ML101241256

and Prairie Island Nuclear Generating Plants Units 1 & 2, Request for Approval of a Change to the Northern States Power Company - Minnesota Quality Assurance Topical Report, NSPM-1

ML101241256
Person / Time
Site:	Monticello, Prairie Island
Issue date:	05/04/2010
From:	Salamon G Northern States Power Co, Xcel Energy
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-XE-10-006
Download: ML101241256 (4)

Text

- 414 Nicollet Mall RESPONSIBLE BY NATUREm Minneapolis, MN 55401 May 4,201 0 L-XE-10-006 10 CFR 50.54(a)(4)

U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 2055-0001 Monticello Nuclear Generating Plant Docket 50-263 License No. DPR-22 Prairie Island Nuclear Generating Plants Units 1 and 2 Dockets 50-282 and 50-306 License Nos. DPR-42 and DPR-60 Request for Approval of a Change to the Northern States Power Companv -

Minnesota Qualitv Assurance Topical Report, NSPM-1 In accordance with 10 CFR 50.54(a)(4), Northern States Power Company, a Minnesota corporation (NSPM), requests U. S. Nuclear Regulatory Commission (NRC) review and approval of the following proposed change to the NSPM Quality Assurance Topical Report (QATR), NSPM-1, Revision 2.

Revise the portion of section A.7.3 (on page 18 of the QATR) that currently reads:

"Regulatory Guide 1.143, Revision 2, November 2001, "Design Guidance for Radioactive Waste Management Systems, Structures and Components Installed in Light-water-cooled Nuclear Power Plants" (Position C.7) -

NSPM commits to the quality assurance guidance cited in Position C.7.

Compliance with the remainder of the [technical] positions of Regulatory Guide 1.I43 is site specific, as addressed in each plant UFSAR."

To read instead:

"Regulatory Guide 1.143, Revision 2, November 2001, "Design Guidance for Radioactive Waste Management Systems, Structures and Components Installed in Light-water- Cooled Nuclear Power Plantsn- Compliance to the quality assurance guidance cited in Regulatory Guide 1.143, Revision 2, November 2001 is site specific, as addressed in each plant USAR."

Document Control Desk Page 2 Reason for Change Detailed QATR implementation reviews have identified that the commitment to Regulatory Guide 1.I43 in the QATR is overly broad. The QATR applies to both the Monticello Nuclear Generating Plant (MNGP) and the Prairie Island Nuclear Generating Plant (PINGP). There are commitments to Regulatory Guide 1.I43 in the Monticello Nuclear Generating Plant Updated Safety Analysis Report (USAR); however, there are none in the Prairie Island Nuclear Generating Plant USAR. This proposed change will remove the broad commitment from the QATR and utilize a reference to each site's USAR as the basis for commitment to Regulatory Guide 1.143.

Basis for Continuing to Meet Appendix B and Previouslv Accepted Commitments The current licensing basis establishes appropriate quality assurance requirements for structures, systems and components that are included within the scope of the guidance of Regulatory Guide 1.143, Revision 2, November 2001. Specific commitments to Regulatory Guide 1.143, Revision 2, November 2001 are in accordance with each site's USAR. NSPM concludes that the QA program presented in the QATR, as revised herein, will continue to satisfy 10 CFR 50, Appendix B criteria.

Summary of Commitments This letter makes no new commitments. It revises an existing commitment.

Gabor Salamon Director, Nuclear Licensing and Emergency Preparedness Northern States Power Company - Minnesota Enclosure cc: Administrator, Region 111, USNRC Project Manager, Monticello, USNRC Project Manager, Prairie Island, USNRC Resident Inspector, Monticello, USNRC Resident Inspector, Prairie Island, USNRC

ENCLOSURE 2 REVISED PAGE 18 FOR SECTION A.7.3 OF THE NSPM QATR 1 page follows

NSPM Quality Assurance Topical Report Regulatory Guide '1.143, Revision 2, November 200'1, "Design Guidance for Radioactive Waste Management Systems, Structures and Components Installed in Light-woter-Cooled Nuclear Power Plants" -Compliance to the quality assttrance guidance cited in Regulatory Guide 1.143, Revision 2, November 2001 is site specific, as addressed in each plant USAR.

I Regirlatory Guide '1.152, Revision '1, January 1996, "Criteria for Digital Conlpllters in Safety Systems of Nuclear Power Plants" - None of the current NSPM plants were conimitted to this Regirlatory Guidance during original constructioti. Regulatory Guide 1:I52 niay be ilsed for plant niodifications on a case by case basis, but this QATR makes no generic commitnient thereto.

Regulatory Guide '1.155, Revision 0, August '1988, "Station Blackout" (Position C.3.5) -

NSPM conimits to the quality assurance guidance cited in Position C.3.5, Appendix A.

Conipliance with Appendix B and the remainder of the [technical] positions of Regulatory Guicle 1.1 55 is site specific, as addressed in each plant UFSAR or License comtnitments.

Generic Letter 89-02lEPRI-NP-5652 (March 1988, and silpplements through March 1993) - NSPhrl conimits to conipliance with the endorsed industry guidance regarding selection and qualification of conitnercial grade suppliers and dedication of commercial grade items for use in safety related applications.

Branch Tecllnical Position CMEB 9.5-1, Revision 2, July 1981 (Positions C.2 and C.4) -

NSPM provisions for administrative controls for Fire Protection comply with site specific commitments, or with tlie provisions of Position C.2 of CMEB 9.5-1, Rev. 2, as specified in NRC approved site fire protection programs and the applicable NRC Safety Evaluation Reports. Application of the provisions of this QATR to fire protectiori activities provides ele~nentsof quality assirrance that coinply with site specific fire protection quality assurance commitments or with CMEB 9.5-1, Revision 2, Position C.4.

Regulatory Giride 4.'15, Revision I, Febrirary 1979, Quality Assurance for Radiological Monitoring Programs (Normal Operations) - Effluent Streams and the Environment" -

NSPM commits to compliance with Regulatory Guide 4.15.

Regulatory Giride 7.10, Revision I, June 1986, "Establishing Quality Assurance Progranis for Packaging Used in the Transport of Radioactive Material" - NSPM cornmits to implelnelit the quality assurance guidance for activities related to the packaging and transport of radioactive material that are under its control. Quality Assurance for the design, fabrication and licensing of shipping containers is the responsibility of the container certificate holders.

Generic Letter 85-06, April 1985, "Quality Assurance Guidance for ATWS Equipment That Is Not Safety-Related" - NSPM conirnits to the quality assurance guidance cited in tlie Generic Letter.

Regulatory Issue Surnnlary 2000-18, October 2000, "Guidance on Managing Quality Assurance Records in Electronic Media" - Should NSPM choose electronic niedia storage as a means of maintaining required records, NSPM will comply with the guidance of this Regulatory Isslle Summary.

18 NSPM-1 QATR, Rev 3, X X l X X I l O