ML20237E799

Forwards non-proprietary Results of AP600 Design Assurance Review (Dar) That Was Commitment in W Response to NRC Insp Rept 99900404/97-02.Info Should Assist in Closing Nonconformances & Unresolved Item Identified in Insp Rept

ML20237E799
Person / Time
Site:	05200003
Issue date:	08/21/1998
From:	Mcintyre B WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:	Quay T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20237E801	List: ML20237E799 ML20237E816
References
REF-QA-99900404 99900404-97-02, 99900404-97-2, NSD-NRC-98-5646, NUDOCS 9809010186
Download: ML20237E799 (2)

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Westinghouse Electric Company g33 pirisburgn pennsylvania 1523Soass NSD-NRC-98-5646, Rev. 2 DCP/NRC-1324, Rev. 2 Docket No.: 52-003 August 21,1998 Document Control Desk U. S. Nuclear Regulatory Commission Washington, D C 20555 Attention:

T. R. Quay i

Subject:

Revised Response to NRC Inspection No. 99900404/97-02 of AP600

Reference:

1. Letter, S. C. Black to N. J. Liparulo, "NRC inspection Report No. 99900404/97-02" dated January 28,1998

2. Letter, B. A. McIntyre to S. C. Black. " Reply to a Notice of Nonconformance" dated February 27,1998

3. Letter, Wilson to McIntyre," Request for Withholding Proprietary Information-AW-98-1223", dated July 13,1998

Dear Mr. Quay:

Reference I requested that Westinghouse " assess the adequacy of the AP600 QA design review process and the integrity of the AP600 design." Attachment 1 A presents the results of the AP600 Design Assurance Review (DAR) that was a commitment in the Westinghouse response (Reference 2) to the NRC inspection report. The information should assist in closing the nonconformances and unresolved item identified in the subject NRC inspection. The DAR was performed by a team of engineers, independent of the AP600 project, under the leadership of Dr. W. S. LaPay of the Westinghouse Nuclear Service Division according to the procedure described in the review report. Potendally significant issues identified by the team are also

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presented in the attachment.

I As documented in Reference 2, a large majority of concerns identified by the NRC, in Reference 1, were related to the level of documentation provided in the calculation notes. These have been resolved by providing additional information. The three SSAR modifications resulting from our corrective actions to the nonconfornace and the unresolved item are not expected to change the conclusions reached in the SSAR reuew.

Reference 3 sets forth the NRC assessment of the Westinghouse claim for treatment of proprietary information '

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submitted by Westinghouse in a letter dated April 3,1998, which letter provided the Westinghouse response to the Nuclear Regulatory Commission inspection #99900404/97-02. The NRC assessment was that no portion of the Westinghouse letter was marked as proprietary, no nonproprietary version was provided and that, in their opinion, nothing in the letter met the requirements of 10 CFR 2.790(a)(4). The NRC determination was based, in part, on the Westinghouse letter of April 17,1998.

The revised letter that follows addresses the NRC comments in reference 3 by providing a nonproprietary version of the material as discussed with your staff on August 21,1998. The type of material considered nonproprietary in this revision is consistent with that of the Westinghouse letter of April 17,1998.

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NSD-NRC-98-5646, Rev. 2 2

August 21,1998 DCP/NRC,-1324, Rev. 2 Westinghouse initiated the DAR to evaluate an additional sample of calculations that support the Chapter 15 analysis and the containment analysis section of Chapter 6. The purpose of the DAR was to further assess the integrity of the AP600 design process. The review plan was discussed with the NRC in a meeting on February 11,1998. At that time, we had planned to review a sample of 24 calculation notes. During the course of the review, the sample sir was increased to 73 calculations due to the need to review supportirg, or referenced calculations. Results o 'the assessment are presented in Table 3 of Attachment l A.

A corrective action pl~a was developed to resolve the "Potentially Significant Technical and Documentation Quality issues"identitled by the DAR. The plan, Attachment iB to this letter, identifies the planned actions, the expected effect on the results reported in the SSAR, and the current status of each corrective a:: tion. The DAR evaluated 73 safety related and software documentation calculation packages. In addition,22 LOCA related design change proposals were reviewed. Most of the calculations were found to be acceptable. As in the case of the NRC review, the majority of the concerns involve the clarity of the documentation. These will be addressed by revising the calculation to provide clarification or additional information. Two suggestions were made to clarify SSAR wordings and these were incorporated into the in-progress Revision 22. Subject to confirmation by the planned actions, none of the issues are expected to have significant effects on the results of the analysis reported in the SSAR. An updated status of the results of the corrective actions will be reviewed in the meeting scheduled for April 13,1998.

The NRC review and the DAR together included approximately one third of the calculations that support the Chapter 15 analysis and the containment analysis section of Chapter 6. A concern from both reviews involved the level of documentation provided in the calculation notes. Corrective actions have been implemented to enhance the level of documentation provided in support of the AP600 Project.

Based on our evaluation of the results of the November 1997 NRC inspection observations and the DAR, we believe that the AP600 design process conforms to the requirements of 10CFR50 Appendix B.

Please destroy Revision 1 to letter DCP/NRCl324 faxed to you on August 19,1998.

Please contact me on 412-374-4334 or Bob Tupper on 412-374-5219 if you have any questions concerning this transmittal.

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x Brian A. Mc ntyre, M ager Advanced Plant Safety and Licensing Attachments cc:

T. R. Quay, NRC/NRR/DRPM (w/ Attachments)

H. A. Sepp, Westinghouse (w/o Attachments)

J. J. Bastin, Westinghouse (w/o Attachments)(Rockville Office) 368'aR2 doc

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