. EVENT DATE |.FACILITY / SYSTEM SUPPLIER REPORT DATE EVENT DESCRIPTIONPET 900 0F DISCOVERY NSSS / A/E REPORT TYPE CAUSE DESCRIPTION

TARGET ROCK CORPORATION 05000277 030178 DURING DYE PENETRATION INSPECTION OF TWO TARGET ROCK SAFETY RELIEF VALVEVALVES 78-013/01X-1 071978 5 PRIOR TO OVERHALLING AND TESTING. INDICATIONS WERE FOUND ON THE INTERI

ANGLE 020684 OTHER OR SURFACE NEAR THE SEATING AREA. TWO ADDITIONAL VALVES, REMOVED RECENT

DESIGN / FABRICATION ERROR NSSS LY, ALSO SHOWED INDICATIONS. MAXIMUM INDICATION DEPTH 5/16 INCH; VALVE,

MANUFACTURING GE BUDY THICKNESS AT INDICATIONS 13/8 INCHES; MINIMUM WALL THICKNESS 5/8 IFEACH BOTTOM-2 BECH NLH. CONSEQUENCES ARE MINIMAL BECAU SE DEEPEST INDICATION DID NOT APPROAMAIN STEAM SYSTEMS + CONTROLS CH WALL THICKNESS.ROUTINE TEST /INSPECTICN REPAIRS MADE BY GRINDING OUT AND WELDING. RADIOGRAPH SATISFACTORY. BOA

T SAMPLE REMOVED FOR ANALYSIS. ANALYSIS CONCLUDED THAT THE INDICATION WAS CAUSED BY A PRE-EXISTING CASTING DEFECT WHICH PROBABLY OCCURRED DURING SOLIDIFICATION AND COOLING OF THE CASTING AND HAD NOT PROPAGATED IN SEPVICE.

TELLDfNt-bkUwN LNGINEERlkG 65000483 12121) THE Wh0NG ELEC1ROULS hlPE USED IN Iht WLLDING PROCESS ON 12 RLAC10R COOLPUMPS 77 /02X- 042778 ANT PUMPS. SPECIFICALLY THIS INVOLVES THE USE OF E7018 ELECTRODES INSTE

NO SUBCOMP0NENT PROVIDE 0 021808 OTHER AD OF E10018 WEEN WELDING A533 TO A533 MATERI AL.CESIGN/ FABRICATION ERROR * UNS

CAUSE SUBCODE NOT PROVIDED WEST

CALLAKAY-1 BECH

COGLANT RECIRC SYS + CONTROLSOPEFATIGNAL EVENT CAUSE WAS ATTRIBUTED TO MISINTERPRETATION OF CONTRACT DOCUMENTS BY FABRI

CATOR COUPLED WITH A FAILUPE TO ADEQUATELY FOLLOW APPROVED PROCEDURES.ALL 12 PUMPS WERE REPAIRED USING APPROVED WELDING FROCEDURES.

TELEDYNE-GE0 TECH 05000334 030778 ON 3/7/78, THE MAGNETIC TAPE PECORDER WHICH RECORDS DURING SEISMIC EVENT

INSTRLMENTAT10N + CONTPOLS 78-028/991-1 062978 5 WAS DETERMINED TO BE INOPERABLE. A NEW RECORDING HEAD WAS INSTALLED 0RECORCER 021045 2-WEEK N 4/5/78 BUT THE PECORDER REMAINED INOPERABLE. THE HEALTH AND SAFETY OF

COMPONENT FAILURE A/E THE GENERAL PUBLIC WAS NOT JEOPARDIZED. THE PEMAINING SEISMIC INSTRUMEELECTRONIC WE.T NTATION IS OPERABLE.

BEAVER VALLLf . 5+W

OTHR INST SYS NOT RE00 FJ SrTYROUTINE TEST / INSPECTION THE INOPERABLE RECORDER WAS RETURNED TO THE VENDOR FOR REPAIR. THE U%

WAS DETERMINED TO BE IRREPARABLE. TELEDYNE GEUTECH MAGNETIC TAPE CARTkIDGE HANDLER MODEL MTS-100. A NEW SEISMIC MONITORING INSTRUMENT WILL BEPURCHASED AND INSTALLED. COMPLETION IS EXPECTED BY 12/31/78.

194.


COMPONENT MANUFACTURER DOCKET NO.COMPONENT / COMPONENT SUECODE LER NO.CAUSE CODE /CAUSE SUBCODE CONTFOL NO. EVENT DATEFACILITY / SYSTEM SLPPLIER REPORT DATE EVENT DESCRIPTIONMETH_00 0F DISCOVFRY NSSS / A/F FFPORT TYPF CAUSE PFSCRIPTION

-

TELEDYNE-GE0 TECH C5000346 061978 ON 6/19/78 DISCOVEPED SEISMIC PECORDER TIMING MARKS OUT OF TOLERANCE. PINSTRUMENTATICN + CONTROLS 78-069/03L-0 071378 LACED UNIT IN ACTION STATEMENT OF T.S. 3.3.3.3. NO DANGER TO HEALTH ANDRECORDER 021857 30-DAY SAFETY OF PUBLIC OR UNIT PERSONNEL. IhREE PEAK RECORDING ACCELEROMETER

CCFPONENT FAILURE A/E S WERE OPEPAELE. BY TRANSMITTING THE RECORDING FOR OFF-SITE ANALYSIS, TINSTRUMENT B+W HE DATA COULD HAVE BEEN CORRELATED TO PROPERLY REFLECT THE ACTUAL SEISMI

DAVIS-EESSE-1 EECH C EVENT.OTHR INST SYS NOT REQD FR SFTYROUTINE TEST / INSPECTION DISCOVERED THE 9 VOLT VOLTAGE REGULATORS ON VOLTAGE CONTROLLED OSCILLATO

R BOARDS WERE CRIFTING. PARTS ORDERED ON 6/21/78. WORK WILL BE PERFORMED UNDER MAINTEiiANCE WORK ORDER. SURVEILLANCE TEST ST 5034.02, WILL BEREVISED TO INCLUDE ACCEPTANCE CRITERIA COVERING llMING MARK TOLERANCE.

TELETYPE 05000254 050578 ON MAY 5, 1978 WHILE PERFORMING THE QUARTERLY RCIC FLOW RATE TEST QOS 13MECHANICAL FUNCTION UNITS 78-015/031-0 060278 00-1. THE PCIC TURBINE EXHIBITED REPETITIVE PREMATURE TURBINE TRIPS AND

SUSCOMPONENT NOT APPLIL,ABLE 02143/ 30-DAY THEREBY RENDERED THE RCIC SYSTEM INOPERABLE. THE HPCI SYSTEM HAD JUST BCOMPONENT FAILURE NSSS EEN DEMONSTRATED TO BE OPERABLE PRIOR TO THE RCIC SURVEILLANCE TESTING,

MECHANICAL GE HENCE, SAFE PLANT OPERATION WAS UNAFFECTED. APR AND ALL LOW PRESSURE ECGUAD CITIES-1 5+L CS WERE AVAILASLE.REAC CORE ISOL COOL SYS + CONTROUTINE TES'/ INSPECTION THE PREMATURE RCIC TURBINE TRIPS WERE DUE TO A DIRTY BALL AND TAPPET ASS

EMBLY IN THE TURBINE OVERSPEED TRIP MECHANISM. THE BALL AND TAPPET ASSEMBLY WAS REPLACED AND THE RCIC SYSTEM WAS DEMONSTRATED TO BE OPERABLE ONMAY 5,1978 AT 2130 HOURS.

TERRY STEAM TURBINE COMPANY 05000366| 072578 RCIC TURBINE TRIPPED EACH TIME AN ATTEMPT WAS MADE TO MANUALLY START THEINSTRUMENTATION + CONTROLS 7E-005/03L-0 080778 TURBIFE DURING SMRTUP TESTING. NO SIGNIFICANT OCCURRENCES RESULTED FRCONTROLLER 022023 30-DAY OM THE EQUIPMENT FAILURE. THE HPCI SYSTEM WAS AVAILABLE AS A REDUNDANT

COMPONENT FAILURE NSSS SYSTEM.ELECTRONIC GE

EDWIN I. HATCH-2 SSC/BECHREAC CORE ISOL COOL SYS + CONTSPECIAL TEST 71NSPECTION THE FAILURE IAS CAUSED BY THE ELECTRONIC OVERSPEED SETPOINT CRIFTING BEL

OW ITS ASSIGNED VALUE. THE OVERSPEED SETPOINT WAS RECALICRATED TO THE PR0PER VALUE.

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COMPCNENT MANUFACTURER DOCKET NO.COMPCNENT/C0MPONENT SUBC0CE LER NO.CAUSE CODE /CAUSE SUBCODE CONTROL NO. EVENT DATEFACILITY / SYSTEM SUPPLIER PEPORT DATE EVENT DESCRIPTIONW Tu00 0F DISCCVEov NSSS / A/E PEPnPT TYPE

,C AUM DE SCRIPTION

TRACER LAB 05000029 061078 DURING N0PMAL PLANT OPERATION, LOOP SEAL RADIATION MONITOR INDICATLD LESINSTRUMENTATION + CONTROLS 78-016/03L-0 071078 5 THAN 0 COUNTS / MINUTE. NO RELEASES TOOK PLACE DURING THE EVENT. SIX SP0kV SUPPLY 021685 30-DAY IMILAR EVENTS HAVE GCCURRED PREVIOUSLY (SE E LER 77-24 AND LER 78-13).

CCMFONENT FAILURE LICINSTRUMENT WEST

YANKEE FCwE 5+W

AIPEORNE RADI0ACT MCNITOR SYSCPERATICNAL EVENI CEIFT OF HIG: ' CLIAGE (TRALL R LAB, MODE L EM-40, S/N 325). HIGH VOLTAGE,

WAS ADa iTf D. l' '4 [f,GlM E RING CHANGE IS FLANNED TO REPLACE THE PRESENT L'>Q ATILN NNITURING SYSTE M.00P SEAL r

TRACER LAB 0500CC29 061278 CURING Nuf MAL ORPATION, LOOP SE/L RADIATION MONITOR INDICATED LESS THANINSTRUMENTATICN + CONTRCLS 78-017/C3L-0 071278 0 CFM CAUSL DLE TO [ RIFT OF HIGH VOLTAGE. THERE WERE NO RELEASES DURPCkER SUPPLY C21711 30-DAY ING TLE cVENT. THIS T)FE OF EVfNT HA5 OCCURRED 7 TIMES PREVIOUSLY; SEE

COMPONENT FAILURE LIC LER 78-13, 77-24, AND 78-16.INSTRUMENT WEST

YANKEE RCWE 5+WAIRBORNE RADICACT MONITCR SYSOPERATIONAL EVENT DRIFT CF HIGH VOLTAGE SLPPLY (TRACERLAC MODEL RM-40). HIGH VOLTAGE WAS

READJUSTED. PLAN 5 ARE CLING MADE TO REPLACE THE PRESENT LOOP SEAL RADIATION MONITORING SYSTEM.

TRANE CO CECG0317 CE1678 CURING NORM OPNS, 12 [0NT FOCM A/C UNIT STOPPED AT 4:15 P.M. AND WOULD NMEAT EXCHANGERS 18-C33/03L-0 070778 OT RESTART. 11 CONT ROOM A/C UNIT WAS IMMED PLACED IN SERVICE AND PERF0OTHER 021090 30-DAY FMED SATISFACTORILY THRCUGHOUT THIS E WNT. 12 CONT ROOM A/C UNIT WAS RE

COMPONEN' f AILURE A/E PAIRED AND SATISFACTORILY TESTED AT 4:00 P.M. ON 5/22/78 WITHIN THE 7 DAMECHAM CAL CCMB YS ALLOWE D BY T.S. 3. 7.6.1. THIS IS NOT A REPETITIVE EVENT.

CALVERT CLIr: BECH'

AIR CCND, HEAT. COOL. VENT SYST9CPERATIONAL EVENT CONCENSER FAN M0iLP BEARING SEIZURE STALLED MOTOR WHICH CAUSED MOTOR WIN

DINGS TO BURN. MOTOR WAS PEMOVED, REWOUND, NEW EEARING INSTALLED, & REINSTALLED IN CONDENSER UNIT. UNIT WAS TESTED & RETURNED TO SERVICE. EEARING INVOLVED, SKF 6207-2RS IS SEALED BEARING, DOES NOT REQUIRE LUBRICATION; THEREFORE, NO FURTHER ACTION IS REQUIPED.

196


COMPONEKr MANUFACTURER DOCKET NO.COMPONENT / COMPONENT SUBCODE LER NO.CAUSE CODE /CAUSE SUBCODE CONTROL NO. EVENT DATEFACILITY / SYSTEM SUPPLIER PEPCRT DATE EVENT DESCRIPTIONMETHOD OF DISCOVERY N'R5 / A/F PEPOPT TYPE CAUSE DESCRIPTION

TRANSMATION. INC. 05000318 Of0978 I&C TECHNICIANS, WHILE INVESTICATING A GREATER THAN 0.1 VOLT DEVIATION BINSTRUMENTATION + CONTROLS 8-016/03L-0 070778 ETWEEN 21 STEAM GENERATOR LOW PRESSURE ENGINEERED SAFETY FEATURES ACTUATOTHER 021696 30-CAY ION SYSTEM (ESFAS) CHANNEL ZF AND THE OTHER CHANNELS, DETERMINED 2 E/E 1

COMPONENT FAILURE NSSS 013C WAS DEFECTIVE. CHANNEL ZF WAS BYPASSED WHILE 2 E/E 1013C WAS REPLAELECTRICAL COMB CED. THE THREE REDUNDANT CHANNELS REMAINED OPERATIONAL. LER 78-57 (U-2

CALVERT CLIFFS-2 BECH ) DESCRIBES A SIMILAR EVENT.OTHER ENGNRD SAFETY FEATR SYSROUTINE TEST / INSPECTION ISCLATION TRANSFORM:" FGU:2 TO BE NON-LINEAR AND OSCILLATING AT MID-RANG

E, OUTPUT VOLTAGE APPROXIMATELY .25V HIGH IN NON-CONSERVATIVE DIRECTION.ISOLATOR WAS REPLACED. TRANSMATION MODEL 230-IT. ITEM 15 - ISOLATION

TRANSFORMER ITEM 19 - AN ENGINEERING EVALUATION OF THE REFETITItE FAILUprs or THESE UNITS IS CEING CONDUCTED.

TRAN5MATION, INC. 05000333 062978 WHILL PERFCRMING INSTRUMLNT SURVEILLANCL ILSI F-15P-10 "hPCI STEAM LINLINSTRUMENTATION + CONTROLS 78-049/03L-0 071278 HIGH TEMPERATURE INSTRUMENT FUNCTIONAL TEST / CALIBRATION" F OUND TEMPERATU

SWITCH 021712 30-DAY RE SWITCH 13-TS-107C INOPERATIVE. THIS SWITCH ACTIVATES UPON RECEIPT OFCOMPONENT FAILURE A/E A HIGH AMBIENT TEMPERATURE SIGNAL FROM THE TORUS AREA AND INITIATES A C

INSTRUMENT GE LOSE SIGNAL TO WCI STEAM SUPPLY INBOARD ISOLATION VALVE 23-MOV-15.FITZPATRICK-1 5+W

SYS REQRD FOR SAFE SHUTDOWNROUTINE TEST / INSPECTION SWITCH WAS REMOVED AND REPLACED. DEFECTIVE SWITCH WAS RETURNED TO VENDO

R FOR EVALUATION AND REPA!R.

UNITED ELEC. CONTROLS CO. 05000237 052878 DURING NORMAL PLANT OPERATION MAIN STEAM LINE (MSL) TEMPERATURE ISOLATIOINSTRUMENTATION + CONTROLS 78-034/03L-0 062278 N SWITCH 2-261-1S INITI ATED A GROUP I ISOLATION SIGNAL ON CHANNEL "A".

SWITCH 021539 30-CAY PLANT OPERATION CONTINUED AS PERMITTED BY T.S.3.2.A. THIS TYPE OF EVENTCOMPONENT FAILURE NSSS LAST OCCURRED ON 9/8/77 REPORT NUMBER 77-.'34. PLANT SAFETY WAS NOT CEG

ELECTRICAL GE RADED BECAUSE THE SWITCH FAlllPC La5 in THE CONSERVATIVE DIRECTION.DRESDEN-2 S+LCNTNMNT ISOLATION SYS + CONTOPERATIONAL EVENT CONTROL ROOM INSTRUMENTATION INDICATED N0 ABNORMAL TEMPERATURE IN MSL TU

NNEL AREA. VISUAL INSPECTION REVEALED NO STEAM LEAKS. AREA COOLERS WERE FUNCTIONING PROPERLY. THE 2-261-18A SWITCH, (1) 0F (16) INSTALLED SWITCHES. WAS JUMPERED TO CLEAR THE ISOLATION SIGNAL AND WILL BE CALIBRATEDAT THE EARLIEST POSSIBLE DATE.

CIm? 197

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COMPONENT MANUFACTURER DOCKET NO.COMPONENT / COMPONENT SUBCODE LER NO.CAUSE CODE /CAUSE SUSCODE CONTROL NO. EVENT DATEFACILITY / SYSTEM SUPPLIER REPORT DATE EVENT DESCRIPTIONMETHOD 0F DISCOVERY NSSS / A/E PEPORT TYPE CAUSE DESCRIPTION

,

UNITED ELEC. CONTROLS C0. 05000237 061978 DURING NORMAL PLANT OPERATION MAIN STEAM LINE (MSL) TEMPERATURE ISOLATIOINSTRUMENTATION + CONTROLS 78-038/03L-0 063078 N SWITCH 2-261-18C INITIATED A GROUP I ISOLATION SIGNAL ON CHANNP "A"

SWITCH 021678 30-DAf PLANT OPERATION CONTINUED AS PERMITTED BY TECH SPEC 3.2.A. THIS TYPE OCOMPONENT FAILURE NSSS F EVENT LAST OCCURRED ON S/28/78 REPORT NUMBER 78-034. THE SWITCH FAILU

ELECTRICAL GE RE ES IN THE CONSERVATIVE DIRECTION.DRESDEN-2 5+LCNTNMNT ISOLATION SYS + CONTOPERATIONAL EVENT CONTROL ROOM INSTRUMENTATION INDICATED NO ABNORMAL TEMPERATURE IN MSL TU

NNEL AREA. VISUAL NSPECTION REVEALED NO STEAM LEAKS AND THAT AREA COOLERS WERE FUNCTIONING. THE SWITCH, WHICH IS 1 0F 16 INSTALLED WAS JUMPER

ED TO CLEAR THE ISOLATION SIGNAL AND WILL BE CALIBRATED AT EARLIEST POSS19t E DATF.

