ML18219B576

Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report (RO 78-035/03L-0), a Resubmittal of LER 78-034/03L-0 Dated 6/19/1978

ML18219B576
Person / Time
Site:	Cook
Issue date:	06/21/1978
From:	Shaller D American Electrtic Power System, Indiana Michigan Power Co
To:	James Keppler NRC/RGN-III
References
LER 1978-035-03L
Download: ML18219B576 (12)

Text

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

DISTRIBUTION FOR INCOMING MATERIAL 50-316 REC: KEPPLER J G ORG: SHALLER D V DOCDATE: 06/21/78 NRC IN 5 MI PWR DATE RCVD: 06/23/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED

SUBJECT:

LTR 1 ENCL 1 FORWARDING LICENSEE EVENT REPT <RO 50-316/78-035) QN 05/19/78 CONCERNING WHILE IN MODE 1 OPERATION REACTOR COOLANT SYSTEM UNIDENTIFIED LEAKAGE EXCEEDED TECH SPEC 3. 4. 6. 2. B... W/ATT.

PLANT NAME: COOK UNIT 2 REVIEWER INITIAL: X JM DISTRIBUTOR INITIAL:

+++++++4+4+4++++~ DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS NOTES:

1. SEND 3 COPIES OF ALL MATERIAL TO ISE ED REEVES-1 CY ALL MATERIAL INCIDENT REPORTS (D ISTR I BUT I QN CODE A002 )

FOR ACTION: LWR82 BC++W/4 ENCL INTERNAL: REG FI /ENCL NRC PDR+4W/ENCL 4+W/H ENCL MIPC++W/3 ENCL I 8. C SYSTEMS BR+wW/ENCL EMERGENCY PLAN BR>>W/ENCL NQVAK/CHECK4~W/ENCL EEB++W/ENCL AD FOR ENG++W/ENCL PLANT SYSTEMS BR>+W/ENCL HANAUER44W/ENCL AD FOR PLANT SYSTEMS4%W/ENCL AD FQR SYS 8. PROJ+~W/ENCL REACTOR SAFETY BR++W/ENCL ENGINEERING BR+4W/ENCL VOLLMER/BUNCH~+W/ENCL KREGER/J. COLLINS++W/ENCL POWER SYS BR+4W/ENCL K SEYFR IT/IE++W/ENCL EXTERNAL: LPDR'S ST. JOSEPH' I ++M/ENCL TI C4~+W/ENCL NS I C+4W/ENCL ACRS CAT B~~W/16 ENCL DISTRIBUTION: LTR 45 ENCL 45 CONTROL NBR: 781770011 SI ZE: iP+1P+1P TIRE END

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/II/O/AIVA8 MICHIGA/VPON'EH COMPAItIV DONALD C. COOK NUCLEAR PLANT C3 Vl I' P.O. Box 458, Bridgman, Michigan 49106 A

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~f11 June 21, 1978 C)

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=t Mr. J.G. Keppler, Regional Director f77 CO B

Office of Inspection and Enforcement United States Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, IL 60137 Operating License DPR-74 DocketNo. 50-316

Dear Mr. Keppl er:

Pursuant to the requirements of the Appendix A Technical Specifications the following report is submit)ed:

RO 78-035/03L-O.

This report is a resubmittal of our License Event Report No. 78-034/03L-0 dated June 19, 1978. A Licensee Event Report by the same number was previously submitted on June 13, 1978.

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 PE W. Steketee, Esq.

R. Walsh, Esq.

G. Charnoff, Esq.

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

~~+700gg '

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Dir., MIPC (3 copies)

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NRC FORM 366 U. S. NUCLEAR REGULATORY COMMISSIO PQZJ LICENSEE EVENT REPORT CORRECTED COPY CONTROL BLOCK: OI {PLEASE PRINT OR TYPE ALL REOUIRED INFORMATION) 6

~o M I D C C 2Q20 14 15 0 0 0 0 0 0 LICENSE NUMBER 0 0 0 OQ34 25 26 LICENSE TYPE 1

30 Os~Os 57 CAT 58 7 8 9 LICENSEE CODE CON'T 0 6 1 9 7 8 Qe LJLO6 0 5 0 0 0 3 O7 QB 80 EVENT DATE 74 75 REPORT DATE 60 61 DOCKET NUMBER EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10

~02 WHILE IN MODE 1 OPERATION REACTOR COOLANT SYSTEM UNI N F

~O3 CEEDED TECH. SPEC. 3.4.6.2sb LIMIT. UNIT WAS STARTED DOWN HOURS AFTER 4 DISCOVERY BUT WAS RETURNED TO ORIGINAL LOADING WHEN LEAKAGE INDICATED WI

~OS THIN LIMITS. LEAKAGE EXCEEDED LIMITS THE SECOND TIME. THE UNIT WAS START ED DOWN 4 HOURS AFTER DISCOVERY AND REMIOVED FROM SERVICE 23 HOURS LATER.

~O6 THE REACTOR WAS COOLED DOWN TO MODE 5 IN THE NEXT 17 HOURS.

