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In Reply Refer To: $ ggDocket: 50-267
Public Service Company of ColoradoATTN: Robert 0. Williams, Jr.
Vice President, Nuclear Operations2420 W. 26th Avenue, Suite 15cDenver, Colorado 80211
Gentlemen:
- This letter documents a meeting held March 3,1988, in the NRC Region IV,
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office with you and members of your staff. An attendance list for the meetingis enclosed. The meeting addressed:'
'The interchanged Helium circulator speed cables and other maintenance-*
related concerns.
The leakage of Helium into the core support floor.*
The Helium circulator QA program quality levels.
We found the meeting to be beneficial. Enclosed are the handouts presented.
Sincerely,
/L. J. lan, Director
Divisi of Reactor Projects
Enclosures:As stated
cc:Fort St. Vrain Nuclear StationManager, Nuclear Production Division16805 WCR 191Platteville, Colorado 80651
Fort St. Vrain Nuclear StationP. Tomlinson, Manager, Quality
Assurance Division(sameaddress)
Colorado Radiation Control Program Director
Colorado Public Utilities Commission ,S
0-8803160049 880309PDR ADOCK 05000267 \bP DCD
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Public Service Companh of Colorado 2
DISTRIBUTION:
bec to DMB (IE01) - DRS & DRP
bec distrib by RIV:
*RRI R. D. Martin, RA*SectionChief(DRP/8) * Project Engineer, DRP/B*RPSB-DRSS Lisa Shea, RM/ALF*K. Heitner, NRR Project Manager *RIV File*R. Hall *DRS*DRP
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FORT ST. VRAIN
MANAGEMENT MEETING ATTENDEES
NRCTT F. Westerman NRC/RIV Chief, Reactor Projects Section DJ. P Jaudon NRC/RIV Deputy Director, DRSL. J. Callan NRC/RIV Director, DRPR. F. Farrell NRC/RIV Senior Resident InspectorR. P. Mullikin NRC/RIV Project Engineer
PSCRT 0. Ililliams, Jr. PSC VP Nuclear OperationsDon Warembourg PSC Manager, Nuclear EngineeringH. L. Brey PSC Manager, Nucl. Licensing and FuelRalph Sargent PSC Asst. to VP Nuc. Ops.P. F. Tomlinson PSC Manager,QA
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EVENTS
MISLANDED PPS LEAD (LER 87-029)*
TRIP OF RESERVE AUXILIARY TRANSFORMER (LER 87-028)*
EMERGENCY LIGHT!NG BATTERIES DAMAGE*
HOT REHEAT ROD RUNBACK*
MISLANDED CIRCULATOR SPEED CABLES (LER 88-002)*
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MISLANDED PPS LEAD
EVENT DESCRIPTION*
FIRE RECOVERY ACTIVITY*
ELECTRICIAN PLACED TERMINATIONS ON*
POINTS 46, 47, 48, AND 49, VERSUSPOINTS 46, 47, 48, AND 53
CAUSE DESCRIPTION - PERSONNEL ERROR=
ACTIONS TAKEN*
RELANDED LEAD*
SITUATION DISCUSSED, PERSONNEL ADMONISHED*
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A k
IC CS
115-22133 - Cit IS9-1 A--
~1~~C
120V AC
llSV-22133-1 IISV-22133-3 on Decent >ar i, 1981 falsowin9 wuskperformed ursde s Clea sege Notice
ICH-2iOI, ca ts le 78a8 7 was retssessed tosesvice. Dur Iseg t fie s c rosuecc t ionof t ieu ca ta le is 3 7 leads to HS isss
1-05, tisc grousul s et ess es wise for
A '"'""oids usv-22:33-1 asus1 F llSV-22833-3 was 8ssadvus te set a y
connected to time s eset c i s cosi t of_- -
183-53 ' sotay MCH-93159-A at IBS-8 9 Isistead4
g or ti e psoper location at ina-33.8 I ndepesidesat ve ri f ica t ioss failed to
183-49 XCR-93159-A 4 ISV DC ''"*"C' ""'"'5""''''*"*d '"*d-'
I tse application o f' I?OV AC t enXCH-9 31*>9- A damaged tino selay andcasssed it to cteat ter wficsi esic s g i zed
7 f' r om tlee ope r a t iosa of lea sed sw i t cle
HS-22133 "S-22si s . it 8 s clia t t e r a sus i ridi.ced~~
7{ g seoise into tise wide range clea nsee lneu t rena i Isex rate or cisange
115-2241 2-~ CS c i rcui t s and ps odi.ced t ris, scactorpg { sesam ac t esa t i ose s , lie f e r to
1EH 81-O?9.
