B13207, Forwards Westinghouse Reload Safety Evaluation for Millstone Unit 3,Cycle 3. Rept Demonstrates That Core Reload Will Not Adversely Affect Safety of Plant for Either Four or Three Loop Operation

Forwards Westinghouse Reload Safety Evaluation for Millstone Unit 3,Cycle 3. Rept Demonstrates That Core Reload Will Not Adversely Affect Safety of Plant for Either Four or Three Loop Operation

ML20244B478
Person / Time
Site:	Millstone
Issue date:	04/12/1989
From:	Mroczka E NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20244B480	List: B13207, Forwards Westinghouse Reload Safety Evaluation for Millstone Unit 3,Cycle 3. Rept Demonstrates That Core Reload Will Not Adversely Affect Safety of Plant for Either Four or Three Loop Operation ML20244B482
References
B13207, TAC-71942, NUDOCS 8904190219
Download: ML20244B478 (3)

Text

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General Offices

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.on aNnYu,N. HARTFORD, CONNECTICUT 06141-0270 aca'*<at =ucam p iaov cw- (203) 665-5000 April 12, 1989 Docket No. 50-421 B13207 Re: 10CFR50.90 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555

References:

(1) E. J. Mroczka letter to U.S. Nuclear Regulatory Commission, " Proposed Revision to Technical Specifica-tions," dated January 24, 1989.

(2) E. J. Mroczka letter to U.S. Nuclear Regul atory Commission, " Proposed Revision to Technical Specifica-tions," dated February 23, 1989.

(3) R. L. Ferguson letter to E. J. Mroczka, " Issuance of Amendment," dated January 20, 1988.

(4) R. A. Newton, Chairman, Westinghouse Owners Group, letter to U.S. Nuclear Regulatory Commission, " Assessment of Compliance with ATWS Rule Basis for Westinghouse PWRs,"

dated March 1, 1989.

Gentlemen:

Millstone Nuclear Power Station, Unit No. 3 Cycle 3. Proposed Revision to Technical Specifications (TAC No. 71942)

Pursuant to 10CFR50.90, Northeast Nuclear Energy Company (NNECO) submitted a proposed amendment to Facility Operating License NPF-49 (Reference (1)). That amendment would revise Millstone Unit No. 3 Technical Specification Section 5.3.1, which describes the fuel assemblies and Section 5.3.2 wh-:ch describes the control rod assemblies.

In Reference (2), NNECO provided the Staff with additional information regard-ing fuel assemblies to be used for Cycle 3 and the contingency plan for use of silver-indium-cadmium control rod assemblies. Reference (2) also stated that additional information concerning the fuel mechanical design would be described in the Westinghouse Reload Safety Evaluation Report and submitted to the NRC in a separate submittal. Accordingly, enclosed is a copy of the Westinghouse Reload Safety Evaluation report for Millstone Unit No. 3 Cycle 3.

This report demonstrates that the core reload will not adversely affect the safety of the plant for either four or three loop operation. This evaluation was accomplished utilizing the methodology described in WCAP-9273-A.

" Westinghouse Reload Safety Evaluation Methodology."

8904190219 890412 8 t PDR ADOCK 05000423 P I l PDC

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. , U.S. Nuclear Regulatory Commiss. ion *

. B13207/Page 2 . .'

.'- April 12, 1989 In Reference (3), the NRC requested that, for future Millstone Unit No. 3 reload core cycles, NNEC0 provide an expected Anticipated Transients Without Scram (ATWS) moderator temperature coefficient (MTC) at equilibrium Xenon ,

conditions, pending the Staff's evaluation of a forthcoming Westinghouse I Owners Group (WOG) response to a Staff request for information on ATWS MTC dated June 12, 1987. On March 1, 1989, the WOG submitted to the NRC a report, WCAP-11993, " Joint Westinghouse Owners Group / Westinghouse Program: Assessment of Compliance with ATWS Rule Basis for Westinghouse PWRs," (non-proprietary)

(Reference (4)). This report presents results of a joint WOG and Westinghouse effort to quantify the frequency of core damage resulting from . ATWS for Westinghouse. pressurized water reactors (PWRs) and demonstrates compliance with the ATWS Rule as specified in SECY-83-293 for Westinghouse PWRs.

Althwah the WOG submittal (Reference (4)) demonstrates compliance with the ATh'5 R.ile, a plant-specific response to Millstone Unit No. 3 is provided bel . . .

For the Cycle 3 core, full power BOL equilibrium Xe MTC is -9 pcm/*F which is more negative than the -5.5 pcm/*F assumed in Westinghouse letter, NS-EPR-83-2833 (E. P. Rahe Westinghouse to S. J. Chilk, NRC, October 3,1983).

If there are any questions, please contact our licensing representative directly.

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY E. J. Noczka Y^'

v W

Senior Vice President ,

cc: W. T. Russell, Region I Administrator D. H. Jaffe, NRC Project Manager, Millstone Unit No. 3 W. J. Raymond, Senior Resident Inspector, Millstone Unit Nos. 1, 2, and 3 Mr. Kevin McCarthy Director, Radiation Control Unit Department of Environmental Protection Hartford, Connecticut 06116 l

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. c " , U.S. Nuclear3Regulatory Commiss.

B13207/Page .. ion .

> April-12, 1989 STATE OF CONNECTICUT)

) ss. Berlin COUNTY OF HARTFORD )

Then personally ' appeared before me, E. J. Mroczka, who being duly sworn, did state that he is Senior Vice President of Northeast-Nuclear Energy Company, a Licensee - herein, that. he is authorized to execute and file the foregoing information in the name and on behalf of the Licensees herein, and that the statements contained in said information are true and correct to the best of his knowledge ard belief.

b_ oYn Notary Public AM 1

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