05000316/LER-2078-063-03, Letter Enclosure of Licensee Event Report

Letter Enclosure of Licensee Event Report

ML18219B521
Person / Time
Site:	Cook
Issue date:	09/19/1978
From:	Shaller D American Electrtic Power System, Indiana Michigan Power Co, (Formerly Indiana & Michigan Power Co)
To:	James Keppler NRC/RGN-III
References
LER 1978-063-03L
Download: ML18219B521 (5)

LER-2078-063, Letter Enclosure of Licensee Event Report

Event date:
Report date:
3162078063R03 - NRC Website

text

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS >

DISTRIBUTION FOR INCOMING MATERIAL 50-316 REC:

KEPPLER J G

ORG:

SIIALLER D V

DOCDATE: 09/19/78 NRC IN 5 MI PWR DATE RCVD: 09/22/78 DOCTYPE:

LETTFR NOTARIZED:

NO COPIES RECEIVED

SUBJECT:

LTR 1

ENCL 1

FORWARDING LICENSEE EVFNT REPT (RO 50-316/78-063)

ON 08/20/78 CONCERNING WHILE TE T CLO ING TURBINE VALVE WERE AT 99/

PWR TEAM FLOW WAS REDUCED CAU ING REACTOR COOLANT TEMP.

TO INCREASE TO 557 DEGREE F AND PRESSURE TO DECREASE TO 2105 PSIA VIOLATING PLANT NAME: COOK UNIT 2 REVIEWER INITIAL:

XJM DISTFiIBUTOR INITIAL:RM

++++<<<<+++>.>w44+4~<<DISTRIBUTION OF THIS MATEI"IAL I AS FOLLOWS NOTES:

i.

SEND 3 COPIES OF ALL MATERIAL TO ISE INCIDENT REPORTS (DISTRIBUTION CODE A002)

FOR ACTION:

INTERNAL:

BR CHIEF ORB81 BC+4W/4 ENCL G

<<+W/ENCL 5 E~<<nW/4 ENCL I

8(

C SYSTEMS BR44W/ENCL NOVAK/CHECKHW/ENCL AD FOR ENG<<~W/ENCL HANAUER~<<W/ENCL AD FOR SYS 5 PROJ4+W/ENCL ENOI NEER ING BR+~W/ENCL KREGER/J.

COLLINS+4<<Ii/ENCL K SEYFR IT/IE+4W/ENCL NRC PDR~~W/ENCL MIPC~%W/3 ENCL EMERGENCY PLAN BR+<W/ENCL EEB++W/ENCL PLANT SYSTEMS BR+<W/EhlCL AD FOR PLANT SYSTEMS>>W/ENCL REACTOR SAFETY BR4<W/ENCL VOLLMER/BUNCII~4 l4/ENCL POWER SYS BR++W/ENCL EXTERNAL:

LPDR S ST.

JOSEPH MI~<<4 W/ENCL NSIC+<W/ENCL ACRS CAT B+4W/16 ENCL LTR 44 ENCL 44 DI Tf;IBUTION SIZE:) 1P+1P

%4%%4%%% 4 4%%%%%%%-k%% %%%4%%%%%4%%%4%

CONTROL NBR:

780810 66 THE END

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!~.IIIIILLILIIIIIIIIIIILIIIIY1IIIIIIII DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106 September 19, 1978 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 C3

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Operating License DPR-74 Docket No. 50-316

Dear Nr. Keppler:

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

RO 78-063/03L-O.

Sincerely, D.V. Shaller Plant Manager

/bab cc:

J.E.

Dolan R.M. Jurgensen R.F.

Kroeger R. Kilburn R.J.

Vollen BPI K.R. Baker RO: I II R.C. Callen MPSC P.W. Steketee, Esq.

R. Malsh, Esq.

G. Charnoff, Esq.

G.

Olson J.H.

