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 NRC ORG: SHALLER D V IN 5 MI PWR DOCDATE: 06/21/78 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 I STR I BUT I QN CODE A002)FOR ACTION: INTERNAL: EXTERNAL: LWR82 BC++W/4 ENCL REG FI/ENCL 4+W/H ENCL I 8.C SYSTEMS BR+wW/ENCL NQVAK/CHECK4~W/ENCL AD FOR ENG++W/ENCL HANAUER44W/ENCL AD FQR SYS 8.PROJ+~W/ENCL ENGINEERING BR+4W/ENCL KREGER/J.COLLINS++W/ENCL K SEYFR IT/IE++W/ENCL LPDR'S ST.JOSEPH'I++M/ENCL TI C4~+W/ENCL NS I C+4W/ENCL ACRS CAT B~~W/16 ENCL NRC PDR+4W/ENCL MIPC++W/3 ENCL EMERGENCY PLAN BR>>W/ENCL EEB++W/ENCL PLANT SYSTEMS BR>+W/ENCL AD FOR PLANT SYSTEMS4%W/ENCL REACTOR SAFETY BR++W/ENCL VOLLMER/BUNCH~+W/ENCL POWER SYS BR+4W/ENCL DISTRIBUTION:

LTR 45 ENCL 45 SI ZE: iP+1P+1P CONTROL NBR: 781770011 TIRE END e~e e I~I I e I~~I~I e e~e~~~~r~)~~I e~e~e t e e~)~e e~~~~~~t t)I I~~'e e~~0~'~e e~I I~~~~~~I e~e I~e~~~r~~I~~~g e)~~~~e~)

/Hecato/II/O/AIVA 8 MICHIGA/V PON'EH COMPAItIV 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 C3 Vl A l'/7 I C)~~5 f77 (R f77 CO I'~f11~CA~~ar=t B 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)Dir., MIPC (3 copies)~~+700gg'o&"\i ra r iJ I NRC FORM 366 PQZJ U.S.NUCLEAR REGULATORY COMMISSIO LICENSEE EVENT REPORT CORRECTED COPY 1 Os~Os LICENSE TYPE 30 57 CAT 58 CONTROL BLOCK: OI{PLEASE PRINT OR TYPE ALL REOUIRED INFORMATION) 6~o M I D C C 2Q20 0 0 0 0 0 0 0 0 0 OQ34 7 8 9 LICENSEE CODE 14 15 LICENSE NUMBER 25 26 CON'T LJLO6 0 5 0 0 0 3 O7 QB 0 6 1 9 7 8 Qe 60 61 DOCKET NUMBER EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10~02 WHILE IN MODE 1 OPERATION REACTOR COOLANT SYSTEM UNI N F~O3 4 CEEDED TECH.SPEC.3.4.6.2sb LIMIT.UNIT WAS STARTED DOWN HOURS AFTER DISCOVERY BUT WAS RETURNED TO ORIGINAL LOADING WHEN LEAKAGE INDICATED WI~OS~O6 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.THE REACTOR WAS COOLED DOWN TO MODE 5 IN THE NEXT 17 HOURS.~OB 80 7 8 7 8 SYSTEM CAUSE CAUSE COMP.VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE~OB~CE QAA E Gs~XO>>V A L V E X G4~EOs LOI Os 9 10 11 12 13 18 19 20 SEQUENTIAL.

OCCURRENCE REPORT REVISION LERIRP EVENT YEAR REPORT NO.CODE TYPE NO.017 RsssRT~78~~03 8~w~03~L-~0 21 22 23 24 26 27 28 29 s 30 31 32 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPR~PRIME COMP.COMPONENT TAKEN ACTION ON PLANT METHOD HOURS~22 SUBMITTED FORM SUB.SUPPLIER MANUFACTURER

~AGB~ZS L~JO2O L~JO 0 2 B>>0 L>JO24 MNO26 A 5 5 02.33 34 35 36 37 40 41 42 43 44 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.7 8 9 7 8 O 7 8 9 11 12 LOSS OF OR DAMAGE.TO FACILITY Q43 TYPE DESCRIPTION

~ZQ42 NA 9 10 PUBLICITY ISSUED DESCRIPTION

~S Q44 9 10 NAME OF PREPARER 7 8 9 FACILITY STATUS TsPOWER OTHER STATUS QBO s~EQss~08 0 Qss NA 8 9 10 12 13 44 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY Q~z Q33~ZQ34 NA 7 8 9 10 11 44 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39~ll~00 0 O~ZS NA 7 8 9 11 12 13 PERSONNEL INJURIES NUMBER DESCRIPTIONQ41 L0000 JQ4o NA 80 80 45 80 80 80 PHONE: 68 69 80 NRC USE ONLY ss O 80 o 0 METHOD OF DISCOVERY DISCOVERY DESCRIPTION Q32~BQ31 ROUTINE SURVEILLAN E 45 46 LOCATION OF RELEASE Q 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.

'P P~L-/59 eaerta~yg)~NDIA NA&NICHIGA N PD%EH COII/IPA NY 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 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)1978 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 0 0 0 0 0 0 0 0 D 0 0 Qo 4 1 1 1 1 Q4~Qo 7 8 9 LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE 30=57 CAT 58 CON'T~L0 5 0 0 0 3 1 Qe Qs 0 6 1 9 7 8 QB 8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 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 7 8 9 e 80 SYSTEM CAUSE CAUSE COMP.VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE~~CE 0" E O~xOo v A L v 5 x Olo~EO LoJOo 9 10, 11 12 13 18 19 20 SEQUENTIAL OCCUR RENCE REPORT REVISION LERIRP EVENT YEAR REPORT NO.CODE TYPE NO.Qll Roeooe~78~~03 5~~~03~L~0 21 22 23 24 26 27 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRDQ PRIME COMP.'OMPONENT 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 33 34 35 36 37 40 41 42 43 44 CAUSE DESCRIPTION AND CORRECTIVE'ACTIONS 027 o ISOLATION VALVE BfTWfEN RCS AND RHR FOUND TO HAVE EXCESSIVE STEM'EA'F~Os 7 8 47 026 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 LEAKI NG THROUGH.SAFETY VALVE RE 4 PLACED AND LEAKAGE WAS REDUCED TO NORMAL.45 7 8 9 FACILITY~3P METHOD OF STATUS 55 POWER OTHER STATUS~DISCOVERY DISCOVERY DESCRIPTION Q32 E Qoo~08 0 Qoo NA~BQ31 ROUTINE SURVEILLAN E 7 8 9 10 12 13 44 45 46 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY Q3 LOCATION OF RELEASE 036~Z Q33~Z03 NA NA 7 8 9 10 11 44 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION

~36~le~00 0 Q>>Z Qoo NA 7 8 9 11 12 13 PERSONNEL INJURIES NUMBER DESCRIPTION041 o~00 0 Q4o NA 80 80 80 80 7 8 9 11 12 LOSS OF OR DAMAGE,TO FACILITY Q43 TYPE DESCRIPTION o Z Q42 NA 7 8 9 10 PUBLICITY ISSUED DESCRIPTION

~N~N 44 8 9 10 NAME OF PREPARER PHONE: 68 69 80 80 NRC USE ONLY eo a 80 0 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.

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