7
Desi n ledd corinection.A. 9
t
| B. t1iswired lead connection.|
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ClitCullRY SillPLiflED FOR CLARITY .
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TRIP OF RESERVE AUXILIARY TRANSFORMER
EVENT DESCRIPTION*
POST MAINTENANCE TEST ACTIVITY*
TEST PROCEDURE PREPARED BY BACKUP SYSTEM ENGINEER*
RAT TRIP FUNCTION TO BE DISABLED FOR PURPOSE OF TEST*
FIELD WALKDOWN OF PMT RESULTED IN INCORRECT CHANGE TO*
PROCEDURE
FIELD ERROR FAILED TO DEFEAT RAT TRIP DURING TEST*
CAUSE DESCRIPTION*
PERSONNEL ERROR*
PROCEDURAL INADEQUACY*
ACTIONS TAKEN*
PROCEDURE CORRECTED*
ORIGINAL DESIGN FUNCTION OF EQUIPMENT VERIFIED*
IN-PLANT OPERATING EVENT REVIEW PERFORMED (OER 87-22)*
ADMINISTRATIVE PROCEDURE BEING REVISED TO INCORPORATE*
INDEPENDENT REVIEW FOR PMT DEVELOPMENT
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}|F400 *Pt1T Intended to .'
_ disable these contacts
2 RA-92201 2 86 RT86RTD--
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2C Iland Reset 2C ~ E1203 P30Helay
A_I~~
PilT disabledthese contacts Un.s is a portion of. .
2I,
drawing E-1011. It was on> this drawing that the 2-2c86RT 2C-- contacts of 86RT were
mistaken for the 2-2ccontacts of 86RTD.
_ Trip
f401 IS2RT2E-10ll
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* PMI - Post Maintenance Test
Prior to reac t o r startup, a Post Maintenance Test was to be performed on fi rewater deluge control relay CR-4505.Thi s relay initiates numerous actions including local and remoto a larms, fi rewa ter pump starts, and firewater systemvalve closures. CR-4505 was disassembled and cleaned following the inadvertent RAT deluge actuation that occurredon October 30, 198 T . following these maintenance activities, Post Maintenance Testing (f*MI) was required. The test.plan was to actuate the RAT deluge system and CR-4505, via HS-4516 and verify completion or the various automaticactions that are initiated by CR-8 505. Actuation of the RAI deluge system automatical y opens the RAI reedb realte rs;4
this automatic RAT trip runction was to be disabled. To accomplish this, without disabling other functions, one orthe leads on the 2-2C contact or XRA-92201 (86HID) was to be lifted. Af ter a field walkdown it was discovered thatdue to its physical l oca t i s,n, XRA-92201 was relatively inaccessible; to remove its housing cover as to allow thedisconnection of the 2-2C contact leads would require a substantial amount o f- time. Plant electrical d rawings werereferenced. On [-1011, the 2-2C contacts or 86RI (see Iigure 2) were mistaken for the 2-2C contact of 86 RID. Thiserror railed to prevent the automatic opening of the RAI feedbreakers during the test as intended.
CIRCUITRY SIMPLif110 f0R CLARIlY
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EMERGENCY LIGHTING BATTERIES DAMAGE
EVENT DESCRIPTION*
VENDOR INSTALLATION PRECAUTION NOT INCORPORATED INTO*
FIELD INSTALLATION INSTRUCTIONS
INSTALLATION RESULTED IN DAMAGE TO BATTERIES*
PROBLEM DISCOVERED DURING PRE-OPERATIONAL TESTING*
CAUSE DESCRIPTION - PROCEDURAL INADEQUACY*
ACTIONS TAKEN*
NEW BATTERIES OBTAINED AND INSTALLED CORRECTLY*
(IN PROGRESS)
THE DESIGN CHANGE PROCESS IS BEING CHANGED WITH ONE OF THE*
OBJECTIVES BEING IMPROVING WORK PACKAGES
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Charger - - -
277V AC Inverter '- - - --
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T- T- T-- .