~OB 80 7 8 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE

~OB ~CE 10 QAA E Gs ~XO>>

12 13 V A L V E X 18 G4 ~EOs 19 LOI Os 20 7 8 9 11 SEQUENTIAL. OCCURRENCE REPORT REVISION 017 LERIRP RsssRT ACTION FUTURE EVENT YEAR

~78 21 22 EFFECT

~23 SHUTDOWN

~03 24 REPORT NO.

8 26

~w 27

~03 28 ATTACHMENT CODE 29 NPR~

s TYPE

~L 30 PRIME COMP.

31

~0 NO.

32 COMPONENT TAKEN ACTION ON PLANT METHOD HOURS ~22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER

~AGB~ZS 33 34 L~JO2O 35 L~JO 36 37 0 2 B>> 40 41 0 L>JO24 42 MNO26 43 44 A 5 5 02.

47 CAUSE DESCRIPTION AND CORRECTIVE'ACTIONS 027 o ISOLATION VALVE BETWEEN RCS AND RHR FOUND TO HAVE EXCESSIVE STEM LEA'F AND PACKAGE LEAKAGE. VALVE REPACKED AND STEM LEAKOFF URNED TO OPERATING PRESS. AND TEMP. AND LEAKAGE WAS STILL EXCESSIVE. SAF S ETY VALVE ON FAILED FUEL DETECTOR FOUND LEAKING THROUGH. SAFETY VALVE RE 4 PLACED AND LEAKAGE WAS REDUCED TO NORMAL.

80 7 8 9 FACILITY METHOD OF STATUS TsPOWER OTHER STATUS QBO DISCOVERY DISCOVERY DESCRIPTION Q32 s ~EQss ~08 0 12 Qss NA 44

~BQ31 45 46 ROUTINE SURVEILLAN E 80 8 9 10 13 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY Q LOCATION OF RELEASE Q

~z Q33 ~ZQ34 NA 45 80 7 8 9 10 11 44 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39

~ll ~00 7 8 9 0

11 O~ZS 12 13 NA 80 PERSONNEL INJURIES NUMBER DESCRIPTIONQ41 8

L0000 9

JQ4o 11 12 NA 80 7

LOSS OF OR DAMAGE.TO FACILITY TYPE DESCRIPTION Q43 9 ~ZQ42 NA 80 7 8 9 10 PUBLICITY NRC USE ONLY ISSUED DESCRIPTION ~S ss O

O Q44 10 68 69 80 o 7 8 9 0

NAME OF PREPARER PHONE:

SUPPLEMENT TO LER No. 78-035/03L-0 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS INITIAL INSPECTION FOUND EXCESSIVE LEAKAGE FROM THE PACKING OF THE ISOLA TION VALVE BETWEEN THE REACTOR COOLANT SYSTEM AND THE RESIDUAL HEAT REMO VAL 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" TWI N DISK GATE MANUFACTURED BY COPES VULCAN WITH A 2500 PSIG RATING. THE VA LVE WAS REPACKED AND THE STEAM LEAKOFF WAS DISCONNECTED AND TERMINATED I N BOTH DIRECTIONS.

WHEN THE REACTOR COOLANT SYSTEM WAS RETURNED TO OPERATING PRESSURE AND T EMPERATURE '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 VALVE WAS ISOLATED AND THE LEAKAGE RATE:REDUCED TO NORMAL.

THIS SAFETY VALVE IS A >~" INLINE MANUFACTURED BY NUPROCO. MODEL Pr4A SS 8 CPA2-50. IT WAS REPLACED BY A DUPLICATE. THE FAILED VALVE WAS NOT DISASS EMBLED TO DETERMINE FAILURE DUE TO HIGH CONTAMINATION.

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/ 59 eaerta NDIANA & NICHIGAN PD %EH COII/IPANY

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DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106 June 21, 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 License DPtR-74 Docket:".No. 50-316

Dear Mr. Keppler:

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

RO 78-035/03L-O.

This report is a resubmittal of our License Event Report No. 78-034/03L-0 dated June 19, 1978. A Licensee Event Report by the same number was previously submitted on June 13, 1978.

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 1978 R.C. Callen MPSC P.W. Steketee, Esq.

R. Walsh, Esq.

G. Charnoff, Esq.

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

Dir., MIPC (3 copies)

2~

'RC FORM 366 U. S. NUCLEAR REGULATORY COMMISSION (7.77) hg LICENSEE EVENT REPORT CORRECTED COPY CP NTR0L B LOC K: Qi (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

I 6

~ol N 1 D C C 2 Qo 14 15 0 0 0 0 0 0 LICENSE NUMBER 0 0 D 0 0 25 Qo 26 4 1 1 LICENSE TYPE 1 1 30 Q4~Qo

= 57 CAT 58 7 8 9 LICENSEE CODE CON'T 8

~L0 60 61 5 0 0 0 DOCKET NUMBER 3 1 68 Qe 69 EVENT DATE 74 Qs 75 0 6 1 9 REPORT DATE 7 8 80 QB EVENT DESCRIPTION AND PROBABI.E CONSEQUENCES QIO

