Insp Repts 50-528/78-05,50-529/78-04 & 50-530/78-04 on ...

U, S. NUCLEAR REGULATORY COMMXSSXON

OFFICE OF INSPECTXON AND ENFORCEMENT

5t)-528/78-0550-529/78-04

Report No.

REGION V

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Licensee: Arizona Public Service Com any

Safeguards Group

P. 0. Box 21666

Phoenix, Arizona 85036

Faci1 ity Name Pal o Verde Uni ts 1 . 2 and 3

Xnspection at: Palo Verde Site Marico a Count Arizona

Xnspection conducted: J -2 1978

Inspectors;L. J. Garvi , Rea tor Inspector Date%igned

".",>proved By:

Summary:

. Vorder rueg en, Reactor Inspector~

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T. H. Bishop, React r Inspector

G. S. Spencer, hief, Reactor Construction andEngineering Support Branch

Date 'gned

Date Signed

Date Signed

Ins ection on Jul 14-21, 1978 Re ort No. 50-528/78-05, 50-529/78-0450-530/78-04

d: R f, d f p f factivities including: Follow-up items, tour, audits, nonconformingreports, containment welding, tendon sheath installation, drawingcontrol and pipe welding. The inspection involved 90 inspector-hoursonsite by three NRC inspectors.

Results: Four items of noncompliance were identified in the area oftendon sheath installation and inspection. Ho items of noncompliance ordeviations were identified in the other areas inspected.

~89.03g o 3(fRV Form 219 (2)

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DETAILS

Persons Contacted

*E*J*W*R.*B*W

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E. Van Brunt, Jr., Vice President/Project DirectorA. Roedel, quality Assurance ManagerM. Petro, ANPP Construction ManagerL. Robb, Assistant Project DirectorS. Kaplan, guality Systems SupervisorE. Ide, guality Systems EngineerD. Webster, guality Assurance EngineerPankonin,,guality Assurance EngineerD. Forrester, guality Assurance Engineer

Bechtel Power Cor oration

W. G. Bingham, Project Engineering NanagerJ. A. Packard, Field Construction Manager

*S. N. Nickell, Project Superintendent*A. K. Priest, Project Field Engineer

S. R. Abraham, Resident Engineer*J. E. Braun, guality Assurance Engineer*C. F. Gaither, Field Project Engineer

J. R. Beers, Lead Civil EngineerN. McCormick, Assistant Project Field Engineer

~H. P, Smith, Project Field g.C. Engineer*L. Afek, Lead Mechanical EngineerG. Pattan, Auxiliary Building Area EngineerR. Rubick, Containment Area EngineerR. Maturani, Field Weld EngineerN. Yaldo, Group Leader Welding EngineerL. B. Mayville, Assistant Welding SuperintendentR. NcConkey, Lead Field Welding EngineerL. Blackburn, guality AssuranceL. Wikie, guality Assurance EngineerM. Creager, Civil Engineer (Containment)E. Kovacevich, Field Engineer - Codes and StandardsG. Beaugrand, Field Engineer - Codes and StandardsR. Randels, Construction Liaison EngineerG. Engels, Field Engineer - PipingG. Patton, Lead Field Engineer - MechanicalY. Ducket, Lead Field Engineer - Hechanical

Western Concrete

C. Spievak, gC Inspector

*Denotes those present at the exit interview.

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2. Licensee Action on Previous Ins ection Findin s

a ~ (Open) Noncompliance (50-528/78-03): A Marathon drawingchange notice was not distributed to or used at the locationwhere the work was being performed.

Although the licensee's written response to the Notice ofViolation had not been received as of the current inspection,preliminary constructor's action had been completed, and wasexamined. As corrective action, the constructor had revisedMPP/QCI 3.0, "field Control of Design Documents," to allowarea engineers(AEs) to determine where, and to whom, individualdocument changes are to be issued. This action creates someconcerns in that incomplete, and out-of-date, drawings are nowallowed to be in the field. A sampling of 25 drawings in usein the field revealed seven which did not include the latestchanges. It is also noted that the AE is not required todocument the issuance of individual changes so that it is notpossible to effectively audit the revised document controlprogram. The above concerns were acknowledged by licenseerepresentatives. This item will be further examined uponreceipt of the licensee's written response to the Notice ofViolation.

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(Closed) Open Item (50-528/78-03): Non-rotating equipment instorage did not have procedures defining storage requirements.The procedure has been developed and observed equipmentappeared to be stored acceptably.

(Closed) Open Item (50-528/78-03): An inspection manual hasbeen prepared to organize the pipe welding inspection procedures.

(Closed) Open Item (50-528/78-03): Pipe welding QC inspectorshave received training in the procedures contained in the pipewelding inspection manual.

(Open) Open Item (50-529/78-02): The Unit 2 reactor vesselwas dropped at the manufacturer's shop while being movedbetween work stations. Volumetric examination of welds willbe performed to assure that no hidden damage resulted.

(Closed) Open Item (50-528/78-03): A provision allowinginprocess inspection documentation has been incorporated intoQCI 2.4.

(Closed) Open Item (50-528, 529, 530/78-01): Rejection ofmajor component hold-down bolts.

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NRC CC713 was initiated to evaluate the subject of the improperinstallation of several of'he hold-down bolts. The bolts

.were accepted-as-is (due to sufficient strength). The NCR

will remain open to assure that proper attention is given thetensioning of the bolts.

(Open) Open Item (50-528/78-04): Existing procedures fortranslating engineering directions noted on SDDR's to con-struction or gC forces are inadequate. Procedures were beingrevised to incorporate provisions to assure that the constructionforces were informed.

(Open) Open Item (50-528/78-03): Seismic qualification ofUni-Strut electrical tray supports. This item was not inspected.

(Open) Open Item (50-528/78-04): Codes and standards used inthe construction of the containment lines.

Discussions were held with the licensee regarding the con-struction codes and standards used in containment lines erection.The licensee was still developing a list to be submitted tothe Region Y office.

k. (Closed) Open Item (50-528/78-04): Containment welder records.Records of containment liner welder identity were not sufficientin all cases to identify the exact areas welded by each welder."As-built Welding Control System" Procedure NPP/gCI 101.4 wasdeveloped to correct this problem.

1. (Closed) Open Item (50-528/78-04)': Radiographic examination.. of containment liner welds. The licensee stated that the PSAR

reference to regulatory guide would continue to be in force.

3. Construction Status

The licensee reported that Unit 1 was 26.8%%d, Unit 2 was 6.3!, andUnit 3 was 0.5/ complete as of July 1, 1978. The overall projectwas reported to be 12.3X complete.

4. ~Fili T

Equipment storage, housekeeping, concrete curing, reinforcing steelplacement, backfilling, pipe welds, equipment installation andcable tray installation were observed.

Several large nuts were noted laying in the dirt without threadprotection near primary coolant pump hold-down bolts in Unit l.Before the end of the inspection, the threads had been protectedand the nuts were attached to the pump hold-down bolts.

No other items of concern were noted.

5. Containment Liner i/eldin

ilelding on the first ring of Unit 2 containment liner was visuallyexamined. Also examined were horizontal and vertical seams onrings 9, 10 and 11, uni-strut welded to liner, crane rail supportattachments and welding on penetr ations in the containment ofUnit l.The welder identity mar kings on Unit 2 seemed to be sufficient totrace the welder qualification and testing records. On the upperrings of the Unit 1 containment, the welder identity markings hadimproved so that identity was easily traced (Ref. Report 50-528/78-04). For the most part, the welding that was visually examinedappeared to meet requirements. The areas that did not meet require-ments had not been inspected by the quality control inspectors.

Radiographs of approximately ten feet of liner plate welds wereexamined. No anomalies were noted during the examination.

6. Containment Prestressin S stem

a 0 Review of ualit Im lementin Procedures

Installation Specification No. 13-CH-37, Rev. 2, and blork PlanProcedure/guality Control Instruction Ho. 66, Rev.2, for thepost-tensioning trumplate assemblies and sheathing were ex-amined with the following items noted.

(1) The Construction Inspection Planning (CIP) sheets attachedto HPP/gCI 66 do not clearly reference each of designatedinspection hold points listed in the procedure. The .

CIP s are used to document 'required inspection activities.

(2) Inspection descriptions in the CIP are misleading, forexample, one description reads "Replace plastic plugswith thread protectors," whereas the referenced procedureparagraph (3.1.1 of Exhibit 660-5) deals with the posi-tioning of trumplates, deformations, installation ofmounting bolts, tightners to forms, and rust.

(3) Designated inspections are not listed on the CIP. Forexample, the inspection of vents and drains (Paragraph3.1.5 of Exhibit 66.0-5) is not listed on the CIP.

(4) The CIP calls for inspections which are not required andcannot be readily performed. For example Item 9.1 ofExhibit 66.0-6 calls for post concrete placement inspectionof sheathing positioning, alignment and installation,

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referencing Paragraph 3.1.4 of Exhibit 66.0-5. Para-graph 3.1.4 calls for pre-concrete placement inspectionof sheathing position and alignment, wire tie-offs, andtaping of sheathing couplers. These inspections cannotbe readily performed after concrete placement.

b. Observations of Work and Work Activities

Unit 1 trumplate, trumplate extension, and sheathing instal.=lation activities were observed. The installation was inpreparation of concrete placement No. 1C109. The activitiesinspected included sheathing positioning and alignment, wiretie-off, coupler taping, vent line installations, sheathingcondition, and inspection coverage. The observations wereconducted on July 18, 19, and 20, 1978. tetany items of in-complete work were observed on July 18 and 19. .The concretejump forms had only been positioned on a portion of thecontainment at that time. The inspector was advised byconstructor representatives that most of the incomplete itemswould be completed prior to final form positioning. However,on July 20, 1978,„after form positioning was completed, numerousitems of incomplete work were found to be still in existance.In addition, several items contrary to the requirements ofspecifications, procedures, and drawings were observed. Theseincluded:

(1) Vertical and horizontal sheaths in each of the buttresseswere tied at intervals greater that the maximum intervalof 3'6" specified in WPP/gCI 66.0. It was noted thataction had been taken to correctly tie the sheathingtoward the top of the forms, but sheathing at the bottomwas found to be untied for distances up to eight feet.Numerous other improperly tied vertical and horizontalsheaths were identified to licensee and constructorrepresentatives.

(2) Six trumplate extensions were found to be unwired attheir ends contrary to the requirements of WPP/gCI 66.0.

(3) Fittings, which appeared to be non-galvanized, wereinstalled in the vent lines Nos. H21-023, and H21-025.WPP/gCI 66.0 specifies the use of galvanized fittings.The fittings in question were subsequently removed andreplaced. with galvanized fittings.

(4) Two vertical sheathings (the 17th and 19th clockwise fromthe center of the equipment hatch) were found to befirmly wired in position, yet out of alignment by twoinches in ten feet,.whereas Drawing 13-C-ZCS-175, Rev. 2DCN 1 specifies a maximum misalignment of 3/4" within tenfeet.

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(5) A hole was found in the lowest visible horizontal sheathat a location approximately ten feet to the left ofbuttress No. 3. This hole was reportedly repaired, butupon observation by the inspector was found to be un-repaired. The hole was subsequently repaired.

(6) Horizontal sheaths above the equipment hatch were found tobe firmly wired in position, yet they were within l-l/2"of each other, whereas Drawing 13-C-ZCS-175, Rev. 2,DCN 1 specifies a minimum clearance of three inches inthis area.

(7) Yertical tendon sheath No. Y-79 was found to have anabrupt change in alignment of approximately three inches.This sheath was installed in conjunction with the previousconcrete lift (No. 1C108) on July 7, 1978. Tolerances ineffect at that time limited misalignment to + 3/4 inch.This tolerance was subsequently changed to + 3 inches,but with no abrupt changes.

Discussions with cognizant guality Control and FieldEngineers on July 19, 1978 revealed that mandatory in-spection hold points were not executed as required byWPP/gCI 66.0. Rev. 2. Specifically, the engineers statedthat the hold points for drilling of vent holes, instal-lation of vent piping, wiring of sheathing, and positioningof sheathing were inspected on a random basis only. Itwas also reported that no inprocess records of the randominspections were generated. Accordingly, it is notpossible to identify which items were inspected, even onthe random basis. It was noted also, that WPP/gCI 66.0specifies that inspections for position, alignment,vents, and tie wiring are to be conducted prior to placementof the concrete forms. Contrary to this requirement, theforms were positioned in place on July 20, 1978 prior tocompletion.

Review of ualit Records

As of noon, July 20, 1978, no quality records had been generatedfor the sheathing installation associated with Unit 1 containmentwall placement No. 1C109, despite the fact that the placementwas planned for the night of July 20, 1978. As noted inParagraph 6.b, guality Control Engineers had not documentedtheir inprocess inspections or hold point inspections performedon the sheathing installation. The lack of inprocess inspectionrecords, and documentation of those inspection hold pointsthat were inspected, is contrary to the requirements of 10 CFR

50, Appendix B, Criterion XYII and the PSAR Section 17 whichrequire inspection records.

The Construction Inspection Plan (CIP) addressing sheathinginstallation for the previous concrete placement (No. 1C108),was examined. It was noted that both Survey and Field Engineeringhad signed-off the CIP indicating correct sheathing (tie-wiring, taping, etc) was verified after concrete placement.It is not clear how such an inspection could have been performed.It was further noted that no Nonconformance Report had been .

issued for the abrupt change in alignment existing in verticalsheath V-79. The failure to properly document the nonconformingcondition to prevent its inadvertent use is contrary to therequirements of 10 CFR 50, Appendix B, Criterion XV and thePSAR Section 17.

7. Safet Related Pi in

During a tour of the auxiliary building, several installed pipingsections were seen to have shrinkage distortions that appeared tobe associated with welds joining individual shop-furnished spools.One of particular interest was associated with a 20-inch LPSIsystem spool No. 1-SI-194-S-105 at the 40-foot elevation in theauxiliary building. Two other spools in the outdoor storage yardwhich appeared to have similar weld strinkage conditions were alsoexamined. These were 24-inch, schedule 30, 0.562-inch wall thicknessspool No. 1-SI-307-S-005, and 20-inch schedule 20, 0.375-inch

wall'hicknessspool No. 1-CH-142-S-Oll. Upon further investigation, itwas learned that this weld shrinkage condition had been an item ofconcern to Bechtel and NCR No. PA-126 wa's issued on December 14,1977 to investigate the situation. Bechtel performed an engineeringanalysis of the distortion configuration to determine its effect onflow characteristics and joint stresses, and destructively analyzedtypical specimens for metallurgical attributes. In addition,personnel from Bechtel, Combustion Engineering and Nuclear EngineeringServices met with the supplier, Pullman Power Products, to discussthe matter and resolve any issues associated with surface preparationto properly provide for in-service inspection.