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12 V Battery-
Signal Ground_
O DC Current Ilow
The charger inverter supply was turned off with the batteries connected. This allowed the batteriesto completely discharge. When the switch was turned on, high current for charging boiled the electrolyteand ruined the batteries.
CIRCUITRY SlHPLIflED FOR CLARITY
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HOT REHEAT ROD RUNBACK
EVENT DESCRIPTION*
TROUBLESHOOTING EFFORT FOR CORRECTIVE MAINTENANCE*
UNDERWAY
SYSTEM WAS RECONFIGURED FOR PRIMARY EFFECTS WITHOUT*
ADEOUATE CONSIDERATION OF SECONDARY EFFECTS
MAINTENANCE ACTIVITY INTRODUCED UNANTICIPATED SECONDARY*
CIRCUIT RESPONSE
CAUSE DESCRIPTION*
PROCEDURAL INADEQUACY*
ADMINISTRATIVE CONTROLS*
ACTIONS TAKEN*
OPERATOR RESPONSE MINIMlZED EFFECT OF TRANSIENT*
SECONDARY CIRCUIT AND OTHER CONTROLS WERE CONFIGURED TO*
MAINTAIN PARAMETERS
CONTROLS RECAllBRATED AS INTENDED*
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Reheat -
SteamTemperature - !
1002 i fol' ; |11-22237 3 gp p fM-22237-1
$""a
l P2 & % TCw mFW Flow " ToTM-2256-8 2256
"
Fluxm100a y r Controller
-3
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fli-22237-3p
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> DC Current flow
p instrunent Plug
Leads disconnected by Instronera Tech.
Results: When the leads to IM-22237-3 were disconnected the current (ma) output of Itt-22237went to zero.
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The loss of input to IM-2256-8 feeds through to the setpoint of TC-2256 and theflox controller as an error. The magnitude was sufficient to cause a rod runback.
CIRCulTRY SIMPLIFIED FOR CLARITY
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MISLANDED CIRCULATOR SPEED CABLES
EVENT DESCRIPTION*
PLANT PERFORMANCE TESTING IDENTIFIED POTENTIAL PROBLEM*
CORRECTIVE MAINTENANCE ACTIVITY UNDERTAKEN*
INCORRECT CABLE FROM 'B' CIRCULATOR ATTACHED TO*
'A' CIRCULATOR CONTROLS
PLANT TRANSIENT RESULTED FROM 'A' CIRCULATOR CONTROLS*
RESPONDING TO 'B' CIRCULATOR PROCESS INPUTS
CAUSE DESCRIPTION*
PERSONNEL ERROR*
PROCEDURALINADEQUACY*
ACTIONS TAKEN*
ALL SPEED CABLES COLOR CODED FOR CORRESPONDING*
CIRCULATORS
CABLE NUMBERS 'AND LOCATIONS VERIFIED TO DESIGN DO( JMENTS,*
| NO OTHER DEFICIENCES FOUND
PLANT PERFORMANCE TEST SURVEILLANCE WAS REVISED+
TO DOCUMENT CABLE CHANGES AND PROVIDE FOR INDEPENDENTREVIEW OF SURVEILLANCE DRIVEN ACTIVITIES
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LOOP I Circulator Speed Set Point. " I
r
sn-
2105 "
> 11 I SC
, 2105SEL
v
Sn +."
21091A SpeedControl Valve:
1 P
To IB llelium CirculatorSC-2111
2 A Circulator Speed Control,-------------. ----------------------------------- -------_____
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A. lA lleltwo Circulater measured signal.
B. 18 llelium Circulator speed cable improperly connected to IA llelium Circulator.
RESULT: When B llelium Circulator speed exceeds A IIelium Circulator speed and isabove the speed set point.
1. lA IIelium Circulator speed controller starts closing the speedvalve which decreases IA IIelium Circulator speed. This processrepeats until 1A Circulator trips on progranuned speed low.
NOTE: CIRCUITRY SI!1PLIFIED FOR CLARITY.