UNITED LNG. & CONST RUCI. , INC. 05000289 051978 INSPLCIING REL1LF VALVL PIPING, A/L'5 FIELD LNGINLLRS D15 COWERED 2 RL5TRHANGERS SUPPORTS SHOCK.SUPPRSS 78-018/01T-0 060278 AINTS NOT INSTALLED ON EMERGENCY FEED PUMP TURBINE MAIN STEAM SUPPLY LINOTHER 021613 2-WEEK E RELIEF VA 1ES PIPING DRAWING. IF MS-V22A/B REQUIRED TO ACTUATE DUE T

DESIGN / FABRICATION ERROR A/E 0 TRANSIENT OR FAILURE, FAILURE OF RELIEF DISCHARGE FLEXIBLE CONNECTIONCONSTRUCTION /lNSTALLATION B+W COULD REts ' POTENTIALLY UNSAFE CONDITION WOULD OCCUR IN EVENT OF FIRE

THREE MILE ISLAND-1 GIL REQUIRING EVACUATION OF CONTROL E90M CONCURRENT WITH DISCHARGE LINE FAIMAIN STEAM SUPPLY SYS + CONT LURE.EXTERNAL SOURCE RELIEF DISCHARGE RESTRAINTS NOT INSTAiLED DURING CONSTRUCTION AS REQUIRE

D. IMMEDIATE CORRECTIVE ACTION: RE5141CT NONESSENTIAL ACCESS TO RELIEFVALVE AREA AND INITIATE ENGINEERING UCSIGN OF PROPER RESTRAINTS. EACH

OPERATING SHIFT ADVISED OF EMERGENCY ACTION TO ISOLATE SUCH A FAILURr

VALMONT INDUSTRIES 05000333 072178 BOTH INSTALLED PH METERS WHICH MONITOR MAKEUP DEMINERALIZER WASTE NEUTRAINSTRUMENTATION + CONTROLS 78-055/04L-0 080478 LIZER TANK (MUDWNT) DISCHARGE TO THE LAKE WERE FOUND TO BE INOPERATIVE.

SENSOR / DETECTOR / ELEMENT 0219351 30-DAYCOMPONENT FAILURE A/E

ELECTRICAL GE

FITZPATRICK-1 S+WPRCSS + EFF RADIOL MONITOR SYSRDUTINE TEST / INSPECTION ELECTRICAL GROUND IN CABLE. WATER TO BE DISCHARGED WAS MONITORED BY CHE

MISTRY LABORATORY PERSONNEL USING A PORTABLE PH METER AND AN APPROVED M0NITORING PROCEDURE. THE ELECTRICAL GROUND ON THE 'NSTALLED METERS WILLBE REPAIRED.

.

198


COMPONENT MANUFACTURER DOCKET NO.COMPONENT / COMPONENT SUBCODS LLR NO.CAUSE CODE /CAUSE SUBCODE CONTROL NO. EVENT DATEFACILITY / SYSTEM SUPPLIER REPORT DATE EVENT DESCRIPTIONMETHOD OF DISCOVERY NSSS / A/E REPORT TYPE CAUSE DESCRIPTION

VELAN VALVE CORP. 05000324 060378 DURING PLANT SHUTDOWN RHR VALVE WOULD NOT OPEN FROM CONTROL ROCH. DRYWEVALVE OPERATORS 78-052/03L-0 070378 LL INNER AIRLOCK DOOR WOLD NOT OPEN. ENTRY MADE THRU CRD HATCH. RHR V

ELECTRIC MOTOR - AC 021663 30-DAY ALVE OPENED. AIRLOCK DOOR GASKET WAS STICKING BECAUSE OF LEAK TEST PERFCOMPONENT FAILURE NSSS ORMED ON 6/6/78.

ELECTRICAL GEBRUNSWICK-2 UECRESIDUAL HEAT REMOV SYS + CONT ,

ROUTINE TEST / INSPECTION RHR VLV E11-F009 WAS OPND & AIRLOCK 000R MECHANISM WAS FOUND TO BE FUNCT(0NING PROP. SLI AB0VE NORMAL FORCE WAS APPLIED TO D00R FROM INSIDE PERSONNEL AIRLOCK & DOOR WAS OPENED. THE 000R WOULD NOT OPEN UNDER NORM FORCE DUE TO GA5kETS STICKING. THIS WAS CAUSED BY THE LRG AMT OF COMPRESSIVE FOPCE APPLIED TO TW CASvfTS PY A STPONG BArv

VELAN VALVE CORP. 0$000346 060778 FROM 6/7/78 10 6/11/78 SIX CONTAINMLNI 150LAllON CHLLK VALVLS INOPLRA3LVALVES 78-065/03L-0 070578 E DURING PERFORMANCE OF CONTAINMENT LOCAL LEAK RATE TEST. VALVE LEAKA3E

CHECK 021849 0-DAY IN EACH CASE WAS IN EXCESS OF LOCAL LEAK RATE TEST REQUIREMENTS. NO G.WCOMPONENT FAILURE A/E GER TO HEALTH AND SAFETY OF PUBLIC OR UNIT PERSONNEL. CONTAINMENT ISOLA

MECHANICAL B+W TION MAINTAINED BY EXISTING REDUNDANT ISOLATION VALVES IN SERIES WITH IZDAVIS-BESSE-1 BECH OPERABLE VALVES.CNTNMNT ISOLATION SYS + CONTROUTINE TEST / INSPECTION COMPONENT FAILURE. PARTICLES OF DIRT OR WEAR AND PITTING PREVENTED PROP

ER SEATING OF VALVES. DISCS AMD SEATS OF THREE VALVES WERE CLEANED OF DIRT. ALL THE VALVES WERE LAFPED AND SUCCESSFULLY RETESTED PER LOCAL LEAK RATE TEST.

VELAN VALVE CORP. 05000247 052378 DURING LOW POWER PHYSICS TESTING TEST OPERATIOZ0F ONE OF THE HIGH HEADVALVES 78-014/03L-0 062078 SIS PUMPS CONFIRMED SUSPECTED LEAKAGE PAST THE SEAT OF ONE OF SWING CHECHECK 021653 30-DAY CK VALVESZDOWNSTREAM UF PUMP NO. 22. SINCE THERE ZAS NO CONVENIENT WAY

COMPONENT FAILURE NSSS TO 4ANTIFY THE AMOUNT OF LEAKAGE, THE REACTOR WAS BROUGHT SUBCRITICALMECHANICAL WEST FOR DISASSEMBLY AND INSPECTION OF THE VALVE INTERNALS. THIS EZNT IS OF

INDIAN POINT-2 UEC THE TYPE DESCRIBED IN TECH SPEC 3.3.A.I.D.EMERG CORE COOLING SYS + CONTOPERATIONAL EVENT A VELAN 4-INCH PRIMARY SWING CHECK VALVE (DWG. 78501) WAS DISASSEMBLED

TO DETERMINE ZAUSE OF SEAT LEAKAGE. ON INSPECTION, THE VALVE DISC WAS FOUND ADRIFT WITH THE TWO HANGER BRACKET BOLTS AND LOCK BRACKETS MISSING.

THE VALVE WAS REASSEMBLED WITH NEW BOLTS.

cc 199

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CT:y,,NLO'J.

LICENSEE EVENT REPORTS Al

COMFONENT MANUFACTURER DOCKETNO.COMPONENT / COMPONENT SUBCODE LER NO.CAUSE CODE /CAUSE SUBCODE CONTROL NO. EVENT DATEFACILIT/ SYSTEM SUPPLIER REPORT ZATE EVENT DESCRIPTIONPETH0n OF DISCOVEPY NSSS / A/E PEPORT TYPE CAUSE OfSCPIPTION

VELAN VALVE CORP. 05000346 060578 AT 1529 6/5/78 DECAY HEAT FLOWRATE WAS REDUCED TO LESS TH;N 2600 GPM TOVALVES 78-063/03L-0 062878 LOWER REACTOR WATER LEVEL TO PERFORM MAINTENANCE ON CORE FLOOD LINE DISCCHECK 021851 30-DAY HARGE CHECK VALVE CF30. THI ZLACED UNIT IN ACTION STATEMENT OF T.S. 3.COMPONENT FAIZURE NSSS 9.8. NO DANGER TO HEALTH AND SAFETY OF PUBLIC OR UNIT PERSONNEL. ADEQUOTHER B+W ATE CORE COOLING EXISTED EVEN AT THE LOWER DECAY HEAT FLOWRATE.DAVIS-BZZSE-1 BECHRESIDUAL HEAT REMOV SYS + CONTOPERATIONAL EVENT

PLANNED REDUCTION OF WMEZ LEVEL TO REPAIR BONNET LEAK ON CORE FLOOD CHECK VALVE CF30. CAUSE OF BONNET LEAZWAS FAILURE OF BONNET GASKET. NEWGASKET INSTALLED ON CF30. AT 1325 6/6/78. Ri " '" WATER LEVEL WAS RAISE-

D AND DECAY HEAT FLOW RETLRNED TO 2800 GPM C. r ~.4.

SZELtN VALVE CORP. 05000346 050478 AT 0200 ON 5/4/7r, PERFORMING SERVICE WATER SYSTEM REFUELING TEST FOUNDVALVES 78-046/03L-0 z53073 EMERGENCY CORE COOLING R00f1 COOLING COIL AND CONTAINMENT AIR COOLER 1-1CHECK 021583 30-DAY OUTLET CHECK VALVE SW-82 INOPERABLE. VALVE FAILED REZRSE FLOW TEST. UCOMPONENT FAILURE A/E NIT IN MODE 6 DID NOT ENTER ACTION STATEMENT OF 3.7.4.1. NO DANGER TO H

CORROSION B+W EALTH AND SAFETY OF PUBLIC OR UNIT PERSONNEL. REVERSE FLOW PROTECTION MDAVIS-BESSE-1 BECH AINTAlt.ED BY REDUNDANT CHECK VALVES.STATION SERV WATER SYS + CONTROUTINE TEST / INSPECTION ''o 0F INTERNALS OF SW-82 WERE RUSTED PREVENTING PROPEOPERATION. VALV

E WAS OPENED, TOP INTERNALS CLEANED, AND OTHER VALVE COMPONENTS VISUALLYINSPECTED ON 5/7/78 PER SURVEILLANCE TEST ST 5075.02.

VICTOREEN INSikUMENT DIV. 05000345 | 072878 ON 07/28/78 AT 2110 CONTAINMENT VESSEL POST ACCIDENT RADIATION MONITOR RINSTRUMENTATION + CONTROLS 78-085/03L-L 082178 E 5029 DECLARED INOPERABLE. LOW FLOW LIGHT WAS LIT. PLACED UNIT IN ACTOTHER 022055 30-CAY ION STATEMENT A 0F T.S. 3.3.3.6 WHICH REQUIRES OPERABILITY OF BOTH POSTDESIGN / FABRICATION ERROR A/E ACCIDENT MONITORS IN MODES 1, 2 AND 3. NO DANGER TO HEALTH AND SAFETY 0MANUFACTURING B+W F PUBLIC OR UNIT PERSONNEL. THE REDUNDANT MONITOR RE 5030 WAS OPERABLEDAZZS-BESSE-1 BECH THROUGHOUT.AIRBORNE RADI0ACT MONITOR SYS '

ROUTINE TEST / INSPECTION COMPONCNT FAILURE. MOTOR PULLEY WAS REPLACED AND BELT INSTALLED. THE sUCCESSFUL COMPLETION OF SURVEILLANCE TEST ST 5099.05 AT 2022 ON 08/01/78

REMOVED UNIT FROM ACTION STATEMENT.

.

200

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COMPONENT MANUFACTURER DOCKET NO.COMPONENT / COMPONENT SUBCODE LER NO.CAUSE CODE /CAUSE SUBCODE CONTROL NO. EVENT DATEFACILITY / SYSTEM SUPPLIER REPORT DATE EVENT DESCRIPTIONMETHOD OF DISCOVERY NSSS / A/F "EPORT TYPE CAUSF DFSCRIPTION

_

VICTOREEN INSTRUMENT DIV. 05000346 051578 DURING ST 5031.04 DELTA T 0200 ON 5/15/78, FADIATION MONITOP. RE 20J4 C0INSTRUMENTATION + CONTROLS 78-052/03L-0 061278 ULD NOT BE CALIBRATED WITHIN TOLERANCE LIMITS. PLACED UNIT IN ACTION STSENSOR / DETECTOR / ELEMENT 021577 30-DAY ATEMENT 9 0F T.S.3.3.2.1. AT 0910 RE 2004 FOUND TO HAVE tsEEN UNTRIPPED

COMPONENT FAILURE A/E SINCE 0700 THAT DAY. UNIT THEN PLACED IN LCO 3.0.3. THREE OTHER PADIATOTHER B+W ION INSTRUMENT STRINGS OPERABLE WHILE RE2004 WAS OPERABLE.

DAVIS-BESSE-1 BECHENGNRD SAFETY FEATR INSTR SYSROUTINE TEST / INSPECTION COMPONENT FAILURE OF RADIATION MONITOR RE 2004. RADIATION DETECTOR RE 2

004 WAS REPLACED. RADIATION MONITOR WAS LEFT IN UNTRIPPED CONDITION DUETO PERSONNEL ERROR. AT 09I0 ON 5/15/78, RE 2004 AGAIN PLACED IN TRIPPE

D CONDITION.

VICT0REEN INSTRUMENT DIV. 05000346 062978 ON 6/29/78 AND 62f0/78, CONTAINMENT POST-ACCIDENT RAZIATION MONITOR RE 5INSTRUMENTATION + CONTROLS 78-075/03L-0 072678 03D FOUND INOPEfABLE MIT IN MODE 5. REPORT SUBMITTED AS DOCUMENTATI0SENSOR / DETECTOR / ELEMENT 021961 30-DAY N OF COMPONENT FAILL NO DANGER TO HEALTH AND SAFETY OF PUELIC OR UNI

COMPONENT FAILURE ZA/E T PERSONNEL. THE OTH T WTAINMENT POST-ACCIDENT RADIAT ION MONITOR, REINSTRUMENT B+W S029, OPERABLE WHILE RE 60 Ih7PERABLE.

DAVIS-BESSE-1 BECH

ENGNRD SAFETY FEATR INSTR SYSOPERATIONAL EVENT CAUSE WAS COMP 0NENT FAILURE. MOTOR PULLEY REPLAcrD AND BLT LOOSENED.

RE 5030 DECLARED OPERABLE 6/30/78.

-

VICT0REEN INSTRUMENT DIV. 05000346 060878 OPERATIONS PERSONNEL DISCOVERED LARGE FLOW OSCILLATIONS IN FLOW RATE OFPUMPS 78-064/03L-0 070578 CONTAINMENT POST-ACCIDENT RADIATION MONITOR RE 5030. MONITOR PUMP FAILE

VANE TYPE 021850 30-DAY D SHORTLY THEREAFTER. OPERABILITY OF THIS MONITOR NOT REQUIRED AS UNITCOMPONENT FAILURE A/E WAS IN MODE 6zz NO DANGER TO HEALTH AND SAFETY OF PUBLIC OR UNIT PERSONN

MECHANICAL B+W EL. REPORT SUBMITTED AS DOCUMENTATION OF COMP 0NENT FAILURE.DAVIS-BESSE-1 BECHAIRBORNE RADI0ACT MONITOR SYSOPERATIONAL EVENT THE CAUSE OF PUMP FAILURE STILL UNDER INVESTIGATION. MONITOR WILL BE RE

PAIRED PRIOR TO ENTERING MODE 4. REPORT WILL BE UPDATED WHEN MORE INFORMZION IS OBTAINED. PREVIOUS PUMP RELATED PROBLEMS WITH RADIATION MONITORS REPORTED IN LERS XZZZ#_&* #) AND NF-33-78-54._

9 201N7:5;

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LICENSEE EVENT REPORTS O

COMPONENT MfNUFACTURER DOCKET NO.COMPONENT / COMPONENT SUBCODE LER NO.CAUSE CODE /CAlFr 8 CODE C0fTROL NO. EVENT DATEFACILITV''"'..n SUPPLIER REPORT DATE EVENT DESCRIPTIONMFTHnD Ut DISCOVERY NSSS / A/E PEPORT TYP' CAUSE DESCRIPTION

VITRO ENGINEERING DIVISION 05000317 070878 DURING NORMAL OPERATION AN "SIAS ACTUATED" ALARM WAS RECEIVED AT 1632 WHINSTRUMENTATION + CONTROLS 78-034/03L-0 072778 EN SIAS LOGIC MODULE B-8 FAILED. THE MODULE WAS REPLACED AND SATISFACTOCOMPUTATION MODULE 021845 30-DAY RILY TESTED AT 1730. A SECOND SI AS LOGIC MODULE A-8. C APABLE OF ACTUATI

COMPONENT FAILURE NSSS NG REDUNDANT COMPONENTS, REMAINED OPERABLE THROUGHOUT THIS EVENT. T HIS

ELECTRONIC COMB IS NOT A REPETITIVE EVENT.CALVERT CLIFFS-1 BECH

EMERG00RE COOLING SYS + CONTOPERATIONAL EVENT SIAS B-8 LOGIC MODULE FAILED ACTUATING ALL SIAS B-8 EQUIPMENT. MODULE W

AS REPLACED WITH A SPARF. AND TESTED SATISFACTORILY. NO FURTHER CORRECTIVE ACTION IS DEEMED NECESSARY.