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According to Bechtel personnel, the shrinkage distortion phenomenonis associated only with large diameter, thin wall stainless steelpipe and is caused by the application of weld overlay to the outsidesurface of the spool piece and, when necessary, the weld overlayprocess is the approved method for satisfying specification re-quirements pertaining to I.D. and wall thickness dimensions subsequent .

to the weld prep counterbore operation. Bechtel concluded fromtheir analyses that flow characteristic and stress level effectswere well within design margins, that the shrinkage distortion didnot impair the performance of ISI and radiographic examination, andthat the distortion was metallurgically acceptable. The inspectoragreed that ASNE code requirements were not compromised, and'nformedthe licensee that the subject was considered closed.

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8. Safet Related Structures

The inspector examined the foundations for the Train A safetyinjection pumps and the records associated with the insta1lation.Concrete placement 1A05 served the HPSI pump and placement 1A06 wasfor the LPSI pump. The records included the Construction InspectionPlans (CIP's) for concrete preplacement, placement, and post-placement, concrete delivery tickets, and cylinder break strengthtest reports. No anomalies were noted.

9. Exit Interview

At the conclusion of the inspection, a meeting was held with thelicensee and contractor representatives denoted in Paragraph l.The areas covered dur ing the inspection, and the observations andconclusions of the inspectors were reviewed. The inspectors ex-pressed strong concern in regard to quality systems that allowedthe tendon sheath installation to deteriorate to the level found bythe inspectors. The inspectors also expressed concern that theBechtel and APS guality Assurance site groups had not taken actionon July 19 or 20th when it was apparent that extreme correctiveaction was necessary.

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UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION V

SUITE 202, WALNUT CREEK PLAZA1990 N, CALIFORNIA BOULEVARD

WALNUT CREEK, CALIFORNIA 94996

Docket No. 50-530 Oy 7 19Q

Arizona Public Service CompanyP. 0. Box 21666Phoenix, Arizona 85036

Attention: Nr. E. E. Van Brunt, Jr.Vice President, Construction Projects and ANPP Director

Gentlemen:

Subject: Inspection of Palo Verde Unit 3

This refers to the inspection conducted by Hr. North of this office onOctober 11-12, 1977 of activities authorized by NRC Construction PermitNo. CPPR-143, and to the discussion of our findings held by Hr. Northwith you and other members of your s'taff at the conclusion of theinspection.

=Areas examined during this inspection are described in the enclosedinspection report. llithin these areas, the inspection consisted ofselective examinations of procedures and representative records, inter-views with personnel, and observations by the inspector.

No items of noncompliance with NRC requirements were identified withinthe scope of this inspection.

In accordance with Section 2.790 of the NRC's "Rules of Practice,"Part 2, Title 10, Code of Federal Regulations, a copy of this letter andthe enclosed inspection report will be placed in the NRC's PublicDocument Room. If this report contains any information that you believeto be proprietary, it is necessary- that you submit a written applicationto this office, within 20 days of the date of this letter, requestingthat, such information be withheld from public disclosure. The applica-tion must include a full statement of the reasons why it is claimed thatthe information is proprietary. The application should be prepared sothat any proprietary information identified is contained in an enclosureto the application, since the application without the enclosure will

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Arizona Public Service Company -2- goy 7 19'l7

also be placed in the Public Document Room. If we do not hear from youin this regard within the specified period, the report will be placed inthe Public Document Room.

Should you have any questions concerning this inspection, we will beglad to discuss them with you.

Sincerely,

. cf.

H. E. Book, ChiefFuel Facility and Materials

Safety Branch

Enclosure:IE Inspection Report

No. 50-530/77-05

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. iU. S. NUCLEAR REGULATORY COMMISSION

OFFICE OF INSPECTION AND ENFORCEMENT

REGION V

Report No. 50-530/77-05

Docket No. 50-530 License No. CPPR-143 Safeguards Group

Licensee: Arizona Public Service Com an

P. 0. Box 21666

Phoenix, Arizona 85036

Facility Name: Palo Verde Uni.t 3

Inspection at: Buckeye, Arizona

Inspection conducted; October 11-12, 1977/

Inspectors: 7>cVC"'rt

, a sation Specialistw7 7

Date ign d

Date Signed

Approved by:

Summary:

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oo , le , ue ac> sty an atersa sSafety

Branch'ateSigned

/o 9( 77Date Signed

Ins ection on October 11-12, 1977 Re ort No. 77-05Areas Ins ected: Environmental protection during construction includingstatus o complementation of each construction permit requirement;implementation of all applicable construction permit requirements andverification of existence of implementing procedures at the workinglevel. The inspection involved 13 inspector-hours on site (total forUnits 1, 2, and 3) by one NRC inspector.

Results: No items of noncompliance or deviations were identified.

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IE:V Form 219 (2)

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DETAILS

Persons Contacted

-Arizona Public Service Com an

2.

*E. E. Van Brunt, Jr., Vice President Construction Projectsand ANPP Director

*R. Robb, Manager, Nuclear Services*M. Pietro, Manger, Site Construction~J. Roedel, Manager, quality Assurance~J. Mann, Senior Health Physicist

D. Karner, Licensing Engineer Units 4 and 5R. Hand, Supervisor, Sste guality AssuranceC. Young, Environmental Scientist

'N. Millsey, Mechanical EngineerL. Icard, Instrument Control Technician

Bechtel Cor oration

J. Dyer, Site Advisor General Environment (SAGE)T. Cheville, Assistant Field EngineerC. Betzhold, Supervisor, guality Assurance

*Denotes those present at the exit interview.

Audits

The inspector questioned applicant and Bechtel personnel concerningaudits of environmental program related activi,ties performed sincethe last environmental program inspection (Inspection Report 50-528, 529, 530l76-02, September 8-10, 1976). A total of four audits

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been performed. The inspector examined all audit reports, Theaudits performed included one by the applicant's gA staff, two bythe Bechtel onsite gA staff and one of the applicant's samplecollection technique by Controls for Environmental Pollution (CEP),a contractor for the applicant. The audits identified two items of

~ an administrative nature for which corrective action was required.Appropriate cor rective action, verified by subsequent audits, hadbeen completed at the time of inspection. Audits and correctiveactions were appropriately documented.

No items of noncompliance were identified.

3. Im lementation of Construction Permit Re uirement E 1

The inspector discussed and examined documents describing the.implementation of sections 4. 5. 1 and 4.5.2 of the Final Environ-mental Statement (FES). The documents examined included Mon~thlSummar -Environmental Activit Re orts number 007, July 30 ~976to number 020, August 26, 1977 and weekly Environmental ControlPro ram-Environmental Archiolo ical Protection Re orts up to and

'including the report dated September 30, 1977. During an onsitetour . the inspector observed the applicant's actions with respectto the following FES requirements:

FES Section 4.5.1;

Item 2; No organic materials from the plant site were inevidence.

Item 5. No unnecessary grading was observed.

Item 7. Drainage has been provided to direct onsite runnoffto the south and east toward the East Wash drainageline. Onsite drainage is direct to a "J" hook im-poundment basin at the. south end of the East Washdiversion embankment. The East Wash diversion em-bankment has been completed and riprap placed alongits entire length. Rain at the site shortly beforethe inspection established that onsite drainage wasto the sout6 and east and was contained by the "J"hook basin.

Item 8.. Water trucks were in evidence and little dust wasnoted. Chemicals have not been used for dust control.

Item 10.

Item 12.

Item 13.

Item 14.

It was observed that spoil area slopes were gradedto meet existing contours.

An air curtain incinerator has been installed andis operating under a county permit. The residue isbeing buried. The inspector noted that the con-struction site was clean and orderly and free ofconstruction trash and blowing paper and debris.

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Batch plant and truck wash waste is being dischargedto a settling pond which will be buried.

Permanent sanitary facilities have been installedhowever, contractor serviced portable facilities arein use by the construction force.

Item 17. The inspector observed that energy dissipators wereinstalled at the bottoms of drop pipes.

Item 22.h Although construction of transmission corridorsand water pipe line routes has not commenced, theapplicant is currently conducting EnvironmentalAwareness Seminars for contractor and applicantpersonnel including the use of a video taped pre-sentation used for supervisory personnel. Environ-mental requirements are contained in all contracts.

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FES Section 4.5.2

Item 4. The applicant is sampling and Controls for Environ-mental Pollution,' contractor, is analyzing waterfrom onsite and neighborhood wells to identifypossible effects of station construction. No ad-verse effects have been noted to date.

Item 5. Silt loads from construction area runoff to the EastMash is contained by the "J" hook basin extention ofEast Wash diversion embankment.

Item 6., The applicant plans the construction of three stillingbasins on Winters Wash tributaries which originateon or traverse the west and northwest corner of thesite west of the railroad embankment. The applicant'sevaluation of the effects of the September 24, 1976,0. 66 inch rainstorm, was that no siltation attributableto construction was identifiable. In examiningaerial photographs of the site, the inspector observedthat a substantial area located in Winters Washsouth west of the site has been placed under cultivation.

Item 7. The applicant has informed all onsite personnel thatphysicians statements are required for any cases ofValley Fever (coccidioidomycosis) among onsitepersonnel. On October 12, 1977, the inspector wasinformed that the first case had been reported onOctober 11, 1977. The applicant was preparing toreport the occurrence to local health authorities.

- No items of noncompliance were identified.


The applicant and Bechtel Corporation have established a controlprogram and written procedures and instructions as required by thissection of the construction permit. The inspector verified thatcurrent procedures were available to individuals responsible forimplementation of the environmental conditions. Provisions havebeen included for management audits of the implemention of environ-mental conditions, previously reported (Para. 2 Audits).

The applicant has maintained records, sufficient to furnish evidenceof compliance with the environmental conditions in the FES.


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5. Im lemention of Construction Permit Re uirement E 3

The applicant in procedure NS-11, Environmental Evaluation Procedureand Bechtel in procedure No. 402.0 Environmental Control Pro<rram-Construction ~Activit Environmental Evaluation CAEE make provisionsfor the identification of the environmental impacts of constructionactivities not evaluated by the NRC.

The inspector examined CAEE reports 04-76 and 01-77 through 012-77;The only item referred to the NRC was the subject of CAEE report06-77 which concerned the use of the East Wash riprap haul road onthe north side of the site as an emergency evacuation route. Theapplicant discussed this item with the Palo Verde EnvironmentalProject Manager, NRC, and was informed that since the road was notpaved, it did not constitute an unevaluated item and no NRC actionwas required.


6. . Im lementation of Construction Permit Re uirement E 4

The applicant has established a procedure, NS-11, previouslyidentified (Para. 5) which provides for response to identifiedunexpected harmful effects or evidence of serious damage detectedduring facility construction. The inspector's discussion withapplicant personnel, examination of records and tour of the sitedid not disclose any unexpected harmful effects or evidence ofserious damage.


7. . Im lementation of Construction Permit Re uirement E 5

The applicant has taken the following steps in the implementationof Section 6 Environmental Monitorin Pro rams of the FES:

FES Section 6.1.1.1 Surface Water; the, applicant stated thatth b I f u ~pd i ff

the NPDES permit exempted the applicant from requirements formonitoring construction area runoff for total suspended solids.As previously noted (Para 3, Item 7) the East Wash riprapped,diversion embankment and "J" hook basin area have been constructed.

FES Section 6.1.1.2 Groundwater: the perched and regionalgroundwater levels are measured weekly and summarized andreported to the applicant semiannually by NUS. Samples arecollected and analyzed quarterly by CEP. The inspector ex-amined the CEP report dated March 31, 1977.

FES Section 6. l. 1.3 Treatment Plant Water; water samples arecollected and analyzed quarterly by CEP. The inspector

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examined the report dated June 1, 1977. The analyticalprogram has included a quarterly study of the concentration of

„ ...-.="-.-.-M-131 and gross alpha and beta and gamma spectrum measurements.In addition, the samples have been analyzed for heavy el ments,

:.:-..—:. -. hardness, B00, dissolved and suspended solids, chlorides,-. = - sulphates, total phosphorus, nitrogen and ni trates, pesticides,

,chlorinated hydrocarbons, chlorophenyoxy componds and coliform.and streptococci organisms.

FES Section 6.1.2 Onsite Meteorolo ; the inspector toured.— .the onsite meteorological station and verified that the equip-

ment conformed as to type and installation. In addition tothe onsite strip chart records, digital data is telemetered tothe applicant's Deer Valley facilities for transmission to NUS

for evaluation.

FES Section 6.1.3 ~EcoIo ; the app1icant through their con-tractor Bechtel is presenting environmental awareness seminarsto construction personnel. On a continuous basis SAGE andsemiannually NUS evaluate habitat alteration, revegetationpractices and the presence of rare or endangered species. Saltdrift monitoring plots (six) have been established, fenced andplacarded as protected environmental monitoring locations.



Final transmission line routing has not yet been established. Theroute of the water pipe line from the 91st Avenue Sewage TreatmentPlant has been established. The applicant has prepared an aerialphoto map of the route and has identified areas of possible arch-eologically interest on the map. The archeological walk over of theroute is complete. Prior to excavation for the line, archeologicaltrenching will be performed at several sites the line will traverse.The applicant is presently preparing the aerial photo maps, arch-eological data and pipe line plan and profile drawings for submissionto the NRC staff for review.


9 . Exit- Interview

. The inspector met with the applicant representatives (denoted inPara. 1) at the conclusion of the inspection on October 12, 1977.The inspector identified the areas included in the inspection andinformed the applicant that no items of noncompliance had beenidentified.

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5.2. 3 REACTOR COOLANT PRESSURE BOUVDARV MATERIALS

5.2.3.1

See CESSAR Section 5.2.3.1

5.2.3.3 Fabrication and Processin of Ferritic Materials:

5.2.3.3.1 'racture Tou hness

See.CESSAR Section 5.2.3.3.1

In Addition:

Fracture toughness testing was performed in accordance with applicable ASME

Code and Addendas (See Section ").

Fracture toughness data for the Reactor Coolant Pressure Boundary componentsfor Palo Verde Unit 1 is presented in Tables 5.2.3-1 through 5.2.3-21.Full Charpy Transition Curves (including upper and lower shelf levels forenergy absorbed, Lateral Expansion, and percent Cleavage fracture) for thesix beltline plate materials, obtained from specimens tested in the weakdirection (transverse orientation), are shown in figures 5.2.3-1 through5. 2. 3-6.

