ML18219B578

D.C. Cook - Submit Licensee Event Report RO 50-316/78-034/03L-0 for Unit 2

ML18219B578
Person / Time
Site:	Cook
Issue date:	06/19/1978
From:	Shaller D American Electrtic Power System, Indiana Michigan Power Co, (Formerly Indiana & Michigan Power Co)
To:	James Keppler NRC/RGN-III
References
LER 1978-034-03L
Download: ML18219B578 (11)

Text

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

DISTRIBUTION FOR INCOMING MATERIAL 50-316 REC: KEPPLER J G ORG: SHALLER D V DOCDATE: 06fi9/78 NRC IN 5 MI PWR DATE RCVD: 06/23/76 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED

SUBJECT:

LTR 1 ENCL 1 FORWARDING LICENSEE EVENT REPT (RO 50-316/78-034) ON 05/19/78 CONCERNING WHILE IN MODE 1 OPERATION REACTOR COOLANT SYSTEM UNIDENTIFIED LEAKAGE EXCEEDED TECH SPEC 3. 4. 6. 2. 8 LIMIT... W/ATT.

PLANT NAME: COOK UNIT 2 INITIAL: XJM REVIEWER DISTRIBUTOR DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS INITIAL:~

NOTES:

1. SEND 3 COPIES OF ALL MATERIAL TO ISE

'D REEVES-1 CY ALL MATERIAL INCIDENT REPORTS (DISTRIBUTION CODE A002>

FOR ACTION: BR LWRN2 BC4~W/4 ENCL INTERNAL: /ENCL NRC PDR++W/ENCL I 5 E~~W/~ ENCL MIPC44W/3 ENCL I 0 C SYSTEMS BR++W/ENCL EMERGENCY PLAN BR>~W/ENCL NOVAK/CHECK44W/ENCL EEB++W/ENCL AD FOR ENG++W/ENCL PLANT SYSTEMS BR>+W/ENCL HANAUER~~W/ENCL AD FOR PLANT SYSTEMS++W/ENCL AD FOR SYS 5 PROJ++W/ENCL REACTOR SAFETY BR++W/ENCL ENGINEERING BR4+W/ENCL VOLLMER/BUNCII44W/ENCL KREGER/J. COLLINS++WfENCL POWER SYS BR+>W/ENCL K SEYFRIT/IE+4W/ENCL EXTERNAL: LPDR'S ST. JOSEPH'I ++WfENCL TI C~~W/ENCL NSIC++WfENCL ACRS CAT 8++W/16 ENCL DISTRIBUTION: LTR 45 ENCL 45 CONTROL NBR: 781770010 SIZE: 1P+1P+1P

PDR SPECIAL WEEKLY LIS FILE. l t. Vt Lb

~IN-bu-b~O NE.~i ENGLAND POWER COMPANY NE.P Ai 50 06/07/ IQ ACCE:SSION NBRo 77301-0153 TASK NB a'~o ~ C "

DOCUAENT SIdi: 1P NOTARIZ LOCKE:T DATE,: LPDR:

RECP: VASSALLO D RE.CP ORe: TE:DFSCO R ORS A

SUBJECT:

R4V. 1 TO THE DRAFT SAFLTY E;V

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Op IIVDIAIVA 8 MICHIGAIV PO 8'ER COMPA IVV IHII.QIIW Igg pZ (tn f %.a" y f C'll DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106 M CD f'n CA~ ~

C, KI June 19, 1978 CD Hr. J.G. Keppler, Regional Director Office of Inspection and Enforcement United States Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, IL 60137 i

Operating License DPR-74 Docket No. 50-316

Dear Hr. Keppler:

Pursuant to the requirements of the Appendix A Technical Specifications the following report is submitted:

RO 78-034/03L-O.

Sincerely, D.V. Shaller Plant Manager

/bah CC: J.E. Dolan R.W. Jurgensen R.f. Kroeger R. Kilburn R.J. Vollen BPI K.R. Baker RO:III R.C. Callen MPSC P.W. Steketee, Esq.

