ML18219B561

Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Reports (RO 78-052/03L-0, RO 78-053/03L-0, RO 78-054-03L-0 and RO 78-055/03L-0)

ML18219B561
Person / Time
Site:	Cook
Issue date:	08/18/1978
From:	Shaller D American Electrtic Power System, Indiana Michigan Power Co
To:	James Keppler NRC/RGN-III
References
LER 1978-052-03L, LER 1978-053-03L, LER 1978-054-03L, LER 1978-055-03L
Download: ML18219B561 (10)

Text

DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106 Ob August 18, 1978 f~

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Mr. J.G. Keppler, Regional Director A

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Office of Inspection and Enforcement tg United States Nuclear Regulatory Commission Region III CA 799 Roosevelt Road Glen El lyn, 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 reports are submitted:

RO 78-052/03L-0 RO 78-053/03L-0 RO 78-054/03L-0 RO 78-055/03L-O.

Sincerely, D.V. Shaller Plant Manager

/bab cc: J.E. Dolan R.W. Jurgensen R.F. Kroeger R. Ki lburn 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 ] JG 911978 PNSRC J.F. Stietzel R.S. Keith T.P. Beilman/JUL. Rischling Dir., IE (30 copies)

Dir., MIPC (3 copies)

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NP)P FORhfiy6 ~S. NUCLEAR REGULATORY COMMISSION I7L7>

LlCENSEE EVENT REPORT CONTROL BLOCK: Q1 {PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

I 8 7 8 9 1 0 C C LICENSEE CODE 2

14 Q2 15 0 0 0 0 0 0 0 LICENSE NUMBER 0 0 0 0 Q34 26 1 1 LICENSE TYPE 1 1 30 ps~ps 57 CAT 58 CON'T

~ooff ioooos ~LL Qs 0 5 0 0 0 3 1 6 Q10 7 1 9 7 8 Qs0 8 1 8 7 8 Qs 8 68 69 EVENT DATE '74 75 REPORT DATE 6O 61 DOCKET NUMBER EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10

~o2 UNIT IN NODE 1 CONDUCTING SCHEDULED SURVEILLANCE TESTS. RHR PUHP SUCTION VALVE IHO-320 CYCLE TIt'1E EXCEEDED tlAXIHUN STROKE TINE OF 2 MIN. IN VIOLATION OF APP. A 4 TECH SPEC CRITERIA ESTABLISH IN 4.0.5. THE VALVE ttAS RETESTED AND OPERATED AT THE NORMAL TItlE CYCLE DETERMINED FROt1 PREVIOUS TESTS. THIS IS FIRST OCCURRENCE OF THIS

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~os TYPE. THIS EVENT HAD NO EFFECT ON THE HEALTH AND SAFETY OF THE PUBLIC.

~OS 80 7 8 9 SYSTEM CAUSE CAUSE If COMP. VALVE.

CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE

~Os ~CF Q11 X Q12 ~Z Q13 V A L V E X Q14 ~Epis ~0 Qs 7 8 9 10 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION EVENT YEAR REPORT NO. CODE TYPE NO.

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7 8 9 80 FACILITY STATUS 56 POWER OTHER STATUS Q METHOD OF DISCOVERY DISCOVERY DESCRIPTION Q32

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Q33 CONTENT RELEASED OF RELEASE

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44 45 I'lA LOCATION OF RELEASE Q 80 NUMBER TYPE DESCRIPTION Q39

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80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES ~10 DURING A PLAf'JNED UNIT SHUTDOlJN llITH TAE REACTOR IN OPERATIONAL MODE 2 THE AVERAGE COOLANT TEMP. DECREASED BELOW 541 QF TLJICE AND lJAS RECOVERED EACH TIffE. ONCE

'EACTOR 4 FOR A PERIOD OF 10 MIN. AND THE SECOND TIME FOR A PERIOD OF 9 MIN. THE I fINIMUM TEMP.

OF BOTH TRANSIENTS WAS 540.2 F. RECOVERY FROM EACH TRANSIENT lJAS WITHIN THE 15 MIN.

~o 6 ALLOWED BY TECH'PEC ~

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

CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE

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ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRDP PRIME COMP. COMPONENT TAKEN ACTION ON PLANT METHOD HOURS O22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER L~JQER ~NQER ~ZQER ~ZQEE 0 0 0 TI N Q22 ~NQ24 ~ZQ25 Z 9 9 9 Q24 33 34 35 36 37 46 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS &27 UNIT WAS UNLOADED FROM ~57K BY BORAQION TO STAY 'lJITHIN THE AXIAL FLUX TARGET BAND AND THEN HELD AT 4X FOR 53 HIN.'OR COOLING OF TURBINE METAL. CONTROL RODS klAD BEEN MAINTAINED TOO FAR OUT OF THE CORE TO COMPENSATE FOR THE XENON TRANSIENT ON POWER 3 REDUCTION.DURING FUTURE SHUTDOltNSCONTROL RODS W ILL BEDR I YEN FURTHER IN THE CORE 4 TO ASSURE REACTOR CONTROL 7,8 9 80 FACILITY STATUS

~00 95 POWER OTHER STATUS ~'AQEE

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12 Qs 13 NA 44 45 46 OPERATIONAL OBSERVATION ANO RLARN 80 6