VITRO ENGINEERING DIVISION 05000155 071278 CHANNEL B 0F THE REACTOR DEPRESSURIZATION SYSTEM WAS REMOVED FROM SERVICINSTRUMENTATION + CONTROLS 78-030/03L-0 080778 E FOR CORRECTIVE MAINTENANCE AT 0852 HOURS FOLLOWING A TROUBLE ALARM WHEOTHER 021986 30-DAY N THE BATTERY FOR THAT LOOP WAS PLACED ON OVERCHARGE. THE OTHER THREE C

COMPONENT FAILURE A/E HANNELS WERE TESTED WITHIN FOUR HOURS PER T/S 4.1.5E. CHANNEL B WAS RES

ELECTRONIC GE T0ZZD TO SERVICE THE SAME DAY. THE COMPONENT FAILURE DID NOT DISABLE THE CHANNEL. FAILURE NOT REPE11TIVE.BIG ROCK POINT BECH

'

OTHER ENGNRD SAFETY FEATR SYS |

OPERATIONAL EVENT INVESTIGATION REVEALED DIODE FAILURES IN THE ANNUNCIATOR CIRCUITRY WHICHCAUSED AN ANNUNCIATOR POWER SUPPLY FUSE TO BLOW. THE DIODES WERE REPLA

CED. THE FAILURE IS NOT REPETITIVE AND WAS SELF ALARMING. REMOVAL FROMSERVICE IS REPORTABLE UNDER T/S 6.9.2.B.2.

WALWORTH CO. 05000277 060978 CONTROL ROOM OPERATOR OBSERVED THE DRYWELL SUMP PUMP 0UT RATE EXCEEDED THVALVES 78-029/03L-0 062678 E TECH SPEC LIMIT OF 5 GPM FROM AN UNIDENTIFED SOURCE. AN ORDER LY SHUTDGATE 021554 30-DAY (WN WAS INITIATED. PACKING LEAKS ON RECIRCULATION SYSTEM VALVE AND A Hr.

COMPONENT FAILURE A/E AD VENT MANUAL VALVE WERE REPAIRED AND THE UNIT WAS RETURNED TO SEZZICEMECHANICAL GE IN 48 HOURS. SAFETY SIGNIFICANCE IS MINIMAL.

PEACH BOTTOM-2 BECH

C00LANT RECIRC SYS + CONZROLSOPERATIONAL EVENT PACKING LEAK ON A HEAD VENT MANUAL VALVE AND RECIRC SYSTEM CROSS CONNECT

VALVE MO-2-2-65B CAUSED THE DRYWELL SL"P PUMPOUT RATE TO EXCEED THE TECh SPEC LIMITS. THE PACKING WAS REPLACED flD THE UNIT RETURNED TO SERVIC

E. SIMILAR OCCURRENCES HAVE BEEN REPL <TED IN THE PAST.

202


COMPONENT MANUFACTURER DOCKET NO.COMPONENT / COMPONENT SUBCODE LER NO.CAUSE CODE /CAUSE SUBCODE CONTROL NO. EVENT DATEFACILITY / SYSTEM SUPPLIER REPORT DATE EVENT DESCRIPTIONMETHOD OF CISCOVERY NSSS / A/F REPORT TYPF CAUSF DESCRIPTION

.

WATLOW ELECTRIC MFG. CO. 05z00255 062178 DURING NORMAL PLANT OPERATION, ONE OF THE TWO HEATERS F0ZZT-53B (CONCENTHEATERS ELECTRIC 78-025/03L-0 072078 RATED BOIC ACID TANK) FAILED. REPAIRS NECESSITATED REMOVING THE TANK F

SUBCOMPONENT NOT APPLICABLE 021804 30-DAY ROM SERVICE. THIS OCCURRENCF IS A DEGRIDED MODE PERMITTED BY THE LC0 0FCOMPONENT FAILURE NSSS T.S. 3.2.3. EVENT HAD NO ADVERSE EFFECT ON PUBLIC HEALTH OR SAFETY.

ELECTRICL COMBPALISADES-1 BECHCHEM, V0L CONT + LIQ POISN SYSMETHOD OF DISC. NOT APPLICABLE THE ELECTRIC HEATER FOR T-53b burned out. the heater was repla ced and t

he tank was returned to service. this type of failure is considered tobe normal; NO FURTHER CORRECTIVE ACTION IS CONTEMPLATED.

WAUKESHA ELEC. MACH. MFG. CO. 05000261 070278 AT 0808 ON JULY 2, 1978, THE ENGINE DRIVEN FIRE WATER PUMP FAILED TO STAENGINES. INTERNAL COMBUSTION 78-017/03L-0 073178 RT DURING PERIODIC TESTING RESULTING IN OPERATION IN A DEGRADED MODE PER

SUBCOMPONENT NOT APPLICABLE 021897 30-DAY MITTED BY TECHNICAL SPECIFICATIONS PARAGRAPH 3.14.2.2. THE MOTOR DRIVENCOMPONENT FAILURE A/E FIRE WATER FUMP WAS OPERABLE DURING THE PERIOD THAT THE ENGINE DRIVEN F

CORROSION WEST IRE WATER PUMP WAS OUT OF SERVICE. THIS CONSTITUTES A REPORTABLE OCCURRH. B. ROBINSON-2 EBASCO ENCE PER TECHZICAL SPECIFICATION PARAGRAPH 6.9.2.B.2.FIRE PROTECTION SYS + CONTROUTINE TEST / INSPECTION THE EP31NE DRIVEN FIRE WATER PUMP FAILED TO START DUE TO CORROSION ON TH

L CONTACTS OF THE DISTRIBUTOR CAP. THE CORROSION WAS REMOVED AND THE LNIT WASRETURNED TO SERVICE AT 1405 ON JULY 5, 1978.

WEST. ELECTRIC CO. (EL V DIV) 05000029 060778 DURING NORN PLANT OPNS, THE #1 STEAM GENERATOR RADIO ACTIVE 1' QUID MONITINSTRUMENTATION + CONTROLS 78-015/031.-0 070778 OR OPERATED ERRATICALLY. AT NO TIME DID THE STACK MONIT0" sR THE AIR E

SENSOR / DETECTOR / ELEMENT 021684 30-DAY JECTOR MONITOR INDICATE AN INCREASE IN RADIATION L EVELS. THEREFORE, THEDESIGN / FABRICATION ERROR LIC RE WAS NO EFFECT ON PUBLIC HEALTH OR SAFETY.

CONSTRUCTION / INSTALLATION WESTYANKEE R0WE 5+WOTHER COOLANT SUBSYS + CONTROLOPERATIONAL EVENT DEFECTIVE SOLDER CL''.ECTlun IN THE RADIATION MONITOR COMPUTER-INDICATOR

(WESTINGHOUSE TYFE FN 2508, MODEL CS10-G) TEMPORARY MONITOR PROVIDED WHILE DEFECTIVE MONITOR REPAIRED. CHANNEL WILL BE REPLACED.

203mNOh.)w3N

CQfwNLC

LICENSEE EVENT REPORTS Nv


_

WESTERN INC. 05000338 080278 DURING CRITICAL STEADY STATE OPERATION AN INDICATED QUADR ANT POWER TILTINSTRUMENTATION + CONTROLS 78-075/03L-0 082178 0F GREATER THAN 1.02 WAS NOTED. THIS WAS IN VIOLATION OF THE 1.02 LIMI

SENSOR / DETECTOR / ELEMENT 022040 30-DAY T AS PER T.S. 3.2.4. (THE CALCULATED TILE RATIO WAS 1.0209). THE HEALTHCOMPONENT FAILURE NSSS AND SAFETY OF THE GENERAL PUBLIC WERE NOT AFFECTED. PREV OBUR - LER 7

INSTRUK NT WEST 8-71.NORTH ANNA-1 S+WREACTOR COREOPtRATIONAL EVENT THE OV.URRENCE IS BELIEVED TO BE DUE TO A FAULTY POWER RANGE DETECTOR (N

-44). THIS DETECTOR IS PRESENTLY BEING MONITORED FOR DRIFT AND WILL BEREPLACED OUPING THE NEXT APPROPRIATE OUTAGE. THE IMMEDIATE ACTION WAS T0 WITHDRAW RODS WHICH REDUCED THE QUADRANT POWER RATIO TO WITHIN TECH. SPEC LIMITS.

WESTINGHOUSE LLECTRIC CORP. 05000271 1 042678 UURING MUNTHY SURVEILLANCE, SBGT SYSTLM 'B' FAN TRIPPED ON THERMAL OVERLCIRCUIT CLOSERS / INTERRUPTERS 78-011/03L-0 052678 OAD. 'A' TRAIN WAS AVAILABLE. AN OPERATOR ADJUSTED A FLOW DPMPER TO IN

OTHER 021458 30-DAY CREASE FLOW TO EXPECTED LEVELS. FOLLOWING READJUSTMENT TO GIVE NORMAL FCOMPONENT FAILURE A/E AN AMPERAGE READINGS AND NORMAL SYSTEM FLOW. NO PROBLEMS OCCURRED.

ELECTRICA GEVERMONT YANKEE-1 EBASCOCNTNMNT AIR PURI + CLEANUP SYSROUTINE TEST / INSPECTION FAN TRIPPED ON THERMAL OVERLOAD FROM HIGH FLOW RATE. FLOW INSTRUMENTATI

ON WAS READING LOW AND WAS CORRECTED. THIS PLUS DAMPER ADJUSTMENT CAUSEDFAN TO OVERSPEED, ADJUSTED FAN OVERLOAD SETTING FROM 100 TO 115 % ON B0

TH SBGT UNITS.

WESTINGHOUSE ELECTRIC CORP. 05000348 , 070678 ATTEMPTING TO PERFORM FNP-1-STP-26.0, CONTROL ROOM TRAIN B VENTILATION 0CIRCUIT CLOSERS /INTERRUPTZRS 78-046/03L-0 080378 PEZCBILITY TEST, CONTROL ROOM A/C UNIT IB WAS INOPERABLE. CONTROL ROOMCIRCUIT BREAKER 021976 30-DAY FILTRATION RECIRC FAN IB WILL NOT RUN IF CONTROL ROOM PACKAGED A/C UNIT

COMPONENT FAILURE SS IB IS NOT RUNNING. T/S 3.7.7.1 REQUIRES TWO INDEPENDENT CONTROL ROOM EMELECTRICAL WEST ERGENCY VENTILATION SYSTEMS OPERABLE. IB SYSTEM DECLARED INOPERABLE AT

JOSEPH M. FARLEY-1 SSC/BECH 0740 AND RETURNED OPERABLE AT 1100. T/S REQUIREMENTS MET.CCNT ROOM HABITBLTY SYS + CONTROUTINE TEST / INSPECTION FAULTY CIRCUIT BREAKER IN IB CONTROL ROOM PACKAGED n/C UNIT REPLACED, FN

P-1-STP-26.0 SATISFACTORILY COMPLETED. HEALTH AND SAFETY OF PUBLIC NOTAFFECTED.

204

i_ICENSEE EVENT REPORTS

COVPONENT MANUFACTURER DOCKET NO.C0MPONENT/ COMPONENT SUBCODE LER NO.CAUSE COCE/CAUSE SUBCODE CONTROL NO. EVENT DLTEFAZlLITY/ SYSTEM SUPPLIER REPORT DATE EVENT DESCRIPTIONMFTHOD OF V7500VFPY N;SS / A/F RFPORT TYPF CAUSE DESCRIPTION

WESTINGHC'USE ELECTRIC COPP. 05000244 052978 DURING TEST, OSI PUMP FAILED TO START FROM BUS 14 BREAKER ON 2 ATTEMPTS.CIRCUIT CLOSERS /INTERPUPTERS 78-007/03X-1 060678 THE PUMP WAS STARTED SUCCESSFULLY WITH THE BUS 16 PREAKER. SUB L T

CI*CUIT BREAKER 021670 OTHER LY BUS 14 BREAKER STARTED PUMP SUCCESSFULLY. THIS INCIDENT IS SIMILARCOMPONENT FAILUPE NSSS 0 7 EVENTS INVOLVING THE BUS 16 BREAKER AND 1 EVENT WITH KE BUS 14 BREAOTHER WEST KE R . REPLACEMENT BREAKER WAS TESTED AND INSTALLED.

PCBERT E. GINNA-1 GILEMERG CORE COOLING SYS + .JNTROUTINE TEST / INSPECTION INSPECTION OF CIRCUIT BREAKER REVEALED NO APPARENT CAUSE FOR FAILURE. (I

PCUIT BREAKER IS WESTINGHOUSE MODEL DB-50, 600 VAC. IT WAS RETURNED TO WESTINGHOUSE FOR FURTHER INVESTIGATION. WESTINGHOUSE REPORTSD THAT, AS RECEIVED, BREAKE.1 WAS IN GOODJCONDITION EXCEPT FOR A MISSING BELL ALARM SPPING AND A PENT GPOUND CONTACT.

WESTINGHOUSE ELECTRIC CUkP. 05000266 051778 WHILE AIILMPilNG 10 fha 5L IFL 40 LMLkGtNCY DIESEL GLNERAIUR (EDG, 1 UF 2;w CIRCUIT CLOSERS /INTEPRUPTERS 78-008/03L-0 060578 ) DURING A TEST AT 0410 HOURS ON 5/15/78, THE BREAKER (1-A52-66) WOULD N

CIRCUIT BREAKER 021445 30-DAY OT CLOSE ON TO B.G.NEERED SAFEGUARDS BUS 1-A06. THUS, 4D EDG WAS NOT AVCOMPONENT FAILURE NSSS AILAELE FOR UNIT 1. THE REDUNDANT 3D EDG WAS PLACED ON LINE TO VERIFY 0

ELECTRICAL WEST PE PABIL ITY. T.S.15.3.7.B.1.E PERMITS ONE EDG TO BE INOPERABLE FOR UP TFCINT BEACH-1 EECH 0 SEVEN DAYS.EMERG GENERATOR SYS + CONTROLSRCUTINE TEST? INSPECTION EPEAKER 1-A52-66 WAS REPAIRED AND TESTED AND A SUCCESSFUL TEST RUN OF TH

E 4D ECG WAS COMPLETED. BREAKER F**; FD TO CLOSE BECAUSE A WESTINGHOUSE CAT. NO. 662A143H01 LATCH-CHECKING SWIisti WAS DEFECTIVE. SWITCH FEPLACED

IN KIND.

WESTINGHOUSE ELECTRIC COFP. 05000338 072878 WHILE INVESTIGATING A SIMULTANE0US HI AND LO FLOW ALARM IN THE SAMPLE LIFILTERS 78-063/03L-0 082178 *E FOR CONTAINMENT PARTICULATE AND GAS RADIATION MONITORS, THE PA RTICULA.

SUBCOMPONENT NOT APPLICABLE 022035 30-DAY TE FILTER AND CHARCOAL FILTER WERE FOUND TO BE CLOGGED. THIS CAUSED BOTCOMPONENT FAILURE A/E H CHANNELS TO INDICATE A RADIATION LEVEL LESS THAN ACTUAL. REPORTAELE B

VECHANICAL WEST Y T.S. 6.9.1.9.B. EVENT HAD NO EFFECT ON HEALTH OR SAFETY OF PUBLIC.NORTH ANNA-1 5+WAIRE 0RNE PADICACT MONITCR SY5OPERATIONAL EVENT THE FILTER F0P, RM-RMS-159, CONTAINMENT PARTICULATE MONITOR BECAME CLOGGE

D EECAUSE THE CRIVING MUHANISM FOR THE CONTINU0US FILTER CECAME JAMMED.CHAPCOAL FILTER FOR RM-RMS-If0z GAS RACIATION MONITOR, WAS ALSO CLOGGE

C. WILL CHECK ON PPCPER OPERATION OF THE CONTINUOUS FILTER AND CHANGE THE CHARCOAL FILTER PERIODICALLY.

2N 2057,

N-Qv%

V:i(s:el

'. 1LICENSEE EVENT REPORT 3 CO

COMPONENT MANUF ER DOCKET NO.COMPONENT / NENT SUBCODE LER N0.CAUSE CODE /CAUSE SUBCODE CONTROL NO. EVE 0T DATEFACILITY / SYSTEM SUPPLIER REPORT DATL EVENT DESCRIPTIONMETHOD OF DISCOVERY NSSS / A/E REPORT TYP CAUSE DESCRIPTION

WESTINGHOUSE ELECTRIC C0rtP. 05000348 053078 120V VITAL AC BUS D DEENERGIZED WHEN INVERTFR ID TRIPPED. REACTOR TRIPGENERATORS 78-032/03L-0 060878 RESULTED. T.S.3.8.2.1 SPECIFIES 120V VITAL AC BUS D SHALL BE OPERABLE, E

INVERTER 021591 30-DAY NERGIZED, AND ALIGNED TO AN OPERABLE DIESEL GENERATOR. 120V AC DIST. PACOMPONENT FAILURE NSSS NEL ID ENERGIZED FROM ALTERNATE SUPPLY TO RESTORE POWER TO AFFECTED INST

ELECTRICAL WEST RUMENTATION. THE OTHER VITAL AC BUSES WERE OPERABLE. TECH SPEC REQUIREJOSEPH M. FAREY-1 SSC/BECH MNTS WERE MET. THE KALTH AND SAFETY OF THE PUBLIC WERE NOT AFFECTED.AC ONSITE POWER SYS + LONTROLSOPERATIONAL EVENT INVERTER TRIP WAS CAUSED BY FAILURE OF CAPACITOR IN INVERTER. REPLACEME

NT OF THE CAPACITOR SHOULD BE COMPLETED BY 6/9/78. REPLACEMENT OF INVERTER CAPACITORS WILL BE ESTABLISHED AS A PREVENTIVF MAINTENANCE PROGRAM I

TEM. PREVIOUS OCCURRENCE REPORTED IN LER 79 031/03L-0.