Fracture toughness data for the Reactor Coolant Pressure Boundary Componentsfor Palo Verde Units 2 8 3 will be provided at a later date.

~Bechtel to provide this information.

. Gt9/oiad 5-l

5.2.3 REACTOR COOLANT PRESSURE BOUNDARY MATERIALS

5.2.3.1 l 1ateri al S ec ificati ons

See CESSAR Section 5.2.3.1.

5.2. 3.3 Fabrication and Processina of Ferritic Yiaterials:

5. 2. 3. 3. 1 Fracture ~Tou hness

See CESSAR Section 5.2.3.3.1.

5. 2. 3. 3. 2 Control of 'ideldin

5.2.3.3,2.1 Avoidance of Cold Cracl:in

See CESSAR Section 5.2.3.3.2. l.

5. 2. 3. 3. 2. 2c 2 U—'4See CESSAR Section 5.2.3.3.2.2.

5.2.3.'3.2.3 Re ulator Guide 1.71

See CESSAR Section 5.2.3.3.2.3.

5.3 REACTOR VESSEL

5.3.1.1 Reactor Vessel t1aterials

See CESSAR Section 5.3.1.

0 S ecial Controls for Ferritic and Austenitic Stainless Steels

See CESSAR Section 5.3.1.4.

I„

5.2.3.3.2 Control of Melding

5.2.3.3.2.1 Avoidance of Cold Crackin

See CESSAR Section 5.2.3.3.2. 1

5. 2. 3. 3. 2. 2 Re ulatory Guide 1.34

See CESSAR Section 5.2.3.3.2.2

5.2.3.3.2 ~ 3 Rec ulatory Guide 1.71

See CESSAR Section 5.2.3.3,2.3~~ ~~ ~~ ~~ ~

TABLE 5.2.3" 1

PALO VERDE-UNIT 1

FRACTURE TOUGHNESS DATA

REACTOR VESSEL (PLATES)

PieceNu.".,ber

ReferenceDrawin No.:

Haterial. Code No:

HaterialLocation

142-102 E-78173-161-003-02 H-4311-1

142-102 E-78173-161-003-02 H-4311-2

SA533-GRB"CL1

SA533-GRB-CL1

Lower Shell PlateLower Shell Plate

142-102-124-102

E-781?3-161-003-02 H-4311-3 SA533-GRB-CLl Lower Shel 1 Plate

E-78173-161-003-02 H-6701-1 SA533-GRB-CLl Intermediate Shell Plate

124-102 E-78173-161 "003-02 H-6701-2

124-102 E-78173-161 "003-02 H-6701-3

122-102 E-78173-161-003-02

122-102 E-78173-161-003-02

P-6701-4

H-6701 "5

.122-102 E-78173-161 "003-02 H-6701-6

102-102A E-78173-161-003-02 H-6709"1

SA533-GRB-CL1

SA533-GRB-CL1

SA533-GRB"CLl

SA533-GRB-CL1

SA533-GRB-CL1

SA533-GRB-CL1

Intermediate Shell PlateIntermediate Shell Plate

Upper Shell Plate

Upper Shell Plate

Upper Shell PlateClosure Head Dome

150-102 E-78173-161-003-02 H-6715-1 SA533-GRB-CLl 'ottom Head Dome

150-102 E-78173-161-003-02 H-6715-2 SA533-GRB-CL1 Bottom Head

Dome'02-102B

E-78173-161-003-02 H-6709-2 SA533-GRB-CLl Closure Head Dome

Drop Meight .

NDT~F-10

-40

-20

-40

-50

-30

"30

"30

-30

-20

-70

-30

"40

~)T10(a)

~ 40(a)

20(a)

+30(a)

+40(a)

+40(a)

+60(')+40(a)

40(a)

+10(a)

20(a)

30(a)

-10(a)

HinimumUpper Shelf

Ener ft-lbs

134

127

142

83

96

100

N/A

N/A

N/A

N/A

N/A

N/A

N/A

(a) Determined per Applicable ASHE-BPV-Code Sect III, Subsection NB, Article NB-2331"(a-1,2,3)

N/A Not applicable (No minimum upper shelf requirement).

189A/js A-

= TABLE 5.2.3"2

PALO VERDE UNIT-1


REACTOR VESSEL (FORGIiHGS)

PieceH rber

Reference~orawin Ho:

MaterialCode Ho:

MaterialS ecification

128-301

128-301

E-78173-161-003-02

E-78173-161-003" 02

131-102, E"78173-161-003" 02

131-102 E- 78173-161 "003"02

128-101 E-?8173-161 "003-02

128-101 E-78173-161 "003-02

128-101

128-101

126-101

E-78173-161-003-02

E-?8173-161-003-02

E-78173"161"003-02

M-4304"1

M-4304"2

M-4307-1

M-4307-2

M-6703-1

M-6703-2

M-6703-3

Yi-6703"4

M-6705-1

SA508-CL2

SA508-CL2

SA508-CL2

SA508"CL2

SA508-CL2

SA508-CL2

SA508-CL2

SA508-CL2

.SA508-CL2

106-101 E-78173-161-003" 02 M-6706-1

E-781I3-161-003-02128-501

128-501 E-17873-161-003-02

128-501 E-78173-161-003-02

128-501 E"78173-161-003-02

M-6708-1

Yi-6708-2

M-6708-3

lj-6708-4

SA508-CL2

SA508-CL2

SA508-CL2

SA508-CL2

SA508-CL2

131-101

131-101

. E-78173-161-003-02 . M-6712-1

E"781 I 3-161-003-02 M"6712-2

SA508-CLl

SA508"CL1

131-101 E-78173-161-003-02 M-6712-3 SA508" CL1

131-101 E-78173-161-003-02 - M-6712-4 SA508-CL1

Location

Outlet NozzleOut'let Nozzle

Outlet Nozzle Safe End


Inlet Nozzl e

Inlet Nozzle

Inlet Nozzle

Inlet Nozzle

Vessel Flange

Closure Head Flange

Inlet Nozzle Extension

Inlet Nozzle Extension~ .

In'let Nozzle 'Extension

Inlet Nozzle Extension

Inlet Nozzle Safe End

Inlet Hozzle Safe End



Drop VeightNOT F0 180

-10 -10

-10 -'l0

"10 -10

-10 "10

-20 "20

+10 +10

-10 -10

0 0

-70 -70

-70 -70

+20 +20

+20 +20

+20 +20

+20 +20

-10 -10

-10 "10

-10 -10

"10 -10

0

10(a)

lp(a)+10(a)

+10(')p(a)

+10(a)

10(a)p(a)

-70(')-70(')+2p(a)

+20(')+20(a)

+20(')lp(a)10(a)

10(a)

10(a)

180

1p(a)

10(a)

+10(a)

+lp(a)0(a)

+1 0 (a)

10(a)p(a)

70(a)

70(a)

+20')+20(a)

,20(a)+20(a)

lp(a)-lp(a)-10(a-lp(')

RTHDT ( F)

(a) Detersiined per applicable ASME-BPV Code and addenda, Sect III, Subsection NB, Article NB-2331-(a"1,2,3)

TABLE 5.2.3-3

PALO VERDE UNIT-1

FRACTURE TOUGHNESS DATA FRO<1 MELD vETAL CERTIFICATION TESTS

REACTOR VESSEL

(DATA TO BE PROVIDED AT A LATER DATE)

Seaa 8 Seam Nomenclature Meld Filler Lot 8 RNDT ( F)

189A!js F" ""

Sea "lNu.",.ber

TABLE 5.2.3-4

PALO VERDE UNIT-1

FRACTURE TOUGHNESS DATA FROM WELD PROCEDURE (UALIFICATIONTESTS

REACTOR VESSEL


~t<DT FDetailed Weld Meld Procedure Meld Filler materials Joined HAZ HAZ

IL""'R'NOTl~'el d~OF

TABLE 5.2.3"5

PALO VERDE .UNIT-1


REACTOR COOLANT PIPING (PLATES)

PieceNu".ber .

722-102

722-102

722" 102

722" 102

722-104

722-'104

722-1C4

722-104

722-104

722-104

722" 104

722-104

722-106

722-106

722" 106

722-106


E"78473"761-001-00

E-78473-761-001"00

E-78473-761-001-00

E-78473-761-001-00

E-78473-761-002-02

E-78473-761-002-02

E-78473"761-002-02

E-78473-761-002-02

E-78473-761-002-02

E-78473-761-002-02

E-78473-761-002-02

E-78473-76'l-002-02

E-78473-761-002-02

E-78473" 76'l -002"02

E-78473-761-002-02

E-78473-761-.002-02

llaterialCode No:

H-7601" 1

H-7601-2

H"7601-3

H-7601-4

Yi-7602-1

H-7602-2

H-7602-3

H-7602-4

H-7602-5

H-7602-6

Yi-7602-7

H-7602-8

H-7603-1

Yi-7603-2

H-7603-3

H-7603-4

HaterialS ecification

Sl61 6-GR70

SA516-GR70

SA516-GR70

SA516-GR70

SA516-GR70

SA516-GR70

SA516-GR70

SA516-GR70

SA516-GR70

SA516-GR70

SA516-GR70

SA516-GR70

SA516-GR70

SA516-GR70

SA516-GR70

SA516-GR70

Location

Segment

Segment

Segment

Segment

Segment

Segment

Segment

Segment

Segment

Segment

Segment

Segment

Segment

Segment

Segment

Segment

StraightStraightStraightStraightStraight

- StraightStraightStraightStraightStraightStraightStraightStraightStraightStraightStraight

Drop Meight~NDT 'F

-'l0

-10

-10

-10

-10"'l0

-10

0

-10

-10

-10

-10

-'lD

-10

-10

~lT.10(a)

+10(a)

.10(a+10(a)

+10(a)

+10(a)

+20(a)

+20(')

+10".10')+20(a)

+10(a)

0(a)

0(a)

0(a)

0(')

189A/js H-~~ (TABLE 5.2.3-5 (Continued)

PALO YERDE UNIT"1


REACTOR COOLANT PIPING {PLATES)

PieceNumber

722-106

722-106

722-106

722-106

722-102

722-204

722-204

722-204

722-204

722-208

722-208

722-104

722-104

722-104

ReferenceDrawino No.:

E-78473-761-002"02

E-78473-761-002-02

E-78473-761-002-02

E-78473-761-002-02

E-78473-761-002-02

E-78473-761-002-02

E-78473-761-002-02.

E-78473-761-001-00 .

E-78473-761-001-OD

E-78473-761-001-00

E"78473-761-001-00

E-78473-761.-002-02

E-78473-761-002-02

E-78473-761-002-02

HaterialCode No:

H-7603-5

H-7603-6

M-7603-7

H-7603-8

H-7604-1

H"7605-1

H-7605"2

H-7605-3

H-7605-4

M-7606-1

H-7606-2

M-7606-6

H-7606"7

H-7606-8


SA516-GR70

SA516-GR70

SA516-GR70

SA516"GR70

SA516-GR70

SA516"GR70

SA516-GR70

SA516-GR70

SA516-GR70

SA516-GR70

SA516-GR70

SA516-GR70

SA516-GR70

SA516"GR70

Location

Straight Segment

Straight Segment

Straight Segment

Straight Segment

Elbow Segment

Elbow Segment

Elbow Segment

Elbow Segment

Elbow Segment

Elbow Segment

Elbow Segment

Straight Segment

Straight Segment

Straight Segment

Drop Weight~NOT F

-10

-10

"10

-10

-10

-10

-10

"10

-10

-10

"10

"10

-10

-10

~o)DTRT

0(a)0(a)0(a)0(')

lp(a)

+1 p(a)

lp(a)lp(a)

+1 p(a)

+10(a)

lp(a)+10(a)

+20(a)

+10(a)

(a) Determined per applicable ASHE BPV Code Sect III, Subsection NB. Article NB-2331(a-l,2,3)

TABLE 5.2.3-6

PSLO VERDE UNIT-1


REACTOR COOLANT PIPING (FORGINGS)

PieceNumber

Reference~Drawin No:

728-101 E-78473" 761-001-00

728-201

728-201

728-202

E"78473-761-001-00

E-78473-761 "001-00

E-78473-761-002-02

728-202 E-78473-761-002-02

728-102 E-78473-761-002-02

728-102 E-78473-761"002-02

728-102 E-78473-761"002-02

728-102 E-78473-761-002-02

728-103 E-78473-761-002-02

728-103 E-78473-761-002-02

728-103 E-78473-751-002-02

728"103 E-78473-761-002-02

728-203 E-78473"761-002-02

MaterialCode No:

M-7607-1

H-7608-1

H-7608-2

H-7609-1

H-7609-2

H-7610-1

M-7610-2

H-7610-3

Material

SA541-CL1

SA541-CLl

SA541-CLl

SA541"CL1

SA541-CLl

SA541-CLl

SA541-CL1

SA541-CL1

M"7610-4 SA541-CLl

H-7612" 1 SA182-GRF1

M-7612-3

H-7612-4

M-7613-1

SA182-GRF1

SA182-GRF1

SA182-GRFl

H-7612-2 SA182-GRF1

Location

Surge Nozzle

Shutdown Cooling Outlet Noz.

Shutdown Cooling Outlet Noz.