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MANAGEMENT ASSESSMENT ANALYSIS
COMMON CONDITIONS
PERSONNEL - ERROR*
PROCEDURAL INADEQUACY*
VARI ABLE CONDITIONS
PLANT STATUS*
PERSONNEL INVOLVED*
WORK ACTIVITY IN PROGRESS*
MAINTENANCE
MODIFICATION
TESTING
PERFORMANCE MONITORING
CONCLUSION
ROOT CAUSE*
MIXED SIGNALS TO PERFORMANCE LEVEL PERSONNEL
CONTRIBUTING FACTORS*
OPERATIONAL FACTORS
!_ QUALIFIED PEOPLE NEW TO FORT ST. VRAINi'
NEW PR* GRAMS / PROCEDURESl
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ROOT CAUSE - ISSUE SPECIFIC
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ACTIONS TAKEN
ISSUE- PRESENTED TO If,C TECHNICI ANS AND PLANT ELECTRICI ANS*
MANAGEMENT EXPECTATIONS CLARIFIED , "ZERO DEFECTS"*
USER DEVELOPED "LIFTED LEADS" POLICY DRAFTED*
"LIFTED LEADS" POLICY UNDER MANAGEMENT REVIEW+
PMT CONTROLS REVISED TO INCORPORATE INDEPENDENT REVIEW*
PMT PROGRAM UNDER REVIEW*
FUTURE ACTIONS
PRESENT ISSUE AND MANAGEMENT EXPECTATIONS TO REMAINING*
STAFF
FORMALIZE AND ISSUE ADMINISTRATIVE PROCEDURES FOR*
LIFTED LEADS
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ROOT CAUSE - ORGANIZATIONAL SOLUTION
ENHANCE'THE COMMUNICATIONS OF MANAGEMENT EXPECTATIONS*
ENCOURAGE AN ATMOSPHERE WHICH PROMOTES CONSISTENCY AND*
FEEDBACK
IMPROVE THE MONITORING OF NEW PROGRAMS AND ADJUST AS*
NECESSARY .
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PLAN FOR IMPLEMENTATION OF ORGANIZATIONAL SOLUTION
PROMOTE TOP LEVEL STATEMENT OF WORK:*
"THE NUCLEAR OPERATIONS ORGANIZATION SHALL USE ITS BESTJUDGEMENT, SKILL AND CARE IN ALL MATTERS PERTAINING TO ITSPERFORMANCE, AND SHALL USE GOOD BUSINESS PRACTICES INOPERATING AND MAINTAINING THE FORT ST. VRAIN NUCLEARFACILITY TO COMBINE EFFICIENCY WITH SAFETY, QUALITY,SECURITY AND PLANT RELI ABILITY."
CLARIFY MANAGEMENT EXPECTATIONS TO ALL NUCLEAR ORGANIZATION*
PERSONNEL WITH THE FOLLOWING PRIORITY:
FIRST - SAFE OPERATIONSECOND - QUALITY OF WORKTHIRD - FINANCIAL
CONTINUE ISSUE SPECIFIC PERFORMANCE LEVEL DISCUSSIONS*
IMPROVE UTILIZATION OF FEEDBACK TO IMPLEMENT SPECIFIC SOLUTIONS*
CONTINUE TO FOCUS RESOURCES TO RESOLVE ISSUES*
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WATER SEAL REVERSETHRUST
COMPRESSOR SHUT DOWN BRAKE BEARING TURBINESEAL c' O /
COMPRESSOR ) [ M -TURBINE\ -
STATORSTATOR .,
u. - p ,' "
~THRUST'BEARING.