~02 WHILE IN MODE 1 OPERATION REACTOR COOLANT SYSTEM UN D IF CEEDED TfCH. SPEC. 3.4.6.2.b LIMIT. UNIT WAS STARTED DOWN 43 HOURS AFTER DISCOVERY BUT WAS RETURNED TO ORIGINAL LOADING WHEN LEAKAGE INDICATED WI THIN LIMITS. LEAKAGE EXCEEDED LIMITS THE SECOND TIME. THf UNIT WAS START

~O6 ED DOWN 4 HOURS AFTER DISCOVERY AND REMOVED FROM SERVICE 23 HOURS LATER.

THE REACTOR WAS COOLED DOWN TO MODE 5 IN THE NEXT 17 HOURS.

~OS 80 7 8 9 e SYSTEM CAUSE CAUSE COMP. VALVE SUBCODE ~

CODE CODE SUBCODE COMPONENT CODE SUBCODE

~Os 7 8

~CE 10, 9

0" 11 E O ~xOo 12 13 v A L v 5 x 18 Olo ~EO 19 LoJOo 20 SEQUENTIAL OCCUR RENCE REPORT REVISION Qll Roeooe LERIRP EVENT YEAR

~78 21 22 EFFECT

~23

~03 24 REPORT NO.

5 26

~~

27

~03 28 ATTACHMENT CODE 29 NPRDQ TYPE

~L 30 PRIME COMP.

~

31 NO.

0 32

'OMPONENT ACTION FUTURE SHUTDOWN TAKEN ACTION ON PLANT METHOD HOURS Q22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER

~AQlo ~ZQlo ~AQoo ~AQ>> 0 2 8 7 ~YQoo LYJQo4 ~NQ>> A 5 026 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE'ACTIONS 027 o ISOLATION VALVE BfTWfEN RCS AND RHR FOUND TO HAVE EXCESSIVE STEM'EA'F AND PACKAGE LEAKAGE. VALVE REPACKED AND STEM LfAKOFF URNED TO OPERATING PRESS. AND TEMP. AND LEAKAGE WAS STILL EXCESSIVE. SAF 3 ETY VALVE ON FAILED FUEt. DETECTOR FOUND LEAKING THROUGH. SAFETY VALVE RE 4 PLACED AND LEAKAGE WAS REDUCED TO NORMAL.

80 7 8 9 FACILITY STATUS E Qoo ~08 55 POWER 0 Qoo NA OTHER STATUS ~

~3P METHOD OF DISCOVERY

~BQ31 ROUTINE SURVEILLAN DISCOVERY DESCRIPTION Q32 E

7 8 9 10 12 13 44 45 46 80 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITYQ3 LOCATION OF RELEASE 036

~Z Q33 ~Z03 NA NA 80 7 8 9 10 11 44 45 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION ~36

~le ~00 0 Q>>

12 Z Qoo 13 NA 80 7 8 9 11 PERSONNEL INJURIES NUMBER DESCRIPTION041 o

8

~00 9

0 11 Q4o 12 NA 80 7

LOSS OF OR DAMAGE,TO FACILITY TYPE DESCRIPTION Q43 o Z Q42 NA 7 8 9 10 80 PUBLICITY NRC USE ONLY ISSUED DESCRIPTION ~N aeo 44

~N 80 8 9 10 68 69 0

NAME OF PREPARER PHONE: 0

0 SUPPLEMENT TO LER No. 78-035/03L-0 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS INITIAL INSPfCTION FOUND EXCESSIVE LEAKAGE FROM THE PACKING OF THE ISOLA TION VALVf BETWEEN THf REACTOR COOLANT SYSTEM AND THE RESIDUAL HEAT RfMO VAL SYSTEM. THE PACKING BOX OF THIS VALVf WAS ALSO EQUIPPED ltJITH A STfAM LEAKOFF PIPED'O THE REACTOR COOLANT DRAIN .TANK. THIS VALVE IS A 14" TWI N DISK GATE MANUFACTURED BY COPES VULCAN WITH A 2500 PSIG RATING. THE VA LVE WAS REPACKED AND THE STEAM LEAKOFF WAS DISCONNECTED AND TERMINATED I N BOTH DIRECTIONS.

WHEN THE REACTOR COOLANT SYSTEM WAS RETURNED TO OPERATING PRESSURE AND T EMPERATURE 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 KNOLJN. THE SAFfTY VALVE WAS ISOLATED AND THE LEAKAGE RATE REDUCED TO NORMAL.

THIS SAFETY VALVE IS A >" INLINE MANUFACTURED BY NUPROCO. MODEL 84A SS 8 CPA2-50. IT lJAS REPLACED BY A DUPLICATE. THE FAILED VALVE WAS NOT DISASS EMBLED TO DETERMINE FAILURE DUE TO HIGH CONTAMINATION.

1