B13150, Forwards Topical Rept NUSCO-165, Large Break LOCA Fuel Rod Response (NUFRAP-T6) & Core Oxidation Evaluation Models (Nucom). Final Rept Providing plant-specific Large Break LOCA Analysis Remains Scheduled for Submittal in Jul 1989

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Forwards Topical Rept NUSCO-165, Large Break LOCA Fuel Rod Response (NUFRAP-T6) & Core Oxidation Evaluation Models (Nucom). Final Rept Providing plant-specific Large Break LOCA Analysis Remains Scheduled for Submittal in Jul 1989
ML20235H845
Person / Time
Site: Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 02/17/1989
From: Mroczka E, Sears C
CONNECTICUT YANKEE ATOMIC POWER CO., NORTHEAST UTILITIES
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20235H847 List:
References
B13150, TAC-66958, NUDOCS 8902240074
Download: ML20235H845 (2)


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HARTFORD. CONNECTICUT 06141-0270 k ' J (203) 665-5000 i February 17, 1989 Docket No. 50-213 B13150 Re: Zircaloy Clad Conversion ISAP Topic 2.17 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555

References:

(1) E. J. Mroczka letter to U.S. Nuclear Regulatory Commis-sion, "Small Break LOCA Analysis - Response to NULAPS SER Concerns (TAC Nos. 45830 and 48169) - Zircaloy Clad Fuel Topical Report (TAC No. 66958)," dated December 30,198C.

(2) E. J. Mroczka letter to U.S. Nuclear Regulatory Commis-sion, "Large Break LOCA Topical Report - Zircaloy Clad Fuel Conversion (TAC No. 66958)," dated January 31, 1989.

Gentlemen:

Haddam Neck Plant Large Break LOCA Topical Report Zircalov Clad Fuel Conversion (TAC No. 66958)

References (1) and (2) submitted to the NRC the first and second of four topical reports that will provide the loss of coolant accident (LOCA) reanaly-sis for the Haddam Neck Plant with zircaloy clad fuel. Northeast Utilities

. Service Company (NUSCO), on behalf of Connecticut Yankee Atomic Power Company (CYAPC0), hereby submits the third topical report for NRC review.

The attached report, NUSCO-165: Large Break LOCA Fuel Rod Response (NUFRAP-T6) and Core Oxidation Evaluation Models (NUCOM), contains descrip-tions of the NUFRAP-T6 and NUCOM codes which will be used for large break LOCA ECCS performance evaluations of the Haddam Neck Plant. NUFRAP-T6, which is a modified version of FRAP-T6/M001, will be used to determine the hot rod thermal and mechanical response for comparison with the peak clad temperature and oxidation criteria of 10CFR50.46. NUCOM provides a calculation of the total core clad oxidation and the maximum hydrogen generation for comparison I with the 10CFR50.46 acceptance criteria.

The final topical report providing the plant-specific large break LOCA analy-sis of the Haddam Neck Plant remains scheduled for submittal in July 1989.

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U.S. Nuclear Regulatory Commission B13150/Page 2 February 17, 1989 We are prepared to interact with the Staff and their contractors as necessary to facilitate the review and approval process of our methodology in time for the scheduled conversion to zircaloy clad fuel, beginning with Cycle 17 in January 1991.

If you have any questions regarding the attached topical report, please contact our licensing representative directly.

Very truly yours, CONNECTICUT YANKEE ATOMIC POWER COMPANY n lb d . Neto gt E. J. Mroczka 9 Senior Vice President L

By: C. F. Sears Vice President cc: W. T. Russell, Region I Administrator (w/0)

A. B. Wang, NRC Project Manager, Haddam Neck Plant (w/2)

J. T. Shediosky, Senior Resident Inspector, Haddam Neck Plant (w/1) l l

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