View source for NSD-NRC-98-5646, Forwards Proprietary Results of AP600 Design Assurance Review,Per Commitment Contained in W Response to Violations Noted in Insp Rept 99900404/97-02. Proprietary Portion of Document Was Sent to Westinghouse

{{Adams
| number = ML20248J643
| issue date = 04/03/1998
| title = Forwards Proprietary Results of AP600 Design Assurance Review,Per Commitment Contained in W Response to Violations Noted in Insp Rept 99900404/97-02. Proprietary Portion of Document Was Sent to Westinghouse
| author name = Mcintyre B
| author affiliation = WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
| addressee name = Black S
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| docket = 05200003
| license number = 
| contact person = 
| case reference number = REF-QA-99900404
| document report number = 99900404-97-02, 99900404-97-2, NSD-NRC-98-5646, NUDOCS 9806090230
| title reference date = 02-27-1998
| package number = ML20248J647
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE
| page count = 5
}}

=Text=
{{#Wiki_filter:f Westinghouse Box 355 O
PmsWp Pennsylvania 15230-0355 Electric Company NSD-NRC-98-5646 DCP/NRC-1324                              i Docket No.: 52-003 April 3,1998 Document Control Desk U. S. Nuclear Regulatory Commission Washington, D C 20555 Attention: Suzanne C. Black

==Subject:==
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 j
l Reference I requested that Westinghouse " assess the adequacy of the AP600 QA design review process                 ,
and the integrity of the AP600 design." Attachment l 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 repon. 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 repon. Potentially significant issues identified by the team are also presented in the attachment.
As documented in Reference 2, a large majority of concems 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 nonconformance and the unresolved item are not expected to change the conclusions reached in the SSAR review.
Westinghouse initiated the DAR to evaluate an additional sample of calculations that suppon 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.
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During the course of the review, the sample size was increased to 73 calculations due to the need to L                                       review supporting, or referenced calculations. Results of the assessment are presented in Table 3 of Attachment I A.
A corrective action plan was developed to resolve the "Potentially Significant Technical and Documenta: ion Quality Issues *' identified 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 cornctive action. 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 concems involve the
                                  . clarity of the documentation. These will be addressed by revising the calculation to provide clari6 cation 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 msults 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.
_                                    -I 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.                                l
                                . This submittal contains Westinghouse proprietary information consisting of trade secrets, or commercial information which we consider privileged or confidential pursuant to 10CFR2.790. Therefore,'it is requested that the Westinghouse proprietary information attached hereto be handled on a confidential basis and be withheld from public disclosure.                                                                              -1
                              - The Westinghouse Electric Company copyright notice, proprietary information notice, application for J withholding and affidavit are also attached.
                               . This material is for your internal use only and may be used for the purpose for which it is submitted. It should not be otherwise used, disclosed, duplicated, or disseminated, in whole or in part, to any other person or organization outside of the Commission, the Office of Nuclear Regulation, the Office of Nuclear Regulatory Research and the necessary subcontractors that have signed a proprietary nondisclosure agreement with Westinghouse without the express written approval of Westinghouse.                              l Correspondence with respect to the application for withholding should reference AW-98-1223 and                                j should be addressed to Brian A. McIntyre. Manager of Advanced Plant Safety and Licensing,                                     l Westinghouse Electric Company, P. O. Box 355, Pittsburgh, Pennsylvania, 15230-0335.

o Please contact me on 412-374- 4334 or Bob Tupper on 412-374-5219 if you have any questions concerning this transmittal.
4h f Brian A. McIntyre,. Manager Advanced Plant Safety and Licensing Attachments cc: T. R. Quay, NRC/NRR/DRPM (w/ Enclosures)
R. L. Pettis, NRC/NRR/PSIB/ DISP (w/ Enclosures)
R. A. Gramm, NRC/NRR/DRCH/HQMB (w/ Enclosures)
N. J. Liparulo, Westinghouse (w/o Enclosures)
J. J. Bastin, Westinghouse (w/o Enclosures)(Rockville Office) 1 I
I r

a                                                                                                                                                          i I
COPYRIGHT NOTICE                                                    i l
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                                              - The reports transmitted herewith each bear a Westinghouse copyright notice. The NRC is permitted to          i make the number of copies of the information contained in these reports which are necessary for its          !
internal use in connection with generic and plant-specific reviews and approvals as well as the              i issuance, denial, amendment, transfer, renewal, modification, suspension, revocation, or violation of a -    l license, permit, order, or regulation subject to the requirements of 10 CFR 2.790 regarding restrictions     l on public disclosure to the extent such information has been identified as proprietary by Westinghouse, copyright protection notwithstanding. With respect to the non-proprietary versions of these reports, the NRC is permitted to make the number of copies beyond those necessary for its internal use which are necessary in order to have one copy available for public viewing in the appropriate docket files in the public document room in Washington, D.C. and in local public document rooms as may be required by NRC regulations if the number of copies submitted is insufficient for this purpose. Copies made by the NRC must include the copyright notice in all instances and the proprietary notice if the original was identified as proprietary.
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PROPRIETARY INFORMATION NOTICE l
Transmitted herewith are proprietary and/or non-proprietary versions of documents furnished to the NRC in connection with requests for generic and/or plant specific review and approval.
In order to conform to the requirements of 10 CFR 2.790 of the Commission's regulations concerning
                                                             ' the protection of proprietary information so submitted to the NRC, the justification for claiming the information as proprietary is that these are types of information Westinghouse customarily holds in confidence as identified in Section (4XiiXa) and (4XiiX6) of the affidavit accompanying this transmittal pursuant to 10 CFR2.790(bXI).
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