ML18219B558

Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report RO 78-058/03L-0

ML18219B558
Person / Time
Site:	Cook
Issue date:	08/30/1978
From:	Shaller D American Electrtic Power System, Indiana Michigan Power Co
To:	James Keppler NRC/RGN-III
References
LER 1978-058-03L
Download: ML18219B558 (7)

Text

QQ n4/of REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS >

DISTRIBUTION FOR INCOMING MATERIAl 50-316 REC: KEPPLER J G ORG: SHALLER D V DOCDATE: 08/30/78 NRC IN S. MI PWR DATE RCVD: 09/05/76 DQCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED

SUBJECT:

l TR 1 ENCL 1 FORWARD1NG LICENSEE EVENT REPT 9RO 50-316/78-053) ON 03/20/78 CONCERNING UNIT IN SCHEDULED OUTAGE AND HAD BEEN COOLED DOWN TO MODE 5... UNIT WAS HEATED UP h ENTERED t'IODE 3 WITHOUT HAVING A CURRENT QUARTERLY SURVEILLANCE TEST COMPLETED ON ECCS TRAIN A... V PLANT NAME: COOK "- UNIT 2 II REVIEWER INITIAL: XJM DISTRIBUTOR INITIAL:

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

NOTES:

i. SEND 3 COPIES OF ALL MATERIAL TO 15E INCIDENT REPORTS (DISTRIBUTION CODE A002)

FQR ACTION: B C<<<<W/4 ENCL INTERNAL: EG FILE<<<<W/ENC NAC PDR<<<<W/ENCL MIPC<<<<W/3 ENCL I 8c C SYSTEMS BR<<<<W/ENCL EMERGENCY PLAN BR+<<W/ENCL NOVAK/CHECK<<+W/ENCL EEB<<<<W/ENCL AD FOR ENG<<<<W/ENCL PLANT SYSTEMS BR<<<<W/EhlCL HANAUER+<<W/ENCL AD FOR PLANT SYSTEMS<<<<W/ENCL AD i=OR SYS lac PROJ<<<<W/ENCL REACTOR SAFETY BR<+W/EhlCL ENGINEERING BR<<+W/ENCL VOLLMER/BUNCH<<<<W/ENCL KREGER/J. COLI INS<<<<t J/ENCL POWER SYS BR<<<<W/ENCL K SEYFAIT/IE<<<<W/ENCL EXTERNAL: LPDR~S ST. JOSEPH M I <<<<W/ENCL NSIC<<<<W/ENCL ACRS CAT B<<<<W/16 ENCL DlSTRIBUTION: LTR 44 ENCL 44 CONTROL NBR: 7824801 0 I

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C c cnn August 30, 1978 ~C CD Mr. J.G. Keppler, Regional Director Office of Inspection and Enforcement United States Nuclear Regulatory Conmission Region III 799 Roosevelt Road Glen Ellyn, IL 60137 Operating License DPR-74 Docket No. 50-316

Dear Mr. Keppler:

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

RO 78-05'8/03L-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.

J.M. Kennigan G. Olson PNSRC J.F. Stietzel R.S. Keith T.P. Beilman/J.L. Rischling Dir., IE (30 copies)

Dir., MIPC (3 copies)

NRC FORM 366 U. S. NUCLEAR REGULATORY COMMISSION I7-7+-~

LICENSEE EVENT REPORT CONTROL BLOCK: Qi (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6 7 8 9 M I D C LICENSEE CODE C 2Q20.0 14 15 0 0 0 0 0 LICENSE NUMBER 0 0 0 0 25 Q74 26 1 1 LICENSE TYPE 1 I 30 Qo~ps57 CAT 58 CON'T 0 8 ' 7 8 Q

~O 7 8 soURcE ~LO 60 61 0 5 0 0 0 DOCKET NUMBER 3 1 6 68 Q 69 0 8 0 2 EVENT DATE 7 8 74 Qs 75 IO REPORT DATE EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Qlo UNIT IN SCHEDULED OUTAGE AND HAD BEEN COOLED DOMN TO MODE 5. THE UNIT I,'tAS HEATED UP

~o3 AND ENTERED MODE 3 MITHOUT HAVING A CURRENT QUARTERLY SURVEILLANCE TEST COMPLETED ON

~o4 EMER. CORE COOLING SYSTEM TRAIN A IN VIOLATION OF APP. A TECH SPEC 4.0.5. UNIT l'!AS 7

~o5 COOLED TO MODE 4 AND REQUIRED SURVEILLANCE TEST COMPLETED '.lITH NO DISCREPANCIES

~O6 FOUND. TRAIN B SURVEILLANCE 'l'tAS CURRENT WITH NO OUTSTANDING DEFICIENCIES. THIS IS

~o7 FIRST EVENT OF THIS TYPE. THE HEALTH AND SAFETY OF THE PUBLIC WERE NOT AFFECTED.

