IR 05000316/1978034

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 NRC ORG: SHALLER D V IN 5 MI PWR DOCDATE: 06fi9/78 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 REVIEWER INITIAL: X JM DISTRIBUTOR INITIAL:~DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS NOTES: 1.SEND 3 COPIES OF ALL MATERIAL TO ISE'D REEVES-1 CY ALL MATERIAL INCIDENT REPORTS (DISTRIBUTION CODE A002>FOR ACTION: INTERNAL: EXTERNAL: BR LWRN2 BC4~W/4 ENCL/ENCL I 5 E~~W/~ENCL I 0 C SYSTEMS BR++W/ENCL NOVAK/CHECK44W/ENCL AD FOR ENG++W/ENCL HANAUER~~W/ENCL AD FOR SYS 5 PROJ++W/ENCL ENGINEERING BR4+W/ENCL KREGER/J.COLLINS++Wf ENCL K SEYFRIT/IE+4W/ENCL LPDR'S ST.JOSEPH'I++Wf ENCL TI C~~W/ENCL NSIC++Wf ENCL ACRS CAT 8++W/16 ENCL NRC PDR++W/ENCL MIPC44W/3 ENCL EMERGENCY PLAN BR>~W/ENCL EEB++W/ENCL PLANT SYSTEMS BR>+W/ENCL AD FOR PLANT SYSTEMS++W/ENCL REACTOR SAFETY BR++W/ENCL VOLLMER/BUNCII44W/ENCL POWER SYS BR+>W/ENCL DISTRIBUTION:

LTR 45 ENCL 45 SIZE: 1P+1P+1P CONTROL NBR: 781770010 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 a'~o~C" DOCUAENT SIdi: 1P LOCKE:T DATE,: RECP: VASSALLO D ORe: TE:DFSCO R TASK NB NOTARIZ LPDR: RE.CP ORS A SUBJECT: R4V.1 TO THE DRAFT SAFLTY E;V

~j.Op IHII.QIIW Igg pZ y f IIV DIA IVA 8 MICHIGA IV PO 8'ER COMPA IV V DONALD C.COOK NUCLEAR PLANT P.O.Box 458, Bridgman, Michigan 49106 June 19, 1978 (tn f%.a" C'll M CD f'n~CA~C, KI 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 U.S.NUCLEAR REGULATORY COMMISSION NRC FORM 366 LICENSEE EVENT REPORT 4 CONTROL BLOCK: tPLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

1 6 M 1 D C C 2 QE 0 0 0 0 0 0 0 0 0 0 OQE4 1 1 1 104~00 7 8 9 LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE 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 7 8 80~oe 7 8 SYSTEM CAUSE CAUSE COMP.VALVE.CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE~CE QT E Q>>~XQ>>V A L V E X Q74~EQEE~D QEE 9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION LERIRP EVENT YEAR REPORT NO.CODE TYPE NO.QTT REPORT Q++~03 4 21 22 23 24 26 27 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRDC PRIME COMP.COMPONENT TAKEN ACTION ON PLANT METHOD HOURS~22 SUBMITTED FORM SUB.SUPPLIER h'IANUFACTURER

~AQIB~ZQle~AQ2O~AQ21~Y Q23~YQ24 MNQ>>A 5 A 5 QS 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 o IS LATIO AND PACKING LEAKAGE.VALV P 3[NED TO OPERATING PRESS.AND TEMP, A AKA VALVE ON FAILED FUEL DET.C R F 4 D AND LEAKAGE WAS R D 80 80 80 45 80 80 80 NRC USE ONLY 00 O 80 Es 0 a PHONE: NAME Qf PRFPARFR'7 8 9 FACILITY~3P METHOD OF STATUS'YE POWER OTHER STATUS~DISCOVERY DISCOVERY DESCRIPTION Q32 s E Qss~08 0 QEE NA~BQ31 ROUTINE SURVEILLANCE 7 8 9 10 12 13 44 45 46 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY~LOCATION OF RELEASE Q 6~Z Q33~ZQ34 NA 7 8 9 10 44 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q3e~00 OJ0~'ss A 7 8 9 11 12 13 PERSONNEL INJURIES NUMBER DESCRIPTIONQ41 040 A 7 8 9 11 12 LOSS OF OR DAMAGE TO FACILITY Q43 TYPE DESCRIPTION e Z Q42 NA 7 8 9 10 PUBLICITY ISSUED DESCRIPTION Q~2O~NQ NA 7 8 9 10 68 69 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&MICHIGAN POS'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 J.F.Stietzel Dir., IE (30 copies)Dir., MIPC (3 copies)JUi~j g I)978

~~e 4 U.S.NUCLEAR REGULATORY COMMISSION NRC FOI3%l 366 I7 7Y)~P~wW QB 0 6 I 9 7 Q9 EVENT DATE I4 75 REPORT DATE 80 LICENSEE EVENT REPORT CONTROL BLOCK: Qi{PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

I 6~o>N 1 0 C C 2 Q2 0 0 0 0 0 0 0 0 0 0 0 Qo 4 1 1 1 1 QE~QE 7 8 9 LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 CON'T~97 REPRRT 0 60 61 DOCKETNUMBER 68 69 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 7 8 9 80~09 7 8 SYSTEM CAUSE CAUSE COMP.VALVE.CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE~CE Q11 E Q>>~XO V A C V E X Q4 LUQPE LJ Q>>9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION LF RIRO EVENT YEAR REPORT NO.CODE TYPE NO.Q17 REPORT~LI+~03 4 Q~LDJM LLj U L(J 21 22 23 24 26 27 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRDP PRIME COMP.COMPONENT TAKEN ACTION ON PLANT METHOD HOURS Q22 SUBMITTED FORM SUB.SUPPLIER MANUFACTURER

~AO1B~z Q19~AQ20~AO2'VQ23 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 3 VALVE ON FAILED FUEL DETEC F U D i F 4 D AND LEAKAGE WAS R D 45 7 8 9 7 8 9 11 12 LOSS OF OR DAMAGE TO FACILITY Q43 TYPE DESCRIPTION Z Q42 NA 7 8 9 FACILITY~30 METHOD OF STATUS%POWER OTHER STATUS~" DISCOVERY DISCOVERY DESCRIPTION Q32 5 E Q28~08 0 Q29 NA~BQ31 ROUTINE SURVEILLANCE 8 9 10 12 13 44 45 46 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY~LOCATION OF RELEASE Q~z Q~ZO34 7 8 9 10 44 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39 7 L0¹0 0j Q3 7 Q3 8 7 8 9 11 12 13 PERSONNEL INJURIES NUMBER DESCRIPTIONQ 8~pp p Q4o 80 80 80 80 80 o 9 10 PUBLICITY ISSUED DESCRIPTION

~S L~IO44 NA 7 8 9" P 10 NAMEOF PREPARFR R.S.Keith PHONE: 80 NRC USE ONI.Y CE 0 80 0 0 Pp I i I L\

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-

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