ML17318A795

Forwards Updated LER 80-001/03X-1

ML17318A795
Person / Time
Site:	Cook
Issue date:	06/04/1980
From:	Shaller D INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML17318A796	List: ML17318A795 ML17318A797
References
NUDOCS 8006120300
Download: ML17318A795 (4)

Text

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INDIANA & MICIIIGANEIECTRIC COMPANY DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106 (616) 465-5901 June 4, 1980 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 Operating License DPR-74 Docket No. 50-316

Dear Mr. Keppler:

Pursuant to the requirements of the Appendix A Technical Specifications, the following report/s are submitted:

RO 80-001/03X-l.

Sincerely, D.V. Shaller Plant Manager

/bab cc: J.E. Dolan R.S. Hunter R.W. Jurgensen R.F. Kroeger R.W. Kilburn R.E. Masse RO:III R.C. Callen MPSC G. Charnoff, Esq.

G. Olson J.M. Hennigan /os~

W. Lavallee EPRI 5 PNSRC J.F. Stietzel E.L. Townley Dir., IE (30 copies)

Dir., MIPC (3 copies)

/dos(z.oooo.

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ORM 366 NR "UPDATE REPORT PREVIOUS REPORT DATE (7. 2/6)45'CENSEE EVENT REPORT r<

CONTROL BLOCK: Qi (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

I 6

~O 7 8 9 M I D LICENSEE CODE C C 2 14 Q20 15 0 0 0 0 0 LICENSE NUMBER 0 0 0 0 CON'T

('O soURGE ~LQB 0 5 0 3 1 6 07 0 1 1 9 8 0 74 QB 75 0 6 0 REPORT DATE 80 QB 7 8 60 61 DOCKET NUMBER EVENT DATE EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10 WHILE IN THE PROCESS OF PERFORMING A 0 POWER LEVEL APPROXIMATELY 10% 0 THE OPERATORS WERE CHANGING FEEDWATER FROM AUXILIARY FEED TO -NORMAL FEED. THE STEAM GENERATORS WERE INADVERTENTLY FED TOO

~OS MUCH FEEDWATER FLOW. THIS RESULTED IN A DROP IN TAVE TEMPERATURE TO 539 F AND A PRESSURIZER PRESSURE OF 2170 PSIG WHICH CULMINATED WITH A REACTOR AND TURBINE TRIP. THIS IS CONTRARY TO TECH. SPEC. 3.1.1.5 AND 3.2.5.b. SIMILIAR OCCURRENCES

~OB INCLUDE 79-165 AND 79-147.

80 7 8 SYSTEM CAUSE CAUSE 4 COMP. VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE

~ZZ 9 10 Qll X Q12 ~XQ12 12 l3 Z Z Z Z Z Z 18 Q14 ~ZQEE 19

~Z 20 Qs 7 8 11 SEQUENTIAL OCCURRENCE REPORT REVISION Q17 LF RiRP REPORT ACTION FUTURE EVENT YEAR

~80 21 22 EFFECT

~

23 SHUTDOWN

~00 24 REPORT NO.

1 26-

~W 27 ATTACHMENT

~03 28 CODE 29 NPRDP TYPE

~X 30 PRIME COMP.

~

31 NO.

32 1

COMPONENT TAKEN ACTION 33 Ols ~iOls 34 ON PLANT

~>OEO 35 METHOD

~~ORE 36 37 0

HOURS Q22 0

40

~

SUBMITTED 41 O22 FORM SUB.

~04 42 SUPPLIER

~iOEs 43 44 MANUFACTURER z 0 0 0 47 Oss CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 o DURING THIS PHASE IN THE UNIT START-UP STEAM GENERATOR LEVELS ARE CONTROLLED MANUALLY. TO RECOVER A LOW STEAM GENERATOR LEVEL THE STEAM GENERATOR WAS OVER-FED CAUSING AN INCREASE IN THE LEVEL TO THE HIGH LEVEL TRIP POINT. THE 3 EXCESSIVE AMOUNT OF COLD WATER RESULTED IN THE DECREASE IN REACTOR COOLANT SYSTEM 4 TAVE AND PRESSURE. NO FURTHER ACTION PLANNED.

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

~ls ~C Q22 ~01 10 0

12 Q22 13 NA 44

~AQ31 45 46 OPERATOR OBSERVATION 80 7 8 9 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE Q

~6 7 8 9 Z Q33 ~ZQ34 10 NA 44 45 NA 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39

~00 0 Qsl Z Oss 12 13 NA 80 7 8 9 11 PERSONNEL INJURIES NUMBER DESCRIPTION Q41 2 ~OO O Q4o NA 80 8 9 11 12 LOSS OF OR DAMAGE TO FACILITY 43 TYPE DESCRIPTION Z Q42 NA 8 9 10 80 7

O ISSUED PUBLICITY JQ44 DESCRIPTION NA

~ NRC USE ONLY 10 68 69 80' 8 9 C.E. MURPHY (616) 465-5901 X-316 NAME OF PREPARER

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