WESTINGHOUSE ELECTRIC CORP. 05000348 , 022378 120V VITAL AC BUS B WAS DEENERGIZED W5:iN INVERTER IB TRIPPED. REACTOR TGENERATORS 78-031/03L-0 060878 RIP RESULTED. T.S.3.8.2.1 SPECIFIG 120V VITAL AC BUS B SHALL BE OPERAB

INVERTER 021592 30-DAY LE, ENERGIZED AND ALIGNED TO AN OPERABLE DIESEL GENERATOR. 120V AC DISTCOMPONENT FAILURE NSSS . PANEL IB ENERGZED FROM AL'ERNATE SUPPLY TO RESTORE POWER TO AFFECTED

ELECTRICAL WEST INSTRUMENTATION. THE OTHER \lTAL AC BUSES WERE OPERMLE. TECH SPEC REQJOSEPH M. FARLEY-1 SSC/BECH UIREMENTS WERE MET. HEALTH AND SAFETY OF PUBLIC NOT AFFECTED.

5 AC ONSITE POWER SYS + CONTROLS |OPERATIONAL EVENT I FAULTY CAPACITOR lAS REPLACED. KEPLACEMENT OF INVERTER CAPACITORS WILL

BE ESTABLISHED AS A PREVENTIVE MAINTENANCE PROGRAM ITEM. THIS OCCURRENCE WAS CONSIDERED REPORTABLE AT THE TIME OF THE INCIDENT.

WESTINGHOUSE ECTRIC CORP. 05000266 052878 DURING NORMAL OPERATION, INDICATION OF A SMALL PRIMARY-TO-SECONDARY LEAKHEAT EXCHANGERS 78-010/01T-E 061078 ]] IN THE "A" SG WAS NOTED ON 5-24-78. THE LEAK INCREASED TO 145 GPD ON 5

STEAM GENERATOR 021465 2-WEEK -25-78 WHEN THE DECISION WAS MADE TO SHUTDOWN & COMPLETE THE SG REPAIRCOMPONENT FAILURE NSSS I CONJUNCTION WITH A SCHECJLED OUTAG E. THE SOURCE OF THE IEAK WAS VERI

MECHANICAL WEST FIED TO BE A TUBE AT POSITION R44C58. EVENT IS SIMILAR TO LER'S 50-266/POINT BEACH-1 BECH 77-f, AND 78-001/01T-0.COOLANT RECIRC SYS + CONTROLSOPERATIONAL EVENT NO EVIDENCE HAS BEEN FOUND TO CONCLUSIVELY DETERMINE THE CAUSE OF THE TU

BE FAILURE. THE TUBE WAS PLUGGED ON 5-28-78 AND THE UNIT RETURNED TO LIM,E ON 5-30-78.

206

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COMPONENT MANUFACTURER DOCKET NO.COMPONENT / COMPONENT SUBCODE LER NO.CAUSE CODE /CAUSE SUBCODE CONTROL NO. EVENT DATEFACILITY / SYSTEM SUPPLIER REPORT DATE EVENT CESCRIPTIONMETHOD OF DISCOVERY NSSS / A/E PEPORT TYPE CAUSE DESCRIPTION

WESTINGHOUSE ELECTRIC CORP. n5000295 051078 DURING NORMAL OPERATION 3, THE UNIT 1 CONTAINMENT GAS MONITOR.1RE0012. RINSTRUMENTATION + CONTROLS 78-041/03L-0 060978 EPEATEDLY BLEW FUSES. THE MONITOR WAS TAKEN OUT OF SERVICE DURING THE FOTHER 021448 30-DAY IRST SHIFT FOR INSTRUMENT REPAIR. THE MONITOR WAS PUT BACZZIN SERVICE D

COMPONENT FAILURE NSSS URING THE SECONC SHIFT OF THE SAME DAY. NO SAFETY IMPLICATIONS WERE INVELECTRICAL WEST OLVED AND THE HEALTH AND SAFETY OF THE PUBLIC WAS NOT AFFECTED.

ZION-1 S+LAIRBORNE RADI0ACT MONITOR SYSOPERATIONAL EVENT THE INVESTIGATION REVEALED THAT THE POWER LIGHT HOLDER WESTINGHOUSE PAR

T #429151, WAS SHORTING OUT THE RADIATION MONITOR. THIS PART WAS REPLACEO AND THE MONITOR WAS RESTORFD TO SEkVICE. THIS WAS THE FIRST EVENT OFTHIS NATURE. NO FURTHER ACTION NECESSARY.

WESTINGHOUSE ELECTRIC CORP. 05000338 061778 A NONCONSERVATIVE DRIFT WAS FOUND IN A STEAM LINE DELTA-P PROTECTION LOGINSTRUMENTAfl0N + CONTROLS 78-054/03L-0 071278 IC COMPARATOR. THIS WAS PART OF 4 0F 3 LOGIC FOR 2 0F 3 STEAM LINES THU

OTHER 021889 30-DAY S REDUNDANT PROTECTION WAS /,nILABLE IF REQUIRED. THE HEALTH AND SAFETYCOMPONENT FAILURE NSSS OF THE GENERAL PUBLIC WERE NOT AFFECTED.

ELECTRONIC WESTNORTH ANNA-1 S+WENGNRD St.FETY FEATR INSTR SYSROUTINE TEST / INSPECTION THE DRIFT IN SETPOINT WAS FOUND TO BE DUE TO A F/ULTY COMPARATOR CARD.

THE CARD WAS REPLACED AND THE PROTECTION CHANNEL WAS RECALIBRATED AND RETURNED TO SERVICE.

WESTING 9OUSE ELECTRIC CORP. 05000272 961478 DURING STARTUP, THE REACTOR OPERATO3 IDENTIFIED CONTROL BANKS A, B C, DINSTRUMENTATION + CONTROLS 78-030/03L-1 071078 AND SHUTDOWN RODS ISA1 AND ISA3 WERE FOUND TO BE GREATER THAN 12 STEPS

INDICATOR 021671 30-DAY FROM THE BAFK DEMAND POSITION. WITHIN 6 HRS, REACTOR WAS MANUALLY TRIPPCOMPONENT FAILLRE NSSS ED FROM 1% "0WER TO COMPLY WITH T.S. POSITION INDICATORS WERE RECALIBPA

ELECTRONIC WEST TED & CONF'.RMED TO BE OPERABLE. THIS IS THE THIRD OCCURRENCE OF THIS TYSALEM-1 0 PE

CTHR INST SYS NOT REQD FR SFTYROUTINE TEST / INSPECTION THE CAUSE OF THIS OCCURENCE WAS INSTRUMENT DRIFT. CONTROL BANKS WEPE CA

LIBRATED AT THE BOTTOM POSITION. AFTER WITHZRAWEL, NON-LINEAR RANGES RESULTED IN OUT OF SPEC INDICATION. RFCALIBRATION OF CONTROL AND SHUTDOWNRODS CORRECTED THE GREATER THAN 12 STEP CONDITION.

(!) 207ft)17;

?N)s}m

N[wN:.

LICENSEE EVENT REPORTS N1)

COMPONENT MANUFACTURER DOCKET N0.COPPONENT/ COMPONENT SUBCODE LER NO.CAUSE CODE /CAUSE SUBCODE CONTROL NO. EVENT DATEIFACILITY / SYSTEM SUPPLIER REPORT DATE EVENT DESCRIPTIONMETHOD OF DISCOVERY NSSS / A/E REPORT TYPE CAUSE DESCRIPTION

WESTINGHOUSE ELECTRIC CORP. 090v0272 062078 WHILE PERFORMING SURVEILLANCE PROCEDURE FOR R0D CONTROL ASSEMBLIES, CONTINSTRUMENTATION + CONTROLS 76-031/03L-0 071278 ROL BANK D RODS WERE FOUND TO BE GREATER THAN 12 STEPS ABOVE BANK DEMANDINDICATOR 021911 30-DAY POSITION. POSITION INDICATORS WERE REALIGNED AND CONFIRMED TO BE OPERACOMPONENT FAILURE NSSS BLE. THIS IS THE FOURTH OCCURRENCE OF THIS TYPE.ELECTRONIC WEST

SALEM-1 0OTHR INST SYS NOT REOD FR SFTYROUTINE TEST / INSPECTION CONTROL BANK D hAD PREVIOUSLY BEEN CALISRATED AT A LOWER SANK POSITION.

AS THE RODS WERE MOVED TO A HIGHER POSITION SYSTEM NON-LINEARITY AND INSTRUMENT DRIFT DUE TO TEMPERATURE CHANGES IN THE INDICATOR COILS CAUSEDTHE GZZZTER THAN 12 STEP ERROR. REALIGNMENT OF CONTROL BANK D RODS CORprrTF0 Tpr FDDOD

WESTINGHOUSE ELECTRIC CORP. 05000316 050778 DURING NORMAL OPERATION, 22 EVENTS OCCURRED BETWEEN THE DATLS OF MAY 7 AINSTRUMENTATION + CONTROLS 78-031/03L-0 060678 ND MAY 19. WHERE R0D POSITION INDICATION (RPI) DID NOT MEET THE +12 STEPINDICATOR 021425 30zday limit of t.s.3.1.3.2. THE ATTACHED SUPPLEMENT DESCRIBES ALL THESE EVENCDNPONENT FAILURE NSSS TS. AFTER THE EVENT ON 5/16/78 THE RPI FOR D-8 WAS DECLARED INOPERABLOTHER WEST E. THE ACTION REGUIREMENT OF T.S.3.1.3.2A WAS FULFILLED. PRE'v10VS O&CUD. C. C00K-2 AEP RRENCES OF A SIMILAR NATURE INCLUDE R0-050/315-78-07, Ozz 77-34, 33, 28,OTHR INST SYS REQD FOR SAFETY 27, 76-54, 44, 13 R0-050/316-78-22,08.07OPERATIONAL EVENT

INVESTIGATION REVEALED THAT MOST OF THESE EVENTS INVOLVED MEASURING THEAFECTED ROD'S SECONDARY COIL VOLTAGE TO VERIFY THAT THE ROD WAS AT THE PROPER POSITION. THE SIGNAL CONDITIONING MODULE WOULD THEN BE CALIBRATEDAND PLACED BACK IN SERVICE RETURNING RPI TO WITHIN THE +/- 12 STEP LIMI

T.WESTINGh0LSE ELECTRIC CORP. 05000316 060278 DURING N0kMAL OPERATION, kdD PU51TI'N INCICATION FOR CONTROL'n00 0-8 DIDO

INSTRUMENTATION + CONTROLS 78-041/03L-0 L33078 NOT MEET THE +/-12zSTEP LIMIT OF T.S.3.1.3.2. PREVIOUS OCCURRENCE. OFINDICATOR 021630 30-DAY A SIMILAR NATURE INCLUDE: R0-050/316-78-31,2,08,07. R0-050/315-78-37,COMPONENT FAILURE NSSS 04, 77-34,33,it 27,76-54,44,13.

OTHER WESTD. C. C00K-2 AEPOTHR INST SYS REQD FOR SAFETYOPERATIONAL EVENT

INVESTIGATION REVEALED THAT THE SIGNAL CONDITIONING MODt.E OUTPUT VOLT"GE WAS HIGH. AFTER THE ROD'S SECONDARY C0!L VOLTAGE ViS MEASURED TO VERIFY THAT THE R0D WAS AT THE CORRECT POSITION, THE SIGN 4L CONDITIONING WAS

RECALIBRATED AND PLACED IN SERVICE RETURNING RPI TC WITHIN THE +/- 12-5TEP LIMIT.

208


CCMPONENT MANUFACTURER C0CKET NO.COMPONENT / COMPONENT SUECODE LER NO.CAUSE C002/CAUSE SUBCODE CONTROL NO. EVENT DATE

FACILITY / SYSTEM SUPPLIER REPORT DATE EVENT DESCRIPTIONMETHOD OF DISCOVEPY NSSS / A/F PEPORT TYPF CAUSE DESCRIPTION

WESTINGHOUSE ELECTRIC CORP. 05000315 062378 WHILE IN P.DDE 2 THE INDICATED POSITION OF RODS C-3, C-13. N-13, N-3, H-6'

INSTRLMENTATION + CONTROLS 78-038/03L-0 072I78 , F-8 AND K-8 INDICATED A DEVIATION OF GREATER THAN TWELVE STEPS FROM DEINDICATCR 021770 30-DAY MAND POSITION. THIS IS IN EXCESS OF THE LIMIT IDENTIFIED BY T.S.3.1.3.2

COMPONENT FAILLRE NSSS SIMILAR OCCURRENCES PREVIOUSLY SUBMITTED ARE: 0315/76-13, 44 AND 54;OTHEP WEST 0315/77-27,28,33, AND 34; 0315/78-04,07, AND 0316/78-07,08,22,31 AND 41

D. C. C00K-1 AEP

OTHR INST SYS PEQD FOR SAFETYOPERATIONAL EVENT THE CAUSE hAS TRACED TO THE SIGNAL CONDITIONING MODULES WHICH WERE RESPA

NNED AND SATISFACTORILY RETURNED TO SERVICE AFTER SECONDARY VOLTAGE WASVERIFIED TO BE CORRECT PER POSITION DEMAND. THE EXTERNAL CAUSE OF INDICATOR DRIFT HAS NOT BELN DETERMINED ALTHOUGH AN ENGINEERING REVIEW IS INp per,pE( S .

WL5TINGHOUSL LLECTRIL CORP. 05000315 070578 WHILL 2N MODL 1 Iht INDICAILD P051110N OF kOD D-4 INDICATED A ULVIATIONINSTP; MENTATION + CONTROLS 78-040/03L-0 080478 0F GRE ATER THAN TWELVE STEPS FROM DEMAND POSITION. THIS IS IN EXCESS OF

It.DiCATOR 021927 3C-DAY THE LIMIT IPTOSED Bf T.S. 3.1.3.2. SIMILAR OCCURRENCES CF THIS TYPE PR

CLMf0NENT FAILURE NSSS EVIOUSLY SUBMITTED ARE 0315/76-13.44 AND 54; 0315/77-27,28,33 AND 34;INSTPUMENT WEST 0315/78-04,07,38, AND 0316/78-07,08.22,31. AND 41.

C. C. C00K-1 AEP

CTH INST SYS RE00 FOR SAFETYFM TINE TEST / INSPECTION THE CAUSE WAS TRACED TO THE SIGNAL CONDITIONING MODULE WHICH HAD DRIFTED

HIGH. THE MODULE WAS PESPANNED AND THE INDICATED POSITION OF ROD D-4 RETUPNED TO WITHIN SPECIFICATIONS. THE ROOT CAUSE OF THIS FF0BLEM HAS NOT YET BEEN CETERMINED ALTHOUGH AN ENGINEERING REVIEW IS IN PROGRESS.

WESTINCb0u E EIFCTRIC CCRP. 05000315 07197E WHILE IN MCDE 1 THE INDICATED POSITION OF RODS H-10 G-5, E-9, C-9. P-8

INSTPLMENTATICN + CCNTROLS 78-C46/03L-0 081478 AND K-6 INDICATED A DEVIATION CF GREATER THAN TWELVE STEPS FROM DEMAND PINDICATOP 021948 3C-DAY OSITICN. THIS IS IN EXCESS OF THE LIGHT IMPOSED BY T.S. 3.1.3.2. SIMIL

C0f*PONENT FAILLPE NSSS AR OCCURREf.CES OF THIS TYPE PREVIOUSLY SUBMITTED ARE; 050-03B/76-13, 44

INSTPLMENT WEST AND 54, 0315/ 77-27,2'',33 AND 34, 0315/78-04-07,38, AND 050-0316/ 78-07,0D. C. C00K-1 AEP 8,22, 31 AND 41.OTHP INST Sv5 PECD FOP SAFETYCPE PATIONAL EVENT THE CAUSE WAS TRACED TO THE 5. 7AL CONDITIONING MODULES WHICH HAD DRIFTE

D HIGH. THE MODLLES WEFE FESPANNED AND THE INDICATED POSITIONS OF THE SIX ROCS RETURNED TO WITHIN SPECIFICATIONS. THE ROOT CAUSE OF THIS PROBLEM HAS NOT YET BEEN CETEPMINED ALTHOUGH AN ENGINEERING REVIEW IS IN PROGPESS.

CO 209NCiNMG)

(Y:{~N, -

LICENSEE EVENT REPORTS {$COMPCNENT MANUFACTURER DOCKET NO.COMPONENT / COMPONENT SUBCODE LER NO.CAUSE C0CE/CAUSE SUBCODE CONTROL NO. EVENT DATEFACILITY / SYSTEM SUPPLIER REPORT DATE EVENT DESCRIPTIONPETHOD OF DISCOVERY NSSS / A/F PEPORT TYPE CAU(E D ESCRIPTION

!WESTINGHOUS: ELECTRIC CORP. 05000348 070678 PERFORMING FNP-1 ?-5.0, FULL LENGTH CONTROL ROD OPERABILITY TEST, CONTINSTRUMENTATICN + CONTROLS 78-047/03L-0 080378 ROL BANK A WOULD NOT MOVE ON DEMAND. T/S J.1.3.1 REQUIRES ALL FULL LENGOTHER 021977 30-PAY TH RODS OPEPABLE. THEY WERE DECLARED INOPERAEL AT 1000. RETURNED OPER

COMPONENT FAILURE NSSS ABLE AT 1925. T/S PEQUIREMENTS MET. BANK A WOLLD HAVE MOVED IN AUTO ORELECTRONIC WEST NORMAL, AND 4LLD HAVE INSERTED ON SSPS TRIP SIGNA'. ONLY FUNCTION IMP

JOSEPH M. FAPLEY-1 SSC/'ECH AIPED WAS INDIVICUAL BANK SELECT FCR BANK A. HEALT / SAFETY OF PUBLIC NOREACTIV3 Y CONTFCL SYSTEMS i AFFECTED.ROUTINE TEST /INc DEC' ION SJPLRVISORY *EVORY BUlFER PRINTED CIFCUIT CARD FAI' J AND WOULD NOT PASS

DEM ND SIGNAL FOR BANK A ROD MOTION. THE PRINTED ,IRCUIT CAFD WAS REPLACED AN] FNP-I-STP-5.0 WAS SATISFACTCRILY COMPLETE.

