05000316/LER-1980-001, Forwards Updated LER 80-001/03X-1

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: 05000316/LER-1980-001, Forwards Updated LER 80-001/03X-1
References
NUDOCS 8006120300
Download: ML17318A795 (4)

LER-1980-001, Forwards Updated LER 80-001/03X-1

Event date:
Report date:
3161980001R00 - NRC Website

text

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INDIANA& MICIIIGANEIECTRIC COMPANY DONALDC. 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 W. Lavallee EPRI PNSRC J.F. Stietzel E.L. Townley Dir., IE (30 copies)

Dir., MIPC (3 copies)

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NR ORM 366 (7.

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8 CON'T

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8 "UPDATE REPORT PREVIOUS REPORT DATE 2/6)45'CENSEE EVENT REPORT Qi (PLEASE PRINT OR TYPE ALLREQUIRED INFORMATION) 6 2 Q20 0

0 0

0 0

0 0

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14 15 LICENSE NUMBER r<

CONTROL BLOCK:

I M I D

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9 LICENSEE CODE 6

0 QB REPORT DATE 80 soURGE ~LQB 0

5 0

3 1

6 07 0

1 1

9 8

0 QB 0

60 61 DOCKET NUMBER EVENT DATE 74 75 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 AUXILIARYFEED 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 INCLUDE 79-165 AND 79-147.

~OB 80 7

8 SYSTEM

CAUSE

CAUSE 4

COMP.

VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE

~ZZ Qll X

Q12

~XQ12 Z

Z Z

Z Z

Z Q14

~ZQEE

~Z Qs 7

8 9

10 11 12 l3 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION LF RiRP EVENT YEAR REPORT NO.

CODE TYPE NO.

Q17 REPORT

~80

~

~00 1

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~03

~X

~

1 21 22 23 24 26-27 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRDP PRIME COMP.

COMPONENT TAKEN ACTION ON PLANT METHOD HOURS Q22 SUBMITTED FORM SUB.

SUPPLIER MANUFACTURER Ols ~iOls

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~~ORE 0

0

~ O22

~04

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0 0

0 Oss 33 34 35 36 37 40 41 42 43 44 47 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.

7 8

9 FACILITY STATUS JI POWER OTHER STATUS Q

~ls

~C Q22 ~01 0

Q22 NA 7

8 9

10 12 13 44 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNTOF ACTIVITY

~6 Z

Q33

~ZQ34 NA 7

8 9

10 44 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39

~00 0

Qsl Z

Oss NA 7

8 9

11 12 13 PERSONNEL INJURIES NUMBER DESCRIPTION Q41 2

~OO O

Q4o NA 8

9 11 12 LOSS OF OR DAMAGETO FACILITY 43 TYPE

DESCRIPTION

Z Q42 NA METHOD OF DISCOVERY DISCOVERY DESCRIPTION Q32

~AQ31 OPERATOR OBSERVATION 45 46 LOCATIONOF RELEASE Q NA 45 80 80 80 80 80 7

8 O

9 10 PUBLICITY ISSUED DESCRIPTION~

JQ44 NA NRC USE ONLY 80 8

9 10 NAME OF PREPARER C.E.

MURPHY 68 69 80' (616) 465-5901 X-316

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