ML19296A323

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Forwards Amend N12 to PSAR
ML19296A323
Person / Time
Site: New England Power
Issue date: 03/13/1979
From: Stevens J
NEW ENGLAND POWER CO.
To:
Office of Nuclear Reactor Regulation
Shared Package
ML19296A324 List:
References
N-N-105, NUDOCS 7903150343
Download: ML19296A323 (2)


Text

New Englard Power Company 20 Turnpike Road g.e"{

u j, NewEnglandPower westoorouan. vassacnusetts ois8i Tel. (617) 366-9011 NEP 1 & 2 Nuclear Project March 13, 1979 NRC-N-10 5 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, D.C. 20555 DOCKET NOS. STN 50-568 AND STN 50-569 PSAR AMENDMENT N12

Dear Sir:

Pursuant to the Atomic Energy Act of 1954, as amended , the Commission's Rules and Regulations issued thereunder, and the National Environmental Policy Act as implemented by 10 CFR Part 51, New England Power Company (NEP) hereby submits 60 copies of Auendment N12 of the Preliminary Safety Analysis Report.

The following it...armation is included in Amendment N12.

1) PSAR text revisions incorporating previouoly submitted responses to NRC stuff's Request for Additional information.
11) The loss of coolan; accident has been reanalyzed for NEP 1 & 2 and is presented in Chapter 15. Appendix 15D has been added to update the October 1975 Westinghouse ECCS Model results. The updated Feoruary 1978 Westinghouse ECCS Evaluation Model incorporates a number of modifications to previous models, including the clad metal-water heat of reaction correction. The October 1975 ECCS Model ( Amendment 10 to the PSAR) indicates that the Peak Clad Temperature (PCT) for the 0.6, 0.8 and 1.0 Double Ended Cold Leg Guillotine (DECLG) break provided nearly identical peak temperatures (11 F maximum separation).

However, the results of the present analysis (February 1978 ECCS Model) indicates that the 0.6 DECLG is the most limiting break. We find that this result is not unreasanable since the DECLG analysis for the four loop Westinghouse Plt.nt is conducted utilizing nominal inlet temperature, cold leg temperature in the upper head and an optimized accumulator water volume of 850 f t3, iii) Miscellaneous changes resulting from meetings and discussions with NRC's staff.

g o W'O A New England Electric System company

Director of Nuclear Reactor Regulation March 13, 1979 Page 2 NRC-N-105 iv) Miscellaneous and minor editorial changes.

Respectf ully submitted ,

NEW ENGLAND POWER COMPANY

/

Byc (

John L Stevens Executive Vice President STATE OF RHODE ISLAND:

COUNTY OF PROVIDENCE:

Personally appeared before me this /d#' day of A*" , 19 7 9, John R. Stevens, who, being duly sworn, did state that he is Executive Vice President of New England Power Company, an applicant herein, that he is duly authorized to execute and file the foregoing amendment in the name and on behalf of New England Power Company, and that the statements in said application are true to the best of his knowledge and belief.

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