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_
[ {{ ~_I t ' PELTON|
WHEEL'
\, _
7-
-l 1smsms '' s'
' STEAM'e
rii, 'lT % f - $ -
- / LABYRINTH;
,' j,
h SEAL'
g q- _ -
/ JOURNALJOURNAL INSULATION '
INSULATIONBEARING
BEARING WATER c
INLET CHECK {$-VALVE gg
S ?"E
Figure 4.2-1 IIelium Circulator Assembly
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GA'S GRADED QUALITY ASSURANCE PROGRAM:
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! QAL i SAFETY-RELATEDi
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QAL 11 NONSAFETY-RELATEDi
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QAL iII NONCRITICAL APPLICATIONS
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PROBLEM IDENTIFICATION|i
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PSC QA AUDIT OF GA'S PROGRAM CONDUCTED WEEK OF JANUARY 11, 1988
PSC IDENTIFIED filAT A CIRC PELTON WilEEL llAD BEEN PROCURED TO QAL 11
PSC'S P.O.'S TYPICALLY REQUIRED GA TO WORK OR SUPPLY PARTS INACCORDANCE WIIll GA' S QA MANUAL WITil Tile INTENT TilAT GA APPLY
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APPROPRIATE QAL LEVEL REQUlREMENTS FOR SAFETY RELATEDCOMPONENTS (10CFR50 APP B)
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ROOT CAUSE
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PSC'S PROCUREMENT SYSTEM DID NOT RECOGNIZE GA'S GRADEDPROCUREMENT SYSTEM
GA INAPPROPRI ATELY PROCURED TiiE PELTUN WilEEL TO A QAL LEVEL lIREQUIREMENT
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DN T
OA I
TR NR O TY
E NTN N I
O T G EEA A E MFD I
E T N T P EARSUA III
F C M O P UR CRCI l
T f E C L OOSRFPRO Ii I
A PN T E I
YO D C T I
N N A BR G D GLl
l
N N /EDU S i
A CVEET I' l
N A WM M SEVPLOON O G )I
RNT C 1I I
t LPS T f 0 P 0 l
OAPs UN o A O 1l
fl 2 FQAlO Ii
W V R Ai R -l
I
T E R UT O C STETASC R D N I F (
T NA O II
T E D SA S C ETWMNRtE C L N T f
FEET E B A D1 R 1
E2 A C MltA P I l l
S S V R P EllI
EI R UROD N S I
O DR f O QUE I
ECSA OM P N I I
M T O SP tOSI
RENN A I III
PLE G Ol Y N Nl .
D f E CE T E E O NAUM MO R D .lI
S EN l E E PGR R SE V D EU i
R E T B U U MENROTE A C CN II
L 0 0 RIl IE O F Il
MB E EUT1 1T I 1
1 I
QAMA P P PG I1I
S E 0 Ol O NECRIR N CR E EI I
V VN LD O I
E DYPE D N 1 P N I I
M LPE R 2E A I Il l
U R L C Ci LAt l
fV l i
P A AS SAf T il I
DtT 1 I Il i l
oN T N AO S W WB LTEt lPN S E Ei NTNO O I l
U AEAN E I II
CG C CS S V VF ISLSE A S SA S E EE SSEPR G P PW A R R1 EER1
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PARTS IN REACTOR
PSC llAS SELECTED 3 MAJOR COMPONENTS FOR SAFETY FUNCIlc.4 -
'REVIEW (CIRCULATOR, CONTROL ROD DRIVES, MOISTURE MONITORS)
lilE LICENSING BASIS FOR lilE COMPONENTS WAS REVIEWED. A LISTOf IllE SAFETY FUNCTIONS WAS GENERAT ED
AN ENGINEERING EVALUATION WAS PERFORMED TO VERIFYOPERABILITY. FINAL DOCUMENTATION OF Tills REVIEW IS IN PROCESS
OPERABILITY REVIEW RESULTS.
- ALL SAFETY FUNCil0NS ARE VERIFIED OR TilElR PURCilASE WAS QAL I !
