_ _ - _ - - - _ _ _ _ _ ,

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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,

.

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

2/e/o

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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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___________

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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

> i.

FORTST,VPAIN

NRC-PSC

MKBBfT C0FERBICE

ARLINGTG1, TEXAS

MARCH 3,1988

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FORT ST VPAIN

MISlMED [ FADS

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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.|

|

ClitCullRY SillPLiflED FOR CLARITY .

.

.. ..

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_

''s .

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--

-~

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

I

* 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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V *

+ + .'

Charger - - -

277V AC Inverter '- - - --

1 P l '1 r

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-

T- T- T-- .

_n_ -

_

^

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

'I

fli-22237-3p

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I

> 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.

,

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,-------------. ----------------------------------- -------_____

} ..

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.

I

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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

.

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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FORT ST. VRAIN

HELIUM CIRCULATOR

PROCUREMENT 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'

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7-

-l 1smsms '' s'

' STEAM'e

rii, 'lT % f - $ -

- / LABYRINTH;

,' j,

h SEAL'

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/ 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

, -

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

'

APPROPRIATE QAL LEVEL REQUlREMENTS FOR SAFETY RELATEDCOMPONENTS (10CFR50 APP B)

,

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,-,.

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I

ROOT CAUSE

-

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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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

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N N /EDU S i

A CVEET I' l

N A WM M SEVPLOON O G )I

RNT C 1I I

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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

-

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'

-

PSC ENGINEERING / LICENSING TO PROVIDE FINAL RESOLUTION Of ISSUES 10'

Tile NRC. TARGElED IOR APRIL 1988

-

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FORTST,VRAIN

CORESUPPORT

FLOOR ISSLES

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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

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: M ?- ELEMENTSCONTROL ROO ------

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CORE SUPPORT'

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CORE SUPPORTPOSTS -

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FLOOR COLUMN'_fi . CIRCULATORCORE SUPPORT

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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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.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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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

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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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