ML20129J311

Submits Staff Response to Several Request for Addl Info Responses in W Ltr NSD-NRC-96-4823,dtd 960920

ML20129J311
Person / Time
Site:	05200003
Issue date:	11/04/1996
From:	Diane Jackson NRC (Affiliation Not Assigned)
To:	Liparulo N WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
References
NUDOCS 9611060204
Download: ML20129J311 (4)

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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2008tH1001 l

November 4, 1996 Mr. Nicholas J. Liparulo, Manager Nuclear Safety and Regulatory Activities l Nuclear and Advanced Technology Division l Westinghouse Electric Corporation P.O. Box 355 Pittsburgh, Pennsylvania 15230

SUBJECT:

STAFF RESPONSE TO SEVERAL REQUEST FOR ADDITIONAL INFORMATION

, (RAI) RESPONSES IN WESTINGHOUSE LETTER NSD-NRC-96-4823 DATED SEPTEMBER 20, 1996

Dear Mr. Liparulo:

The Nuclear Regulatory Commission (NRC) Containment Systems and Severe Accident Branch (SCSB) has reviewed Westinghouse letter dated Septem-ber 20, 1996, which is in response to certain staff RAIs. Discussions via meetings and telephone conferences between Westinghouse and the SCSB staff and its consultants have been held frequently to discuss the WG0THIC r.omputer code and passive containment cooling system (PCS).

Provided below is the staff evaluation of certain responses in the September 20, 1996 letter.

In letter NSD-NRC-96-4823, Westinghouse provided responses to RAIs, including RAI# 480.330, 480.378-380, and 480.396. These responses reference the following documents: )

(1) D. R. Spencer, " Accident Specification and Phenomena Evaluation for AP600 Passive Containment Cooling System," NSD-NRC-96-4643, Febru-ary 12, 1996.

(2) D. R. Spencer, " Scaling Analysis for the AP600 Containment Pressure During Design Basis Accidents," NSD-NRC-96-4762, July 1, 1996.

1 (3) J. S. Narula, " Assessment of Mixing and Stratification Effects on  !

AP600 Containment," NSD-NRC-96-4763, July 1, 1996.

Reference 1 is used to respond to RAlf 480.396, which requested clarift- I cation on presentation material from the March 29 and 30,1995, Advisory Committee for Reactor Safeguards (ACRS) meeting referenced in WCAP-14382, "WGOTHIC Code Description and Validation." The staff has provided feedback to Westinghouse on the Reference I structure, as well as other l editorial and clarification issues. Westinghouse has informed the staff I that it is revising this report. In Reference 1, Westinghouse used I

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i materials (e.g., steel, concrete, and PCS cooling water), structures 1 (e.g., shell, baffle, and baffle supports), and regions (e.g., external ,

atmosphere, in-containment refueling water storage tank (IRWST), and  !

break pool) to evaluate the AP600. It is the staff's understanding that '

the revised report will be based on spacial regions, a more cosmon approach. A preliminary version of the revised structure was provided to  ;

the ACRS at the May 1996 meeting. The response to RAI# 480.396 should l not depend on a report that is under revision. This response should be i withdrawn until such time that it can be answered in accordance with the  ;

revised phenomena evaluation report and the report is submitted to the  !

l staff.

l The responses to RAI# 480.330, 480.378-380 refer to References 2 and 3.

The staff has provided feedback to Westinghouse on Reference 2 identify- i ing 52 items of concern including errors and omissions in the scaling formulation. The staff has provided feedback to Westinghouse on Refer-ence 3, which was submitted as a draft chapter to WCAP-14407, "WG0THIC l Application to AP600," identifying 143 items of concern with the mixing l and stratification report. The MGOTHIC Application to AP600 report, l submitted by letter dated September 10, 1996, did not contain revisions based on these items. In both cases, Westinghouse has informed the staff that these two reports will be revised to incorporate the staff's com- i ments on the preliminary versions. Reference 2 will be a separate report )

and Reference 3 will be a revised Section 9 in WCAP-14407. Knowing that these reports will be revised, the responses to these RAls should be withdrawn until such a time that they can be answered in accordance with l the revised reports and the reports are submitted to the staff.

The staff can not accept, as references, material that is known to be out l of date or that contains known errors. If Westinghouse does not prefer to withdraw these RAI responses, then the staff will issue the comments provided on References 2 and 3 as formal RAls. It may be necessary to reopen the reviews of the Reference 2 and 3, since the review was per-formed in a cursory manner once the staff was informed that revisions would be made to these reports. The staff would also have to reopen its review of Reference 1 to formalize additional RAls for that report.

l It is also noted that these same three reports are used in support of conclusions presented in WCAP-14407. We request you review this report and update any necessary information and submit it for staff review.

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If you have any questions regarding this matter, you can contact me at (301) 415-8548. i Sincerely, ,

original signed by: ,

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Diane T. Jackson, Project Manager Standardization Project Directorate  :

Division of Reactor Program Management .

Office of Nuclear Reactor Regulation  ;

Docket No.52-003 cc: See next page l

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Mr. Nicholas J. Liparulo Docket No.52-003 Westinghouse Electric Corporation AP600 cc: Mr. B. A. McIntyre Mr. Ronald Simerd, Director Advanced Plant Safety & Licensing Advanced Reac^ar Programs Westinghouse Electric Corporation Nuclear Energr Institute Energy Systems Business Unit 1776 Eye Strat, N.W.

P.O. Box 355 Suite 300 Pittsburgh, PA 15230 Washington, DC 20006-3706 Mr. John C. Butler Ms. Lynn Connor Advanced Plant Safety & Licensing Doc-Search Associates Westinghouse Electric Corporation Post Office Box 34 Energy Systems Business Unit Cabin John, MD 20818 Box 355 ,

Pittsburgh, PA 15230 Mr. James E. Quinn, Projects Manager i LMR and SBWR Programs Mr. M. D. Beaumont GE Nuclear Energy Nuclear and Advanced Technology Division 175 Curtner Avenue, M/C 165 Westinghouse Electric Corporation San Jose, CA 95125 One Montrose Metro  !

11921 Rockville Pike Mr. Robert H. Buchholz Suite 350 GE Nuclear Energy Rockville, HD 20852 175 Curtner Avenue, MC-781 Mr. Sterling Franks U.S. Department of Energy Barton Z. Cowan, Esq.

NE-50 Eckert Seamans Cherin & Mellott 19901 Germantown Road 600 Grant Street 42nd Floor i Germantown, MD 20874 Pittsburgh, PA 15219 Mr. S. M. Modro Mr. Ed Rodwell, Manager Nuclear Systems Analysis Technologies PWR Design Certification Lockheed Idaho Technologies Company Electric Power Research Institute Post Office Box 1o25 3412 Hillview Avenue Idaho Falls, ID 83415 Palo Alto, CA 94303 Mr. Frank A. Ross Mr. Charles Thompson, Nuclear Engineer U.S. Department of Energy, NE-42 AP600 Certification Office of LWR Safety and Technology NE-50 19901 Germantown Road 19901 Germantown Road Germantown, MD 20874 Germantown, MD 20874 l