ACTIVITY CONTENT RELEASED OF RELEASE

~Z Q33 ~ZQ34 AMOUNT OF ACTIVITY NA

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~l7 ~00 0 Q27 Z Qss NA 80 7 8 9 11 12 13 PERSONNEL INJURIES NUMBER DESCRIPTION 41

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,, 7 8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION Q43 2 Z Q42 NA 7 8 9 10 80 PUBLICITY

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NAME OF PREPARER R. S ~ LEASE PHONE. 61 6 465-5901 a

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'75 7 8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 REPORT DATE EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10 WITH THE REACTOR IN MODE 4 CONTAINMENT ISOLATION MANUAL VALVES DW211 AND

~O3 WERE OPENED IN VIOLATION OF TECH. SPEC. 3.6.1.1. THESE VALVES WERE OPENED TWO SEPARATE TIMES. REACTOR COOLANT SYSTEM TEMP. WAS 225'F AND PRES. OF 375 PSIG.

MAXIMUM OPEN TIME WAS 7 HOURS. TECH. SPEC. ACTION REQUIRES BEING IN MODE 3 WITHIN

~OB TOTAL OF 7 HOURS. UNIT WAS IN MODE 4 THROUGHOUT THIS EVENT.

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

CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE

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~Z 43 Q25 44 Z 9 9 9 47 Q26 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 o THE VALVES WERE OPENED UNDER ADMINISTRATIVE CONTROL FOR DECON. 'LEANIN WIT T ASSUMPTION THAT THIS WAS ALLOWED BY TECH. SPEC. 'AS S AND THE PERSON HAS BEEN CORRECTED, "A~ETECH. SPEC..REVISION. WILL BE REQUESTED TO ALLOW OPENING OF THESE VALVES UNDER ADMINISTRATIVE CONTROL SO DECON. WATER NEED NOT BE 4 TRANSPORTED BY BUCKET.

8 9 80

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DISCOVERY DISCOVERY DESCRIPTION Q2 7

8 8 9 0 QEE ~00 10 0

12 QEE 13 NA 44

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NAMC OF PREPARER . ~ LEASE PHDNE, 61 6 465 5901 43

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'0 61 5000 DOCKETNUMBER 3 16 68 07 69 0 7 2 EVENT DATE 6 7 8 74 Qs 75 0 8 1., 8~

REPORT DATE 7 8 80 QB EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10 IT SHUT DOWN FOR SCHEDULED OUTAGE. A TEMPORARY CHANGE SHEET WRITTEN FOR

~03 20HP4030STP017 ON JULY~!7,1'1978 WAS NOT REVIEWED BY PNSRC AND APPROVED BY

~04 PLANT MANAGER WITHIN 14 DAYS IN VIOLATION OF APPENDIX A TECH SPEC 6.8.3.C.

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VIOLATION DISCOVERED BY OPER. SUPT. ON JULY 26, 1978 AND TEMPORARY CHANGE

~oe PRESENTED TO PNSRC AND APPROVED BY PLANT MANAGER JULY 27, 1978 IDENTICAL

~0 7 OCCURENCES REPORTED IN LER 50-316/78-02 AND 78-034/L. NO ADVERSE EFFECTS

~0 s .ON HEALTH AND SAFETY OF THE PUBLIC.

7 8 9 80 SYSTEM CAUSE CAUSE COMP. VALVE.

CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE 7 8

~ZZ 9 10 Qll 11 A Q12 ~BQ12 12 13 Z Z Z Z Z Z Q4 18

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~HQID ~Z Q19 ~Z Q29 ~Z Q2'I 0 0 0 0 ~N Q22 ~NQ24 ~Z Q25 Z 0 Q28 33 34 35 36 37 49 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 o +F A GE OVER OF CLERICAL HELP IN .OPERATIONS DEPARTMENT RESULTED P E E TRAINING (IN METHOD"",'OF.

INSURE THEY ARE PRESENTED TO PNSRC AND PLANT MANAGER IN RE UIRED.TIME FRAME.

3 TEMPORARY EMPLOYEES REPLACED BY TWO PERMANENT EMPLOYEES AND REQUIRED TRAINING 4 OF NEW EMPLOYEES WAS CONDUCTED.

8 9 80 FACILITY METHOD OF STATUS  % POWER OTHER STATUS Q30 DISCOVERY DISCOVERY DESCRIPTION Q32

~ls E Q28 ~09 7 Q29 NA ~AQ31 OPER. SUPT. RECORD REVIEW 8 9 10 12 13 44 45 46 80 ACTIVITY CONTENT

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~Z 9 '0 RELEASED OF RELEASE Q33 ~ZQ34 PERSONNEL EXPOSURES NUMBER TYPE NA AMOUNTOF ACTIVITY DESCRIPTION Q39 44 45 NA LOCATION OF RELEASE 80 7 '"

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0 11 Q~ZQ28 12 13 NA 80 PERSONNEL INJURIES 7 8

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NUMBER 11 Q4o DESCRIPTIONQ41 12 NA 80 LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION Q43 Z O. NA 7 8 9 10 80 O

ISSUED LNl044 PUBLICITY DESCRIPTION ~ NRC USE ONI.Y 94 45 2

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