ML20084T849

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: ML20084T849 ML20084T852
References
BFRO-50-260-761, LER-BFRO-50-259-762, NUDOCS 8306240197
Download: ML20084T849 (2)

Text

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OCENSEE EVENT RsPORT l l l, (PLEACE P;l LL EEZUl!EC INFO!M ATION)

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NAME LCENSE NUVBER

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EVENT OESCR;PTION .

g l W2 have been advised by the General Electric Company that the MAPLHGR limits e for Browns Ferry units l and 2 must be reduced to ensure that the peak clad temperature o 60 O9

'g l' calculated in conformance with 10 CFR50.46 is less than 2200 F.RevisedMAPLEGRcurveg 80 89 l g l have been installed in the unit 1/2 process computer and inis willreport remain in effect until is supplementai 80 r

8 9 Just1Lication is suu:ntted tor turtner modification. l

@l to BFRO-50-259/7627 and BFRO-50-260/7618 dated December 8. 1976. 80 A R V VTCN ho CODE COMPONENT CODE T

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' W9 10 11 12 17 43 44 CAUSE DESCRIPTION part 50.46, l g l V:ndor discovered certain input discrepancies used in the 10 CFR 7 89 l

] l Appendix K analyses previously submitted.

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7 9 METHOD OF 80 FACluTY OrSO'Ji2AY DESCAiPTON

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B0 7 89 10 8306240197 770504

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, 80 ADOITIONAL FACTORS . ,

Revised curves were submitted to NRC on January. 19, 1977. l ta l 80 7 is 9 l l 19 l B0 7 09 I

NAME: _ ______ ________c c o __s e_i_. s_s y_ _ __ _ _.

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February 4, 1977 '

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Mr. Norman C. Moseley, Director - 1 U.S. Nuclear Regulatory Commission  %

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Office of Inspection and Enforcement Region II j

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l Atlanta, Ceorgia 30303 ees Dear Mr. Moselays '

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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 l 2200 0 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

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

Office of Inspection and Enforcement l U.S. Nuclear Regulatory Commission

) Washington, D.C. 20555 , ,

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t An Equa! Opportunity Employer S M. - *_.__. - _. _ _ _ .- _-

I* . U NSEE EVENT. REPORT .

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1 8 tcENSE NuMeER

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7 8 60 61 EVENT DESCR> TION .

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 47 89- l

! R I 1 percent. Based on these results, units 1 and 2 operation has been determined to be 80 99 l b l unnffected by the nreviousiv renorted 'inout errors. 80 7 89 l

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l l We understand that a meetin's between NRC, General Electric, and the utilities 80 7 89 15, 1976, to further discuss this matter]

. gl . involved is being held in Bethesda on December . 80.

-7 89 PHONE:

NAME: cro set.est

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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 AND DPR 41 nr*0RTABLE OCCURRENCE REPORTS BFR0 Q 9/762) AND

{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):

1

{ Director (3)

Office of Manage t Information and Program Control 4

2 U.S. Buelear Raqslatory Commission Washington, D.C. 20555

_ Director (40)

Offiae of Inspection and Enforcement U.S. Wualear Regulatory Commtission Washington, D.C. 20555 1261

An Equal Opportunity Employer i

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