Spray Nozzle

Spray Nozzle

Letdown Drain Nozzle




Safety Injection Nozzle

Safety Injection Nozzle

Safety Injection Nozzle4

1'afetyInjection Nozzle

Charging Inlet Nozzle

~01 8G

-10

-10

-10

N/A

N/A

N/A

N/A

N/A

N/A

0

-10

Drop WeightNDT F)-

RT>DT ( F)/LST"( F)

0 180

+1O(')

~10(a)

+10(a)

/,40(d). /+40(d)

/+40(d)

/+40(d)/.4O(d)/+4O(d)

0(a)

10(a)

0(a)

O(')0(a)

(a) Determined per applicable ASME-BPV Code and addenda Sect III, Subsection NB, Article NB-2331-(a-l,2,3)

(d) 'LOW ST SERVICE TEMPERATURE' Determined per applicable ASML-BPV Code and Addenda Sect III, Subsection NB,

Article NB-2332-a

Lowest service temperature

N/A Not applicable

0TABLE 5. 2. 3-7

PALO VERDE UNIT-1

FRACTURE TOUGHNESS DATA FROiN WELD METAL CERTIFICATION TESTS

REACTOR COOLANT PIPING


Seam ¹ Seam Nomenclature Meld Filler Lot ¹ RTNDT ( F)

TABLE 5.2.3"8

PALO VERDE UNIT-1

FRACTURE TOUGHNESS DATA FROM 'WELD PROCEDURE (UALIFICATIONTESTS

REACTOR COOLANT PIPING

(DATA TO BE PROVIDED AT A LATFR DATE)

Sean Detailed Weld'eld Procedure Weld Filler~NDT F NDT

Materials Joined HAZ HAZ WeldMaterial 1

- Material 2 1 2 ~F

189A/js H-

'iece

NumberReference

Drawin No.:MaterialCode No:

TABLE 5.2.3-9

~ 'ALO VERDE UNIT-1

FRACTURE TOUGHNFSS DATA

PRESSURIZER (PLATES)

HaterialS ecification Location

Drop Meight~DDT F

642-102

642-102

676" 102

622-102

622-102

642-652

E-78473-661-002-03

E-78373-661-002-03

E-78373"651"002-03

E-78373-661-002-03

E-78373-661-002-03

E-78373-661-002-03

H-5008-1

Yi-5008-2

t<-7030-1

H-7309-1

H-7309-2

M-7313-1

SA533-GRB-CL1

SA533".GRB-CL1

SA533-GRB-CL1

SA533-GRB-CL1

SA533-GRB-CL1

SA533-GRB-CL1

Lower Shell Plate

Lower Shell Plate

Top Head Dome

Upper Shell Plate

Upper Shell PlateBottom Head Dome

-10

"10

-10

-10

-10

"10

10(a)

+20(a)

-10(')10(a)

-10(')10(a)

(a) Determined per applicable ASYiE BPV Code Sect III, Subsection NB, Article NB"2331 (a-l,2,3)

I l

189A/js A-2~r 5

1

TABLE 5.2.3-10

PALO VERDE UNIT-.1


PRESSURIZER (FORGINGS)

PieceNu.;ber

Reference~0@awi n Na:

608-303 E-78373"661-002-03

608-304 E-78373-661-002-03

656-652 E-78373-661-002-03

656-101 E-78373-661-002" 03

658-201 E-78373-661-002-03

608-303 E-78373-661-002-03

608-303 E"78373-661-002-03

608 303 E 78373 661 002 03

MaterialCode No:

H-7301-1

H-7302-1

H-7303"1

H-7303-2

H-7303-3

M-7303"4

~ H-7304-1

M-7313-1


k

SA508-CL2

SA541-CL2

SA541-CL2

SA541-CL2

SA541-CL2

SA541-CL2

SA541-CL2

SA508-CL2

Location

Support SkirtSurge Nozzle

Safety Valve Nozzle

Safety Valve Nozzle

Safety Valve Nozzle

Safety Valve Nozzle

Spray Nozzle

Support Skirt

Drop WeightNDT F

0 180

-10

-10

-10

-10

-10

-10

+10

-10

RTNDT ( F)

0 180

-lo(')10(a)

+40(a)

.4o')+4O(a)

40(a)

.lo(')10(a)

(a) Determined per applicable ASHE-BPY Code and addenda Sect III, Subsection NB, Article NB-2331-(a-l,2,3)

~ ~

189A/js B-

'eam

8

TABLE 5.2.3-11

PALO VERDE UNIT-1

FRACTURE TOUGHNESS DATA FROST WELD NETAL CERTIFICATION TESTS

PRESSURIZER

{DATA TO BE PROVIDED AT A LATER DATE)

Seam Nomenclature Weld Filler Lot 0'TNDT { F)

'189A/js F-( .~

SeamNumber

TABLE 5.2. 3-12

PALO VERDE UNIT-1

FRACTURE TOUGHNESS DATA FROH MELD PROCEDURE QUALIFICATION TESTS

PRESSURIZER


~RTgpy,p) RTgpy

Detailed Meld Weld Procedure Meld Filler Yiater ials Joined HAZ HAZ WWeeidI"

189A/js H- "':"

PieceNu-.ber

248-302

254-102

254-102

255-104

244-102A


c 78373 261 003-04

E-78373-261-003-04

E-78273-261"003-04

E-78273-261-003-04

E-78273-261-003-04

244-1028 E-78273-261"003-04

244-102C E-78273-261-003-04

276-3101A

276-3101B

E-78372-261-003-04

E-78273-261-003-04

244-)020 -

E-78273"261-003-04'aterial

Code No:

TABLE 5.2.3-13

PALO VERDE UNIT"1


STEAM GENERATOR UNIT 1 (PLATES)

MaterialSoecification Locat'.on

M-2105-1 SA516-GR70 Stay Cap

H-7021-1 SA533-GRB-CLl Primary Head

H-7021-2 SA533-GRB-CL1 Primary Head

H-7202-1 SA533-GRB-CLl Support SkirtH-8104-1 SA533-GRB-CLl Primary Extension Ring

H"8104-1 SA533-GRB-CL1 Primary Extension RingH-8104-1 SA533-GRB-CLl Primary Extension RingH-8104-1 SA533-GRB-CL1 Primary Extension Ring

H-7243-1 SA533-GRB-CL1 Primary Hanway Cover

H-7243-1 SA533-GRB-CLl Primary Hanway Cover

Drop Meight~HDT F

-40

-10

-10

-35

-20

-20

-20

-20

+10

+10

~o)P

~-0(a)

10(a)

10(a)

35(a)

20(a)

-20(')0(a)

p0(a)

~10(a)

+10(a)

(a) Determined per applicable ASME-BPV-Code Sect III Subsection NB, Article NB-2331-(a-1,2,3)

189A/js A-

TABLE 5.2.3-14

PA 0 VERDE UNIT-1


STEAM GENERATOR UNIT 01 (FORGINGS)

PieceNu~ber

246-101

248-101

Reference~Drawin No:

E-78273" 261-003-04

E-78273-261-003-04

252-201

258-101

258-301

258-301

258-202

258-402

258-402

E-78273"261-003-04

E-78273-261-003-04

E-78273-261"003-04

E-78273-261-003-04

E-78273-261-003-04

E-78273-261-003-04

E-78273-261-003"04

248-201 E-78273-261-003-04

252-101 E-78273-261 "003"04

MaterialCode No:

M-4701-1

M-4706-2

M"4710"2

M-7022-1

M-7023-1

M-7024-1

M-7025-1

M-7025-2

M-7026-1

M-7027-2

M-7027-3

Material

SA508-CL2

SA508-CL2

SA508-CL2

SA508-CL3

SA508-CL3

SA508-CL2

SA508-CL2

SA508-CL2

SA508-CL1

SA508-CL1

. SA508-CL1

Location

Tube Sheet

Stay Stub

Stay Cap

Stay Cyl inderStay Ring

Inlet Nozzle

Outlet Nozzle

Outlet Nozzle

Inlet NOzzle Safe End



Drop WeightNDT F)0 180

+40 +40

+40 +40

-30 "30

+10 +10-+10 +10

-5 "5-5 -5+11 +11

-23 "23

-32 "32

"32 -32

0

+so<'>

.40(')-30(a).40(')30(a)5(a)

5(a)

-23(')-12(')

12(a)

180

40(a)

40(a)

30(a)

~40(a)

~30(a)5(a)5(a)

-23(')12(a)

12(a)

RTNDT ( F)

(a) Determined per applicable ASME-BPV Code 8 addenda, Sect III, Subsection NB, Article NB-2331-(a-l,2,3)

1

189A/js B (™'1

1

TABLE 5.2.3-15

PALO VERDE UNIT-1

FRACTURE TOUGHNESS DATA FROM MELD METAL CERTIFICATION TESTS

STEAM GENERATOR 81


Seam 8 Seam Nomenclature Meld Filler Lot 8. RTNDT ( F )

189A/js F

TABLE 5.2.3-1S

PALO VERDE UNIT-1

FRACTURE TOUGHNESS DATA FROM WELD PROCEDURE QUALIFICATION TESTS

STEAM GENERATOR Ol


Seam Detailed MeldNumber Seam Nomenclature Procedure 0

Meld Procedureualification 8

~NDT F NDT

Meld Filler Materials Joined HAZ HAZ MeldMaterial Lot 8 Haterial 1 Haterial 2 1 2 ~F

189A/js H-AXF

PieceNumber

ReferenceDrawin Ho.:

MaterialCode Ho:

TABLE 5.2. 3"17

PALO VERDE UNIT-1


STEAM GEHERATOR UNIT 82 (PLATES)

MaterialS ecification Location

Drop Meight~NDT 'F

248-302

256-'104

276-3101 A

276-3101 B

254-102

254-102

244-102A

244-1028

244-102C

244-102D

E-78273-351-003-02

E-78273-361-003"02

E-78273-361-003-02

E-78273"361-003"02

E-78273"351-003-02

E-78273-361-003-02

E-78273-361-003-02

E-78273-361"003-02

E-78273-361-003-02

E-78273-361-003-02

M-2105-1

l l-4919-1

M-7243-1

M-7243-1

M-7021-3

M-7021-4

M-8104-1

M-8104-1

M-8104-1

M-8104-1

SA516-GR70

SA533-GRB-CLl

SA533-GRB-CL1

SA533-GRB-CL1

SA533-GRB-CL1

SA533-GRB-CL1

SA533-GRB-CL1

SA533-GRB-CLl

SA533-GRB-CLl

SA533-GRB"CL1

Stay Cap

Support SkirtPrimary Manway Cover

Primary Manway Cover

Primary. Head

Primary Head

Primary Extension Ring




-40

+10

+10

+10

-10

-10

-20

-20

-20

-20

+3p(a)

+10(a)

+10(')+10(a)

-10(')0(a)

2p(a)

20(a)

2p(a)

2p(a)

(a) Determined per applicable ASME-BPV-Code Sect III Subsection NB, Article HB-2331-(a-l,2,3)

189A/js A-@P

TABLE 5.2.3-18'ALO

VERDE UNIT"l.


STEAM GENERATOR UNIT 82 (FORGINGS)

PieceNu4Dber

Reference~Drawia Na:

HaterialCode No:

246-101 E-78273-361-003-02 Yi-4701-2

248-201

252-101.

252-201

258" 101

258-301

258-301

258-202

258-402

258-402

E-78273-361-003-02

E-78273" 361-003-02

E-78273-361-003-02

E"78273"361-003-02:-'-78273-361-003-02-".

E-78273-361-003-02

E-78273-361-003-02

E-78273-36't-003-.02

E-78273-361-003-02

H-4710-2

M-7022-2

H-7023-2

M-7024-2

M-7025-3

Yi-7025-4

M-7026-2

M-7027-1

H-7027-4

248-101 E-78273-361-003-02 H-4706" 1

Yiaterial ~ ~

S ecification

SA508-CL2

SA508-CL2.

SA508"CL2

SA508-CL3

SA508-CL3

SA508-CL2

SA508-CL2

SA508-CL2

SA508-CL1

SA508-CLl

SA508-CLl

Location

Tube Sheet

Stay Stub

Stay Cap

Stay CylinderStay Ring

Inlet Nozzle

Out'1et Nozzle

Outlet Nozzle




Drop WeightNDT ( F

8 18D

-20 -20

+40 +40

-30 -30

+10 +10

-10 +10

-15 -15

-16 -16

"16 -16

"23 "23

-32 -32

"32 "32

0

„,(a)~40(a)

30(a)~ .+40(a)

+10(')-15(')-16(a)'16(a)

-23(')

-12(')

180

~40(a)

+40(a)

30(a)

40(a)

~1 0(a)

15(a)

-16(')16(a)

-23(')12(a)

12(a)

RTNDT ( F)

(a) Deterained per applicable ADHE-BPV Code 8 addenda, Sect III, Subsection NB, Article NB-2331-(a-l,2,3)

l

TABLE 5.2.3" 19

PALO VERDE UNIT"1

FRACTURE TOUGHNESS DATA FROM MELD HETAL CERTIFICATION TESTSe

STEAN GENERATOR 82


Seaa ¹ Seam Nomenclature Meld Filler Lot 8 . RTNPT ( F)

189A/js F

TABLE 5.2.3-20

PALO YERDE UNIT-1

FRACTURE TOUGHNESS DATA FROM WELD PROCEDURE QUALIFICATION TESTS

STEAM GENERATOR P2


Seculi Detailed MeldNuaber Seam Nomenclature Procedure ¹

Meld Procedure Meld FillerMaterial Lot 0

~NOT F NOTMaterials Joined HAZ HAZ Meld

Material 1 Material 2 1 2 ~F .

189A/js A-5&'ABLE5.2.3-21

PALO VERDE UNIT-I


REACTOR COOLANT PUHPS (FORGINGS)

(DATA TO BE SUBHITTED AT A LATER DATE)

PieceNumber

Reference~Drawia No:

Hateria'lCode No:


Drop Height~NDT F

0 180

RTNDT ( F)

-0 180

~ ~

~ ~ ~ ~

f,' ": T i' f) CI

y L f~ ) L!PP1 1: /f~A!)~ 1 ('';C >. f. 3': 1"g fi.-'.

"00

180

CijC.PO.Cij0

160C0CL'

CLCiJ

ILJ

140 8

000

RC)

tOKCL0>CCij

120

10G

EOC)

g

6G0

0LU

W

1

1

CG

20

CC0

CL

80

~ X~X~

I

p< ~a

ic

~ X0 7C

+1

0

-80/

-40 0 40 80 120 160 . 200 240

T Eilf'EfiATURK F

Lower Shell Plateimmaterial 'Code Ho: N-4311-1

I'AI 0 'I',= Pic .WU"Li.,R 0'i f.;:"". l i"4 . TAT T

Qt'ffAP,:1

1 -'n;-:Suf.VS

f l fiJ0:":, 5 . 2, 3- 1

"OG

i80R

A

i60

(L

Cf.4J

CJiCQ

C)

KCCoOCUJ

120

i QA

SG

X ~+o

o

0"

00

lACO

IQG

U

0[Uz 40IJj

20

0

-80 -40 0 40 80 120 '60 200 240

TL';ii'"RA~JRi'. F

Lover Shell PlateIiaterial Code Ilo: 14-4311-2

PRLO V. Ri)EilLJCLFHI". G;":l'I'= R'r1T, i<G STAT I '")is

UNI '

CIIAP.i" r i i Sl fk:":SALTS

5~32

~ ~

~ ~

~ ~ ~Q I'.

