NSD-NRC-98-5560, Forwards Proprietary Revs to SSAR 6.2 Resulting from Reanalysis of Containment Pressure DBA & to Describe Changes to AP600 Containment Evaluation Model Used for Reanalysis. Proprietary Encl Withheld (Ref 10CFR2.790)
| ML20203E055 | |
| Person / Time | |
|---|---|
| Site: | 05200003 |
| Issue date: | 02/20/1998 |
| From: | Mcintyre B WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | Quay T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML19317C896 | List: |
| References | |
| NSD-NRC-98-5560, NUDOCS 9802260243 | |
| Download: ML20203E055 (2) | |
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Energy Systems g3,55 k059 0Ril0n g,,,,333 DCP/NRCl247 NSD NRC 98 5560 Docket No.: $2 003 February 20,1998 Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20$$$
- ATiliNI10N: T.R. QUAY SUlijl!CT:
SSAR 6.2 MARKUP AND !! VALUATION MODlil, CilANGliS
Dear Mr. Quay:
The purpose of this letter is to transmit revisions to SSAR 6.2 resulting from reanalysis of the containment pressure DilA (Attachment I), and to describe the changes to the AP600 containment evaluation model used for the reanalysis (Attachment 2). Attachment 3 contains the nonproprietary version of Attachment 2.
4 The Design liasis Analysis pressure transients have been recalculated for LOCA and MSLil. Affected SSAR sectlans are 6.2.1,1 for pressure results and subsections 6.2.1.3 and 6.2.1.4 for mass and energy releases. The calculated peak pressure for the containment DilA analysis incorporating the above modifications is 44.5 psig for the DlICLG l.OCA and 44.4 psig for the limiting MSLil. In addition.
Tables 6.2.1.14 through -7 have been deleted, as agreed to by NRC via telecon on 2/19/98.
1he changes to the Ap600 containment evaluation mmici are (1) upgrade of WGOTillC version 4.1 to versior. 4.2; and (2) cimnges in the evaluation model input.
The Westinghouse filectric Company, a division of CilS Corporation (" Westinghouse"), copyright l
notiv, proprietary information notiec, application for withholding and affidavit are also attached.
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This submittal contains Westinghouse poprietary information consisting of trade secrets, commercial information or financial information which we consider p.-ivileged or confidential pursuant to f:]ftJlf-10CFR2.790. Therefore, it is requested that the Westi,ghouse proprietary infonnation attached hereto L
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be handled on a confidential basis and be withheld from public disclosures,
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DCP/NRCl247 NSD NRC 98 5560 2-l'ebruary 20 1998 l
'lhls material is for your internal use only, and may be used for the purpose for which it is subraitted.
11 should not be otherwise used, disclosed, duplicated, or disseminated, in whole or in part to any other person or organization outside the Commission, the ofGee of Nuclear Reactor Regulation, the Office of Nuclear Regulatory Research and the necessary subcontractors that have signed a proprietary non.
disclosure agreement with Westinghouse without the express written approval of Westinghouse.
Correspondence with respect to the application for withholding should reference AW 981202, and should be addressed to lirian A. McIntyre, Manager of Advanced Plant Safety and Licensing, Westinghouse !!!cettic Company, a ctivision of CilS Corporation (" Westinghouse"), l'.O. Ilox 355, Pittsburgh, Pennsylvania, 15230-03$$.
Please contact I cc Rarig on (412) 374 43$8 if you have any questions concerning this transmittal.
4 lirian A. McIntyre Mannge Advanced Plant 'rafety and Licensing jml Attachments cc:
D. C. Scaletti, NRC (w/ Attachments)
N. J. Liparuto, Westinghouse (w/o Attachments) f
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