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

CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE

~OB 7 8

~ZZ 9 10 Q77

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~AQ73 12 13 Z Z Z Z Z Z p4 18

~Zp15 19 o

~Z 20 Q7s SEQUENTIAL OCCURRENCE REPORT REVISION, Q>>

LF R(RO osooo7 ACTION FUTURE EVENT YEAR

~ID 21 22 EFFECT

<23 SHUTDOWN

~OS 24 REPORT NO.

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, CODE

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28 ATTACHMENT 29 NPRDC TYPE Q

30 PRIME LJ 31 '2 COMP.'OMPONENT NO.

TAKEN ACTION ON PLANT METHOD HOURS +22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER

~ZQ>> 0 0 W ~YQ23 ~NQ24 ~ZQ25 Z 9 9 9

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~CQ2O 36 37 44 47 Q26 33 35 40 41 42 43 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 o THE CAUSE OF THIS EVENT MAS FAILURE TO REVERIFY THAT ALL REQUIRED SURVEILLANCE TESTS

,MERE CURRENT, PRIOR TO CHANGING FROM MODE 4 TO MODE 3 'AFTER 4 PLANNED HEATUP HAD BEEN 2 STOPPED FOR SEVERAL DAYS. PLANT HEATUP PROCEDURE REVISED TO REQUIRE REVERIFICATION OF SURVEILLANCE STATUS IF HEATUP IS DELAYED FOR WORE THAN 24 HOURS.

1 '4 80 7

s 8 9 FACILITY STATUS

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% POWER 0 Qoo NA OTHER STATUS ~ 'AQ77

~gO,'ISCOVERY METHOD OF DISCOVERY DESCRIPTION PRODUCTION SUPV. RECORD REVTEN 7 8 9 10 12 13 44 45 80

~16 ACTIVITY Z Q33 CONTENT RELEASED OF RELEASE Z Q34 NA AMOUNTOF ACTIVITY ~ NA LOCATION OF RELEASE Q 7 8 9 , 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION QSB

~l7 ~00 0 Q37 Z Qos 13 NA 80 7 8 9 11 12 PERSONNEL INJURIES NUMBER DESCRIPTIONQ41 s ~00 0 Qoo NA 80 7 8 9 11 12 LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION Q43 o ~ZQ47 NA 7 8 9 10 80 PUBLICITY NRC USE ONLY ISSUED DESCRIPTION Q o o ~Qo 80 8 9 10 oo 465-5901 0 NAME OF PREPARER R. S. Keith (616) a os

0 SUPPLEMENT ~

I CAUSE DESCRIPTION AND CORRECTIVE ACT'ION Unit 2 has started heating up to return from a scheduled outage on July 24, 1978.

On July 24, 1978 all required surveillance tests were current for entering Mode 3. On July 25, 1978 the decision was made to extend the outage approximately 10 days to effect additional modifications to the Moisture Separator Reheaters and the heatup was stopped and the plant held in Mode 4.

On August 1, 1978 plans were made to continue the reactor plant heatup to normal operating conditions. The Shift Operating Engineer (SOE), with the concurrence of the Production Supervisor-Operations, who was acting as the Outage Coordinator, continued with the heatup and the checkoff list that had been started on July 24, 1978 without having reverified that all required surveillance tests were current. The Production Supervisor -Operations gave permission to the SOE to enter Mode 3 based on the SOE telling him he had a signed off checkoff list indicating he could go to Mode 3 even though he did not have the completed sur-veillance sheet in hand. llhen the Production Supervisor-Operations then reviewed the file he found that the surveillance, which was current for the heatup on July 24, 1978, had expired and was not satisfactory for the heatup on August 1, 1978.

Unit 1 had entered Mode 3 at 0702 on August 2, 1978. At the direction of the Production Supervisor-Operations, Unit 2 was back in Mode 4 at 1009 August 2, 1978 and the required surveillance test was in progress.

The required test was completed with no discrepancies noted and the heatup was restarted. Unit 2 again entered Mode 3 at 1247 on August 2, 1978.

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