+

f' /I EIS-l fllf.IDEAL;:/l'fla",5I Ci~lCI. I: fI /fi('E

229

200

100

us )e

CC)LU

EJ)CO

00

0

lO

1 20ZO

KCC0

lOG

JCCCC

CE

X y, ~

W ~ y ~

0

0'.lsJi-'al CO

20

oI ~

-80 -40 0 40 '. So 120 200 24C

TI,"i'if'f,"llATUR:"; F

Lower. Shell Plate?material Code No: H-4311-3

PRLCi 'iERGEf3UCL AR DL":i'i'"i"'1' NG 5TnT I QN

U4! TCIIAfif'( 1":.ST RESULTS

5 I 2 3 3

4

~ v ~

~ II

~ ~

0 -- f: l /I PSw - L A 7 f' fiL;":Xf'P f ~i f 0 l f+ C I.. f'0 /l'f

f.'-f'+0

200

IRLIJC.>

W0

UJED0:C:LIj

LJ

1BO

160

1CO

Cl

VP

CC

120

100 KIL

0

lAC7

IGO

Wz 40la)

20

o

0 IL ~o ~

C ~,~

X

0

l~ '

-80 -40 0 40 80.

T:NPFRATURE F

120 160 200 2~1

Pi~I 0 Vt=RP.""llUCLERR C","'"..Pg) I >C STR

'fI1 7 Iimmaterial Code No; N-6701-1 „.. CflORf'( 'EST l',;5JL7

F .'1)1/h;.

~ .~

1

~~

++0

200

IRII/LJCt.4J0

4JCDCI:

CKILI

C>

180

160

1CO

tO

120' n

07

CC„0

10G

CCCrIIICC

OG

IC~ IC

COCC)

II" 60II.0 00 0

~ ~

~.' M

4JCO

UJ

20

0

-40 0

0

0

~W

40 80

~ ~

120

. K

200 24C

1F'1P; P,ATUR."" F

PP.LO V(,Pi!~t..Intez11>ediate Shell Plate I]!1pLEp~> p= 1;=p>g,"'T ~)II'. S ~

A!' Q~gHateria3.'ode No: i4-6701-2. - .'. c. f!!qI,py

I

F'lC(11'l" ~ ~ 2

."or,

'Oo

WtJWC

Ioo

CL

C4W

l EJ1CO

Rc5

V7KCC0

bi

l20

$ 00

WI

oo

I60

0

WCot LU

)C )C p:

0

0 0

0

D

~M

~t ~

gH

'0

I

l~

~

'

'80 -40 0 40 80 120 160 200 24t

TEt'IPERATURF. F

PRi g VER(.iL=.Intermediat:e Sh'ell I'3ate ',fU( LI=Rf> Q- J;= Rp f l f')j 5TH, T I Dl'f~,„, -, UNllMQeerLQ1 Code No: bl-6701-3' ' 'C~(Ar'PYJT~ti'1 Rl::"-Ut.T5

F I Cv'R".". 5, 2, 3-6

5.3 REACTOR VFSSEI

5.3.1 REACTOR VESSEL MATERIALS

5. 3.1.1 Material S ecifications

See CESSAR Section 5 ~ 3.1.1

5. 3. 1.4 S ecial Controls for Ferritic and Austenitic Stainless Steels

See CESSAR Secti on 5. 3. 1. 4

5.3.1.5 Fracture Tou hness

See CESSAR Section 5.3. 1.5

In Addition:

Data from fracture thoughness tests of base metal, weld metal and heat-affected-zone (lkAZ) material for Palo Verde Unit 1*are presented in tables5. 2. 3-1 through 5. 2. 3-4 of Section 5. 2. 3. 3. l.

Chemistry analyses for the Beltline plates and weld metal for Palo VerdeUnit 1 are presented in tables 5.3. 1-1 8 2 respectively.

~S'imilar data for Palo Verde Units 2 8 3 will be presented at a later date.

6

5.3.1.6 Reactor Vessel Material Surveillance Pro ram

Palo Verde Unit 1*

The surveillance program monitors the radiation induced

changes in the strength and toughness properties of thereactor vessel beltline materials. These changes are

determined by comparison'of pre- and post-irradiation testresults using uniaxial tension specimens, standard and

precracked Charpy impact specim'ens> and compact tensionpecimens.

This surveillance program was stablished using the

criteria presented in ASTM E185-79, "Standard Practice forConducting Surveillance Tests for Light-Hater Cooled

5:uclear Power Reactor Vessel". It also conforms to the

)equirements of 10 CFR Part 50< Appendix H (October 26>

1979) entitled "Reactor Vessel Material SurveillanceI'rogram Requirements"- The material toughness

requirements are determined in accordance with 10 CFR Part50, Appendix G and ASME Boiler and Pressure Vessel Code@

':ection III, Article NB2300.

5.3.1.6.1 Test Material Selection

'Jhree metallurgically different materials, representativeof the reactor vessel< are inv stigated. These are, base

metall'eld metall'nd heat:-affected-zone material. Base

metal specimens are fabricated from sections of two platesin the beltline region of the vessel which become the

limiting plates with respect to the operation during itslife time.

/'I

*(For Palo Verde Units 2 & 3 see CESSAR Section 5.3.1.6 ~ )

I 0

Bose metal test material is manufactured from two platesaelected from the reactor pressure vessel belt1ine.Selection was based on an evaluation of initial toughness

(characterized by the reference temperature, RT ), and

the pred'icted effect of chemical composition (residualcopper and phosphorus) and neutron fluence on thetoughness (RT shift) during reactor operation. A

NDTplate from the lower shell course had the highestpredicted RT shift. A plate from the intermediate

NDTshell (nozzle) course had the highest adjusted RTNDT

(initial RTNDT plus RTNDT shif').

Weld region test material is p':oduced by fielding togethersections of lower shell course plates from the beltline ofthe reactor vessel. The HAZ test material is manufactured

from a section of the same plate used for lower shellcourse base metal surveillance test material. The weld

metal test material is produced from the same heat of weld

wire or rod and lot of flux u ed in the beltline of the

reactor vessel. Welding parameters duplicate those used

for the beltline welds.

Representative stock (archive material) to provide two

additional sets of test specimens .for each material are

provided with full documentation and identification. Zn

addition, material is includec from a standard heat ofASTH A533-B Class l manganese-molybdenum-nickel steel made

available by the USNRC sponsored Heavy Section Steel

Technology (HSST) Program. This standard referencematerial (SRM) is used as a monitor for Charpy impact

tests, permitting comparisons among the irradiation data

, from operating power reactors and experimental reactors.Compilation of data generated from post-irradiation testsof these correlation monitors will be carried out by the

~ flSST program.

0

5 '.1.6.2 Test S ecimens

5.3.1.6.2.1 e and uantit

The total quantity of specimens furnished in this program

for baseline (unirradiated) and post-irradiation testingis presented in Table 5.3.1-3. The types of specimens are

drop weight, tension,'Charpy impact, and compact tensionfor baseline testing; and tension, Charpy impact, and

compact tension for post-irrad'tion testing.

5.3.1.6.2.2 The type and quantity of test specimens provided forestablishing the properties of the baseline (unirradiated)reactor vessel materials are presented in Table 5.3.1.4.~he data from tests of these specimens provide the basisfor detemining the radiation induced property changes ofthe reactor vessel materials.

Drop weight test specimens are provided to establish the

nil-ductility transition temperatures (T ) of theNDT

unirradiated lower shell course base metal (transverse,orientation), weld metal and EAZ material. Standard

Charpy impact test specimens f.'rom the lower and

intermediate shells are provided to establish the initialimpact energy transition curve and reference temperature

(RT ) of the base metals (longitudinal and transverseNDT

orientation), weld metal and HAZ material. Uniaxialtension test specimens are provided to define the initialstrength versus temperature relationship for the

~ surveillance materials. For intermediate shell course/

base metal, no drop weight or longitudinal tensionspecimens are provided. Reactor vessel materialqual ification test results will be used instead.Precracked Charpy impact and compact tension (lt and

0

1/2t) specimens

are provided tofrom the two base metals and weld metaldetermine the fracture toughness

properties over the range extending from linear elastic toelastic-plastic fracture.

5.3.1.6.2.3 Irradiated S ecimens

The type and quantity of test specimens for monitoring the

properties of the irradiated materials over the lifetimeof the reactor vessel are presented in Table 5.3.1-5.Charpy impact, precracked Charpy, 1/2t compact tension,and tension specimens are used to measure changes in thestrength and toughness of the surveillance materials.

Charpy impact test specimens are provided to establish the

impact energy transition curve after irradiation for the

two base metals {longitudinal and transverse orientation),weld metal and HAZ material. Tension test specimens areprovided to measure the strength and ductility of the two

base metals and weld metal following irradiation. The

precracked Charpy and compact tension specimens are

provided to measure the fracture toughness afterirradiation.

5.3.1.6.3 Surveillance Ca sules

The surveillance test specimens are placed in corrosionresistant capsule assemblies for protection from the

primary coolant during irradiation. The capsules alsoserve to physically locate the test specimens in selected

positions within the reactor vessel and to facilitate the

removal of a desired quantity of test specimens when a

specified radiation exposure has been attained. Sixsurveillance capsule assemblies are provided for the

4

reactor vessel. A summary of specimen type, origin, and

quantity contained 'in each capsule assembly is presented

in Table 5'3.'1-6 ~

A typical capsule assembly, il'ustrated in Figure 5.3-1,consists of a series of three specimen compartments<.

connected by wedge couplings, and a lock assembly. Each

compartment enclosure of the capsule assembly isinternally supported by the surveillance specimens and is

2externally pressure tested to 3125 lb/in during finalfabrication The wedge couplings also serve as end caps

for the specimen compartments which are housed within the

.capsule holders attached to th reactor cladding. The

lock assemblies fix the locations of the capsules withinthe holders by exerting axial forces on the wedge couplingassemblies which cause these assemblies to exerthorizontal forces against the sides of the holderspreventing relative motion. 'Ihe lock assemblies alsoserve as a point of attachment for the tooling used toremove the capsules from the

reactor'ach

capsule assembly consists of three compartments.

Each compartment consists of two sections attached by a

connecting spacer ~ Each capsule compartment section isassigned a unique identification so that a complete record .

of test specimen location within each compartment sectioncan be maintained.

Palo Verde Unit 1'ill have six surveillance capsules

including 2 precracked Charpy assemblies and one compact

tension assembly for lower shell specimens and 2

~ precracked Charpy assemblies and one compact tension

assembly for intermediate shell specimens. The types ofspecimens contained in each is given in Table 5.3.1-6. Inaddition, each of the six capsules contains one set ofnine flux monitorsi two sets of five flux monitorsi and

one set of temperature monitors.

,

'5.3.1.6.3.1 Precracked Char Ca sule Assembl

The four precracked Charpy capsule assemblies consist ofthree capsule compartments< two Charpy and Flux

Compartments and one Temperature, Flux, Tension and Charpy

Compartment. The contents of each compartment are

described below:

a ~ Charpy and Flux Compartment Assembly

This assembly (Figure 5.3-2) contains 15 base metal

(transverse) impact test specimens and a set of five

flux spectrum monitors in the top section. The

bottom section contains nine precracked Charpy testspecimens each of base metal (longitudinal and

transverse). The Charpy test specimens are arranged

vertically in 1 x 3 arrays and are oriented with the

notch toward the reactor core. The temperature

differential between the specimens and the reactor

coolant is minimized by using spacers between the

specimens and the compartment and by sealing both

sections of the assembly in an atmosphere of helium.

b. Temperature, Flux, Tension & Charpy Compartment

Assembly

This assembly (Figure 5.3-3) c'ontains three base

metal (transverse) tension te'st specimens and 12 HAZ

(heat-affected-zone) impact test specimens in the top

section. The tension specimens are placed in a

housing machined to fit the compartment. Splitspacers are placed around the gage length of the

specimens to minimize the temperature differentialbetween the specimen gage length and the coolant.

The impact specimens are arranged vertically in 1 x 3

arrays and are oriented with the notch toward the

reactor core. Spacers a> e utilized between the test

specimens and the compartment. The bottom section

contains a set of nine flux spectrum monitors> a set

of temperature monitors, 9 SRM (Standard Reference

Material) impact test specimens and 3 weld metal

tension test specimens- Both compartment sections

are sealed within an atmosphere of helium.

c» Charpy and Flux Compartment Assembly

This assembly (Figure 5 '-2) contains 15, weld metal

impact test specimens and a set of five flux spectrum

monitors in the top section. The bottom section

contains nine precracked weld metal and 9 base metal

(longitudinal) impact test specimens. The testspecimens are arranged vertically in 1 x 3 arrays and

are oriented with the notch toward the reactor core.

The temperature differential between the specimens

and the reactor coolant is minimized by using spacers

between the specimens and the compartment and by

sealing both sections of the assembly in an

atmosphere of helium.

5.3.1.6.3.2 Com act Tension Ca sule Assemblies

The two CT capsule assemblies consist of 3 capsule

compartmentsr two Charpy< Flux and Compact Tension

Compartments> and one Temperature, Flux, Tension, and

Charpy Compartment. The contents of each compartment are

described below:

a ~ Charpy, Flux & Compact Tension Compartment Assembly

This assembly (Figure 5.3-4) contains 15 base metal

(transverse) impact test specimens and a set of fiveflux spectrum monitors in the top section. The

bottom section contains 10 base metal (transverse)

1/2t compact tension tes': specimens. The 1/2t

compact tension specimen. are oriented so that

opening of the crack starter notch is facing the top

of the

compartment. This orientation will result in a

neutron flux gradient parallel to *the crack front.The temperature .differential between the specimens

and the reactor coolant is minimized by using spacers

between the specimens and the compartment and by

sealing both sections of the assembly in an

atmosphere of helium.

b. Temperature, Flux, Tension & Charpy Compartment

Assembly

This assembly (Figure 5.3-3) is the same as that inthe precracked Charpy capsule

c ~ Charpy, Flux 6 Compact Tension Compartment Assembly

This assembly (Figure 5.3-4) contains 15 weld metal

impact test specimens and a set of five flux monitors

in the top section. The bottom section contains 10

weld metal 1/2t compact tension test specimens. The

Charpy and compact tension specimens are arranged inthe same manner as in (a) and are surrounded by

spacers to minimize temperature differentials between

the specimens and ~ the reactor coolant.

5.3.1.6.4 Neutron Irradiation and Tem erature Ex osure

Predicted changes in the properties of the reactor vessel

materials are based on data from specimens irradiated to

various fluence levels and in different neutron energy

spectra. In order to permit accurate evaluations of the

radiation induced changes in the surveillance materials,

complete information on the neutron flux, neutron energy

spectra< and the irradiation temperature of the

encapsulated specimens must be available.

5.3.1.6.4.1 Flux Measurements

Past neutron flux measurements are obtained by insertionof thresholds d'etectors into each of the six irradiationcapsules. Such detectors are particularly suited for theproposed application, because their effective threshold

energies lie in the range of interest (0.5 to 15 MeV).

