ML19320A963: Difference between revisions

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N Westinghouia          Water Reactor                          Ndadechmicgy Dvh Electric Corporation  Divisions                              g,333 PittsburghPennsylvania15230 June 25,1980 i;3-TMA-2269 Mr. Harold Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission 50-339 Phillips Building 7920 Norfolk Avenue Bethesda, Maryland 20014
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Westinghouia          Water Reactor                          Ndadechmicgy Dvh Electric Corporation  Divisions                              g,333 PittsburghPennsylvania15230 June 25,1980 i;3-TMA-2269
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Mr. Harold Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission 50-339 Phillips Building 7920 Norfolk Avenue Bethesda, Maryland 20014


==Dear Mr. Denton:==
==Dear Mr. Denton:==


Supplement 10 to the North Anna Safety Evaluation Report, NUREG-0053, re-quests ommitment to respond to outstanding questions on several topical reports. No reference is made to these reports in the North Anna or other dockets for NT0L plants (other than Section 15 of the NRC SSER's). It should be noted that the forthcoming responses are not directly applicable to North Anna,but to avoid delays in the approval of Unit 2 for full power Westinghouse will provide the responses to outstanding questions on the following topicals.
Supplement 10 to the North Anna Safety Evaluation Report, NUREG-0053, re-quests ommitment to respond to outstanding questions on several topical reports. No reference is made to these reports in the North Anna or other dockets for NT0L plants (other than Section 15 of the NRC SSER's). It should be noted that the forthcoming responses are not directly applicable to North Anna,but to avoid delays in the approval of Unit 2 for full power Westinghouse will provide the responses to outstanding questions on the following topicals.
WCAP-9226, " Reactor Core Response to Excessive Secondary Steam Releases" - July 31, 1980
WCAP-9226, " Reactor Core Response to Excessive Secondary Steam Releases" - July 31, 1980 WCAP-9230, " Report on the Consequences of a Postulated Main Feedline Rupture" - August 30, 1980 WCAP-9236, "NOTRUMP - A N0DAL Transient Steam Generator and General Network Code" - Requests for additional information not received to date We assume that this information will allow the safety evaluation of North Anna 2 and other NT0L plants to proceed.
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WCAP-9230, " Report on the Consequences of a Postulated Main Feedline Rupture" - August 30, 1980 WCAP-9236, "NOTRUMP - A N0DAL Transient Steam Generator and General Network Code" - Requests for additional information not received to date We assume that this information will allow the safety evaluation of North Anna 2 and other NT0L plants to proceed.
If you have any questions relative to this subject, please do not hesitate to contact Mr. R. W. Steitler of my staff (412/373-4705).
If you have any questions relative to this subject, please do not hesitate to contact Mr. R. W. Steitler of my staff (412/373-4705).
Very truly yours, 4                    -
Very truly yours, 4                    -
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cc:    T. P. Speis B. J. Youngblood
cc:    T. P. Speis B. J. Youngblood

Revision as of 04:05, 1 February 2020

Lists Topical Repts for Which Responses to Outstanding Questions Will Be Provided to Allow SER to Proceed & to Avoid Delays in Approval of Full Power Operation.Includes WCAP-9226,-9230 & -9236
ML19320A963
Person / Time
Site: North Anna Dominion icon.png
Issue date: 06/25/1980
From: Anderson T
WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To: Harold Denton
Office of Nuclear Reactor Regulation
References
NS-TMA-2269, NUDOCS 8007080371
Download: ML19320A963 (1)
v • d • e


Text

_ _ ____ _ _ _ _ _

N Westinghouia Water Reactor Ndadechmicgy Dvh Electric Corporation Divisions g,333 PittsburghPennsylvania15230 June 25,1980 i;3-TMA-2269 Mr. Harold Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission 50-339 Phillips Building 7920 Norfolk Avenue Bethesda, Maryland 20014

Dear Mr. Denton:

Supplement 10 to the North Anna Safety Evaluation Report, NUREG-0053, re-quests ommitment to respond to outstanding questions on several topical reports. No reference is made to these reports in the North Anna or other dockets for NT0L plants (other than Section 15 of the NRC SSER's). It should be noted that the forthcoming responses are not directly applicable to North Anna,but to avoid delays in the approval of Unit 2 for full power Westinghouse will provide the responses to outstanding questions on the following topicals.

WCAP-9226, " Reactor Core Response to Excessive Secondary Steam Releases" - July 31, 1980 WCAP-9230, " Report on the Consequences of a Postulated Main Feedline Rupture" - August 30, 1980 WCAP-9236, "NOTRUMP - A N0DAL Transient Steam Generator and General Network Code" - Requests for additional information not received to date We assume that this information will allow the safety evaluation of North Anna 2 and other NT0L plants to proceed.

If you have any questions relative to this subject, please do not hesitate to contact Mr. R. W. Steitler of my staff (412/373-4705).

Very truly yours, 4 -

T. M. Anderson, Manager

\

O

/bek Nuclear Safety Department b \Q ~

cc: T. P. Speis B. J. Youngblood

800708o 3 7/

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