ML17250B203

Provides Closeout of MPA-D05,per Util 900312 Commitment to Use Westinghouse Evaluation Model Applying SECY-83-472

ML17250B203
Person / Time
Site:	Ginna
Issue date:	07/03/1990
From:	Andrea Johnson Office of Nuclear Reactor Regulation
To:	Mecredy R ROCHESTER GAS & ELECTRIC CORP.
References
TAC-07739, TAC-7739, NUDOCS 9007090101
Download: ML17250B203 (6)

Text

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% **R4 Docket No. 50-244 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O. C. 20555 July 3, 1990 Dr. Robert C. Mecredy, General Manager Nuclear Production Rochester Gas 5 Electric Corporation 89 East Avenue Rochester, New York 14649

SUBJECT:

UPPER PLENUM INJECTION (CLOSEOUT) - TAC NO. 07739 The Commission has completed the review of your letter dated March 12, 1990 dealing with the upper plenum injection (UPI) model that will be applied for the R.E. Ginna Nuclear Power Plant.

The letter commits Rochester Gas and Electric Corporation to using the Mestinghouse Electric Corporation evaluation model that applies the NRC SECY-83-472 interpretation of 10 CFR 50.46 and 10 CFR Part 50, Appendix K.

'Hestinghouse Corporation submitted the same evaluation model using the SECY-83-472 approach to analyze the UPI for Prairie Island Nuclear Generating Plant Unit Nos.

1 and 2 and the Point Beach Nuclear Generating Station Unit Nos.

1 and 2.

The staff completed the review of the evaluation model submitted by Mestinghouse and by letter dated August 29, 1988, the staff issued an SER finding the evaluation model (i.e., MCAP-10924) acceptable.

Mhen this evaluation was applied in the plant specific analyses for both plants, it showed excess margin did exist when the coolant injected into the upper plenum was factored into the analysis.

Subsequently, the licensees for Prairie Island and Point Beach did request a change to the technical specifications for which the staff has issued amendments regarding changes to FdeltaH and F~

taking into account the excess margin.

The staff has judged a similar margin exists when the Mestinghouse evaluation model is applied in the plant specific analysis for the Ginna Nuclear Power Plant.

Rochester Gas and Electric targets mid-1991 before the evaluation model will be completed and the applicable Technical Specification amendments requested.

Therefore, the staff concludes that based on this margin no safety concern exists and with your comitment to perform the analysis with an approved evaluation model, this closes the Multi Plant Action (MPA)-D05.

9007090101 900703 PDR ADOCK 05000244 P

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Dr. Robert C. Mecredy Ginna CC:

Thomas A. Moslak, Resident Inspector R.E. Ginna Plant U.S. Nuclear Regulatory Commission 1503 Lake Road

Ontario, New York 14519 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406 Hs.

Donna Ross Division of Policy Analysis 5 Planning New York State Energy Office Agency Building 2 Empire State Plaza

Albany, New York 12223 Nr. Bruce A. Snow, Superintendent Nuclear Production Rochester Gas 5 Electric Corporation 89 East Avenue Rochester, New York 14649-0001 Charlie Donaldson, Esq.

Assistant Attorney General New York Department=of Law 120 Broadway New York, New York 10271 Earnest J. Ierandi, Esquire Nixon, Hargrave, Devans and Doyle Lincoln First Tower P.O.

Box 1051 Rochester, New York 14603 July 3, 1990 In addition, when you request a change to the Technical Specification regarding, changes in F>>

and Fg, it will be handled in a normal manner where a new TAG number will hid lgned.

This action closes t1PA D-05 and TAC No. 07739.

Sincer ely, cc:

See next page Allen Johnson, Project hlanager Project Directorate I-3 Division of Reactor Projects - I/II, Office of Nuclear Reactor Regulation DISTRIBUTION DOCKET FILE)

NRC 8

LOCAL PDRs PDI-3 R/F JZMOLINSKI PSHUTTLEMORTH AJOHNSON OGC EJORDAN ACRS(10)

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July 3, 1990 In addition, when you request a change to the technical specification regarding changes in F

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This action closes MPA D-05 and TAC No. 07739.

Sincerely, cc:

See next page Allen Johnson, Project Manager Project Directorate I-3 Division of Reactor Projects - I/II, Office of Nuclear Reactor Regulation DISTRIBUTION XRBTTKE EJORDAN NRC 5 LOCAL PDRs ACRS(10)

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