Henni gan PNSRC J.F. Stietzel R.S. Keith T.P. Beilman/JUL. Rischling Dir., IE {30 copies)

Dir., HIPC

{3 copies) bcc:

R.L. Dudding "L.J. Matthias D.D. Nelson E.A. Smarrella 780810266

J (777)'t I

P CONTROL BLOCK:

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,Q (PLEASE PRINT OR TYPE ALLREQUIRED INFORMATION]

V 0 I'VUl 4LtiII II ORT LICENSEE EVENT REP

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D C

C LICENSEE CODE 4444 [L JOI 0

5 0

0 0

3 1

5 00 8

2 60 61 DOCKET NUMBER 68 69 EVENT DATE EVENT DESCRIPTION ANO PROBABLE CONSEQUENCES Q10 WHILE TEST CLOSING TURBINE VALVES AT Qs 74 75 REPORT DATE 80 Oe 2 QI0 0

0 0

0 0

0 0

0 0

0 QI4 1

1 1

I 04~OR 14 15 25 26 LICENSE TYPE 30 57 CAT 58 REACTOR COOl ANT TEMP ~

TO INCREASE TO 577oF AND PRESSURE T

D IN VIOLATION OF TECH.

SPEC.

3.2. 5.

MAXIMUMTIME IMIT E

~OS ACTION REQUIRES RETURNING TO WITHIN LIMITS WITHIN TWO HOURS.

NO PROBAB E

~06 CONSE IJENCES.

~07

~08 80 7

8 SYSTEM

CAUSE

CAUSE CODE CODE SUBCOOE

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0>>

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9 10 ll 12 13 SEQUENTIAL LFR)RO EVFNT YEAR REPORT NO.

Qll I RORI ~78

~

~05 3

21 22 23 24 26 ACTION FUTURE EFFECT SHUTDOWN TAKEN ACTION ON PLANT METHOD HOURS

~GQIB ~GQe

~ZQ2o

~ZQ2'3 34 35 36 37 CAUSE DESCRIPTION ANO CORRECTIVE ACTIONS Q27 o

THE CAUSE OF THIS EVENT WAS TESTING VALVE

~oe 7

8 COMP.

VALVE COMPONENT CODE SUBCODE SUBCOOE Q14 I~ Q15 ~

Q16 18 19 20 OCCURRENCE REPORT REVISION CODE TYPE Np.

~03

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~

LoJ 27 28 29 30 31 32 Q

ATTACHMENT NPADP PRIME COMP.

COMPONENT 22 SUBMITTED FORM SUB.

SUPPI.IER MANUFACTUAEA LJOII mOI4

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9 9

9 QII 40 41 42 43 44 47 ATT H

TURBINE VALVE TESTS WILL BE AT A REDUCED P

W R

TECH.

SPEC.

3.2. 5 ALLOWS FOR A POWER INCREASE TRANSIENT.

W T

A TECH.

SPEC.

REVISION TO ALSO ALLOW FOR A POWER DECREASE TR 4

7 8

9 FACILITY STATUS

'fi PolVER OTHERSTATUS 0 5

~E Q28 L(~~Q2e 7

8 9

10 12 Ig 44 ACTIVITY CONTENT AELEASED OF RELEASE AMOUNTOF ACTIVITYQ35 6

~Z Q33

~ZQ34 NA 8

9 10 11 44 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39

~ll I ~00 0

QOI 2

QOI NA 7

i 8

9 II 12 13 PERSQNNCL INJURIES NUMBER DESCRIPTIONO41

~JQJQ4o 7

18 9

11 12 LOSS OF OR DAMAGETO FACILITYQ43 TYP E

DESCRIPTION

7 8'9 10 PUBLICITY ISSUco DESCRIPTION Q5 o

~NQ44 NA 7

8 9

10 NAME OF PREPARER R.S.

L METHOD OF DISCOVEAY MQ31 45 46 NA 45 LOCATION OF RELEASE Q 80 80 80 80 80 NRC USE ONLY II I

80 o OIP" 68 69 PHDNE'16 465 5901 DISCOVERY DESCRIPTION Q32

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