L-85-300, Advises That Util Working w/C-E to Develop Schedule for Resolution of Potential Nonconservatism in One Element of C-E Large Break LOCA Evaluation Model.Schedule Will Be Available by 850930

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Advises That Util Working w/C-E to Develop Schedule for Resolution of Potential Nonconservatism in One Element of C-E Large Break LOCA Evaluation Model.Schedule Will Be Available by 850930
ML17216A266
Person / Time
Site: Saint Lucie NextEra Energy icon.png
Issue date: 08/02/1985
From: Williams J
FLORIDA POWER & LIGHT CO.
To: Thompson H
Office of Nuclear Reactor Regulation
References
L-85-300, PNS-EP-85-164-1, NUDOCS 8508070159
Download: ML17216A266 (3)


Text

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AGCESQTON NBR!8508070159 DOC ~ DATE! 85/08/02 NOT'ARIZED:

NO PACK',:50~389 St ~ 'ucie'Plantg Un,it 2g Florida Power 5 Light Co>

AUTH',NAME AUTHOR AF F ILIATI ON WILLIAMS~J~ W, Florida Power 8 Light Cp, RECIP ~ NAME.

RECIPIENT 'AFFILIATION THOMPSONiH'iL, Division of Licensing SUBJECT!: Advises that'ti'I working w/C E! to develop schedule for resolution-of potential noncqnservatism in one. elemen,t" of C"E large break LOCA evaluat;ion models Schedule~ will be available by.850930

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~yak V/i FLORIDAPOWER 8( LIGHTCOMPANY August 2, 1985 L-85-300 Office of Nuclear Reactor Regulation Attention: Mr. Hugh L. Thompson, Director Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C. 20555

Dear Mr. Thompson:

Re:

St. Lucie Unit No. 2 Docket No. 50-389 C-E Lar e Break LOCA Anal sis On July 3, 1985, Florida Power R Light Company (FPL) received notification from Combustion Engineering (C-E) of a potential non-conservatism in one element of C-E's large break loss-of-coolant accident (LOCA) evaluation model.

That notification was received by copy of a letter to NRC from C-E (A. E.

Scherer to G. W. Knighton, LD-85-031, July 2, 1985).

The particular element in question was the treatment of axial power distribution and peaking factor.

On July 10, 1985,'PL attended a

meeting between NRC Staff and C-E representatives, in which C-E provided detailed information on this subject as well as a status summary for those plants for which C-E performed the large break LOCA evaluations.

The current LOCA analysis for St. Lucie Unit 2 was performed for Cycle 2 and resulted in a worst case peak clad temperature (PCT) of 2001 F for the Technical Specification Linear Heat Rate Limit of 13 kw/ft. Although no. St.

Lucie Unit 2 specific axial power distribution/peaking sensitivity studies have been performed, C-E has informed FPL that for St.

Lucie Unit 2 the estimated increase in PCT still demonstrates margin to the 10 CFR 50.06 acceptance criterion of 2200 F.

In addition, current and anticipated operation throughout Cycle 2 for St. Lucie Unit 2 is at levels well below the 13 kw/ft. limit.

FPL is continuing to work with C-E to develop a schedule for resolution of this matter. We expect that the schedule willbe available by September 30, 1985.

Very truly yours, J. W. Williams, Jr.

Group Vice President Nuclear Energy JWW/RJS:dkw PNS-EP-85-160/I 8508070159 850802 roe aDOCZ o50OOSS9

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