- SAFETY FUNCTION IS DEMONSTRATED VIA NORMAL OPERATION,SURVEILLANCES AND SPECIAL TESTS
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COMPLETEDFOLLOW-UP ACTIONS
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ON FEBRUARY 10, 1988, A JolNT PSC, GA, NRC REGION IV MEETINGWAS HELD IN SAN DIEGO TO DISCUSS ISSUES AND ACTION PLANS
PSC QA COMPLETED A REVIEW OF ALL APPROVED VENDORS TO ENSURESIMILAR PROBLEMS DO NOT EXIST WITH OTHER VENDORS
EQUIPMENT SAFETY FUNCTION ANALYSES COMPLETED
PSC QA COMPLETED AN AUDIT OF CLOSED GA PO'S TO ASSESSOVERALL PROGRAM COMPLIANCE
COMPLETED QAL LEVEL CLASSIFICATION OF CIRCULATOR PARTSFOR UPCOMING OUTAGE
IDENTIFIED CLOSED GA PURCilASE ORDERS AND CATEGORIZEDTHESE ORDERS TO IDENTIFY QAL LEVEL ISSUES
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ON G0 LNG ACTION
PSC ENGINEEltlNG FINALIZING DOCUMENTATION (ENGINEERING EVALUATIONS) ,
IN SUPPORT Of PLANT OPERATIONS
PSC/GA COMPLETING REVIEW Of SELECTED MAJOR PROCUREMENT PACKAGESi
TO RESOLVE ANY QAL 1EVEL ISSUES
, CONTROL ROD DRIVE REFURBISilMENT - 70% COMPLETE| MOISIURE MONITORS - 80% COMPLETE! CIRCULA10R C-2101 - 10% COMPLETE1
CI RCULATOR C-21till - 10% COMI'LE I E
PSC ENGINEERING DOCUMEN1ING flNAL RESOLUTION of ISSUES IN AN ENGINEERINGEVALUATION OR SERIES Of EVALUATIONS'
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PSC ENGINEERING / LICENSING TO PROVIDE FINAL RESOLUTION Of ISSUES 10'
Tile NRC. TARGElED IOR APRIL 1988
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FORT SAINT VRAIN STATION
CORESUPPORTFLOOR
I PHYSICALORIENTATION
II HISTORICALREVIEW
o COOLINGTIEELEAKS
o LINERLEAK
III EVALUATIONSANDCORRECTIVEACTION
o CSFTlBES,EP0XY
PHYSICAL
ADMIN,
o CSFLINER
PHYSICAL
ADMIN,
; o PASSIVEVENTSYSTH1
o OTER STUDIES
IV ACTIONSINPROGRESS
o B0NITORING/ TRENDING
o SAFETY RELIEF VALVE ITDIFICATI&G
| V SA E1Y IPPLICATIONS
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PENETRATIONS
HELluM ~
[ 'O - PCRVPURIFICATION
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~- ORIFICETOP REFLECTOR % ~
N P f |g ) : % VALVESTHERMAL % - I | w-
BARRIER~
j 1 yl. j|4 N
,"TOP KEY REFLECTOR
: M ?- ELEMENTSCONTROL ROO ------
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Ju i ' S10E REFLECTORphgdi, d'-~
7{1--- ; mt-
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% 'BOTTOM
3 | | ' CORE1
REFLECTOR %'N fl - N* - CORE BARREL KEY{! I 4 i |J
CORE SUPPORT'
s |W,n M~.#S
8 LOCKS ' * *)
CORE SUPPORTPOSTS -
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SUPPORT FLOOR- J | / ^OU E
FLOOR COLUMN'_fi . CIRCULATORCORE SUPPORT
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7 hiFFUSERS (4),
1- m /v v Q! ' - HELIUM
| V / VALVE"
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w |/J ~-e O h CIRCULATORS (4)
'h| '5 .
i %g 'PCRV LINER '-t - LOWER FLOOR| i %:.! S FLEXIBLE COLUMNS! ' -
ry. .
E 80TTOM HEAD- " '' r".I PENETRATIONS,
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l]"- SEE DE Tall A"'t>
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! I.ICLASS n- U SEE DETAIL B "";> gc' ' " TilERMAl DARR!ER(REF) g'
COVER PLATE CORE BARRELDENSE CAST SILICA 50 LB
: SILICA FOAM . * lY. IN. THICK DUCT INLET FAlHING (REF),
3 IN. TillCK 3 IN. THICK (~ ' [~" DENSE CAST SILICA
| TOP OF COREg (
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} %CORE, ..
