ML18142A704

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Furnishing Information Re Logic Inconsistency Identified by Westinghouse in LOCA ECCS Evaluation Model of Applicants Pertaining to Heating Effect of the Zircalloy/Water Reaction. Advising Westinghouse Will Reanalyze Limiting Break
ML18142A704
Person / Time
Site: Ginna 
Issue date: 04/17/1978
From: White L
Rochester Gas & Electric Corp
To: Ziemann D
Office of Nuclear Reactor Regulation
References
Download: ML18142A704 (4)


Text

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REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS >

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WHITE L 9 DOCDATE: 04/17 J'78 NRC ROCHESTER GAS

8. FLEC DATE RCVD: 04121/78 DOCTYPE:

LETTER NOTARIZED; NO COPIES RECEIVED

SUBJECT:

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ENCL 0 FURNISHING INFO RE LOGIC INCONSISTENCY IDENTIFIED BY WESTINGHOUSE IN LOCA ECCS EVAI UATION MODEL OF APPLICANT"S SUBJECT FACILITY PERTAINING TO HEATING FFFECT OF THE ZIRCALLOY/WATER REACTION... ADVISING WESTINGHOUSE WILL REANALYZE LIMITING BRFAK -." SUBJECT sac i ~Y-FoC.

PLANT NAME: RE GINNA UNIT 1 REVIEWER INITIAL:

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89 EAST AVENUE, ROCHESTER, N.Y. 14649 LEON D. WHITE, JR.

VICE PRESIDENT TELEPHONE AREA COOK Tld 546.2700 April 17, 1978 Director of Nuclear Reactor Regulation Attention:

Mr. Dennis L. Ziemann, Chief Operating Reactors Branch N2 U.S. Nuclear Regulatory Commission Washington, D. C.

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Dear Mr. Ziemann:

This letter is in response to a request from a member of your Staff and addresses a logic inconsistency recently identi-fied by our vendor, Westinghouse Electric Corporation, in their LOCA ECCS Evaluation Model.

On March 24,

1978, we were notified by Westinghouse that they had determined that their Evaluation Model did not fully account for the heating effect of the Zircalloy/

water reaction.

Since that time, Westinghouse has performed addi-tional analyses in which they determined the impact on peak clad tem-perature of including the Zircalloy/water reaction in their present models.

These analyses indicate that, taking full account of the Zircalloy/water reaction, and without making other changes in the model, Ginna continues to meet the limits specified in 10 CFR Section 50.46 while operating at the present Technical Specification limits.

Thus, no interim restrictions are required.

This conclu-sion is a result of the large margin to limits and to the assumed level of steam generator tube plugging which existed in the pre-vious analysis.

Westinghouse has informed us that they have submitted several proposed changes to their Evaluation Model to the NRC for review, including a change to fully account for the Zircalloy/water re-action.

Following approval, Westinghouse will reanalyze the limiting break for R.

E. Ginna for our submittal to you.

Very truly yours, L. D.

W 'te, Jr.

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