These neutron threshold detectors and the thermal neutron

detectorsI presented in Table 5 '.1-7, can be used tomonitor the thermal and fast neutron spectra incident on

the test specimens. These detectors possess reasonably

long half-lives and activation cross-sections covering thedesired neutron energy range- These neutron thresholddetectors exceed the number required in ASTM E482.

One set of nine flux spectrum monitors and two sets offive flux spectrum monitors are included in each

surveillance capsule- Each detector is placed inside a

sheath which identifies the material and facilitateshandling. Cadmium covers are used for those materials(e.g.< uranium, nickel, copper, and cobalt) which have

ompeting neutron capture activities. The neutron

threshold detectors are placed in holes drilled instainless steel housings (Figure 5.3-3) ~

Xn addition to these detectors, the program also includescorrelation monitors (Charpy impact tests specimens made

from a reference heat of ASTM A533 Bg Class 1> manganese-

molybdenum-nickel steel) which are irradiated along withthe specimens made from reactor vessel materials. The

changes in impact properties of the reference materialprovide a cross-check on the dosimetry in any given

surveillance program. These changes also provide data forcorrelating the results from this surveillance program

with the results from experimental irradiations and other

l

reactor surveillance programs using specimens of the same

reference material..

5.3.1.6.4.2 Tem erature Estimates

Because the changes in mechanical and impact properties ofirradiated specimens are highly dependent on the

irradiation temperature, it is necessary to have knowledge

of the specimen temperature as well as that of the

pressure vessel. During irradiation, instrumented

capsules are not practical for a surveillance program

. extending over the design lifetime of a power reactor.Thus, maximum temperature of the irradiated specimens can

be estimated with reasonable accuracy by including in thecapsule assemblies small pieces of low melting pointalloys or pure metals. The compositions of candidate

. materials with melting points in the operating range ofpower reactors are listed in Table 5.3.1-8. The monitors

are selected to bracket the operating temperature of the

reactor vessel.

The temperature monitors consist of a helix of low melting

alloy wire inside a sealed quartz tube. A stainless steelweight is provided to destroy the integrity of the wirewhen the melting point of the alloy is reached. The

compositions and therefore the melting temperatures of the

temperature monitors are differentiated by the physicallengths of the quartz tubes which contain the alloy wires.

A set of temperature monitors is included in each

surveillance capsule. The temperature monitors are placed

in holes drilled in stainless steel housings as shown inFigure 5.3-3.

-10-

5. 3. 1. 6. 5 Irradiation Locations

The test specimens are enclosed within six capsuleassemblies, the axial positions of which are bisected by

the midplane of the active core. The capsules are

positioned near the inside wall of the reactor vessel so

that the irradiation conditions (fluence, flux spectrum,

temperature), of the test specimens resemble as closely as

possible the irradiation conditions of the reactorvessel. The neutron fluence of the test specimens isexpected to be within 50% of that seen by the adjacentvessel wall, so the measured changes in properties of the

- surveillance materials will closely approximate the

radiation induced changes in the reactor vessel beltlinematerials.

".he capsule assemblies are placed in capsule holderspositioned circumferentially about the core at locationswhich include the regions of maximum flux. Figure 5.3-5presents the exposure locations for the capsule

,assemblies. All capsule assemblies are inserted intotheir respective capsule holders during the final reactorassembly operation.

5.3.1.6.6 Withdrawal Schedule

The capsule assemblies remain within their capsule holdersuntil the test specimens contained therein have been

exposed to predetermined levels of fast neutron fluence.At that time, the capsule assembly is removed and the

surveillance materials are evaluated. Detailedinstructions for the removal of capsule assemblies are

provided for each plant. The;capsule assembly removal

schedule is presented in Tabl» 5.3.1-9. Removal time isin terms of Effective Full Power Years {EFPY). The

I I

capsule withdrawal schedule has been designed toperiodically monitor the effects of neutron irradiation on

the reactor vessel based on the magnitude of the predicted

RT shift and the decrease in upper shelf energy.NDT

Sufficient standby capsules have been provided to enable

monitoring the effects of any major core change< measure

changes resulting from reactor vessel annealing or

evalu'ating a flaw in the beltline materials. Capsules 3<

5g and 6 are scheduled to meet 10CFR50, Appendix H,

monitoring requirements for weld and HAZ material; capsule

3 is scheduled for removal near 254 of design life or

approximately 50F shift (whichever comes first), capsule 6

near 75'5 of design life< and capsule 5 at an intermediate

time. = Capsules 3 and 5 will provide intermediate shellcourse plate data at 25% and 75% of design fluence for the

intermediate shell course. Capsules 1 and 6 will provide

lower shell course plate data at 30% and 75% of design

fluence for the lower shell course. The two remaining

capsules are designated as standby capsules.

Withdrawal schedules may be modified to coincide with

those refueling outages or plant shutdowns most closely

approaching the withdrawal schedule.

Xrradiation Effects on Prediction Basis

The design curve used to predict the radiation induced

increase in transition temperature is shown in Figure

5.3-6. Predicted changes in the transition temperature

are used to select the surveillance materials (Section'.3.1.6') and to formulate the initial heat-up and

cool-down limit curves for plant operation. Once actual

post-irradiation surveillance data becomes available, ~

these data will be used to adjust plant operating limitcurves.

-12-

Figure 5.3-6 was conservatively drawn using the data givenin Table 5.3.1-10 including SA 533-B Class 1 plate and

weld zone material typical of that used in the fabricationof the Palo Ver'de reactor vessel beltline materials. The

curve is applicable for materials with copper contents of0.10 w/o or less, consistent with Palo Verde beltlinematerial specifications, irradiated at 550F + 25F.

-13-

,109A/js C-1I

TABLE 5. 3. 1-1

PALO VEROE UNIT-1

REACTOR VESSEL BELTLIHE PLATES CHEMICAL ANALYSIS

HaterialCode

Element

Intermediate Shell Plates Louver Shel 1 Plates

M-6701-1 N-6701"2 t5-6701-3 H-4311-1 t1-4311-2 tl-4311-3

Si

Hi

Cr

*Ho

V

Cb

TiCo

Cu

Al

B

M

Sb

As

Sn

ZrPb

H2

0. 23 ~

1. 38

0. 005

0,018'.

24

0. 66

0 ~ 06

0. 52

0. 003

<. 01

<. 01

0. 015

0. 07

0. 032

<. 001

<. 01

0.0024

<.001

0.003

<. 001

<. 001

0. 009

0. 23

l. 34

0. 004

0. 017

0. 28

0. 61

0. 05

0. 53

0. 003

(. 01

<. 01

0. 013

0. 06

0. 035

<. 001

<. 01

0. 0016

<. 001

0. 003

<. 001

<. 001

0. 009

0. 23

l. 35

0. 004

0. 016

0. 28

0. 61

0. 05

0. 53

0. 003

<. Ol

(. 01

0. 013

0. 06

0. 037

<. 001

<. 01

0. 0015

<. 001

0. 003

<. 001

(. 001

0. 009

0. 24

l. 48

0. 004

0. 003

0. 22

0. 65

0. 07

0. 51

0. 003

<. 01

<. 01

0. 012

0. 04

0. 026

<. 001

<. 01

0. 014

0. 001

<.001

<.001

0. 014

0. 20

l. 45

0. 005

0. 007

0. 19

0. 62

0. 04

0,530. 001

<. 01

<. 01

0. 011

0. 03

0. 022

<. 001

<. Ol

0. 012

0.001

<.001

<.001

0. 013

0. 22

l. 46

0. 004

0. 005

0. 19

0. 64

0. 05

0. 53

0. 001

<. 01

(. 01

0. 011

0. 03

0. 022

<. 01

<. 01

0. 017

0. 002

<. 001

<. 001

0. 012

- 189A/js 0-

TABLE 5.3.1-

PALO VERDE UNIT-1

REACTOR VESSEL BELTLIHE MELO NETAI (AS OEPOSITEO) CHENICAI AHALYSIS

Seam

Element 141-142C 101-1428 101-142A

Lower Shell Lon . Seams

101-124C 101-1248 101-124A

Intermediate Shell Lon . Seams Girth Seam

Hn

Si

Hi

Cr

Vio'

Cb* ~*

Ti

Co

Cv

Al

As

Sn

ZrPb

Sb

H2

0. 15

l. 29

0. 005

0.006

0. 21

0. 05

0. 03

0. 53

0. 005

<. 01

<. 01

0. 015

0. 03

0. 005

<.001

0. 01

0. 004

0. 001

0. 001

<. 001

<. 001

0. 005

0. 15

l. 32

0. 005

0.006

0. 20

0. 05

0. 03

0. 52

. 0.005'.01

<. 01

0. 015

0. 03

0. 005

<. 001

0. 01

0. 004

0. 001

0. 001

<. 001

<.001

0.005

0. 15

1.36

0. 006

0.006

0. 21

0. 05

0. 03

0. 54

0. 006

<. 01

<.01

0. 016

0. 03

0. 007

<. 001

0. 02

0. 005

0. 00')

0. 001

<. 001

<. 001

0. 006

0. 13

l. 21

0.009

0.007

0. 12

0. 03

0. 02

0. 49

0. 004

<. 01

<. 01

0. 005

0. 02

0. 004

<.001'.

01

0. 007

0. 003

<. 001

0. 01

0. 14

1. 20

0. 01

0.008

0. 14

0. 03

0. 02

0.49

0. 005

<. 01

<. 01

0. 005

0. 02

0. 004

<.001

<. 01

0. 006

0. 002

<. 001

.006

0. 12

l. 24

0. 012

0. 009

0. 13

0. 03

0. 02

0.52

0. 006

<. 01

<. 01

0. 00o

0. 02

0. 004

<. 001

<. 01

0. 006

0. 003

<.001

0.008

0. 11

1. 51

0. 013

0. 009

0. 54

0. 11

0. 16

0. 52

0. 005

<. 01

<. 01

0. 008

0. 02

0. 01

0. 001

0. 01

0. 001

0. 003

<. 001

<. 001

0. 009

0. 013

TABLE 5.3.1-3

PALO VERDE UNIT 1TOTAL QUANTITY OF TEST SPECIM

Base Metal

Type ofS ecimen Orientation

Lower,Shell

Inter-mediateShell

WeldMetal HAZ SRM* Total

Drop Weight

Standard Charpy

Transverse

Lon yitudinalTransverse

12

4269

3663

12

'14

12

6996

36

'147342

Precracked Charpy LongitudinalTransverse

3030

3030 48

60108

ct Tension lt Transverse1/2t Transverse

8„14

814

824

2452

Tension LongitudinalTransverse

1221 18 30

1269

TOTAL 238 199 236 108 69 850,

*Standard Reference Material

L

'ABLE 5.3.1-4

PALO'VERDE UNIT 1TYPE 'AND 'QUANTITY OF 'SPECIMENS FOR 'BASELINE 'TESTS

Base Metal uantity

Type ofS ecimen

LowerOrientation 'hell

Inter-mediateShell

MeldMetal HM SRM" 'otal

Drop Weight

Standard Charpy

Transverse

LongitudinalTransverse

12

2424

18.18

12

1524 '4 57

90

12 36

Precracked Charpy

sion



1212

1212 12

12

2436

1233

Compact Tension lt Transverse1/2t Transverse

TOTALS

84

120 36 15

2412

324

*Standard Reference Material characterized by HSST Program; provided for correlationwith HSST characterization tests.

TABLE 5.3.1-5

PALO VERDE UNIT 1TYPE AND QUANTITY OF SPECIMENS FOR

IRRADIATION'EXPOSURE 'AND IRRADIATED TESTS

Base Metal uant ity

Type ofS ecimen Orientation

LowerShell

Inter-mediat»Shell

WeldMetal ER,Z SRE1* Total

Standard Charpy LongitudinalTransverse

1845

1845 90 72

54 90252

"..':Precracked Charpy LongitudinalTransverse

1818

1818 36

3672

Tension Transverse 18 36

t Compact Tension Transverse

TOTALS

10

118

10

118

20

72 54 526

*Standard Reference Material

l

.

TABLE 5.3.1-6

PALO VERDE UNIT 1 SURVEILLANCE PROGRAM

CAPSULEASSY. NO.

6TYPE

AZIMUTHALLOCATION

WITHDRAWALSCHEDULE

EFPY *LEAD

FACTOR

SURVEILLANCEMATERIAL

ORIGINS NO.

SPECIMENS

TYPE ORIENTATION

1Pcv

38 8-10 <l.15 1. Base MetalLower Shell PlateM-4311-1 «)

2. Weld Metal(M-4311-2/M-4311-3(c)Weld Wire:B-4 Heat/Lot 90071Flux Linde 0091/1054

3. HAZ MetalLower Shell PlateM-4311-1

4. SRM HSST Plate ul <-)fAK-

159939

315

12

9

Cv'Cv

PCvTension.C

Tension,Cv

PCv

Cv

Trans.Trans.Long'.Trans.Long.

Trans.Trans.

Trans.

Trans.

Lon

43 Standby <1.15 1. Base MetalInter. She)1 PlateM-6701-2(e

2. Weld Metal(b)M-4311-2/M-4311-3Weld Wire;B-4 Heat/Lot 90071Flux Linde 0091/1054

3. HAZ MetalLower Shell Plate M-4311-1(

4. SRM HSST Plate Ol (d)

1510

3

3

15

10

12

Cv4t CTTension.

Tension.Cv

4t CT

Cv

Cv

Trans.Trans.Trans.

Trans.Trans.

Trans.

Trans.

Lon .

*Effective Full Power Years

l

TABLE 5. 3.1-6 (Cont'd)


CAPSULEASSY. NO.

5TYPE

3

PCv

AZIMUTHALLOCATION

137'ITHDRAWALSCHEDULEEFPY

4-5

LEADFACTOR

<1'. 15

SURVEILLANCEMATERIAL

ORIGINS

1. Base MetalInter. Shell PlateM-6701-2 «)

NO.

15993

9

SPECIMENS

CvPCvPcvTensionCv

Trans.Trans.Long.Trans.Long.

TYPE ORIENTATION

4CT

142 Standby <1.15

2. Weld Metal (b)M-4311-2/M-4311-3(

~ - Weld Wire:B-4 Heat/Lot 90071Flux Linde 0091/1054

3. HAZ MetalLower Shell Plate M-4311-1 t

4. SRM HSST Plate Ol(

1. Base MetalLower Shell Plate

2. Weld Metal(M-4311-2/M-4311-3(c)Weld Wire:B-4 Heat/Lot 90071Flux Linde 0091/1054

3. 'AZ MetalLower Shell Plate M-4311-1(a)

4. SRM HSST Plate Ol(

3

15

12

1510

3'

15

10

12

TensionCv

Pcv

.Cv

Cv

Cv4t CTTension

TensionCv

St CT

Cv

Trans.Trans.