- b:k . ;W) i OUTLET * lip,,,f ,
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figure 5.9-4 Class "C" Core Support floor Upper SurfaceThermal Barrier Arrangement
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FIGURE 3 !10NITORED COOLING TUBE ARRANGEMENT
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HISTORICALREVIEW
KEY EVENTS
o 191 DURING PLANT CONSTRUCTION TE CSF WAS
INAINERTENTLY/0VER PRESSURIZED DURING A VENT
SYSTEM PESSURE TEST
o FEB 1972 FOUR (4) LEAKING CSF SIDEWALL TUBES IDENTIFIED
o INITIAL REPAIR ATTEWT UTILIZING A BENA00A, BENTONITE
CLAY SLURRY WAS UNSUCCESSFUL. DlE TO APPLICATION
PESSUES C00 LIFE TUBE LEAK RATE INCREASED
o EP0XY EPAIR SYSTEM WAS DEWLOPED AND IN FEB 1973
TE FOUR (4) CSF SlfBALL TUBES WERE SUCESSFULLY
REPAIED
|
| o ADMINISTPATIVE CONTROLS ESTABLIS D TO ISOLATE CSF
SIDEWALL TUBES AT OR BELOW 150 PSIG EACTOR PESSURE
o APRIL 1%2 ANOTER LEAKlf0 CSF 1UBE IDEt61FIED
TOP EAD TUBE (F4T21)
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EY EVENTS (C0f6'D)
o CSF COOLING 1UBE F4T21 WAS PSTMD FRm SERVIE
.n CAPPED EXTERML TO TE PCfN
o SEPT,1982 SIGNIFICNE CSF M GAS FLOW NOTED
FOLLOWING A REACTOR SCPM Ff0M 70% P06
o TWO (2) 0F TE ORIGIMLLY EP0XY REPAIRED CSF
SIDEWALL TUBES ERE IDENTIFIED AS LEAKING
o INSTAllID A LMIMR FtDW ElRM IN THE CSF
W SYSTEM TO EINIT FLOW DETEfEINATION
NNITORING #01 REM) LNG (DEC 1982)
o CMPACTERIZED CSF LIER LIAK BASED ON PRIMRY
C00lMT C00lT10NS,
!
CSF EALING
1HESH0LD - 500 - 550 PSIA EACTOR PESSUE
- 6000F - 800E PRIMARY C00lMT TDP
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-
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.
. -. . . .
HISTORICAL REVIEW
KEY EWNTS
o FORED WO (2) SPECIAL C0ft11 TEES TO C00RDitMTE
CSF ACTIVITIES
MANArB E R OVERVIEW GROUP
WORKitE CatilTTEE
o Rf1CT10N
C000CT SRlDIES, EVALUAT10t6, AteLYSES TO
CHARACTERIZE LIER LEAK, IDENTIFY POSSIBLE
FLOW PATHS, LOCATE CSF C00 LINS TUBE LEAKS,
DEERMIE CSF STRUCTURAL IIREGRITY, DEFINE
POSSIBLECORRECTIVEACTIONS
|
I
| o STUDIES NO EVALUATIONS #0 Pl#6 TESTitE'
C0f61NUED THROUGHOUT 1983 # 0 1984 INVOLVltE
PSC, PROTO-POWER #0 GA TECHt0LOGIES, AS
lELL AS SEVERAL HIGH TECH RESEARCH GROUPS
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HISTORICAL RElls
EY EWNTS (CONT'D)
o EARLY 1984 - SUCESSR1LY REPAIREI) TE NO (2)
RECURRING CSF SIDEWALL TUBE LEA}G
o SPRING 191 - IDENTIFIED #0TER CSF TE EAD
COOLING TUE LEAK (FST13)
o TlilS TUE AS VALVED OUT E SEPNIE Af0 REMINS
OUT OF ERVIE AT TE PESENT TIE
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EVAulATIONS/CORECTIVE ACTIONS
o FOUR (4) LEAKING CSF SIDEWA3. TUBES EPAIED WITH EP0XY
o TWO (2) ECURRING CSF SIDEWALL TUBES EPAIED WITH EP0XY
o TWO (2) CSF TOP E AD TUBES OlH OF SERVICE
o C0ffTINUE T0 ISOLATE TE FOUR (4) CSF SIDEWALL TUBES AT
REACTOR PESSUE AT OR BELOW 150 PSIG
o ADMINISTRATIW/0ERATOR ACTION TO MINIMlZE CSF LINER
LEAKAGE WHEN NOT IN OPERATION BY CONTROLLING CSF EACK
PESSURE BETWEEN 60 PSIG NO 95 PSIG
|
o 00fRETED A filLTITUDE OF NRYSES, TESTS NO SAFETY
EVAUJATIONS IfMDLVIfE FLOW RATES, CSF STRUCTURAL|
! IffIEGRITY, CSF LIER COOLING TUBE TERf%L NRYSES,|
