ML20046B561
| ML20046B561 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 07/29/1993 |
| From: | Richard Anderson NORTHERN STATES POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20046B562 | List: |
| References | |
| NUDOCS 9308050160 | |
| Download: ML20046B561 (2) | |
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Northem States Power Company 414 Nicollet Mall Minneapolis, Minnesota 55401-1927 Telephone (612) 3345%0 July 29, 1993 10 CFR Part 50 Section 50.90 i
1 Director of Nuclear Reactor Regulation U S Nuclear Regulatory Commission Attn:
Document Control Desk Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 License Amendment Request Dated July 29, 1993 Addition of References to Approved Methodolony Attached is i request for a change to the Technical Specifications, Appendix A of the operating Licenses for the Prairie Island Nuclear Generating Plant.
This request is submitted in accordance with the provisions of 10 CFR Part 50, Section 50.90.
The documents that describe the NRC approved analytical methods used to determine the core operating limits are specified in Technical Specification Section 6.7.A,6 b.
Westinghouse Topical Report WCAP-13677, is currently under i
review by the NRC Staff.
Following NRC review and approval, Westinghouse will
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issue a revised topical report with the NRC Safety Evaluation Report, WCAP-136777-A. Northern States Power topical report NSPNAD-93003, was reviewed and approved by the NRC Staff as documented in an NRC Safety Evaluation Report dated July 16, 1993. Northern States Power will issue a revised topical report with the NRC Safety Evaluation Report, NSPNAD-93003-A.
This license amendment has been submitted to incorporate a reference to the revised methodologies described in WCAP-13677 and NSPNAD-93003 into the Prairie Island Technical Specifications following their approval by the NRC Staff.
The revised methodologies must be incorporated into Section 6.7.A 6.b so the model revisions can be used in the determination of the core operating limits.
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' Director of NRR July 29, 1993 "E"
Nodhem States Power ' ompany C
1 Exhibit A contains a description of the proposed change, the reasons for i
requesting the change and a Safety Evaluation / Determination of Significant
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Hazards Considerations.
Exhibit B contains a current Technical Specification
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page marked up to show the proposed changes.
Exhibit C contains the revised Technical Specification pages.
Because the proposed Technical Specification change is incorporating a l
reference to topical reports that will be required for Unit 2 Cycle 16, i
presented scheduled to begin in December of this year, we request this License Amendment Request be approved by December 1, 1993.
Please contact us if you have any questions related to this request.
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Roger 0 Anderson Director Licensing and Management Issues c: Regional Administrator-III, NRC NRR Project Manager, NRC Senior Resident Inspector, NRC State of Minnesota Attn: Kris Sanda J E Silberg Attachments:
Affidavit Exhibit A - Evaluation of Proposed Changes to the Technical Specifications Exhibit B - Proposed Changes Highlighted on Existing Technical Specification Pages Exhibit C - Revised Technical Specification Pages i
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