ML18219C265

LER-1977-003-00 for Donald C. Cook, Unit 1 - the Inservice Residual Heat Removal (RHR) Loop Was Removed from Service for 2 Hours and 10 Minutes in Violation of Technical Specification 3.9.8

ML18219C265
Person / Time
Site:	Cook
Issue date:	02/02/1977
From:	Jurgensen R American Electric Power Service Corp, Indiana Michigan Power Co, (Formerly Indiana & Michigan Power Co)
To:	James Keppler NRC/IE, NRC/RGN-III
References
LER-1977-003-00
Download: ML18219C265 (6)

Text

U.S. NUCLEAR REGULATORY COMMISSION DOCKET NUMBER NRC Fa9M 195

~I2.781 FILE NUMBER

.NRC DISTRIBUTION FoR PART 50 DOCKET MATERIAL t INCIDENT REPORT FROM: DATE OF DOCUMENT J G Keppler Indiana & Michij n Pwr Co 2-2-77 Bridgman, Michi)an DATE RECEIVED R W Jurgensen 2 15 77

~ETTER .. ONOTORI2ED PROP INI UT FORM NUMBER OF COPIES RECEIVED

- '/ORIGINAL Jc9fNCLASSIFIED - one signed

~HCOPY DESCRIPTION ENCLOSURE.

Ltr trans the following:

concering xemova1-o f~sidQal heat xemoVal loop in excessive. Of time allow~ed 'per tech specs due to personnei errors ......

lp PLANT NAME- Cook gl NOTE: IP PERSONNEL EXPOSURE IS INVOLVED SEND DIRECTLY TO KREGER/Jo COLLINS

... .FORACTION/INFORMATION i1 BRANCH CHIEF!

W 3 CYS FOR ACTION LIC,"ASSTo!

=. =W- .=,i CYS GRS CYS RC~HC S NT --5'

'NTERNAL D ISTR I BUTION sl ~

Q: REG-.F IL

.. ~~

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.NRC PDR

= M=.6r=E (2 MIPC SCHROEDER/IPPOLITO HOUSTON NOVAK/CHECK GRIMES CASE BUTLER HANAUER TEDESCO/MACCARY EISENHUT BAER SHAO VOLUIER/BUNCH KREGER/J COLLINS EXTERNAL DISTRIBUTION CONTROL NUMBER LPDR!. J 05@

TIC!

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j4d/

NRC FORM I96 I2.76)

C 1

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lo DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106 February 2, 1977 ef FEST,

~as'~ ~ t$ 7M 8

~(~~jjproe Afar s Nr. 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 Nr. Keppler:

Pursuant to the requirements of Appendix A Technical Specifications and the United States Nuclear Regulatory Commission Regulatory Guide

1. 16, Revision 4, Section 2.a, the following report is submitted:

RO 50-315/77-03 Sincerely,

. W. Jur nse Plant Na ager RWJ/mj cc: R. S. Hunter'.

~ggO 00 ~ac E. Dolan u~

G. E. Lien qo t t R. Kilburn gpss lb ~qo4 R, J. Vollen BPI R. C. Callen HPSC K. R. Baker RO: III R. Walsh, Esq.

P. W. Steketee, Esq.

G. Charnoff, Esq.'.

Olson J. N. Hennigan PNSRC R. S. Keith Dir., IE (40 copies)

Dir., HIPC (4 copies)

FEB 3 '1977

t vp 4

'J 8

%P A

L(CENBEE EVENT REPORT/

CONTROL BLOCK fPLEASE PRINT AU. REQUIRED INFQRIVIATION)

UCENSEE UCENSE EVENT NAME UCENSE NUMBER TYPE TYPE

[oa~] NI 0 C C 1 0 0 0 00 0 0 0 0 A 1 1 1 1 ~01 7 89 14 15 25 26 30 31 32 REPORT REPORT CATEGORY TYPE SOUACE COCKET NUMBER EVENT OATE REPORT OAl'E

~01 GQN'7~ LLI ~[ 0 5 0 0 3 1 5 0 1 1 9 7 7 0 2 0 1 7 7 7 8 57 58 59 60 61 68 69 74 75 BO I

EVENT DESCRIPTION Jog THE INSERV ICE RESIDUAL HEAT REMOVAL (RHR) LOOP L'tAS REMOVED FROM SERVICE FOR 2 HOURS 7 89 80 AND 10 MINUTES IN VIOLATION OF TECHNICAL SPECIFICATION 3. 9.8 ACTION ITEM (b) l'lHICH 7 89 PERMITS REMOVAL OF THE RHR LOOP FOR UP TO 1 HOUR PER 8 HOUR'ERIOD DURING PERFORMANCE 80'oO4]

7 8 9 80 I005 OF RE ALTERATIONS. CORE ALTERATIONS MERE IN PROGRESS.

7 8 9 80 tOO~] R-RO 15 77-03 7 8 9 PAME 80 SYSTEM CAUSE COMPONENT COMPONENT CODE COOE COMPONENT COOE SUPPUER MANUFACTURER

[oa']~CF ~A Z Z Z Z Z Z Z Z Z Z Z 7 8 9 10 11 12 17 43 44 47 48 CAUSE OESCFIIPTION 7

Qg8 9 THE OPERATOR LOST TRACK OF THE TIME THAT. HAD PASSED SINCE THE RHR LOOP HAD BEEN 80

~09 REMOVED FROM SERVICE.

7 8 9 '80

,7 89 FACAJIY METHOD OF 80 STATUS  % POWER OTHEA STATUS OISCOVEAY OISCOVERY DESCRIPTION N ~00 0 N A. N.A.

7 8 9 10 12 13 44 45 46 80 FOAM OF ACTIVITY COATENT RELEASEO OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE Q~2 Z ~Z N.A.

~ 7 8 9 "

10 11 44 45 80 PERSONNEL EXPOSURES .

NUMBEA TYPE OESCRIPTION

~I3 ~00 0 Z N.A.

7 89 11 12 1g BO PERSONNEL INJURIES NUMBEA DESCRIPTION 7 89 11 12 80 PROBABLE CONSEQUENCES Q~g 7 89 80 LOSS OR DAMAGE TO FACILITY TYPE OESCRIPTION Z N.A.

7 89 10 PUBLICITY N.A.

89 80 ADDITIONAL FACTORS Q~B CONTROL OF THIS OPERATION IS NOW UNDER THE DIRECT SUPERVISION OF THE SENIOR REACTOR 7 89 Q~ 9 OPERATOR IN CHARGE OF CORE ALTERATIONS.

7 89 80 NAME PHDNE 1 055-5901 SPO SSI- aaV

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