Trans.

Trans.

Lon

Trans.Trans.Trans.

Trans.Trans.

Trans.

Trans.

Lon

TABLE 5.3.1-6 (Cont'd)


CAPSULEASSY. NO.

&

TYPE

WITHDRAWALAZIMUTHAL SCHEDULELOCATION EFPY

LEADFACTOR

SURVEILLANCEMATERIAL.

ORIGINS NO.

SPECIMENS

TYPE ORIENTATION

5PCv

230 12-15 <1.15 1. Base MetalInter. Shell PlateM-6701-2 «)

159

3. 9

CvPcvPcvTension.Cv

Trans.Trans.Long.Trans~Lon .

2. Weld Metal(b"M-4311-2/M-4311-3(c)Weld Wire:B-4 Heat/Lot 90071Flux Linde 0091/1054

3

15

9 PCv

TensionCv

Trans.Trans.

Trans.

3. HAZ MetalLower Shell Plate M-4311-1

4. 'RM HSST 01( )

1212

9

CvCv

Trans'rans.

Long.

6Pcv'10 18-24 <l.15 1. Base Metal

Lower Shell PlateM-4311-1(

15993

9

CvPCvPcvTensionC

Trans.Trans.

, Long.Trans.Lon

2. Weld Metal(b)M„4311 2/M 4311 3(c}Weld Wire:B-4 Heat/Lot 90071Flux Linde 0091/1054

3. HAZ MetalLower Shell Plate M-4311-1( )

4. SRM HSST Plate 01( )

TensionCv

9 PCv

12 Cv

Cv

Trans.Trans.

Trans.

Trans.

Long.

0NOTES FOR TABLE 5.3.1-6

'(a) See Table 5.3.1-1 of this FSAR for chemistry of Plate Code

No. M-4311-1 flower shell plates);

~ (b) See Table 5.3.1-2 of this FSAR for chemistry of Plate Code

(c)

No. 101-142 A-C (lower shell long seams).

Surveillance weld metal between plates M-4311-2 6 M-4311-'3

(long seam) .

(d) See ORNL-4315 dated Feb. 1968, for chemistry of SRM

(HSST-Ol Plate).

(e) See Table 5.3.1-1 of this FSAR for chemistry of Plate Code

No. M-6701-2 (intermediate shell plate).

: TABLE 5. 3.1-7

PALO VERDE UNIT-1CANDIDATE*MATERIALS FOR >it:uiRO,~ THRESHOLD DETECTORS

Haterial

Uranium

Sul fur

Iron

t)ickel

'Copper

Titanium

Cobalt

Reaction

0 (n f) Cs1 37

S (n p) P

Fe (n,p) Hn54

Hi (n,P) Co

Cu (n,a) Co60

Ti (n,p) Sc

Co (n,y) Co

Threshold Energy (tleV)

0.7

2.9

4.0

5.0

7.0

8.0

Therm'al

Hal f-Life

30a2 years

14.3 days

314 days

71 days

5.3 years

84 days

5.3 years

1

TABLE 5.3.1-8

PALO VERDE lftfIT-1COHPOSIT) 0th RtfO t)EL fltfG POIt'fTS OF

CANDIDATE HRIEfllRLS FOR TEsii'EltATUf<E VOHXTORS

~ ~

Com osition (Mt%)

80 Au, 20 Sn

90.0 Pb, 5.0 Sn, 5.0 Ag

97.5 Pb, 2.5 Ag

97.5 Pb, 0.75 Sn, 1.75 Ag

Helting TemperatureoF

558

580

~ ~

I

TABLE 5.3.1-9

PALO VERDE UNIT 1CAPSULE ASSEMBLY REMOVAL SCHEDULE

CapsuleAzimuthalLocation

RemovalTime

Base MetalMaterial Included

38

43

137'42

230

310

8-10 EFPY

Standby4-5 EFPY

Standby

12-15 EFPY

18-24 EFPY

Looser Shell PCv

Lowe= Shell CT

Intermediate Shell PCv

Lour Shell PCv

In"ermediate Shell CT

Intermediate Shell PCv

Time in effective full power years (EFPY)

Note: Schedule may be modified to coincide with those refuelingoutages or scheduled shutdowns most closely approximatingthe withdrawal schedule.

TASLE 5.3.1".10~J'ALO

VERDE UNIT-1A5338"CU PLATE AND MELD MATERIAL MITH COPPER CONTENT LES& THAN OR E UAL TO 0.10 w/o

ReferenceData Point

7. 04

7. 05\ 801-8. 01

Material

SA5338-weld

SA5338-weld

SA5338-weld

SA5338-weld

2 ~ 3

2.7

2.0

2.3

Fl ~ence19(n/cm (10) )

.(a) 'b)dfs dfs

1.9

5.0

TransitionTemperature

Increase 'F

88

155

55'

Selectedp

. 020

. 020

.010

. 010

Chemistr

.004

.004

.008

. 008

w/oCv

.10

.05

.05

.05

9. 01

9. 02

9. 05

11. 06

11. 07

11.13

11.14'1.15

11.16- 1 l. 24

11. 25

11. 27

1 l. 28

23. 07

SA5338-plate

SA5338-plate .

SA5338-plate

SA5338-weld

SA5338-weld

SA533S-plate-

SA5338-plate

SA5338-plate

SA5338-plate

SA5338-plate

SA5338-plate

SA5338-plate

, SA5338-plate

SA5338-plate

2.8

2.8

3.1

.5

2.4

;2

2.0

2.0

.5

.5

.52.4.2.4

2.4

2.4

2.7

2.1

.17'2. 18

2. 18

.44

.44

2. 09

2. 09

3.8

40

65

70

80

80

90

35

30

95

35

.008

.008

.008

.005

. 005

.008

.008

.008

.008

. 008

. 008

.008

.008

. 009

.008

.008

.008

. 014

. 014

. 015

. 015

. 015

. 015

. 014

. 014

. 014

. 014

. 017

.03

.03-'. 03

.06

.06'. 09

.09

.09

.09

.09

.09

.09

.09

.09

a. fission spectrum .

b. calculated spectrum

I

TA8LE 5.3.1 "10 {CONT'D)

~ PALO VERDE UNIT"1A5338-CLl PLATE AND MELD MATERIAL WITH COPPER CDNI'ENT LESS'.THAN OR E UAL TO 0.10 w/o

.

Reference0=. a Point Material

Fl)encelg(n/cm (10) )(a) (b)

dfs 'fsTransitionTemperature

Increase 'FSelected

pChemistr w/o)

Cu

23. 08

23. 09

23. 10

23. 11

23. 19

23. 20

23. 21

23. 22

37. 01

37. 02.

49. 11

49.12

59. OI

60. 04

60. 06

60. 07

- SA5338-plate

SA5338-plate

SA5338-plate

SA5338-plate

SA5338-weld

SA5338-weld

SA5338-weld

SA5338-we 1 d

SA5338-weld

SA5338-plate

SA3028-weld

SA3028-weld

SA5338-plate

SA5338-plate

SA5338-plate

SA5338-weld

5.7

4.0

5.4

5.3

4.9

5.0'.9

5.0

2.5

2.5

2;3

6.1

5.0

3.5

4.7

4.6

4.2

4.3

4.2

4.3

.15

.'37

1.6

5.3

4.74.7

55

45

85

65

35

50

15

15

100

0

18

75

75

65

15

.009

.011.

. 011

. 009

'.010

. 010

.004

.004

.002 .

. 003

. 012

. 012

.008

. 010

.007

. 005

. 017

. 018

. 018

. 017

. 010

. 010

. 010

. 010

. 008

. 014

. 017

. 017

. 008

. 012

.011

. 010

.09

.09

.09

~ 02

.07

.07 .

-. G5

.05

.09

.G9

.01

'.Ol.03

.04

.05

.03

'REFERENCES FOR DATA POINTS IN TABLE 5.3.1-10

7. HSST Semi-Annual Progress Report Period Ending Feb. 29, 1972, ORNL-

4816.

8. Hawthorne, "Radiation Resistant Weld Metal for Fabricating A533-B

Nuclear Reactor Vessels", Welding Journal, July 1972, p. 360-S.

9. Hawthorne, "Demonstration of Improved Radiation EmbrittlementResistance of A533-B Steel Through Control of Selected Residual

Elements," NRL Report 7121, January 1970.

ll. Hawthorne, "Trends in Charpy-V Shelf Enc rgy Degradation and YieldStrength'ncrease of Neutron-Embrittled Pressure Vessel Steels", NRL

Report 7011, Dec. 22, 1969, and NRL Repcrt 6772.

23. Hawthorne, Koziol, "Evaluation of Commercial Production A533-B

Plates and Weld Deposits Tailored for Iriproved RadiationEmbrittlement Resistance," ASTM STP 570, 1975, pp. 83-102.

37. Steele, "Irradiation Effects on Reactor Structural Materials," NRL

Report 2027< August 1969.

49. Kass, "Radiation Effects in Boiling Water Reactor Pressure Vessel

Steels," NEDO-21708, October 1977.

59. Hawthorne, "Further Observations on A533-B Steel Plate Tailored forImproved Radiation Embrittlement Resistance," NRL Report 7917, Sept.

22'975.

60. Hawthorne, "NRC-CE-NRL Cooperative Program: Series 3 (Extra Lower

Copper) Materials Evaluations," NRL/NUREG MR 3512, May 1977.

~Lock Assembly

Charpy and FluxCompartment Assembly .

orCharpy, Flux, andCompact TensionCompa rtment Ass embly

M!edge Coupling Assembly

Cor necting Spacer

"Temperature, Flux,Tension and CharpyCompa rtment Ass embly

Charpy and FluxCompa rtment Ass embly

orCharpy, Flux, andCompact TensionCompa [%ment Ass embly

AR IZONAPUB L I C SE R V ICE CO.

Palo Verde StationUnit 1

SURVEILLANCE CAP S ULE ASSEMBLY

V/edge Coupling - End Cap

I

II

l

Charpy Impact.Specimens

Flux Monitor Housing

\

Precracked (:harpyandlor Charpy ImpactSpecimens

'

Connecting Spacer

Space rs

Rectangul ar Tubing

Wedge Coupling - End Cap

" ARIZONAPUBLlC SERVICE CO

Palo Verde StationUnit 1

CHAPiPY AND FLUX COMPARTMENT ASS EMBLYFigure

5. 3-2

" .'IIiedge Coupling = End Cep

Tension Specimens.and Tension SpecimenHousing

Cha rpy Impact Specimens

QonllectIng Spacer ——-

/Lid monitor i-lousIng ----

|

Stainless Steel---fubingTh reshold --.

Pe<ec<or

Ptqx Spectrum Monitor

Temperature Monitor ..

Temperature Monitor .

Hqgsing .

~ Flux Spectrum MonitorCadmium Shielded

Stainless Steel TubingCadmium ShieldThreshold Detector

Quartz Tubing

~Weight

Lomb Melting Alloy

Ch,argy Impact$ pqcimens

R;ton.g u I,'qr"Tu bi:ng--

o I

Tension Specimens andTens ion Speci.men

.H.ous.i.ng

Wedge Coupling-'EncL Cap

AR IZONAPUBLIC SERVICE QO.

Pj)q;Verde StjtjonLJnit 1

TEMPERATURE, Fl'UX'ENS'TON'AND CHA'RPY.CGMPARTM NT ASSEMBLY

'igure5 ~ 3 3

l

Vfedge Coupling — End Cap

I

I

I

III

I

Cha ryy ImpactSpec~ mens

I

Flux Monitor Housing~ -.I

1/2 t Compact TensionSpecimens

Connecting Spacer

'pacers

Rectangul ar Tubing

Wedge Coupling - End Cap

AR IZONAPUB LIC SERVICE CO.

Palo Verde Station,Unit 1

CHARPY FLUX AND COMPACT TENSIONCOMPA RTMENT AS S EMBLY

Figure

5.3-4

TJ

0(o>Cn o)>2.o. >~N~n Wp~R(Q~o>

. lTI

o Op

VESSEI137o

100

VESSEL' ~OUTI ET NOZZI E147o r

rVESSEL

Y ~ - . INLETr i NOZZLE

r

1 r COHL SI IPOUD

~ ——-CORE SUPPORT BARREL Ij

I

Z IC)

OZ

(/)VlmV3I

Vl

4l Q7Cn

~ nEACT<iR VESSEL

I1/

C

I I

/'I (I Il

0o

VESSEL„o

VESSEL

38'NLARGED

PLAN VIEW

VESSEL310o

CORE

REACTORVESSEL

ELEVATIONVIEW

VESSELCAPSULEASSEfilBLY

CORESUPPORTBARREL

J

200

0I- 150K

. K'D

h 100

z0I-cn '50

0

CD

o~0

QO

0

1018 10'gNEUTRON F LENCE, n/cni (E)1MeV)

1 020

D A533B-C1 1 PLATE

Q-tNELD METAL

NOTE: DATAPOINTS ARE DEFINED BY TABLE 5.3.1-10

AR IZONAPUBLIC SERVICE CO.

Palo Verde S:ationUnit 1

TRANSITION TEMPERATURE SHIFT FOR PLATE AND WELDMETALCONTAINING =.0.10 W/0 COPPER

Figure

5.3-6

l J

109A/gs"13

5.3.1.7 Reactor Vessel 8 Other RCPB Fastener

See CESSAR Section 5.3. 1.7

In addition:

Fracture toughness and Tensile test data for Reactor Vessel closure headbolting for Palo Verde Unit-1 is presented in table 5.3. 1.7-1.

Fracture toughness and Tensile test data for all other fasteners used inthe Reactor Coolant Pressure boundary for Palo Verde Unit-1 are presentedin tables 5.3.1.7-2 and 5.3.1.7-3.

Fracture toughness and Tensile Test data for RCPB 8 fasteners for PaloVerde Units 2 6 3 will be provided at a later date.