WESTINGHOUSE ELECTo'C CORP. 050C0302 080178 IN MOCE 6 OISC0kEPED STARTUP RATE AND COUNT RATE INDICATORS FOR NUCLEARINSTRUMENTATICN 4 CONTRCLS 78-039/00L-0 082278 INSTFLMENTATION CHANNEL NI-2 OSCILLATING, CONTRARY TO T.S. 3.9.2. NO SA

SENSCR/ DETECTOR, CLEMENT 022041 30-SAY FETY HAZARD 5 TO PLANT CR GENERAL PUBLIC. REDUNDANT SYSTEM NI-1 AND AUDICOMPCNENT FAILURE NSSS CLE COUNT RATE WERE OPERAELE AND IN SERVICE. FIRST OCCURRENCE THIS TYPE

ELECTRONIC B+WCRYSTAL RIVER-3 GILREACTIVITY CONTROL SYSlEMSCPERATIONAL EVENT FAILED SOURCE RANGE DETECTOR. CETECTOR WAS RENEkED AND SYSTEM OPERABILI

TY RESTOPED UFCN COMPLETION OF POST MAINTENANCE TESTING. FURTHER CORRECTIVE ACTION UNNECESSARY.

WESTINGHOUSE ELECTRIC COPP. 05000338 072676 DURING CRITICAL STEADY STATE CPERATION AN INDICATED QUADRANT POWtd TILTINSTRUMENTATICN + CONTROLS 78-071/0 3L -0 C82173 0F GREATER THAN 1.02 WAS NOTED. THIS WAS IN VIOLATION OF E 1.02 LIMIT

SENSOR /DETECTCR/ ELEMENT 022039 30-DAY AS PER T.S. 3.2.4. (THE CALCULATED TILT RATIO WAS 1.b?l2). THE HEALTHCOMPONENT FAILUPE NSSS AND 5:FETY OF THE PLTLIC WERE NOT AFFECTED.

INSTRUMENT WESTNORTH ANNA-1 5+WPE/.CTOR CORE

OPERATICNAL EVENT THE OCCURRENCE IS BELIEVED TO BE DUE TO A FAULTY POWER RANGE DETECTOR (N-44) THIS DETECTOR IS PRESENTLY BEING MONIT0 FED FOR DRIFT AND WILL BE REPLACED DLRING THE NEXT APPROPRIATE OUTAGE. THE IMMEDIATE ACTION WAS TOWITHDRAW RODS TO 227 STEPS WHICH FEDUCED THE QUADRANT POWER TILT RATIO

TO WITHIN TECH SPEC LIMITS.

210

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LICENSEE EVENT REPOR"

CC"PCNENT MANUFACTURER DOCKET NO.COMPONENT / COMPONENT SUBCODE LER NO.CAUSE C6DE/CAUSE SUBCODE CONTROL NO. EVENT DATEFACILITY / SYSTEM SUPPLIER PEPORT DATE EVENT DESCRIPTIONFETH00 0F DISCOVEPY NSSS / A/E REPORT TYPE CAUSE DESrPIPTION

WESTINGHOUSE ELECTRIC CORP. 05000338 052978 PROTECTON TAVG (TI-1412D) INDICATED LOW. PROTECTION DELTA T (TI-1412G)INSTRUMENTATION + CONTROLS 78-041/03L-0 062778 INDICATED HIGH. A FALSE TEMPERATURE SIGNAL OF LOWER THAN NORMAL COLD LE

POWER SUPPLY 021541 30-DAY G TEMPERATURE WAS SENSED BY DELTA i/TAVG PROTECTION AND CONTROL CHANNELCOMPCNENT FAILURE FSSS 1. THIS RESULTED IN THE TEMPORARY LOSS OF TEMPERATURE CHANNEL T-1412.

ELECTRONIC WEST THE HEALTH AND SAFETY OF ThE GENiRAL PUBLIC NOT AFFECTED.NORTH ANNA-1 5+W

REACTOR TRIP SYSTEMSROUTINE TEST / INSPECTION THE COLD LEG RTD AMPLIF'.ER FAILED SUCH THAT THE OUTPUT WAS VERY LOW WITH

A LIMITFD SPAN. THE FAULTY CAR D WAS REPLACED AND THE LOOP WAS RECALIBRATED.

WESTINGHOUSE ELECTRIC CORP. 05000320 041778 IN MODE 2 ON 4/17/78 RPS CHANNEL C TRIPPED ON HI FLUX. ENTERED ACTION 5INSTRUMENTATION + CONTROLS 78-030/03L-0 051778 TATEMENT E OF T.S.3.3.1.1. CHANNEL EXAMINED, NO PROBLEMS DISCOVERED, RE

SENSOR / DETECTOR / ELEMENT 021612 30-DAY TURNED TO SERVICE. ON 4/20/78, RPS CHANNEL C TRIPPED ON HI FLUX. INVESCOMPONENT FAILURE NSSS TIGATION REVEALED SPIKING NOW CONTINUOUS. CHANNEL PLACED IN TRIPPED CUN

INSTRUMENT B+W DITION, THREE OTHER REDUNDANT INSTRUMENTS CONTINUOUSLY MONITORING THE STHREE MILE ISLAND-2 B+R AME PARAMETER. NO EFFECT ON HEALTH AND SAFETY OF PUBLIC.PEACTOR TRIP SYSTEMSOPERATIONAL EVENT INITIALLY SPIKE ATTRIBUTED TO ELECTRICAL NOISE AND CHANNEL RETURNrD TO 5

ERVICE. AFTER REMOVAL OF NI-7, AND UPON EXAMINATION, FAILURE DETERMINEDTO BE CAUSED BY DAMAGE DURING INITIAL INSTALLATION. NI-7 HAS FEEN REPL

ACED AND FAILED DETECTOR IS BEING RETURNED TO MANUFACTURER Ffo REPAIR.

WESTINGHOUSE ELECTRIC CORP. 05000:38 061478 DURING A PERIODIC TEST ON THE TURBINE TRIP VALVES, ALIMIT SWITCH FAILUREINSTRUMENTATION + CONTROLS 78-050/03L-0 071278 WAS DETECTED. LIMIT SWITCH FAILED TO ACTUATE UPON CLOSURE OF THE TRIPSWITCH 021891 30-DAY VALVE PREVENTING A " VALVE CLOSED" INDICATION AND A TRIP STATUS LIGHT FOR

COMPONENT FAILURE NSSS REALTOR PROTECTION. PROTECTION IS 4 0F 4 LOGIC GIVING REACTOR TRIP WHEMECH ANICAL WEST N ALL 4 TRIP VALVES CLOSE. THIS FAILURE INHIBITED ONE OF THE REACTOR TR

NORTH ANNA-1 5+W IPS VIA TURBINE TRIP.REACTOR TRIP SYSTEMSROUTINE TEST / INSPECTION THC LIMIT SWITCH ACTUATION ARM WORKED LOOSE AND SHIFTED, MISSING THE LIM

IT SWITCHES. THE LIMIT SWITCHES WERE ACTUATED TO PROVIDE A TRIP SIGNALZZHILE REPAIRS WERE MADE. UPON COMPLEZION OF REPAlk5 THE SYSTEM WAS TESTED AND RETURNED TO OPERATION.

(7) 211

P)L:A;

CT)

O

WCD(Q.

;1,e

LICENSEE EVENT REPORTS G'

COMPONENT MANUFACTURER DOCKET N0.COMPCNENT/CCMFCNENT SUECODE LER NO.CALSE COD /CAUSE SLBCOUE CONTPCL NO. EVENT DATEFACILITY / SYSTEM SUPPLIE R RLPART DATE EVENT DESCRIPTIONvETuc9 er gestn E:.y escc / r. i t LEm or TYRE CAUEE prstpIPTION

WESTINGh0USE ELECTRIC C';LP. 0500031t 071078 DURING NORMAL oft PATION, STE AM FLOW CHANNEL MFC-120 WAS PE ADING LOW AND-

INSTRUMENTATION + CONiFOLS 78-05C/03L .e C80Rld WAS DECLARED INCFLRAblE. TH /CTION PEOUIREMENTS OF T.S. TABLE 3.3-1 ITTPAN5MITTER G21946 30-UAY EM 15 AND T.S. TAELE 3.3.3 ITEM 4.0 WERE FULFULLED.

CfMPCidNT FAILUPE A/EINSTRUMENT WEST

D. C. CUM -2 AEPFE ACTCR TRIP SYSTEM 5

KUTINE TEST /INU LCTICN ImLETIGATICN -BEALED iHAT TFL E0thCE OF THE FFCULEM WAS THE TRAN5MITTER TO AIRUkNL RAPI ATICN IPCEllMS, A SPAT 1E TPANSMITTLR WA5 CAtlBPATED, RST4 LEO m D iLALLD IN ELPVICL. TFL CRIGINAL TRAN5MIT iER WAS REMOVED TO A ILIT,, ELE FLPAIR LOCATION W ERL, .T WA5 D15COVLFED THAT THE TRAt.o.ITTrp -tm n ro entri'

WL5IlNe uu5L LLLL!hlL Li VW U/J4/6 UN )/z4/|t int AFLILNI ItFE LI U O blNb idd FOICR In M D 10 WERE 41.3 CMUTOR5 7b-070/5 * -0 CP217h AND 41.1 C , Pf Er!CTIVE L Y. UN F/4/78 TIL AMBIENT TEMP CF CHAPGING PUMP

ELLCfMPC'.+NT NOT M ill' LE C2:037 WE P MOTCP 1A WAS AG.9C. THE r. L f", ! TLFO i)Ci LC ThL 40 C LIMIT GIVEN IN THE A

U!51rn/FAEPIC ATILN EFRU 'a s P[ A TEFF WAITCPING LOG AM 'J F - 4 AML'C*ENT NO. 3 ATTACPFLNT 4 TABLE 1.( 0' r T F UCT !C'./ INST AL L AT IU. M ST TFE CPAPGING MOTOR * PliLATL5 EPECIFY AN AMblENT TLMP OF SOC, IEEPEFORE

I t:P: h e,'. -1 M. .0 ADVERSE EFFECTS AL! EXPELTED.,

F FE FG CCF E LOCL ING SYS + CutI M T l!.I TELT/IN5fECTION . .TILATICN OF T Hi' CHARGI!.G CUEICLE' NUT ADE(JUATE TO MAINTAIN A TEMP OF

'

Liss TFAN 4C C. CN JLLY 24 ADL'ITIGNAL ALXILIARY BUILDING Z) FAUST AND SUFFLY F A',5 WL FL ST AFTE C 70 L OWEk AMLIF N1 TI UP . CN AUGUST 4 A TEN. ORARY FAN WA5 PLACED OilP TFE CDAlGINE ILVP 1A CUBICLE TO LOWER THE CUBICLE AMBm r TEvo

atSii',a% LSt tLtt;rlL Le P. .UJ1t t W7c Lt olN2 A i L ANI 5I AEIti . Tr: i _' I" 4 W NI et u arc LittrutD l'. DISABLE ULEGTHEF CC"ff*.ENTS h ' t/DR -0 C(2278 TO A CCNTIM OUS LGW FLOW AiMM THE AFFLlCAI.LE ACTION FLOUIREMENTS OF T

SLCLt n . 'T n0T AFPLIC ALLL <WO 30-t AY .5. TAELE 3.3-6 WEFE FULF ILLED. N EVICUS DCCUPkENCLS 0F A SIMILAR NATURCESIG% F Ai l ltATION tFR- ' 355 E INCLLCE: R0 050-31E / 78-03, 050-315/ 7 7-3 6, 70-53, 27.6, 75-62, 50,39.

M/nLF ACTL 45T,,

D. C . COC r - AE P

AIFLCR'E FAM cACT MON: - 'MCPEFATICNAL U E',! INVESTIGATION IGE ALID THAT THE FILTE R par EP WA5 WOUND IPPF0FERLY BY THE

MANLT ACTUFER (SUFFLIED Ef WESTINGFOUSL - PART NO. 337A03H01). THIS F<ESULTED WITH it'E FILTEP FATE R BI', LING AND PIFFING GIVING LOW FLOW AL ARMS.

TFE FEMAINING SPOOL 5 OF APD f ILTEk FAff P hAVE EE EN FROPEPLY REWOUND.FUTUPE PUFCHASES WILL LE OF A DIFFEkENT T)FL.

212

LICENSEE EVENT REPORTS.

UCMPONENT MANUFACTURER DOCKET NJ.40MPONENT/ COMPONENT SUBCODE LER NO.CAUSE CODE CAUSE SUBCODE CONTROL NO. EVENT DATE


METHOD OF DISCOVERY NSSS / A/E PEPORT TYPE CAUSF DF5CRIPTION

WESTINGHOUSE ELECTRIC CORP. 05000338 053078 THE CONTAINMENT BULK AVFRAGE TEMP. EXCEEDED THE TECM SPEC LIMIT OF 105 DPUMPS 78-045/03L-0 062878 EG. F. CONSEQUENCES FERE LIMITED SINCE TEMP. INCREASE OVER LIMIT WAS VEF

CENTRIFUGAL 021636 30-DAY Y MINOR; ONE-HALF DEGREE FOR TWO HRS. THE HEALTH AND SAFETY OF THE GENE

COMPONENT FAILURE NSSS RAL PUBLIC WERE NOT AFFECTED. UNIT 2 WATER SYSTEM WAS AVAILABLE.OTHER WEST

NORTH ANNA-1 5+W

CNTNMNT HEAT PEMOV SYS + CONTOPERATIONAL EVENT THE LOWER LUBE OIL COOLER OF REACTOR COOLANT PUMP 1-R C-P-IC DEVELOPED A

LEAK DURING HOT STANDBY. IT WAS NEC TO SECURE THE PUMP TO REPAIR THE C00LE9, THUS REMOVING A SOURCE OF AIR COOLING FROM CUBICLE "C" (THE EXHAUST FROM THE STATOR AIR COOLER), RESTARTED C RPC AFTER MAINTENANCE.

WESTINGHOUSE ELECTRIC CORP. 05000295 051878 WHILE PERFORMING ROUTINE OPERATING SURVEILLANCE ON UNIT 1 SAFEGUARDS LOGRELAYS 7E-047/03L-0 061678 IC. IT WAS FOUND THAT S/G A FEEDWATER ISOLATION W0e_D NOT OCCUR FROM A S

CONTROL, GENERAL PURPOSE 021552 30-DAY AFETY INJECTION SIGNAL ON TRAIN A. THIS PUT THE SAFEGUARDS SYSTEM IN A

COMPONENT FAILURE NSSS DEGRADED MODE WITH RESPECT TO SECTION 3.4 0F THE TECH SPECS. ThE REDUNDELECTRICAL WEST AND TRAIN WAS OPERABLE AND WOULD HAVE PERFORMED THE INTENDED FUNCTION.

ZION-1 S+LFEEDWATER SYSTEMS + CONTROLSROUTINE TEST / INSPECTION THE FAILURE IS ATTRIEUTED TO A DIRTY CONTACT ON THE ACTUATING RELAY. TH

IS RELAY WAS INSPECitD FOR FAULTY CONTACTS. NONE WERE FOUND. THE TRAINWAS RETESTED SATISFACTORILY. THE RELAY CONTACT CLEANED ITSELF UPON SUB

SEQUENT TEST ACTUATIONS. NO FURTHER ACTION 15 REQUIRED.

WESTINGHOUSE ELECTRIC CORP. 05000301 070578 DURING TEST OF REACTOR TRIP BREAKERS, THE "B" BREAKER FAILED TO TRIP FOL

RELAYS 78-008/03L-0 073178 LOWING APPLICATION OF TRIP SIGNAL. LATER A RETEST ON THE BREAKER WAS PECONTROL, GENERAL PURPOSE 021943 30-DAY RFORMED SATISFACTORILY. NO APPARENT PROBLEM WAS FOUND. SAME BREAKER FA

COMPONENT FAILURE NSSS ILED TO TRIP AGAIN ON 7/17/78 DURING NEXT SCHEDULED TEST. PROBLEM WAS AELECTRICAL WEST FAULTY BFD TYPE REACTOR TRIP RELAY (RT-5).

POINT BEACH-2 BECH

REACTOR TRIP SYSTEMSROUTINE TEST / INSPECTION A WESTINGHOUSE MODEL BFD 31 (DC) RELAY FAILED TO DROP OUT AND INITIATE T

RIP SIGNAL TO BREAKER. HIGH TEMPERATURES OF OPERATION HAD CAUSED COIL'SNYLOR SLEEVE TO DETERIORATE AND CRACK THUS PREVENTING RELAY FROM DROPPI

NG OUT. RELAY RE-5 WAS REPLACED.

