ML20084T849

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LERs BFRO-50-259/7627 & BFRO-50-260/7618:on 770119,GE Advised Util That MAPLHGR Limits Must Be Reduced to Ensure Peak Clad Temp Less than 2,200 F.Caused by Input Discrepancies in 10CFR50.46,App K Analyses
ML20084T849
Person / Time
Site: Browns Ferry  
Issue date: 02/04/1977
From: Fox H
TENNESSEE VALLEY AUTHORITY
To: Moseley N
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20084T851 List:
References
BFRO-50-260-761, LER-BFRO-50-259-762, NUDOCS 8306240197
Download: ML20084T849 (2)


Text

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g l W2 have been advised by the General Electric Company that the MAPLHGR limits for e

Browns Ferry units l and 2 must be reduced to ensure that the peak clad temperature 60 o

'g l' calculated in conformance with 10 CFR50.46 is less than 2200 F.RevisedMAPLEGRcurveg O9 80 g l have been installed in the unit 1/2 process computer and will remain in effect until l

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@l 80 7 09 ADOITIONAL FACTORS ta l Revised curves were submitted to NRC on January. 19, 1977.

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Mr. Norman C. Moseley, Director 1

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p Atlanta, Ceorgia 30303 ees Dear Mr. Moselays yyy TENNESSEE VALLEY AUTHORITY - BROWNS FERRY NUCLEAR PLANT UNITS 1 AND 2 -

DOCKET NOS. 50-259 AND 50-260 - FACILITY OPERATING LICENSES DPR-33 AND DPR REPORTABLE OCCURRENCE REPORTS BFRO-50-259/7627 AND BFRO-50-260/7618 The enclosed report is to provide details ceacerning the MAPLIICR limits for Browns Ferry units 1 and 2 thnt must be reduced to ensure that the peak clad temperature calculated in conformance with 10 CFR 50.46 is less than 0

l 2200 F.

This is a follovup of our December 21,1976, letter. This report is submitted in accordance with Browns Ferry Technical Specifications Section 6.

This event occurred on Browns' Ferry Nuclear Plant units 1 and 2.

Very truly your's, TENNESSEE VALLEY AUTHORITY E. S. Fox Director of Power Production Enclosure (3)

CC (Enclosure):

Director (3)

Office of Management Information and Program Control

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U.S. Nuclear Regul'atory Commission Washington,D.C.f20555 Director J 0)

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l l"5fB l We have beeninforrned by General Electric Company that the revised analyses show that 7 89 l

I33l l the results of 'the p'reviously reported input errors to the ECCS analyses is less than 80

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7 89 15, 1976, to further discuss this matter]

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December 21, 1976 t

Mr. Norman C. Moseley, Director U.S. Waelaar Regulatory em mfmaism Office of Inspection and Enforcement Region II 230 Peachtree Street, NW., 8th Floor Atlanta, Georgia 30303

Dear Mr. Moseley:

TENNESSEE VALLEY AUTHORITY - BROWNS FERRY NUCLEAR PLANT UNITS 1 AND 2 -

DOCEET NOS. 50-259 AND 50-260 - FACILITY OPERATINC tTern " S DPR-33 nr*0RTABLE OCCURRENCE REPORTS BFR0 Q 9/762) AND AND DPR 41

{0-50-260/76 The enclosed report is to provide details concerning the revised analyses that show the results of the previously reported input errors to the ECCS analyses to be less than 1 percent. Based on these results, units 1 and 2 operation has been determined to be unaffected by the previously reported input errors. This report is submitted in accordance with Browns Ferry Technical Specifications Section 6.

This event occurred on Browns Ferry Nuclear Plant units 1 and 2.

Very truly yours.

TENNESSEE VALLET ADTHORITY E. S. Fox Director of Power Production Emelosure (3)

CC (Emalosure):

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Director (3) 1 Office of Manage t Information and Program Control 4

2 U.S. Buelear Raqslatory Commission Washington, D.C.

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Offiae of Inspection and Enforcement U.S. Wualear Regulatory Commtission Washington, D.C.

20555 1261 An Equal Opportunity Employer i

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