ML20196F984

Provides Changes to Calculated Peak Fuel Cladding Temp, Resulting from Recent Changes to Plant ECCS Evaluation Model

ML20196F984
Person / Time
Site:	Sequoyah
Issue date:	11/25/1998
From:	Salas P TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9812070183
Download: ML20196F984 (2)

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Tennessee vaney Authorny Post omce Bm am Swdy-Darsy Te eb379 November 25, 1998 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen:

In the Matter of ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328 SEQUOYAH NUCLEAR PLANT (SQN) - 10 CFR 50.46 ANNUAL REPORT The purpose of this letter is to provide changes to the calculated peak fuel cladding temperature (PCT) resulting from recent changes to the SON Emergency Core Cooling System (ECCS) evaluation model. This submittal satisfies the annual reporting requirements in accordance with 10 CFR '

50. 4 6 (a) (3) (ii) . There have been no changes in PCT for SQN Unit 1 or Unit 2 since the last annual report that was submitted on November 25, 1997.

Please direct questions concerning this issue to me at (423) 843-7170 or J. D. Smith at (423) 843-6672.

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/ V I Pea Salas Licensing and Industry Affairs Manager cc: See page 2 1

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, cc: Mr. R. W. Hernan, Project Manager Nuclear Regulatory Commission l One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739 NRC Resident Inspector Sequoyah Nuclear Plant l 2600 Igou Ferry Road

! Soddy-Daisy, Tennessee 37379-3624 Regional Administrator l U.S. Nuclear Regulatory Commission l Region II

! 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303-3415 i

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