G 213m7NCoN

C'WNZ

h}LICENSEE EVENT RFPORTS

COMPONENT MANUFACTURER DOCKET NO.COMPONENT / COMPONENT SUBCODE LER NO.CAUSE CODE /CAUSE SUBCODE CONTROL N0. EVENT DATEFACILITY / SYSTEM SUPPLIER REPORT DATE EVENT DESCRIPTIONFFTHOD OF DISCOVERY NSSS / A/E REPORT TYPE CAUSE DESCRIPTION

WESTINGHOUSE ELECTRIC CORP. 05000261 051178 WHILE UrHT WAS CPERATING AT 100 POWER, THE ;0NTROL OPERATOR OBSERVED NOVALVE CPERATORS 78-013/03L-0 060678 REMOTE INDICATION ON THE RTGB FOR SERVICL WATER VALVE V6-12D. THE PROL

ELECTRIC MOTOR - AC 021414 30-DAY LEM WAS FOUND TO BE A BLOWN CONTROL POWER FUSE FOR THE VALVE MOTOR OPERACOMPONENT FAILURE NSSS TOR. AT THE TIME OF FAltUPE, THE VALVE WAS IN THE OPEN POSITION. FAILU

ELECTRICAL WEST RE OF CONTROL POWER FOR THIS VALVE CONSTITUTED A REPORTABLE OCCURRENCE IH. B. ROBINSON-2 EBASCO N ACCORDANCE WITH TECHNICAL SPECIFICATION 6.9.2.B.2.STATION SERV WATER SYS + CONTOPERATIONAL EVENT FAILURE OF CONTROL POWER FOR SERVICE WATER VALVE V6-12D WAS DUE TO A BLO

WN CONTROL POWER FUSE FOR THE VALVE MOTOR OPERATOR. THE FUEL WAS REPLACED AND THE VALVE WAS CYCLED REPEATEDLY TO VERIFY OPERABILITY, AND RETURNED TO SERVICE.

WESTRONICS, INC. 05000254 061778 THE UNIT ONE DRYWELL TO SUPPRESSION CHAMBER DIGITAL DIFFERENTIAL PRESSUkINSTRUMENTATION + CONTROLS 78-019/03L-0 070678 E INSTRUMLNTATION WAS INOPERABLE UPON RECEIPT OF TECH SPEC GOVERNING POS

INDICATOR 021787 3)-DAY T ACCIDENT MONITORING INSTRUMENTATION REQUIREMENTS. THE REDUNDANT INSTRCESIGN/ FABRICATION ERROR LIC UMENTATION USED TO DETERMINE THE DIFFERENTIAL PRESSURE WAS OPERABLE, HEN

CONSTRUCTION / INSTALLATION GE CE SAFE PLANT OPERATION WAS UNAFFECTED. CONTINUED PLANT OPERATIUN IS PEQUAD CITIES-1 S+L RMITTED FOR 30 DAYS WITH ONE OF THE TWO REQUIRED INSTRUMENT CHANNELS INGOTHR INST SYS REQD FOR SAFETY PEFABLE.OPERATIONAL EVENT THE CAUSE OF THIS OCCURRENCE WAS DUE TO INCOMPLETE INITIAL INSTALLATION

OF THE DIGITAL DIFFERENTI AL PRESSURE INSTRU MENTATION UPON ISSUANCE OF AMENDMENT #46 TO DPR-29 ON 6/7/78. INSTALLATION WAS CELAYED C'F TO QUALITY ASSURANCE DOCUMENTATION PROBLEMS. THE INSTRUMENTATION WAs COMPLETELYINSTAtIFn AND MfDF OPEPAELE ON JU NE 28.1978.

WUODWARD GOVLRNOR CO. 0500031t 072818 A SURVLILLANLL ILSI UN IHL 2 Ab DIL$tL-GLNERATUR kt$ULIED IN AN OVERSFLLENGINES. INTERNAL COMBUSTION 78-056/03L-0 082278 D TRIP AS THE DIESEL-GENERATOR WAS UNLOADED. THIS EXCEEDED T.S. 3.8.1.1

SUBCOMPONENT NOT APPLICABLE 022026 30-CAY , THE APPLICAELE ACTION REQUIREMENTS WEFE FULFILLED. PREVIOUS OCCURRENCOMPONENT FAILURE N/A CES OF A SIMILAR NATURE INCLUDE: 050-315/78-01,09, AND 77-42.

MECHAN CAL WESTD. C. C00K-2 AEPEMERG GENERATOR SYS + CONTROLSROUTINE TEST / INSPECTION THE OVER5 PEED TRIP WAS CAUSED BY A LINFAGE CAP SCREW BREAKING IN THE GOV

ERNGR LINKAGE. AN EXAMINATION OF THE GOVEPNOR LINrJGE FAILED TO REVEALOTHER SIGNS OF WEAR. OTHER DIESELS WERE ALSO INSPECTED. THIS LINKAGE CAP SCREW WAS REPLACED ON EACH. BROKEN CAP SCREW IS BEING EVALUATED FORMODE CF FAILURE AN3 FURTHER PREVENTATIVE ACTION IF REQUIRED.

214


COMPONENT MN.UFACTUPER DOCKET NO.COMPONENT /CCMPONENT SUBC0CE LER NO.CAUSE CODE /CAUSE SUBCODE CONTROL N0. EVENT DATE

FACILITY / SYSTEM SUPPLIER PEPORT DATE EVENT CESCRIPTION

METHOD OF DISCOVERY NSSS / A/E QEPORT TYPE CALSE CESCRIPTION

WOODWARD GOVERNOR C0. 05000296 070678 DURING NOPFAL CPERATICN WHILE PERFCFMING SURVEILLANCE TESTING, THE HPCI

INSTRUMENTATION + CONTROLS 78-016/03L-0 072478 PUMP TRIPPED DUE TO A LOSS OF VOLTAGE TO TFE GOVERNOR. THE bPCIS WAS CECPOWER SUPPLY 021839 30-CAY LARED INOPERABLE (T.5.3.5.E.1.(2) AND THE PEDUNDANT SYSTEMS WERE CEMCNST

COMPONENT FAILURE NSSS PATED TO EE OPERAELE (T.S.3.5.E.2). TFE SYSTEM WAS REPAIRED AND RETURNE

INSTRLMENT GE D TO SERVICE WITFIN TN T.S. TIME LIMIT. THERE WAS N0 HAZARD TO THE PUBBROWNS FEPRY-3 0 LIC HEALTH OP SAFETY. PPEVIOUS OCCURRENCE 29E/7715 AND 259/7722.EMERG CORE COOLING SYS + CONTROUTINE TEST / INSPECTION A PACIFIC RESISTOR CO. 250 chm WATT 31 FESISTOR 100 CH, HAD OPENED WHIC

H CAUSED THE FPCI GOVERNCR TO EE INCPEPATIVE. THE RESISTOR WAS REPLACED,A DESIGN CHANGE HAS BEEN APPROVED TO INCPEASE THE WATTAGE RATING OF Th

E PESISTOR. TFE CHANGE WILL EE MACE AT THE REFUELING OUTAGE.

WORCESTER CONTROLS CORP. 05000295 OS137E, CURING *.CRMAL OPERATION, THE INSTRUMENT FAIL LIGHT INDICATING LO,' FLOW W

INSTRUMENTATION + CONTROLS 78-043/03L-0 C61278 OULD NCT RESET ON THE UNIT 1 FAILED FUEL LIQUID PADIATION MONITOR 1RTPR2SWITCH C/I463 30-CAY 7. THE INSTRUMENT WAS TALEN 005. THE REDUNDANT FAILED FUEL MONITL?, IF

COMPONENT FAILURE A/E TFR18, WAS OPERAELE AS REQUIRED BY TECH SPEC 3.19.3. NO SAFETY IMPLitAT

ME CHANICAL WEST IONS WEPE INVOLVED AND TEE HEALTH AND SAFETY OF TFE PUELIC WAS NOT AFFLtZION-1 5+L TED.

PRCSS + EFF FACIOL MONITOR SYSOPERATIONAL EVENT INVESTICATION REVEALED ACCUMULATEC DEPOSITS CF BORIC ACID etAD IMPINGEC L

N THE MAGNETIC CYLINDER OF THE FLOW SWITCH MECHANISM, WGPLHESTER FART NLMEER F16202X, RESTRICTING ITS MOVEMENT AND CAUSING IT TO STICK IN TFE LOU FLOW POSITION. PIPING WAS FLUSPED AND buMT05 RESTORED TO SERVICE.

WORTHINGTCN CORP. 05000316 061778 DURING SUPVEILLANCE TEST, OhP.STP.027, 2CD DIESEL EXHIBITED WIDELY VARYIENGINES, INTERNAL COMBbiTION 78-042/03L-0 070578 NG CYLINDER TEMPERATURES. 2CD DIESEL WAS UNLLADED, SECUPED, AND TAGGED

SUECOMPONENT NOT APPLICAELE 021681 30-CAY OUT FOR INVESTIGATION AND REPAIRS. PENCERING 2CD DIESEL ITCPEPAELL. ALTCOMPONENT FAILURE A/E HOUGH COMPANION CIESEL, 2AB, WAS CPEPABLE DURING 200 DIESEL FEPAIRS, THE

MECHANICAL WEST UNIT WAS IN A DEGRADED NOCE AS CELINEATED IN TECH SPEC 3.f5.1.1.D. C. C00K-2 AEP

EMERG GENERATOR SYS + CONTROLSROUTINE TEST / INSPECTION THE CAUSE OF CYLInuEP TEMFEPATURI VARIATIONS WAS THE FAILURE CF THL NUMB

ER 6 CYLINCER, REAR BANV, FUEL INJECTION PUMP. THE BENUIX C0FP, TYPE FDX FUEL INJ PUMP PLUNGER WAS BOUND TO THE PLUNGER EARREL. A NEW FUEL INJ

PUMP WAS INSTALLED AND A LO/,DED TEST OF THE DIESEL WAS SAT ISFACTGRY.

s0N 215OyCRb

OGC:-

N'Lna

LICENSEE EVENT REPORTS r},

COMPONENT MANUFACTURER COCAET NO.COMPONENT /COMPO*. TNT SLBCOCE LE R NO.CAUSE CODE /CAUSE SUBCOCE CONTROL NO. EVENT CATEFACILITY / SYSTEM SLPPLIER FEPORT DATE EVENT DESCRIPTIONMETucn 0F Disc 0yEpy Nsss i A/E cErrRT Typr em SE [EstpIPTION

WORTHINGTON CORP. 05000316 C61776 URING NuRMAL OFNS, A WELD WAS DISCOVLFED ON TFE ESSENTIAL SERVICE WATERHEAT EXCHANGERS 78-046/C3L-0 071176 0UTLET ON 2AE DIESEL LUPE OTL #f0LER HEAD. TO ACCCFPLISH REPAIRS, '.T W

COOLER 021675 a0-CAY AS NECESSARY TO TAKE 2AB DIISEL GENERATOR OUT CF SERVICE. ALTHOUGH THEDESIGN / FABRICATION ERROR A/E COMPANION CIESEL, 2CD, WA5 OPERABLE DURING 2Ab REPAIRS. THE LNIT WAS IN

CONSTRUCTION / INSTALLATION WEST A CEGRADED MODE AS DELINEATEC IN TECH SPEC SECTION 3.8.1.1.D. C. C00K-2 AEPEMERG GENERATOR SYS + CONTROLSCPERATIONAL EVENT THE CAUSE OF TFE CRACK WAS MISALIGNFENT STFESS CETWEEN THE C00LER HE AD A

ND CONNECTING PIPING. A NEW PIPING SF00L PIECE WAS FACRICATED TO EllMINATE TFE MISALIGNFENT. THE FOUR INCH CPACK IN TEL COOLER FEAD COULD NOTEE FEPAIRED, THEREFORE, THE C00LER PEAD WAS REPLACED.

YARWAY CORP. 05000254 071878 WFILE FERFORMING THE FLACTCR LCW LOW WATER LEkEL CALIBRATICN, PkOCEDLREINSTRUMENTATION + CONTROLS 78-021/03L-0 081578 QIS-11-1, LEVEL SWITCHES LIS-1-263-72A AND LIS-I-263-72 C TRIFFED IN EXCE

SWITCH 021982 30-DAY SS OF TECHNICAL SPECIFICATION LC0 EY 2.2 ANC 1.1 INCEES OF WATER RESPECTCOMPONENT FAILURE NSSS IVELY. TPE RE C1D ANT SWITCFES CPEPATEC CORFECTLY AND ECCS INITIATI0d WA

INSTRUMENT GE S AT ALL TIMES OFERAELE.QUAD CITIES-1 S+LEMERG CORE COOLING SYS + CONTROUTINE TEST / INSPECTION A SLIGHT SHIFT IN THE ALIGNMENT OF TFE MERC0!D SWITCH ANC CAM-t0UNTED OP

ERATING MAGNET CAUSED THE SETFOINT CRIFT IN EACH CASE. C0FFECTIVE ACTION WAS TO RE-ALIGN THE SWITCHES. IN ADDITION, A REPLACEMENT OF TFE EXISTING REACTOR WATER LEVEL SENSCRS WITH AN ANCLOG TYPE TRIP SYSTEM 15 BEINGCONsTPERED BY ArTION TTFM PErD;D 4-76-75.

VARWAY CORF. 05000265 071776 WHILL FEFFORMINu Tht kEALTUR LOn LOW WATtR LEnEL LALIERATION, FROCLDLktINSTRUMENTATION + CONTROLS 78-027/03L-0 081578 QIS-11-1, LEVEL SWITCH LIS-2-263-72A WAS DISCOVERED TO BE PROVIDING CATA

SWITCH 021983 30-DAY WHICH WAS INCONSISTANT WITH THE REQUIRED TECHNICAL SPECIFICATION LIMITSCOMPONENT FAILURE NSSS ALL REDUNDANT SWITCHES WERE TESTED AND FOUND TO BE OFERATING CCRRECTL

INSTRUMENT GE Y. ECCS INITIATION WAS AT ALL TIMES OPERAELE.QUAD CITIES-2 5+LEMERG CORE COOLING SYS + CONTROUTINE TEST /INSFECTION THE CAM-MOUNTED POTATING MAGNET INSIDE THE YARWAY WAS PUEBING AGAINST TH

E MERC01D ACTUATING SWITCH. THE SWITCH BRACKET WAS RELOCATED 50 AS TO PROVIDE EN0 UGH CLEARANCE FOR PROFER OPERATION. IN ADDITION, A FEPLACEMEN

T OF TFE EXISTING REACTOR WATER LEVEL SENSORS WITH LN ANALOG TYPE TRIP SVSTEM IS BEING CONSIDERED BY ACTION ITEM RECORD 4-75-25.

216


C0MPONENT FANUFACTURER CCCKET NO.(CNF ONE f.T/COMFG',F NT SUCCODE LER N0.CAUSE Ct;CE/CAUSL SUCCCCE CONTFOL NO. EVENT DATEFACILITY /SYST;M SUPFLIER PEFORT DATE EVENT DESCRIPTIONvrium rF pirros r py vce / A/E qp0pr Type CacSr r,rstoIPTION

YAFWAY (CFP. C5000254' 061578 WHILE PERFCRMING THE LOW LOW FEACT0k WATER LEVEL FUNCTIONAL TEST, PROCEDINSTPtPLNTATION + CONIFOLS 78-018/C3L-0 071476 URE Q1511-2, LEVEL SWITCH LIS-1-263-/2A FAILED TO CPERATE. LLVEL SWITCHSWITCH 0217b6 30-DAY ES LIS-1-263-72A, 72B, 72C AND 72D ARE ARRANGED IN A ONE-0UT-OF-TWO-TWIC

C0r PO .U4T F AILURE NSSS LOGIC AND ARE USED FOR ECCS INITIATION. THESE REMAINING THREE SWITCPEe

INSTFLMLNT GE S IN TFE ECCS LOGIC WERE FOUND TO OPERATE CORRECTLY AT THE CESIFED SETF0QUAD CITILS-1 S+t INT THUS, SAFE PLANT OPERATION WAS NOT AFFECTED.FE ACTOP TRIP SYSTEMSFOUilNE TEST /INSFECTION TUE CAUSE OF THIS OCCURRENCE IS COMPONENT FAILURE DUE TO INSTRUMENT SETP

OINT DRIFT IN THE LEtEL SWITCH. THE MERC01D SWITCH WAS NOT ALLIGNED PROFEPLY IN RELATION TO THE CAM-MOUNTED MAGNET AND THIS RESULTED IN THE SWITCH NOT OPENING AT THE CESIRED TRIP POINT. THE SWITCH WAS IMMEDIATELY ADJUSTED AND FUNCTIONALLY RETESTED SATISFACTORILY.

217gNC ',

N00Cr)

SECTION V

INSPECTION AND ENFORCEMENT - BULLETINS AND CIRCULARSi

CONTAINED WITHIN THIS SECTION OF THE " WHITE BOOK"ARE BULLETINS AND CIRCULARS ISSUED BY THE OFFICEOF INSPECTION AND ENFORCEMENT DURING THE PERIODOF TIME COVERED BY EACH PUBLICATION OF THE BOOK.

BULLETINS AND CIRCULARS HEREIN CONTAINED HAVEBEEN MAILED TO APPLICANTS AND LICENSEES ON ASCHED'JLE CONSISTENT WITH ISSUE DATES. THEIRINCLUSION IN THE " WHITE BOOK" IS FOR THE PURPOSEOF PROVIDING NONAPPLICANT/NONLICENSEE INDLSTRYREPRESENTATIVES WITH COPIES ON A ROUTINE BASIS.

