ML18219E154

Submit Licensee Event Report No. RO 78-049/03L-0

ML18219E154
Person / Time
Site:	Cook
Issue date:	09/12/1978
From:	Shaller D American Electrtic Power System, Indiana Michigan Power Co, (Formerly Indiana & Michigan Power Co)
To:	James Keppler NRC/RGN-III
References
LER 1978-049-03L
Download: ML18219E154 (4)

Text

REGULATORY INFORMATION Dl TRIBUTION SYSTEM (RIDS)

DISTRIBUTION FOR INCOMING MATERIAL 50-315 REC: KEPPLER J G ORG: .SIIALLER D V DOCDATE: 09/12/78 NRC IN & MI PWR DATE RCVD: 09/15/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED

SUBJECT:

LTR 1 ENCL 1 FORWARDING LICENSEE EVENT REPT (RO 50-315/78-049) ON 08/14/7$ CONCERNING DISCOVERY THAT ON 5/9/78 & 7/20/78 CONTAINMENT ISOLATION VALVES WCR-962 AND DCR-310 RESPECTIVELY WERE RETURNED TO VC AFTER REPAIRS TO VALVE ACTUATORS WITHOUT VERIFICATION OF ISOLAT PLANT NAME: COOK UNIT 1 REVIEWER INITIAL: X JM DISTRIBUTOR INITIAL:~

DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS 4+4+<<<<<<<+<<+<<<

NOTES:

I & E 3 CYS ALL MATERIAL INCIDENT REPORTS (DISTRIBUTION CODE A002)

FOR ACTION: BR CI-II Bai BC4+W/4 ENCL INTERNAL: CL NRC PDR'~+W/ENCL I & E+4W/2 ENCL MIPC~~W/3 ENCL I & C SYSTEMS BR++W/ENCL EMERGENCY PLAN BR<<W/ENCL NOVAK/CIHECK>+W/ENCL'D EEB44W/ENCL FOR ENG<+W/ENCL PLANT SYSTEMS BR4<W/ENCL HANAUER~~W/ENCL AD FOR PLANT SYSTEMS4<W/ENCL AD FOR SYS 8c PROJ%%W/ENCL REACTOR SAFETY BR~<M/ENCL ENGINEERING BR4>W/ENCL VOLLMER/BUNCH+>W/ENCL KREGER/J. COLLINS >4 M/ENCL POWER SYS BR++W/ENCL K SEYFR IT/IE++W/ENCL EXTERNAL: LPDR'S ST. JOSEPH. MI4 4W/ENCL NS I C< +W/ENCL ACRS CAT B4~W/16 ENCL DISTRIBUTION: LTR 44 ENCL 44 CONTROL NBR: 780870/00 SIZE: 1P+ 1P ~ 'e)

TI IE END

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ttEllNNO BOt',KEl FH.E COPY DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106 y1

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< years September 12, 1978 yyl 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 DPR-58 Docket No. 50-315

Dear Mr. Keppler:

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

RO 78-049/03L-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.

R. Walsh, Esq.

G. Charnoff, Esq.

G. Olson J.M. Hennigan PNSRC J.F. Stietzel 780870300 R.S. Keith T.P. Hei lman/J.L. Rischling Dir., IE (30 copies)

Dir., MIPC (3 copies)

NRC FORM 3P~s NUCI.EAR REGULATORY COMMISSION P.77Yj LICENSEE EVENT REPORT CONTROL BLOCK: Qi (PLEASE PRINT OR TYPE ALL REQUIRED INFORIVIATION)

I 6 N' D C C 1 Q20 0 0 0 0 0 0 LICENSE NUMBER 0 0 0 0 25 Q3 26 4 1 1 LICENSE TYPE 11 30 Qa~Qs 57 CAT 58 8 9 LICENSEE CODE s 14 15 ~

7 CON'T

~o LUQB 0 3 1 5 7 o 8 1 4 7 8 QBO 9 I 2 7 8 Qg 7 8 60 61 DOCKETNUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Qlo DURING A REVIEW OF JOB ORDERS, IT 'HAS DISCOVERED THAT ON 5-9-78 AND 7-20-78

~03 CONTAINMENT ISOLATION VALVES WCR"962 AND DCR-310 RfSPECTIVELY HERE RETURNED TO

~o4 SERVICE AFTER REPAIRS TO VALVE ACTUATORS WITHOUT VERIFICATION GF ISOLATION TIthE

~os AS REQUIRED BY T. S. 4.6.3.1.1. SURVEILLANCE PERFORMED ON 7-31 "78 SHOWED THE

~OB ISOLATION TIt1ES TO BE SATISFACTORY. NO PROBABLE CONSE UfNCES.

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

~Og 7 8

~90 9

CODE 10 Q11 CODE 11 A Gs SUBCOOE

~AQ13 12 13

' COMPONENT CODE L " ' 8 LJg ~

18 SUBCOOE 19 SUBCOOE 20 Gs SEQUENTIAL OCCURRENCE REPORT REVISION Gs LERIRO sssoss ACTION FUTURE EVENT YEAR

~78 21 22 EFFECT

~

23 SHUTDOWN 24 REPORT NO.

~04 9 26

~w 27

~09 28 ATTACHMENT CODE 29 NPRO<

TYPE

~L 30 PRIME COMP.

31 NO.

~0 32 COMPONENT TAKEN ACTION ON PLANT METHOD HOURS Q22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER

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Ois ~Q2O ~ZO21 0 0 0 0 ~N Q23 ~NQ4 ~A Q2s H 0 3 5 Q2B 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 027 o WHEN THE OPERATOR CYCLE TESTED THE VALVE UPON RETURNING IT TO SERVICE, HE FAILED

.TO REALIZE THAT AN ISOLATION TIME TEST WAS RE UIRED. MOST VALVfS HAVING RE UIRED ACTUATION TIf1ES HAD TIME POSTED ON CONTROL PANEL, HOWEVER, SOtdf VALVES INCLUDING 3 THE SUBJfCT VALVES DID NOT..'IMES WERE POSTED AS CORRECTIVE ACTION, FOR ALL VALVES REQUIRING TIIRED RESPONSE.

80

~

7 8 9 FACILITY METHOD OF STATUS  % POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION Q32 7

s 8 9 E Qzs ~09 10 7 Qze 12 13 NA 44 45 46 MANAGEt1ENT REV I EH 80

~ls ACTIVITY CONTENT RELEASEO OF RELEASE

~Z Q33 ~ZO34 AMOUNT OF ACTIVITY NA

~ I'IA LOCATION OF RELEASE Q3B 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39 7

v 8

~00 08 9 11 12 1 Oss 13 NA 80 PERSONNEL INJURIES 7 8 9 11 12 80 LOSS OF OR DAMAGE TO FACII.ITY TYPE DESCRIPTION Q43 9 Z Q42 NA 7 8 9 10 80

~ ~

ISSUED L~JO44 PUBLICITY DESCRIPTION ~ NA NRC USE ONI.Y O

7 8 9 10 68 69 80 o (616) 465-5901 0 l NAME OF PREPARER John RBndol Ph