GAS WASTE NRYSES, EAK 0%RACTERIZAT10N, ETC. TO
! INCLUDE SUPPORTING N% LYSES FOR A PASSIVE VENT SYSTEM
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PASSIVE WNT SYSTEM
o OUT OF M N EVAUMTIONS A PASSIW W SYSEM WAS
IDENTIFIED AS A POSSIBLE SOLUTION TO TE CSF LIE LEAK
o CONSIDEPATIONS
LIER LEAK EXCEEDS GAS WASTE CAPACITY
LIE FAILS TO SEAL AT SCE REJE TIEa
CSF LIE IS ESSENTIAL.LY IfMCESSIBLE
RENTE REPAIR LRESS LIER LEAK AND
TUBE LEAK E E COINCIDENT IS NOT FEASIBLE
o PASSIVE E SYSTEM IS DESIGED TO All0W OPEPATION OF M
REACTOR R.0ATING M CSF INTENAL PESSUE WITH PEACTOR
PESSUE
o EY M
PRIME ( S(STEM DEPESSURIZATION
EACTOR COOLANT PESSUE B0llDR(
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o IfAESTICATim TOOLS
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TELEVISION
MICR0PHOES
WDADPHOES:
SPECTRLM ANALYSES
FIBEROPTICSi
fACQUSTIC10NITORS
o LIERTY TEONOLOGIES t0CK-tF/ TESTING PROGPM
o PEPAIRS
REE WITHIN A TUBE
t9EP#E INSERTION
ETAL FORNING
o ALTEFNATE COOLING EDilMS IN C7 C)0 LING SYSTEM
|
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CMINATIONS (F CSF REES, SUBG)0 LING ARMNT
i REES, ifTILIZING ELith AS A C00UWT, llTILIZING
REDUED FLOWPRESSUPES|
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'o PASSIW WNT SYSTS M BEING RE-eMUJATED FOR
R% SED IN APPROADES
o EVAU RTING K 0IFICATION TO EXISTING GAS WASTE
SYSIB RELIEF VALW ARPMGEMNT
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FIGURE 2 CORE SUPPORT FLOOR VEllT & GAS WASTE SYSTEM
d.
"'u '( RUPTURE DISK, SET 0 APPX,14 PSIG7'
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FIGURE I
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I
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t
CORE SUPPORT FLOOR LEAKCASE COMPARISON
WORST CASE GAS WASTE SYSTEMFSAR CASE ACTUAL EXPERIENCE AT MAXIMUM CAPACITY
Helium Leak Rate 14 lbs/hr 10 lbs/hr 53 lbs/hr
Hold Up Capacity 30 hours 42 hours 7.9 hours
Circulating Primary 30,900 curies 515 curies 8163 curiesCoolant Inventory
Curie Content 60 curies /hr 0.7 curies /hr 60 curies /hrof CSF Leak
Duration of Continuous During Start-up During Start-upRelease
Percent of 100% 1.67% 25%10CFR20 MPC Limit
Off-site Dose Per FSAR 1/84 of FSAR Per FSARTable 11.1-11 Table 11.1-11 Table 11.1-11
ASSUMPTIONS (ALL CASES): Two 700 cu. ft. gas waste surge tanks, capable of operating at 450 psig.FSAR short term Condition F atmospheric dilution based on elevated re-
lease (50m plant vents) with a wind speed of 5 m/sec causing down washper FSAR Figure 14.12-1. No decay during hold-up.
b.
. ..
FORT ST. VRAIN
MANAGEMENT MEETING ATTENDEES
NRCTT F. Westerman NRC/RIV Chief, Reactor Projects Section DJ. P. Jaudon NRC/RIV Deputy Director, DRSL. J. Callan NRC/RIV Director, DRPR. F. Farrell NRC/RIV Senior Resident InspectorR. P. Mullikin NRC/RIV Project Engineer
PSCR. O. Williams, Jr. PSC VP Nuclear OperationsDon Warembourg PSC Manager, Nuclear EngineeringH. L. B rey PSC Manager, Nucl. Licensing and FuelRalph Sargent PSC Asst. to VP Nuc. Ops.P. F. Tomlinson PSC Manager,QA
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