ML20031A814

Forwards Request for Addl Info Re Westinghouse Basic Safety Rept Re Cycle 5 Reload

ML20031A814
Person / Time
Site:	Millstone
Issue date:	09/18/1981
From:	Clark R Office of Nuclear Reactor Regulation
To:	Counsil W NORTHEAST NUCLEAR ENERGY CO.
References
TAC-43380, NUDOCS 8109250495
Download: ML20031A814 (3)

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Dear Mr. Counsil:

In our continuing revicu of the Westinghouse Basic Safety Report to be used for the Cycle 5 reload of fillistone, Unit No. 2, we find that the enclosed additional information is necessary to complete our evaluation of postulated accidents.

Please provide the requested additional information within 30 days of receipt of this letter. This request has been slightly nodified from the request telecopied to your Mr. Mike Cass on Spptember 10, 1981.

Sincerely, Original si2ned by Robert A. Clark Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing

Enclosure:

As stated cc: See next page E109250495 810910

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NRC FORM MS 0480) NRCM 0240 OFFICIAL RECORD COPY usam mi-anno

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Northeast Huclear Energy Company cc:

William H. Cuddy, Esquire Mr. John Shediosky Day, Serry & Howard Resident Inspector / Millstone Counselors at Law c/o U.S.N.R.C.

One Constitution Plaza P. O. Drawer KK Hartford, Connecticut 06103 Niantic, CT 06357 Mr. Charles Brinkman Natural Resource: Defense Council Mar *ger - Washington Nuclear 917 15th Street, N.W.

Operations Washington, D. C.

20005 C-E Power Systems Combustion Engineering, Inc.

Mr. Lawrence Bettencourt, First Selectman 4853 Cordell Aven., Suite A-1 Tovn of Waterford 3etnesda, "D 2001a Hall of Records - 200 Boston ? cst Road Waterford, Connecticut 06385 Northeast Nuclear Energy Company ATTN:

Superintendent Millstone Plant Conrecticut Ener;y A;ency Post Office Sox 128 ATTN:

Assistant Director, Researen Weterford, Connecticut 06385 and Policy Development Department of ?lanning and Energy Waterford Public Library Policy Rope Ferry Road, Route 156 20 Grand Street Waterford, Connecticut 06385

Hartford, C-'

06106

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U. 5: Environmental Protection Agnecy Region I Office ATTU:

Regional Radiation Representative John F. Kennedy Federal'3uilding Beston, Massachusetts 02203 Northeast Utilities Service Company ATTH:

Mr. Richard T. Laudenat, "anager Generation Facilities Licensing i

P. J. Box 270 Ha-tfo rd, - Connecticut 06101 e

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' ADDITIONAL.INFORMAIION_ REQUIRED _

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-WESTINGHOUSE 5ASIC SAFETY REPORT MILLSTONE UNIT 2 DOCKET NO. 50-336 1.

Provide an analysis of the Feedwater Line Break Accident for Millstone Unit No. 2.

Include a specific discussion relative to the appifcability of the analysis to the Millstone reload applications.

2.

Clarify the reference to the THINC code in Section 5.2.6.5 of the SSR; i.e., verify that an NRC-approved version of THINC is used in reload applications. If not, provide documentation for the staff's review.

Provide a qualitative discussion of the broken pump shaft accident and, if 3.

more limiting than a pump seizure, perfom a c;uantitative analysis to show fraction that the acceptance criteria of a calculated dose rate which is a small of 10 CFR Part 100 guidelines and a maximum pressure within 110% of design are meE For the loss of feedwa.er event, provide an analysis assuming the cressurizer 4

ocwer-ocerated relief valves fail to open.

5. For tne steam lir.e rupture event (Section 5.3.15),

(a) provide a qualitative discussion of the event assuming less 'of offsite power; (b) provide the results of an analysis under full power conditions assuming the main feedwater valve fails to close (with offsite pcwer available),

and (c) state the assumption made in all analyses relative to auxiliary feedwater isola tion to the ruptured unit.

6. For the reactor coolant depressurization event (Section 5.3.8), describe the small-break LOCA model used and provide tne results of the determination of pertinent plant variables and peak ' clad temoerature.

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