05000316/LER-2078-022-01, T Re Higher Calculated Peak Clad Temperature

T Re Higher Calculated Peak Clad Temperature

ML18219C203
Person / Time
Site:	Cook
Issue date:	04/07/1978
From:	Shaller D Indiana Michigan Power Co
To:	James Keppler NRC/RGN-III
References
LER 1978-022-01T
Download: ML18219C203 (6)

LER-2078-022, T Re Higher Calculated Peak Clad Temperature

Event date:
Report date:
3162078022R01 - NRC Website

text

og i1 <9 REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

DIS'IRIBUTION FOR INCOMING MATERIAL 50-315 REC:

KEPPLER J G

NRC ORG:

SHALLER D V

IN 5 MI PWR DOCDATE: 04l07l78 DATE RCVD: 04/14/7 DOCTYPE:

LETTER NOTARIZED:

NO COPIES RECEIVED

SUBJECT:

LTR 1

ENCL FORWARDING LICENSEE EVENT REPT (RO 50-315/78-022/01T-0)

ON 03/23/78 CONCERNING WEST1NGHOUSE" S FRENCH LICENSEE FRAMITONE IDENTIFIED A LOGIC INCONSISTENCY IN THE NRC APPROVED APPENDIX K ECCS CALCULATION MODEL WHICH RESULTS IN A HIGHER CALCULATED PEAK CLAD 7~~> +<+ 7

<e'LANT NAME: COOK UNIT 1

REVIEWER INITIAL:

XJM DISTRIBUTOR INITIAL:~

++<~++++<~++++<~<~+~>+ DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS INCIDEN'1 REPORTS (DISTRIBUTION CODE A002)

FOR ACTION:

INTERNAL:

EXTERNAL:

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COPIES NOT SUB)lITTED PER REGULATORY GUIDE 10.1 DISTRIBUT10N:

LTR 45 ENCL 45 SIZE:

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THE END

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4'O Wmorloon INDIANA& MICHIGANPOWER COMPANY DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106 April 7, 1978 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

Dear Mr. Keppler:

Operating License DPR-58 Docket No. 50-315 Pursuant to the requirements of the Appendix A Technical Specifications, the following report is submitted:

RO 78-022/01T-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.

G.

Olson J.M. Hennigan PNSRC J.F. Stietzel Dir., IE (40 copies)

Dir., MIPC (4 copies) p,pp ],0 1978

1

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NRC FORM 366

{7.77)

U. S. NUCLEAR REGULATORY COMMISSION

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1 5 Q 60 61 DOCKET NUMBER 68 69 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10 This re ort is also a

licable to th QB 3

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80 EVENT DATE 74 75 REPORT DATE LICENSEE EVENT REPORT Q1 tPLEASE PRINT OR TYPE ALLREQUIRED INFORMATION) 6 0

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1 1 QE~QE 25 26 LICENSE TYPE 30 57 CAT 58

~O3 No. 050-316.

On March 23, 1978 f. Morris of Westin house notified the D..

Coo Plant of the fol1owin occurrence.

farl in March Westin house'

~OS Framitone, identified a lo ic inconsistenc in the NRC a roved A

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~OB Calculational Model which results in a hi er al u

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CODE TYPE NO.

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0 21 22 23 24 26 27 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRDR PRIME COMP.

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SUPPLIER MANUFACTURER

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Refer to Mr. G.P.

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letter details the problem and interim corrective actions.

3 METHOD OF DISCOVERY

~Q31 45 46 45 J.F. Stietzel/J. L Rischling NAME OF PREPARER 4

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9 FACILITY STATUS

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8 9 '0 11 44 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39

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11 12 13 PERSONNEL INJURIES NUMBER OESCRIPTIONQ41 8

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