{CNT,

NCoM

IE BULLETIN No. 78-H

Page 1 of 3

WILTED STAIL5 IE Bulletin 78-11 In vi'w of tne atiove, on July 7, 1978, the f.RC Cffice of Inspection andNUCLEAR RECLLATORY COMMISSION Cate: July 21, 1978 E nforcemot vert > ally requer '_ed licensee's to perfonn close visual inspec-

GFilCL OF IN1FLETIC1 A*n ENFo? CEMENT tions on similarly N de torus weldm nts at Peach bottom Unit Nos. 2 andn e M'.ST % , D. C 20555 3, Quai Cities Unit M s. I and 2, Hatch Unit No. 1 and Monticello

facilities * ta se inspections revealed no apparent linear indicatior.sthros;h the painted surface. hcwever. Monticello reported that magnetic

D AMINATION OF M W -1 C&.. fENT TORUS WELOS particle examination, taqrtter with visuil inscection revealed tworelevan t surf ace linea r irrii ca t ions , '/2-inch long and 1-1/2 inches long

Lescripti m of Circr stances resptctively, which we re verified by liquid penetrant tests af ter remova:cf tre paint. Both indication 3 were reportedly reroved by grindina at

jn Jun( 2 197 , vermont UnLee hwer Company (V yPC) reparted th3t five less than 14-inch depth,,

non-pm etratin| surfm e crat, indications a 'd one nir e-inch lcng surf acecrack were found in the o'.erlay weld-to-torL> Lase mtal heat af fected ' c_t_ i on tn t o TM en_by li_censeezones %rira the proces, of pe: f orm n9 nodi fications (addi tion ofs t rer g t r e n i n .; ,,. sets) to the torus sJpport colonns at the ',ernent Licensees for Pe3ch bottom Units 2 and 3, Quad Cities Units I and 2,var iee 1. clear f acility. These modif ications were being perfor ed as Ntch Unit 1 and Ponticello are further requested to provide thepart af '.iPL'> overall program to re s t o re the originally i. tended design fc.llowing inf orr:aticn:safety urgins f or tne Veruont ud t. Ma rk I contairant sys*en (re:<a r k I Lantair ont l ong Te rm Pro +; ram). Itrm A

.ned u; no initial indications of the depth, DPC rerf orrd an analysis 1. Provido descriptions of the welding procedures, procedure cualifica-of the structural capability of the torus shells in the af fected areas tions, welder qualifications and electrode controls erployed into support contirued operation of the facility and proceeded to attenct strengthening the support column to tor s conrections (i.e.,ut o .; rind out the nine-iecq c rau On June 30, 197M, the Crack was still addition of gJssets, saddle su[ ports, wet's, etc).vparent after < , to the calculated deptn of 0.25 inches. The"

plant v is plated in a cold shutdawn coniition un July 2, 1978 in 2 Provide a description of the preventive reasures used to assure tha*evaluatien is in pr<qre< condensation did not oc'ur on surfaces to te wolded prior to and

during the welding.welding operations at wrmot Unkee were perfonned at locations on

the torus % ell whicn were low"r than th? water level in the torus. 3. Describe the chronology of nondestructive examinations perform dAltbomh the un 9 rlying causes of th cracking have not yet teen deter- subseq;ent to such welding operations. Inc?ujo procodore s , ne t hod snir d, to ore ' ce of water on the opnosite side of the torus shell and techniques, the tir.e pericJ of 'CE application af ter specificJuring the wellinq op" rations appears to have teen a pri ary contrib- welds completed have been at ambient temperature, and the resultsutor. Con #qa ntly, a generic concern has arisen that the potential for of these examinations.cratking tuuld exist w' en welding is performed on a torus containingwater.

(centinuod next page)

CD 221N-M8

f)2@

G:mNON

IE BULLETIN NO, 78-]1 OPage 2 of 3

Item B ENCLOSURE

ancre the NDE documentation (Item A3) is not sufficiently definitivi to LISTING OF IE ButtETINSshow tha welding t the torus was nondestructively examined af ter tne ISSUED IN 1979completed welds were at ambient tempercture for a minimum period of 72hours, the follod w neasures should be taken. Bulletin Subject Date hsued Issued To

No.1. Remove paint from surfaces of the overlay weld and torus base metal

heat af fected zones (if not already done so) by rotary wire 78-01 Flamable Contact 1/16/78 All Power Reactorbrashing or equiv; lent reans. Am Retainers in G.F. Facilities with an

CR12CA Relays Operatino License2. Esamine tne exposed interbead fu W r Jone o' the overlay weld and (0L) or Construc-

the assosted base Mai heat af 4tted Zond utilizing magnetic tion Permit (CT)particle 'echniques in accordance with the applicable section ofthe ASME Code. 78-02 Terminal Block 1/30/78 All Power Reactor

Qualification Facilities with an

3. Any indi ations detected c. a result of MT are to be evaluated as Operating Licenseto their A.ceptability in accordance with the applicable ASME code. (OL) or Construc-E xamir.4 ions that detect relevant linear indications may be supple- tion Pemit (CP)ren+6 b) c*' er ne". destructive methods cnd techniques to deteminethe cMrrter of the flaws (i.e. , est0 4ted size, shape, depth, 78-03 Potential Explosive 2/8/78 All BWR Powerorientation, etc.). Gas Mixture Accumula- Reactor Facilities

tions Associated with with an Operating

4. Results of the field sxamination of indiv % al weldmen's is to be BWR Offgas System License (OL) ordocunented. Opera tions Construction

Permit (CP)Within ten days of the date of issue of this Bulletin, report in w. 4 tingto the Director of tne' Qropric te NRC Regional Office, the infomation 78-C4 Environmental Quali- 2/21/78 All Power Reactorrequested in Item A, and your proposed plan of action and schedule fication of Certain Facilities with an

regarding item C if the 72 hour minimum period described above was not Stem Mounted Limit Operatina Lic m e

ve t . A copy of your report as sutnitted to the Regioral Office should Switches inside (OL) or ConStruc-be sent to 'ha United States Nuclear Regulstory Corrission. Office of Reactce Containment tion Fermit (CP)Inspection Wi Entorcecent Division of Reictor Operetions Inspection,' ishir aten. D. C. 20555.

aAppro.ea by GAO, BIS 0225(R0072), c?earance exp'.m Jt.ly 31, 1980.|

Approval was given under a blanket clearance specifically foridentified ger.ric problems.

(continued nest page)- = _ _ _ -

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IE BULLETIN NO. 73-11

Page 3 of 3

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18-05 Malfunctioning of 4/14/18 All Power Reactor 78-10 Bergen-Paterson 6/27/78 All BWR PowerCircuit Crr iker facilities with an Hydraulic Shock Feactor FacilitiesAuxiliary Contact Operating License Suppressor Accumulator with an OperatingMechanism - General (OL) or Construc- Spring Coils License (OL) orElectric Model tion Permit (CP) Construction Per-CR105x mit (CP)

7H-06 befective Lutler- 5/31/18 All Pcwer Reactorru rer, Type M Pelays facilities with anWitn oC Coils Operating License

(OL) or Construc-tion Permit (CP)

10 07 Protection Afforded 6/12/78 All Power Reactert>y Ai r-L ine Facilities with anRespirators and Operating License (OL)and supplied-T.ir all class E and FHoods Research Reactors

with an OL, all fuelCycle facilitieswith an OL, and allPriority 1 MaterialLicensees

>adi,ition levels frnn 6/12/78 All Power andIurl ilenant Transfer Research ReactorIo w facilities with a

Fiel Element Trans-f er f utie and anOperating License

(OL)

/a-09 BWR Drywell leakage 6/14/78 All PWR PowerPaths Assuiated wi th Reactor facilitiesinadequate Drywell with an OperatingClosures License (OL) or

Construction Per-mit (CP)

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IE BULLETIN N0. 78-R0

Page 1 of 4

UNITED STATES IE Bulletin 78-12 Action To Be Taken By Licensees and Permit Holders:NUCLEAR REGULA10RY COMMISSION Date: September 26, 1978

0FFICE OF INSPECTION AND ENFORCEMENTFor all power reactor facilities with an operating license or aconstruction permit, except those already identified as possibly havingWASHINGTON, D. C. 20555atypical weld material 1/:

ATYPICAL WELD MATERIAL IN REACTOR PRESSURE VESSEL WELDS 1. Conduct a record search 2/ of all primary reactor pressure vesselweldments (excluding partial penetration welds) and submit the

Description of Circumstances: following information 3/:

On August 4,1978, the NkC was informed by the Duke Power Company andthe Babcock and Wilcox Company (B&W) that the weld wire used in some of 1/ The twelve nuclear units identified as having possible atypicalthe reactor vessel welds in Oconee Unit No. 3 may have differed from that ~

specified. A chemical analysis of one sample of archive material by B&W pressure vessel weldments are: Three Mile Island Unit Nos. I and 2disclosed that the nickel content was measured to be 0.1 percent (versus Crystal River Unit No. 3, Arkansas Nuclear One Unit No.1, Oconee0.45 to 0.8 percent nominal specified) and the silicon content was Unit No. 3 Rancho Seco Unit No. 1, Midlan Unit No. 1. Qua'i Citiesmeasured to be 1.0 percent (versus 0.3 to 0.6 percent nominal specified). Unit No. 2, Browns Ferry Unit No. 1, Turkey Point Unit No. 4 andThe heat of weld metal in question was supplied by the Page Company, a Zion Unit Nos. I and 2.Division of the American Chain & Cable Co., Bowling Gmen, Kentucky toB&W, the manufacturer of the Oconee, Unit 3 vessel. Further checks by 2/ The record search may be perfomed by the vessel manufacturer and the

B&W of its records have identified eleven additional vessels in which ~ requested information reviewed as appropriate by each lic nsee priorthe incorrect weld material may have been used. Owners of these vessels to fomarding to the NRC. It is not the intent of this Bulletin to

require each licensee to individually examine manufacuring records ofhave been notified. a generic nature. Records of nonconforming conditions that may beThe NRC staff has made a detemination of the possible ef fects on reactor identified by the manufacturer and are uniquely applicable to avessel integrity of the use, or possible use, of the improper weld specific vessel should, however, be carefully examined by the owner.material. Weldments containing the atypical material are likely to haehigher than normal nil-ductility transition temperature characteristics. 3/ Some of the infor-ation requested by this Bulletin may have beenTherefore iu maintain reactor vessel safety margins, implementation of - previously supplieJ to the NRC under the Surveillance Program,new conservative pressure / temperature operating limits may be required. Iniomation previously submitted may be referenced in lieu of

resubmi ttal .While the specific problem has been identified as possibly affectingtwelve vessels manufactured by B&W, it is not possible to conclude inthe absence of specific information that similar atypical weld materialwas not also supplied to other vessel manufacturers and used in reactorpressure vessel fabrication.

(continued next page)

224


Page 2 of 4

a. The principal vessel manufacturer. If other manufacturers 3. Identify those cases of weld filler material which did not meetwere utilized, identify those companies and the weldnents procurement specifications based on verification tests, i.e.completed by those fims. mechanical or chemical properties. Describe the disposition

action taken or the acceptance basis for utilization in m selb. The type and form of weld materials and the identifying heat fabrication. In such cases, discuss the ef fect that the atypical

and lot numbers used in each weldment. weld composition has on the fracture toughness of the weld metal.

c. The weld material manufacturer (s) and the types and fom of 4 Provwe infomation on the availability of archive welJ materialsmaterials supplied. which might be used veri fication purposes,

d. The specified properties of the weld materials and the 5. Please provide your response in writing within 60 days. Reportscompleted weldments (Chemistry, tensile and impact should be submitted to the Director of the appropriate NRC Regionalproperties, as appropriate). Office and a copy should be forwarded to the U.S. Nuclear Regulatory

Commission, Office of Inspection and Enforcement, Division of2. Describe the procedures utilized during fabrication to verify Reactor Core ruction Inspection, Washington, D.C. 20555.

confomance to the specifications. Specifically provide thefollowing: Approved by GAO, B180225 (R0072); clearance expires 7/31/80. Approval

was given under a blanket clearance specifically for identified generica. Describe the type, number and dates of tests perfomed on problems,

welding materials to satisfy the material conformance testingrequirements for each heat, lot or combination of heat and ENCLOSUREbatcn, etc., of welding materials used in the construction or -

repair of the reactor pressure vessel in your facility. LISTING OF IE BULLETINSIndicate whether each heat, lot or batch subdivision (coil or ISSUED IN 1978spool) was tested and the extent of such testing, i.e. , wereboth ends of a coil or spool of wire tested for each sub-arc Bulletin Subject Date Issued IssuM Ioflux-wire combination or heat-flux batch combination? No.

b. Describe the type, number and dates of other tests such as 78-01 Flammable Contact - 1/16/78 All Power Peactorprocedure qualification, welder performance tests, in-process Am Retainers in G.E. Facilities with orchecks on post-weld tests which were performed. CR120A Relays Operating License

(OL) or Construc-c. For each of the tests described in 2(a) and 2(b) above, tion Permit (CP)describe the parameters of each test and provide the resultsobtained. Identify the applicability to specific weldmentsby correlation of heat, lot or batch as appropriate.


GD 225ei7.

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hIEBULLETINNO.78-IjJPage 3 of 4

78-02 Terminal Block 1/30/78 All Power Reactor 78-07 Protection Afforded 6/12/78 All Power ReactorQualification Facilities with an by Air-Line Facilities with an

Operating License Respirators and Operating License (OL)(OL) or Construc- and Supp.ied-Air all class E and Ftion Pemit (CP) Hoo,. s Research Reactors

with an OL, all Fuel78-03 Potential Explosive 2/8/78 All BWR Power Cycle facilities

Gas Mixture Accumula- Reactor Facilities with an OL and alltions Associated with with an 0;wrating Pi f ority 1 MaterialBWR Offgas System License (0L) or LicenseesOperations Construction

Permit (CP) 78-08 Radiation Levels from 6/12/78 All Power andFuel Element Transfer Research Reactor

78-04 Environmental Quali- 2/21/78 All Power Reactor Tubes facilities with a

fication of Certain Facilities with an fuel Element Trans-Stem Mounted Limit Ooerating License fer Tube and anSwitches Inside (OL) or Cont truc- Operating License

Reactor Containment tion Pemit (CP) (OL)

78-05 Malfunctioning of 4/ d/78 All Power Reactor 78-09 BWR Drywell Leakage 6/14/78 All BWR PowerCircuit Breaker Facilities with an Paths Associated with Reactor FacilitiesAuxiliary Contact Operatin; License Inadequate Drywell with an nporating

Mechanism - General (0L) nr Construc- Closures License (ot) orElectric Model tion Permit (CP) Construction Per-CR105X ait (CP)

78-06 Defective Cutler- 5/31f,8 All Power Reactor 78-10 Bergen-Paterson 6/27/78 All BWR PowerHanner, Type M Relays facilities with an Hydraulic Shock Peactor FacilitiesWith DC Coils Operating License Suppressor Accumulator with an Operating

IOL) or Construc- Spring Coils License (OL) ortion Permit (CP) Construction Per-

mit (CP)


226


Page 4 of 4

78-11 Examir.ation of Mark I 7/21/78 BWR Power ReactorContainment Torus Facilities forWelds action: Peach

Bottom 2 and 3Quad Cities 1 and2, Hatch 1 Monti-cello and VemontYankee

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NIE CIRCULAR N0. 78-13 GO

Page 1 of 2

UNITED STATES IE Circular No. 78-13 The safety significance of this event stems from the potential, underNUCLEAR REGULATORY C0ttilSSION Date: July 10, 1978 a unique set of environmental circumstances, for a complete loss of

0FFICE OF INSPECTION AND ENFORCEMENT service water.WASHINGTON, D. C. 20555

Corrective actions included the establishment of a periodic surveillanceprogram to ensure that silt levels in the service water bays do not

INOPERABILITY OF SERVICE WATER PUMPS mach a level sufficiently high to cause recurrence of this event.

Description of Circumstances: Holders of operating licenses or construction pemits for power reactorswho receive this Circular should review the service water design and

Ja..ua ry 11, 1978, Salem Generating Station Unit No.1, a 4-loop pcstulated conditions in the ultimate heat sink to ensure that a similarstinghouse PWR with once-through cooling located on the Delaware combination of surface ice, water level, and forebay silting could not

diver, experienced high strainer differential pressures and the loss precipitate inoperability of the service water system. if such condi-of four of six installed service water pumps within a period of tions are credible, a program to monitor the conditions at the serviceapproximately thirty minutes. At the time of this occurrence. the water intake structure st ould be implemented and procet es establishedriver surface was covcred with a layer of frazil (slush) ice to an for corrective action to be taken under normal and emery icy conditions.unknown depth.