189A/js E-'

TABLE 5.3.1.7-1

PALO VERDE UNIT-1

FRACTiURE TOUGHNESS DATA

"REACTOR VESSEL FASTENERS

MaterialCode No:

M-6720-1

M-6720-1

Ye-6720-1

M-6720-1

Mi-6720-0

M-6720-1

M-6720-2

.Yi-6720-2

Yi-6720-2

M-6720-2

M-6720-2 .

e>i-6720-2

M-6720-2

M-6720-2

M-6720-2

M-6720-2

Yi-6720"3

M-6720-3

M-6720-3


SA540-GRB-24-CL3

SA540-GRB-24-CL3

SA540-GRB-24-CL3

SA540"GRB-24-CL3

SA540-GRB-24-CL3

SA540-GRB-24-CL3

SA540-GRB-24-CL3.

SA540-GRB-24-CL3

'A540-GRB-24-CL3

SA540-GRB-24-CL3

SA540-GRB-24-CL3

SA540-GRB-24"CL3

SA540-GRB-24-CL3

SA540-GRB-24-CL3

SA540-GRB-24-CL3

SA540-GRB-24-CL3

SA540-GRB-24-CL3

SA540-GRB-24"CL3

SA540-GRB-24-CL3

Location .

Closure Head Studs

Closure Head Studs

Closure Head Studs

Closure Head Studs

Closure Head Studs

Closure Head Studs

Closure Head Studs

Closure Head Studs

Closure Head Studs

Closure Head Studs

Closure Head Studs

Closure Head Studs

Closure Head Studs

Closure Head Studs

Closure Head Studs

Closure Head Studs

Closure Head Studs

Closure Head Studs

Closure Head Studs

Tube/BarNo:

479-00

479-01

482-00

482-01

485-00

485-01

462-00

462"ply463-00

463-01

470-00

470-01

472-00

472-01

475-00

475-01

623"00

623"OI

624"00

Pre-Load~Tem F

«lp(a)«10(a)

.lo(')+1O(a)

«1 p(a)

«lp(a)«Ip(a)+10(a)

10(a)

«10(a)

«10(a)

«10(a)

+lo(').lo(')«10(a)

+lo(')«10(a)

«10(a)

1p(a)

Yield~STR KSI

136. 2

'140. 0

140. 2

145. 0

144. 5

143. 0

133. 7

135. 5

142. 7

142. 2

145. 0

141. 2

141. 0

133. 2

141. 0

137.0

142.5

143. 5

135. 0

Ultimate~STRIKSI

- 154.0

157. 5

156. 5

160. 0

158. 5

158. 0

'I48. 0

151. 0

158. 5

157. 0

160. 0

156. 0

156. 0

149. 0

155. 0

152. 0

156. 0

157. 5

150. 0

7 C'

TABLE 5.3.1.7-1 (Cont'd.)

PALO VERDE UNIT-1


"REACTOR VESSEL FASTENERS (Cont'd.)

MaterialCode No:


Tube/BarNo:

Pre-Load~Tee F

Yield~STR KSI

Ultia'ate~STR KSI

M-6720-3

M-6720-3

M-6720-3

!

M-6720-4

M-6720-4

M-6720-4

M-6720-4

M-6720-4

M-6720-4e

M-6720-4

M-6720-4

MI-6720-4

H-6720-4M-6720-4

M-6720-41

M-6720-5

Mi-6720-5

M-6720-5

M-6720-5

SA540-GRB-24-CL3

SA540-GRB-24-CL3

SA540-GRB-24-CL3

SA540-GRB-24-CL3

SA540-GRB-24"CL3

SA540-GRB-24-CL3

SA540-GRB-24-CL3

SA540-GRB-24-CL3

SA540-GRB-24-CL3

SA540-GRB-24-CL3

SA540-GRB-24"CL3

SA540-GRB-24-CL3

SA540-GRB-24-CL3

SA540-GRB-24-CL3

SA540-GRB-24-CL3

SA540-GRB-24-CL3

SA540-GRB-24-CL3

SA540-GRB-24-CL3

SA540-GRB-24-CL3

Closure

Closure

Closure

Closure

Head Studs.

Head Studs

Head Studs

Head Studs

Closure Head Studs

Closure Head Studs

Closur'e Head Studs

Closure Head Studs

Closure Head Studs

Closure Head Studs

Closure Head Studs

Closure Head Studs

Closure Head Studs

Closure Head Studs

Closure Head Studs

Closure Head Studs

Closure Head Studs

Closure Head Studs

Closure Head Studs

624-01

628-00

628-01

633-00

633-01

635-00

635-01

639-00

639-01

643-00

643-01

649-00

649-01

650-00

650-01

556-00

556-01

557-00

557-01

10(a)

+1 0(a)

10(a)

+lp(a)+10(a)

10(a)

+10(a)

+1 p(a)

10(a)

+10(a)

+lp(a)lp(a)

+10(a)

+) 0(a)

+10(')+10(a)

+10(a)

.10(')

.10(')

137. 5

135. 3

139. 5

130. 0

137. 5

132. 0

132. 5

131. 5

134. 8

131. 3

131. 0

131. 5

132. 0

134. 2

133. 5

138. 3

136. 0

139. 7

152. 0

150. 0

155. 0

147. 0

154. 0

149. 0

149. 0

148. 0

150. 0

'48.0149. 0

149. 0

149. 0

150. 0

150. 0

'1 54. 0

153. 0

155. 0

140.0 ~ 156.0

C f

t

t

t

f

189A/js E-

TABLE 5.3.1.7-1 (Cont'd.)

PALO VERDE UNIT"1

FRACTORE TOVGHNESS DATA

"REACTOR VESSEL FASTENERS (Cont'd.)

HaterialCode No:

H-6721-1

M-6721-1

l"-6721'"1

14-6721-1

H-6721-1

H-6721-1

M-6721-1

Ys-6721-1

N-6721-1

H-6721-1


SA540-GRB-23-CL3

SAS40-GRB-23-CL3

SA540-GRB-23-CL3

SA540-GRB-23-CL3

SA540-GRB-23-CL3

SA540-GRB-23-CL3

SA54o-GRB-23" CL3 .

SA540-GRB"23-CL3

SA540-GRB-23-CL3

SA540-GRB-23-CL3

Location

Closure Head Nuts & Mashers










Tube/BarNo:

156-00

156-01

157-00

157-01

161-00

161-01

163-00

163-01

165-00

165-01

Pre-Load~Tee 'F

+lo(')+lo(')

10(a)

+1 0( a)

10(a)

+1 0(a)+.0(a)

+10(a)

+10(a)

+lo(')

Yield~STR Kc1

143. 0

146. 0

148. 0

147. 0

148. 0

145. 7

144. 5

148. 5

155. 5

154. 7

Ultimate~STR KST

156. 0

158. 5

160. 0

159. 5

160. 0

158. 0

157. 0

160.0.

167. 0

165. 5

(a) Determined per applicable ASIDE-BPV Code 8 Addenda, Sect III, Subsection NB, Article NB-2333-A (dia. over 4.0")Piece Numbers Reference Drawing

Studs Nuts Mashers ~ Number

179-'301 179-3401 179-3402 E-78173-161-004-02

C t

l

'89A/js E-

MaterialCode Ro:

ltateri alS ecification

TABLE 5.3.1.7-2

PALO VERDE. UNIT"1


Location

t PRESSURIZER", STEAM GENERATORS 1"" & 2""" MAHMAY

Tube/BarHo:

FASTENERS

Pre-Load~Tee F

Yield~STR KST

Ultimate~STR KST

HS-306-1

MS-306-1

MS-306-1

MS-314-1

Yi5-314-1

HS-314" 1

HS-314" 1

HS-314-1

MS-314-1

MS-314-1

HS"314-.1

YiS-314-1

MS-314-1

HS-314-1

MS-314-1

MS-314-1

MS-314-1

HS-314-1

HS-314-1

SA193"GRB7

SA193-GRB7

SA193-GRB7

SA540-GRB-24-CL3

SA540-GRB-24-CL3

SA540-GRB-24-CL3

SA540-GRB-24-CL3

SA540" GRB-24"CL3

SA540-GRB-24-CL3

SA540-GRB-24-CL3

SA540-GRB-24-CL3

SA540-GRB-24-CL3

SA540-GRB-24-CL3

SA540-GRB-24-CL3

SA540-GRB"24-CL3

SA540-GRB-24-CL3

SA540-GRB-24-CL3

SA540-GRB-24"CL3

SA540-GRB-24-CL3

Nuts 8 Mashers

Huts 8 Mashers

Nuts 5 Mashers

Studs

Studs

Studs

Studs

Studs

Studs

Studs

Studs

Studs

Studs

Studs

Studs

Studs

Studs

Studs

Studs

1A

18

lc

71-00

71-01

217-00

217" 01

237-00

237"01

43-00

43-01

70-00

70-01

69-00

69-01

204-00

204-01

208-00

40(b),4,(b)-.40(b)

lp(b)10(a)

+1 p(b)

+lp(b)lp(b)

+10(b)

lp(b)

+1 p(b)

+10("+10(b)

10(b)

+10(b)

+1 p(b)

10(b)

lp(b)lp(b)

128. 5

135. 0

128. 5

150. 0

149. 0

150. 7

148. 2

147. 2

150. 0

N/R

N/R

H/R

H/R

N/R

N/R

N/R

H/R

H/R/

143. 5

151. 0

145. 0

162. 5

162. 0

161. 0

159. 0

159. 0

162. 0

H/R

N/R

N/R

N/R

N/R

N/R

H/R

H/R

N/R

1

C

MaterialCode No:

MS-314-1

MI5-314-1

Mate~ialSDecification

SA540-GRB-24-CL3

SA540-GRB-24"CL3

Studs

Studs

LocationTube/Bar

No:

208-01

240-00

TABLE 5.3. 1.7-2 (Cont'd.)

PALO VERDE UHIT-1


f PRESSURIZER~, STEAM GENERATORS l~~ 8I 2"+" MAWAY

H/R

H/R

FASTENERS (Cont'd.)

Pre-Load Yie'ldT~ee 'I — ~STR KSI

10(b)

+10{')

Ultimate~STR KSI

H/R

H/R

""Steam Generator Ol

"""Steam Generator 82

(b) Determined per applicable ASME-BPV Code 8 Addenda, Sect III, Subsection NB, Article NB-2333-A {dia 1"-4" incl)Note: Since the same material lot was used for Pressurizer K| Steam Generators (Units 1 8 2) Primary Manways listed below

are the respective Piece Numbers 8 Reference Drawing Numbers.

. Piece Number Reference Drawing

Huts 8'shers Studs Number

"Pressurizer „ 676-3101 676-3301 E-78373-661-002"03

276-3901 = 276-3501 E-78273-261-003-03

276"3901 276-3501 E-78273-361-003-02

H/R Not required

189A/js E- "

TABLE 5.3.1.7"3

PALO VERDE UNIT-1


REACTOR COOLANT PUMPS (FASTENERS)

(DATA TO BE SUBMITTED AT A LATER DATE)

MaterialCode No:

MaterialLocation

Tube/BarNo.

Pre-Load~Tee eF

Yield~STR KSI

Ultimate~STR KSI

I

5.4. 2.4 Steam Generator fiaterials

See CESSAR Section 5.4.2.4

In addition:

Fracture toughness data for the primary side of Steam Generators Units 1 8

2 for Pa'lo Verde Unit-1 are presented in Section 5.2.3.3. 1.

Fracture toughness data for the Secondary Side of Steam Generators Units 1

8 2 for Palo Verde Unit-1 are presented in Tables 5.4.2.4-'1 through 9. (Tobe provided at a later date).

Similar data for Palo Verde Units 2 5. 3 will be provided at a later date.

189A/js B-~~

Seam ¹

'ABLE 5.4.2.4-3

FRACTURE TOUGHNESS DATA FROM WELD YiETAL CERTIFICATION TESTS

PALO VERDE UNIT-1

STEN< GENERATOR SECONDARY SIDE ¹1


Sean Ncmenclature Meld Filler Lot ¹ NDT < '>

189A/js A-

TABLE 5.4.2.4-2

FRAC1URE TOUGHNESS DATA

PALO VERDE UNIT-1

STEAM GENERATOR 8'1 SECONDARY SIDE (FORGINGS)


PieceNumber

Reference~0vawin 00:

Mater ial Materi alLocation

Dropweight RTNDT ( F)NDT oF

0 180 0 180

189A/js A-

TABLE 5.4.2.4-1


PALO VERDE UNIT-1

STEAM GENERATOR 81 SECONDARY SiDE (PLATES)


Piece .

Nu;..herReference

~Dvawin No:Material Material

Location

Drop~eight~NDT ( F

RTNDT { F)

I

189A/$ s F-Qr

TABLE 5.4.2.4-4

FRACTURE TOUGHNESS DATA FROM MELD PROCEDURE QUALIFICATIONTESTS

PALO VERDE UNIT"1

STEAM GENERATOR SECONDARY SIDE ¹1


SeanNu ober

Detailed Meld Meld Procedure~HDT oF "

NDT

Meld Filler Materials Joined HAZ HAZ WeldHaterial Lot ¹ Material 1 Hateria1 2 1 2 QFF

C

18SA/js H-

TABLE 5 ~ 4.2.4-5

PALO VERDE UNIT-1


STEAM GENERATOR 82 SECONDARY SIDE (PLATES)


PieceNua:her


MaterialCode No:


Drop Weight RT

~NDT F

189A/js H-

TABLE 5.402.4-6


PALO VERDE UNIT-1 =

STEAM GENERATOR 02 SECONDARY SIDE (FORGINGS)~t


PieceDu-,.bee

ReferenceD"oM1htM Nu:

Matei ial.Code No: .


Drop Weight: ~DDT F).' 180

RTNDT ( F)

0 100

L~

189A/js B- "'ABLE5.4:2.4-7

FRACTURE TOUGHNESS DATA FROM WELD METAI CERTIFICATION TESTS

PALO VERDE UNIT-1

STEAM GENERATOR SECONDARY SIDE 02


Seam 8 Seam Nomenclature Meld Filler Lot 0'TNPT ( F)

189A/js F-M

TABLE 5.4.2.4-8

FRACTURE TOUGHNESS DATA FROM MELD PROCEDURE QUALIFICATION TESTS

PALO VERDE UNIT"l

STEAM GENERATOR SECONDARY SIDE ¹2


~Ropy op RTgpySeam Detailed Meld Meld Procedure Weld Filler Materials Joined HAZ HAZ h'eld

iH-

fiK

H

I

i

t

1

189A/js E

TABLE 5.4.2.4-9

~ FRACTURE TOUGHNESS DATA

PALO VERDE UNIT-1

STEAN GENERATORS 1 Ec 2 SECONDARY SIDE FASTNERS


0

materialCode No:


Tube/BarRo:

Pre-Load Yield~Tem 'T ~STR KSI

Ultinate~STR KSI

t

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