G. Charnoff, Esq.

R. Walsh, Esq.

G. Olson J.M. Hennigan PNSRC J.F. Stietzel Dir., IE (30 copies)

Dir., MIPC (3 copies) 781770010

NRC FORM 366 U. S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT 4

CONTROL BLOCK: tPLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6 7 8 9 M 1 D C LICENSEE CODE C 2 14 QE 15 0 0 0 0 0 0 0 LICENSE NUMBER 0 0 0 OQE4 25 26 1 1 LICENSE TYPE 1 104~00 30 57 CAT 58 CON'T Q Qs 0 6 I 9 Qe 7 8 60 61 DOCKET NUMBER 68 69 EVENT DATE '74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Qlo

~O2 WHILE IN MODE I OPERATION REACTOR COOLANT SYSTEM UNIDENTIFIED LEAKAGE EX CEEDED TECH. SPEC. 3.4.6.2.b LIMIT. UNIT WAS STARTED DOWN 4> HOURS AFTER

~O4 DISCOVERY BUT WAS RETURNED TO ORIGINAL LOADING WHEN LEAKAGE INDICATED WI

~Os THIN LIMITS. LEAKAGE EXCEEDED LIMITS THE SECOND TIME. THE UNIT WA'S STARTED

~OB DOWN 4 HOURS AFTER DISCOVERY AND R M R

~O7 REACTOR WAS COOLED DOWN TO M DE 5 IN THE T 17 HOURS.

~OS 80 7 8 SYSTEM CAUSE CAUSE COMP. VALVE.

CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE

~oe ~CE QT E Q>> ~XQ>> V A L V E X Q74 ~EQEE ~D QEE 7 8 9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION QTT LERIRP REPORT ACTION FUTURE EVENT YEAR Q+

21 22 EFFECT

+

23 SHUTDOWN

~03 24 REPORT NO.

4 26 27 28 ATTACHMENT CODE 29 NPRDC TYPE 30 PRIME COMP.

31 NO.

32 COMPONENT TAKEN ACTION ON PLANT METHOD HOURS ~22 SUBMITTED FORM SUB. SUPPLIER h'IANUFACTURER

~AQIB ~ZQle ~AQ2O ~AQ21 37

~Y Q23 ~YQ24 MNQ>> A 5 A 5 QS 33 34 35 36 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 o IS LATIO AND PACKING LEAKAGE. VALV P

[ NED TO OPERATING PRESS. AND TEMP, A AKA 3 VALVE ON FAILED FUEL DET. C R F 4 D AND LEAKAGE WAS R D

'7 8 9 80 s

FACILITY STATUS E Qss ~08

'YE POWER 0 QEE NA OTHER STATUS ~

~3P METHOD OF DISCOVERY

~BQ31 ROUTINE SURVEILLANCE DISCOVERY DESCRIPTION Q32 7 8 9 10 12 13 44 45 46 80 6

ACTIVITY CONTENT RELEASED OF RELEASE

~Z Q33 ~ZQ34 NA AMOUNT OF ACTIVITY ~ LOCATION OF RELEASE Q 7 8 9 10 44 45 80 PERSONNEL EXPOSURES

~00 NUMBER OJ0~ 'ss TYPE DESCRIPTION Q3e A

80 7 8 9 11 12 13 PERSONNEL INJURIES NUMBER DESCRIPTIONQ41 040 A 7 8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION Q43 e Z Q42 NA 7 8 9 10 80 PUBLICITY ISSUED DESCRIPTION Q NRC USE ONLY 00

~2O 7 8

~NQ 9 10 NA 68 69 80 O

Es 0

a NAME Qf PRFPARFR PHONE:

CAUSE DESCRIPTION AND CORRECTIVE ACTIONS INITIAL INSPECTION FOUND EXCESSIVE LEAKAGE FROM THE PACKING OF THE ISOLATION VALVE BETWEEN- THE REACTOR COOLANT SYSTEM AND THE RESIDUAL HEAT REMOVAL SYSTEM. THE PACKING BOX OF THIS VALVE WAS ALSO E(UIPPED WITH A STEAM LEAKOFF PIPED TO THE REACTOR COOLANT DRAIN, TANK. THIS VALVE IS A 14" TWIN DISK GATE MANUFACTURED BY COPES VULCAN WITH A

'500 PSIG RATING. THE VAI VE,WAS REPACKED AND THE STEAM LEAKOFF WAS DISCONNECTED AND TERMINATED IN BOTH DIRECTIONS.

