05000316/LER-2078-049-03, Submit Licensee Event Report No. RO 78-049/03L-0

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)

LER-2078-049, Submit Licensee Event Report No. RO 78-049/03L-0

Event date:
Report date:
3162078049R03 - NRC Website

text

REGULATORY INFORMATION Dl TRIBUTION SYSTEM (RIDS)

DISTRIBUTION FOR INCOMING MATERIAL 50-315 REC:

KEPPLER J G

NRC ORG:.SIIALLER D V IN & MI PWR DOCDATE: 09/12/78 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:

XJM 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:

INTERNAL:

EXTERNAL:

BR CI-II Bai BC4+W/4 ENCL CL I & E+4W/2 ENCL I

& C SYSTEMS BR++W/ENCL NOVAK/CIHECK>+W/ENCL'D FOR ENG<+W/ENCL HANAUER~~W/ENCL AD FOR SYS 8c PROJ%%W/ENCL ENGINEERING BR4>W/ENCL KREGER/J.

COLLINS>4 M/ENCL K SEYFR IT/IE++W/ENCL LPDR'S ST.

JOSEPH.

MI4 4W/ENCL NSIC< +W/ENCL ACRS CAT B4~W/16 ENCL NRC PDR'~+W/ENCL MIPC~~W/3 ENCL EMERGENCY PLAN BR<<W/ENCL EEB44W/ENCL PLANT SYSTEMS BR4<W/ENCL AD FOR PLANT SYSTEMS4<W/ENCL REACTOR SAFETY BR~<M/ENCL VOLLMER/BUNCH+>W/ENCL POWER SYS BR++W/ENCL DISTRIBUTION:

LTR 44 ENCL 44 SIZE:

1P+ 1P TI IE END CONTROL NBR:

780870/00

~ 'e)

I"

ttEllNNO BOt',KEl FH.E COPY DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106 September 12, 1978

~.X-~y

< years yyl y1 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

Dear Mr. Keppler:

Operating License DPR-58 Docket No. 50-315 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 R.S.

Keith T.P.

Hei lman/J.L. Rischling Dir., IE (30 copies)

Dir., MIPC (3 copies) 780870300

NRC FORM 3P~s P.77Yj LICENSEE EVENT REPORT NUCI.EAR REGULATORY COMMISSION 7

8 CON'T

~o 7

8 CONTROL BLOCK:

Qi (PLEASE PRINT OR TYPE ALLREQUIRED INFORIVIATION)

I 6

N' D

C C

1 Q20 0

0 0

0 0

0 0

0 0

0 Q3 4

1 1

11 Qa~Qs 9

LICENSEE CODE s

14 15

~

LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 LUQB 0

3 1

5 7

o 8

1 4

7 8

QBO 9

I 2

7 8

Qg 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

~Og 7

8 SYSTEM

CAUSE

CAUSE COMP.

VALVE.

CODE CODE SUBCOOE COMPONENT CODE SUBCOOE SUBCOOE

~90 Q11 A

Gs

~AQ13 L

8 LJg ~ Gs 9

10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION LERIRO EVENT YEAR REPORT NO.

CODE TYPE NO.

Gs sssoss

~78

~

~04 9

~w

~09

~L

~0 21 22 23 24 26 27 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRO<

PRIME COMP.

COMPONENT TAKEN ACTION ON PLANT

=

METHOD HOURS Q22 SUBMITTED FORM SUB.

SUPPLIER MANUFACTURER Ois ~O

~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 ANDCORRECTIVE 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 METHOD OF OTHER STATUS ~

DISCOVERY 45 46 45 REQUIRING TIIRED RESPONSE.

7 8

9 FACILITY STATUS

% POWER s

E Qzs ~09 7 Qze NA 7

8 9

10 12 13 44 ACTIVITY CONTENT RELEASEO OF RELEASE AMOUNTOF ACTIVITY~

~ls

~Z Q33

~ZO34 NA 7

8 9

10 11 44 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39 v ~00 08 1

Oss NA 7

8 9

11 12 13 PERSONNEL INJURIES 7

8 9

11 12 LOSS OF OR DAMAGETO FACII.ITYQ43 TYPE

DESCRIPTION

9 Z

Q42 NA 7

8 9

10 PUBLICITY ISSUED DESCRIPTION~

~

~

L~JO44 NA l

7 8

9 10 NAME OF PREPARER John RBndol Ph LOCATIONOF RELEASE Q3B I'IA 80 80 80 80 80 80 NRC USE ONI.Y O

80 o

0 68 69 (616) 465-5901 DISCOVERY DESCRIPTION Q32 MANAGEt1ENT REV I EH