No written response to this Circular is required. If you requireEach service water pump discharge is eouipped with an R. P. Adams additiona. enfonnation regarding this matter, contact the Director ofVDWS-68 automatic self-cleaning strainer. The indication of failure the appropriate NRC Regional Office.was high strainer dif ferential pressure. Subsequent investigationshowed that each of the four strainers had broken shear pins in the ENLLOSUREhadww.h shaf t which caused the self-cleaning feature to becomei nope ra bl e. The internals of the strainers revealed no unusual debris LISTING OF IE CIRCULARS ISSUED IN 1978whit.h could have caused dif ferential pressures high enough to shearthe pins. Ci-cular Subject First Date Issued To

No. Of IssueEach service water pump takes suction near the bottom of individual bcysin the intake structure. Examina; ion of the bays revealed that silt had 78-01 Loss of Well Logging 4/5/78 All Holders ofaccumulated to significant heights between the treveling screen and pump Source Well Logging Sourcesuction in each of the bays associated with failed strainers. The Licensescombined ef fects of high silt " walls " low river water level, and thesurface ice, probably caused the pump suction to receive only ice- 78-02 Proper Lubricating 4/20/78 All Holders ofentrained water. This mixture then caused the strainers to clog and Oil for Terry Reactor Operatingshear tLe backwash shear pins r ue to the high differential pressures. Turbines Licenses (OL) orBy the time the strainers were opened for inspection, the ice had Constructionmelted. Permits (CP)

_ _ Jcontinued next page)

228

IE CIRCULAR NO 78-13

Page 2 of 2

78-03 74ckaging Creater 5/12/78 All Holders of 78-09 Arcing of General 6/5/78 All Holders of1en Type A Reactor Operator Electric Company Reactor OperatingQuintities of Low Licenses (OL). Size 2 Contactors Licenses (OL) orSpecific Activity Construction ConstructionRadioactive Material Permits (CP). Fuel Pemits (CP)for Transport Cycle. Priority IMaterial and Waste 78-10 Control of Sealed 6/14/78 All MedicalDisposal Licenses Sources Used in Licensees in

Radiation Therapy Categories G and78-04 Installation Error 5/15/78 All Holders ofG1That Could Prevent Reactor Operating

Closing of Fire Licenses (OL) or 78-11 Recirculation M-G 6/15/78 All Holders ofDoors Construction Set Overspeed Stop BWR OperatingLicenses (OL) or78-05 Inadvertent Safety 5/23/78 All Holders of ConstructionInjection During Reactor Operating Permits (CP)Cooldown Licerses (OL) or

Construction 78-12 HPCI Turbine Control 6/30/78 All Holders ofPermits (CP) Value Lift Rod BWR Operating

Bending Licenses (OL) or78-06 Potential Common 5/25/78 All Holders of ConstructionMode Flooding of Reactor Operating Permits (CP) withECCS Equipment Licenses (0L) or Similar HPCIRooms at SWR Construction DesignFacilities Pemits (CP)

78-07 Damaged Components 5/31/78 All Holders ofOn a Bergen-Paterson Reactor OperatingSeries 25000 Hydrau- Licenses (OL) orlic Test Stand Construction

Permits (CP)

78-08 Environmental Quali- 5/31/78 All Holders offication of Safety- Reactor OperatingRelated Eauipment Licenses (0L) orat Nuclear Power ConstructionPlants Permits (CP)

tr 229NC1NtoO

f*C7NCN

IECIRCULARNO.78-lbPage 1 of 2

UNITED ST5TES IE Circular No. 78-14 Information supplied by the Terry Steam Turbine Company indicates thatNUCLEAR REGULATORY COMMISSION Date: July 12, 1978 similar turbines were supplied for HPCI systems at the following

0FFICE OF INSPECTION AND ENFORCEMENT facilities: Browns Ferry Unit Nos.1, 2, and 3; Brunswick Unit Nos.1WASHINGTON, D. C. 20555 and 2: Cooper; Vermont Yankee; Fermi Unit No. 2; J. A. FitzPatrick; Hatch

Uni + vos.1 and 2; Hope Creek Unit Nos. I and 2; Limerick Unit Nos.1 and2; Pilgrim Unit No.1; Shoreham; Susquehanna Unit Nos. ' and 2. In

HPCI TURBINE REVERSING CHAMBER HOLD DOWN BOLTING addition, HPCI Terry Turbines were also supplied for Monticel'o and DuaneArnold; however, these applications involved smaller machines w ic

Recent inspections by the Philadelphia Electric Company of HPCI turbines incorporata a single turbine wheel and reversing chambers which areat Peach Bottom Unit Nos. 2 & 3 facilities disclosed broken cap screws supportes .hout clamping plates, and therefore are not subject toand missing Clamping plates which secure the turbina reversing chambers. similar failure of cap screws.The cap screws are used to fasten clamping plates and reversing chamberrails to the support ring. Additional detailed information is available All holders of EWR operating licenses or construction permits forin Section 6 of the HPCI Terry Turbine instruction manual. Missing parts facilities with a similar HPCI Terry Turbine should be aware of thewere recovered from components in the turbine steam exhaust piping and potential for failure of the turbine reversing chamber hold down bolting.unrecovered parts are believed to be in the torus. Subsegunt examina- It is recorriended that inspection of the clamping plate cap screws betion of the cap screws indicated the failures resulted from fatigue. included in the next inepection of these turbines. If the present

bolting design is inadequate, it is further recommended that the nuclearThe design of the cap screws includes a 1/4 inch deep concentric steam supplier and vendor be contacted for assistance in determining thecounterbore from the threaded end. Failures generally occurred at the appropriate modification.base of the counterbore with a few failures occurring at the base of thescrew head. The screw length of 1-1/4 inches allows about 5/16 inches No written response to this Cir<i;r is required. If additionalof thread engagement in the support ring. information is needed regarding this matter, contact the Director of

Af ter review, the vendor (Terry Steam Turbine Company) recommendedmodification of the bolting design to prevent recurrence. An interim ENCLOSUREsolution was to replace the 3/8-16 X 1-1/4" long ASTM A574 socket headcap screws with similar 1-1/2" long cap screws. This required deeper LISTING OF IE CIRCUL ARS ISSUED IN 1978drilled and tapped holes in the support ring to prevent the longer screwsfrom bottoming. Later, the General Electric Company advised of a further Circular Subject First Date Issued Tomodification from Terry Turbine consisting of bolting the reversing No. Of Issuechamber directly to the sunport ring, lockwiring the cap screws andeliminating the clamping plate. In addition, the replacement cap screws 78-01 Loss of Well Logging 4/5/78 All Holders ofwem changed to 3/8-16 X 1" long ASTM A193 Gr. 66 with a Rockwell Source Well Logging SourceHardness of Rc28 or less. Licenses

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230

IE CIRCULAR NO. 78-14

Page 2 of 2

78-02 Proper Lubricating 4/20/78 All Holders of I 78-08 Environmental Quali- 5/31/78 All Holders of011 for Terry Reactor Operating fication of Sa'aty- Reactor OperatingTurbines Licenses (OL) or Related Equipment Licenses (OL) or

Construction at Nuclear Power ConstructionFemits (CP) Piants Pemits (CP)

78-03 Packaging Greater 5/12/78 All Holders of 78-09 Arcing of General 6/5/78 All Holders ofThan Type A Reactor Operator Electric Company Reactor OperatingGuantities of Low Licenses (OL), Size 2 Contactors Licens2s (OL) orSpecific Activity Construction ConstructionRadioactive Material Pemits (CP), Fuel Permits (CP)for Transport Cycle, Priority I

Material and Waste 78-10 Control of Scaled 6/14/78 All MedicalDisposal Licenses Sources Used in Licensees in

Radiation Therapy Categories G and78-04 Installation Error 5/15/78 All Holders of G1

That Could Prevent Reactor OperatingClosing of Fire Licenses (0L) or 78-11 Recirculation M-G 6/15/78 All Holders ofDoors Construction Set Overspeed Stop B"R Operating

Permits (CP) micenses (OL) orConstruction

78-05 Inadvertent Safety 5/23/78 All Holders of Permits (CP)Inject. ion During Reactor OperatingCooldown Licenses (OL) or 78-12 HPCI Turbine Control 6/30/78 All Holders of

Construction Valve Lift Rod BhR OperatingPermits (CP) Bending Licenses (0L) or

Construction78-06 Potential Cormion 5/25/78 All Holders of Pemits (CP) with

Mode Flooding of Reactor Operating Similar HPCIECCS Equipment Licenses (0L) or DesignRooms at BWR ConstructionFacilities Pemits (CP) 18-13 Inoperability of 7/10/78 All Holders of

Service Water Pumps Reactor Operatira78-07 Damaged Components 5/31/73 All Holders of Licenses (OL) or

Of a Be/ gen-Paterson Reactor Operating ConstructionSeries 25000 Hydrau- Licenses (OL) or Permits (CP)lic Test Stand Construction except for plants

Permits (CP) located in: AL,AK, CA, FL, GA,iA. Ms er

231CDfi71NLaG)

CQCSu,

OIE CIRCULAR NO. 78-15 [yPage 1 of 2 2)

UNITED STATES IE Circular No. 78-15 If you require additional information regarding this matter, contact theNUCLEAR REGULATORY COMMISSION Date: July 20, 1978 Director of the Regional office.

OFFICE OF INSPECTION cND ENFORCEMENTWASHINGTON, D. C. 20555 ENCLOSURE

LISTING OF IE CIRCULARS ISSUED IN 1973TILTING DISC CHECK VALVES FAR TO CLOSE WITH GRAVITY IN VERTICALPOSITION Circular Subject First Date issued To

No. Of IssueThe Anchor / Darling Valve Company reported to the NRC on May 23, 1978 acondition at the San Onofre Nuclear Plant where an 8" - 1500d tilting 78-01 Loss of Well Logging S/5/78 All Holders ofdisc check valve failed to close with gravity because it was installed Source Well Logging Sourcein a verticcl rather than a horizontal pipeline. The valve disc was Licensescounter weignted to close with the force of gravity when installed ina horizontal pipe. The manufacturer did not determine the reverse flow 78-02 Proper Lubricating 4/20/78 All Holders ofnecessary to close the improperly installed valve. The check valve is Oil for Terry Reactor Operatinglocated in the Low Pressure Safety Injection System as the first valve Turbines Licenses (OL) orinside the containment and may not have closed as required to maintain Constructionthe containment integrity. Permits (CP)

Anchor / Darling has notified all purchasers of such valves and indicated 78-03 Packaging Greater 5/12/78 All Holders ofto then possible implications of vertical installations. Than Type A Reactor OperatorQuantities of Low Licenses (OL),

It should be noted that similar problems may arise with tilting disc Specific Activity Constructioncheck valves from other manufacturers. Radioactive Material Permits (CP), Fuel

for Transport Cycle, Priority ITilting disc check valves can be designed for either horizontal or Material and Wastevertical piping but not for both. Improperly installed tilting disc Disposal Licensescheck valves will not function properly.

78-04 Installation Error 5/15/78 All Holders ofAll holders of operating licenses or construction permits should be That Could Prevent Reactor Operatingaware of the potential for malfunction of safety-related systems caused Closing of Fire Licenses (OL) orby improperly positioned tilting disc check valves. Consideration Doors Constructionshould be given to the importance of verifying that all such valves Fernits (CP)in critical systems are installed only in the orientation specifiedby the manufacturer.

No written response to this circular is required.


232

IE CIRCULAR NO. 78-15

Page 2 of 2

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78-05 Inadvertent Safety 5/23/78 All Folders of 78-11 Recirculation M-G 6/15/78 All Holders ofInjection During Reactor Operatin9 Set Overspeed Stop BWR OperatingCooldown Licenses (OL) erConstruction Licenses (OL) or

ConstructionPermits (CP)Permits (CP)

78-06 Potential Common 5/25/78 All Holders of 78-12 HPCI Turbine Control 6/30/78 All Holders ofMode Flooding of Reactor Operating Valve Lift Rod BWR OperatingECCS Equipment Licenses (OL) or Bending Licenses (OL) orRooms at BWR ConstructionConstructionFacilities Permits (CP) Permits (CP) with

78-07 Damaged Components 5/31/78 All Holders of Similar HPCIOf a Bergen-Paterson Reactor Operating DesignSeries 25000 Hydrau- Licenses (OL) or 78-13 Iroperability of 7/10/78 All Holders oflic Test Stand Construction Service Water Pumps Reactor OperatingPermits (CP) Licenses (OL) or

78-03 Environmental Quali- 5/31/78 All Holders of Constructionfication of Safety- Reactor Operating Permits (CP)Related Equipcent Licenses (OL) or except for plants

at t clear Power Construction located in: AL,a

Plants Fermits (CP) AK, CA, FL, GA,LA, MS, SC

78-09 Arcing of General 6/5/79 All Holders of 78-14 HPCI Turbine Reversing 7/12//8 All Holders ofElectric Company Reactor Operating Chamber hold Down BWR OperatingSize 2 Cor:tactors Licenses (OL) or Bol ting Licenses (OL) orConstruction ConstructionPermits (CP) Permits (CP) for78-10 Control of Sealed 6/14/78 All Medical plants with a HPCI

Soarces Used in Licensees in Terry TurbineRadiation Therapy Categories G and excepting Deane

A rro .u oe.uG1 Monticello

(?)233&

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IE CIRCL".M NO. 78-16N03

Page 1 of 3

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UNITED STATES IE Circular 78-16 The licensee estimated that the failure of the Type SMB-2 valve actuatorNUCLEAR REGULATORY COMMISSION Date: July 26, 1978 occurred after it had been clutched 25 to 100 times. The valve which

0FFICE OF INSPECTION AND ENFORCEMENT failed to function at Rancho Seco (SFV-25003) is operated by theWASHINGTON, D. C. 20555 actuator and is a safety feature valve in a line connecting the borated

water storage tank to a high pressure safety injection pump and a decayheat removal (low ha d safety injection) pump. The valve actuator is

LIMITORQUE VALVE ACTUATORSwired so that the valve which it controls will drive to the fully openor fully closed position once the motor is energized.

Description of Circumstances: 5FV-25003 is used for various routine operations during refueling, e.g.At Rancho Seco, a Limitorque SMB-2 motor-driven valve actuator in a adding borated water to the primary cooling system. In these instances,safety feature system failed to function. The failure resulted from the operator uses SFV-25003 as a throttle valve. To do this, the valveclutch wear which was due to manual operation of the valve and improper must be actuated manually, givi a rise to the poten ial damage to theheat treatment of the clutch parts. Other SMB valve actuators at lugs as described above. This would not occur with the type of valveRancho Seco had been subjected to undue clutch wear but were still actuator that is clutched with the motor at rest. Likewise, a separateoperable. Based on infomation obtained from the licensee and from throttle valve for supplying borated water during routine operationLimitorque Corporation, undue wear appears to De limited to Type SMB-0, would preclude the need for manual operation of the subject valve1, 2, and 3 valve actuators equipped with 3600 rpm motors. sctuator.

The type SMB valve actuator is provided with a handwheel so that the Limitorque Corporation nas a tes*. program in progress for deteminingvalve can be actuated manually in the event that power is unavailable. the clutch life of Type SMB 0,1, 2, and 3 valve actuators. Results toTo shif t from motor drive to handwheel drive, the operator must manually date are inconclusive. Panding other resolution of the prcblem, theposition a clutch so that the motor is disengaged from the drive train licensee has stated tFat the valve will be stroked with the motor driveand the handwheel is engaged. The clutch latcnes into this position to ensure that the c'utch has engaged the motor following manualand cannot be manually repositioned. The next time that the motor is actuation of the valv?.energized, the latch releases automatically and a spring repositionsthe clutch so that the motor engages the drive train. All licensee and constre tion permit holders should consider:

When the clutch is repositioned, a pair of lugs on the motor-side of For Limitorque Type SMo-0, . 2 and 3 valve actuators with 3600the clutch engage a pair of lugs on the valve-side. At the instant rpm motors which are used or w;11 be used in engineered safetythe lugs engage, the lugs on the motor-side are being accelerated to systems;full speed and the lugs on the valve-side are stationary. Before themotor is energized, the relative position of the lugs is random. This 1) The potential for failure of the actuators resultinginitial position detemines the depth of engagement or bite at the from manual operation,instant the lugs make contact. When a full bite occurs, no damage iscaused to the lugs. When a grazing bite occurs, the edges of the lugs 2) Means for minimizing manual operation and,are chipped or upset. Af ter the edges are sufficiently rounded, theclutch will not engage and hold for motor actuation. (continued next page)

234

IE CIRCUU\R NO. 78-16

Page 2 of 3

3) Procedures for verifyini that the actuator is 78-05 Inadvertent Safety 5/23/78 All Holders ofoperable with the datc; < Fler manual operation. Injection During Reactor OperatingCooldown Licenses (0L) orNo written response to this Circular is required. If you require Constructionadditional information regarding this matter, contact the Director of Permits (CP)the aporopriate NRC Regional Office.

78-06 Potential Corinon 5/25/78 All Holders ofENCLOSURE Mode Flooding of Reactor Operating

ECCS Equipment Licenses (0L) orLISTING 0F IE CIRCULARS ISSUED IN 1978 Rooms at BWR Construction

Facilities Permits (CP)Circular Subject First Date Issued ToNo. Of Issue 78-07 Damaged Components 5/31/78 All Holders of

Of a Bergen-Paterson Reactor Operating78-01 Loss of Well Logging 4/5/78 All Holders of 0. ries 25000 Hydrau- Licenses (OL) or

Source Well Logging Source itc Test Stand ConstructionLicenses Permits (CP)

78-02 Proper Lubricating 4/20/78 All Holders of 78-08 Environmental Quali- 5/31/78 All Holders ofOil for Terry Reactor Operating fication of Safety- Reactor OperatingTurbines Licenses (OL) or Related Equipment Licenses (OL) or

Construction at Nuclear Power ConstructionPermits (CP) Plants Permits (CP)

78-03 Packaging Greater 5/12/78 All Holders of 18-09 Arcing of General 6/5/78 All Holders ofThan Type A Reactor Operator Electric Company Reactor OperatingQuantities of Low Licenses (OL), Size 2 Coru'ctors Licenses (0L) orSpecific Activity Construction ConP ructionRadioactive Material Permits (CP), Fuel Permit: (CP)for Transport Cycle, Priority I

Material and waste 78-10 Control of Sealed 6/14/78 All MedicalDisposal Licenses Sources Used in Licensees in

Radiation Therapy Categories G and78-04 Installation Error 5/15/78 All Holders of G1

That Could Prevent Reactor OperatingClosing of Fire Licenses (OL) orDoors Construction

Permits (cpi(continued next page)

Cf, 235N'J:"..p

N

0"aL,.

; r,.

to

IE CIRCULAR NO. 78-16 fJG

Page 3 of 3

/8-11 Recirculation M-G 6/15/78 All holders of 78-15 Tilting Disc Check 7/20/78 All Holders ofSet Overspeed Stop BWR Operating Valves rail to Close Reactor Operating

Licenses (OL) or With Gravity N Licenses (0L) orConstruction Vertical Position ConstructionPermits (CP) Pemits (CP)

78-12 HPCI Turbine Control 6/30/78 All Holders ofValve lif t Rod BWR OperatingBending Licenses (0L) or

ConstructionPermits (CP) withSimilar HPCIDesign

78-13 Inoperability of 7/10/78 All Holders ofService Water Pumps Reactor Operating

i :enses (OL) orConstructionPermits (CP)except for plantslocated in: AL,AK, CA, FL, GA,LA, MS, SC

78-14 HPCI Turbine Reversing 7/12/78 All Holders ofChamber Hold Down CWR OperatingBolting Licenses (OL) or

ConstructionPermits (CP) forplants with a HPCITerry Turbine

excepting DuaneArnold andMonticello

--

236

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