WHEN THE REACTOR COOLANT SYSTEM WAS RETURNED TO OPERATING PRESSURE AND TEMPERATURE THE LEAKAGE RATE WAS STILL IN EXCESS OF ALLOWABLE LIMITS.

A 75 PSIG SET SAfETY VALVE IN THE FAILED FUEL DETECTOR SYSTEM WAS FOUND TO BE LEAKING THROUGH. THIS FINDING WAS 4 3/4 HOURS AFTER THE LEAK RATE BECAME KNOWN. THE SAFETY VAL'VE WAS ISOLATED AND THE LEAKAGE RATE REDUCED TO NORMAL.

THIS SAFETY VALVE IS A 1/2" INLINE MANUFACTURED BY NUPROCO.

MODEL 8 4A SS 8 CPA2-50. IT WAS REPLACED BY A DUPLICATE. THE FAILED VALVE WAS NOT DISASSEMBLED TO DETERMINE FAILURE DUE TO HIGH CONTAMINA-

INDIANA & MICHIGANPOS'EH COMPANY DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106 June 19, 1978 Mr. J.G. Keppler, Regional Director Office of Inspection and Enforcement United States Nuclear Regulatory Commission.

Region III 799 Roosevelt Road Glen Ellyn, IL 60137 Operating ~cense DPR-74 Docket . 50-316

Dear Mr. Keppler:

Pursuant to the requirements of the Appendix A Technical Specifications the following report is submitted:

RO 78-034/03L-O.,

Sincerely, D.V. Shaller Plant Manager

/bab cc: J.E. Dolan R.W. Jurgensen R.F. Kroeger R. Kilburn R.J. Vollen BPI K.R. Baker RO:III R.C. Callen MPSC P.W. Steketee, Esq.

G ~ Charnoff, Esq.

R. Walsh, Esq.

G. Olson J.M. Hennigan PNSRC JUi~j g I )978 J.F. Stietzel Dir., IE (30 copies)

Dir., MIPC (3 copies)

~ ~

4 e

NRC FOI3%l 366 U. S. NUCLEAR REGULATORY COMMISSION I7 7Y)

~ P

~ wW LICENSEE EVENT REPORT CONTROL BLOCK: Qi {PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

I 6

~o>

7 8 9 N 1 0 C C LICENSEE CODE 2

14 Q2 15 0 0 0 0 0 0 LICENSE NUMBER 0 0 0 0 0 25 Qo 26 4 1 1 1 LICENSE TYPE 30 1 QE~QE 57 CAT 58 CON'T

~97 REPRRT 60 61 DOCKETNUMBER 68 0 69 EVENT DATE I4 QB 75 0 6 I 9 REPORT DATE 7

80 Q9 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10

~02 WHILE IN MODE 1 OPERATION REACTOR COOLANT SYSTEM UNIDENTIFIED LEAKAGE EX

~03 CEEDED TECH. SPEC. 3. 4. 6. 2. b LIMIT. UNIT WAS STARTED DOWN 4> HOURS AFTER

~04 DISCOVERY BUT WAS RETURNED TO ORIGINAL LOADING WHEN LEAKAGE INDICATED WI

~os THIN LIMITS. LEAKAGE EXCEEDED LIMITS THE SECOND TIME. THE UNIT".WA'5 "STA'RTEI3

~06 DOWN 4 HOURS AFTER DISCOVERY A D RE D

~0 7 REACTOR WAS COOLED DOWN TO MODE 5 IN THE EXT 1 HOURS.

~OB 80 7 8 9 SYSTEM CAUSE CAUSE COMP. VALVE.

CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE

~09 7 8

~CE 9 10 Q11 11 E Q>> ~XO 12 13 V A C V E X 18 Q4 LUQPE 19 LJ Q>>

20 SEQUENTIAL OCCURRENCE REPORT REVISION Q17 ACTION FUTURE LF RIRO REPORT EVENT YEAR

~LI 21 22

+

23

~03 24 REPORT NO.

4 26 Q~

27 LDJM 28 ATTACHMENT CODE 29 NPRDP TYPE LLj 30 U

PRIME COMP.

31 NO.

L(J 32 COMPONENT

~AO2'VQ23 EFFECT SHUTDOWN TAKEN ACTION ON PLANT METHOD HOURS Q22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER

~AO1B ~z Q19 ~AQ20 LYJQ24 LNJQ25 A 5 A 0 QE 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 027 o IS LATIO AND PACKING LEAKAGE. VALV R P PNN PN PPNPA NN AN~AN P. A A i

3 VALVE ON FAILED FUEL DETEC F U D F 4 D AND LEAKAGE WAS R D 80 8

~

7 9 FACILITY ~30 METHOD OF STATUS  % POWER OTHER STATUS "

DISCOVERY DISCOVERY DESCRIPTION Q32 5 E Q28 ~08 0 Q29 NA 44

~BQ31 ROUTINE SURVEILLANCE 80 8 9 10 12 13 45 46 ACTIVITY RELEASED OF RELEASE

~z Q CONTENT

~ZO34 AMOUNT OF ACTIVITY ~ LOCATION OF RELEASE Q 7 8 9 10 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39 7

7 8

L0¹00j 9 11 Q3 7

12 Q3 8 13 80 PERSONNEL INJURIES NUMBER DESCRIPTIONQ 7

8 8

~pp 9

p 11 Q4o 12 80 LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION Q43 9 Z Q42 NA 7 8 9 10 80 PUBLICITY NRC USE ONI.Y ISSUED DESCRIPTION ~S CE 0

o L~IO44 NA 7 8 9 P

10 80 0 0

NAMEOF PREPARFR R. S. Keith PHONE:

Pp L

I \

i I

CAUSE DESCRIPTION AND CORRECTIVE ACTIONS INITIAL INSPECTION FOUND EXCESSIVE LEAKAGE FROM THE PACKING OF THE ISOLATION VALVE BETWEEN THE REACTOR COOLANT SYSTEM AND THE RESIDUAL HEAT REMOVAL SYSTEM. THE PACKING BOX OF THIS VALVE WAS ALSO EQUIPPED WITH A STEAM LEAKOFF PIPED TO THE REACTOR COOLANT DRAIN TANK. THIS VALVE IS A 14" TWIN DISK GATE MANUFACTURED BY COPES VULCAN WITH A 2500 PSIG RATING. THE VALVE WAS REPACKED AND THE STEAM LEAKOFF WAS DISCONNECTED AND TERMINATED IN BOTH DIRECTIONS.

WHEN THE REACTOR COOLANT SYSTEM WAS RETURNED TO OPERATING PRESSURE AND TEMPERATURE THE LEAKAGE RATE WAS STILL IN EXCESS OF ALLOWABLE LIMITS.

A 75 PSIG SET SAFETY VALVE IN THE FAILED FUEL DETECTOR SYSTEM WAS FOUND TO BE LEAKING THROUGH. THIS FINDING WAS 4 3/4 HOURS AFTER THE LEAK RATE BECAME KNOWN. 'THE SAFETY VAL>VE WAS ISOLATED AND THE LEAKAGE RATE REDUCED TO NORMAL.

THIS SAFETY VALVE IS A 1/2" INLINE MANUFACTURED BY NUPROCO.

MODEL 8 4A SS 8 CPA2-50. IT WAS REPLACED BY A DUPLICATE. THE FAILED VALVE WAS NOT DISASSEMBLED TO DETERMINE FAILURE DUE TO HIGH CONTAMINA-

~ V~ ~ ~

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