ML20096D630
| ML20096D630 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 05/07/1992 |
| From: | Parker T NORTHERN STATES POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20096D632 | List: |
| References | |
| GL-91-08, GL-91-8, NUDOCS 9205180164 | |
| Download: ML20096D630 (2) | |
Text
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s" Northem States Power Company 414 Nicollet Mall Minneapohs. Minnesota 55401 1927 Telephone (612) 330-5500 May 7, 1992 10 CFR Part 50 Section 50.90 U S Nuclear-Regulatory Commission Attn: Document Control Desk Washington, DC 20555 PRAIRIE ISIAND NUCLEAR GENERATING PiANT Docket Nos. 50 282 License Nos. DPR-42 50-306 DPR-60 License Amendment Request Dated May 7, 1992 Containment Penetration List Removal and Miscellaneous Charmes Attached are requests for changes to the Technical Specifications, Appendix A of the Operating Licenses, for the Prairie Island Nuclear Generating Plant. These requests are submitted in accordance with the provisions of 10 CFR Part 50, Section 50.90.
The first license amendment request proposes the relocation of the Containment Penetration List from Section 4.4 of the Prairie Island Technical Specifications into plant procedures per the guidance in Generic Letter-91-08, " Removal of Component Lists From Technice' Specifications".
The second license amendment request proposee. changes to Section 3.6.C of the Prairie Island Technical Specifications which will clarify when non-automatic containment isolation valves are required to be operable and what actions are to be taken - in response to the inoperability of a non-automatic containment isolation valve.
The third license amendment request proposes the deletion of condensate cross connect valve C-41-1 from-Section 3.4.B. l.g of the Prairie Island Technical 3
Specifications.
Exhibit A contains a description of the proposed changes, the reasons for requesting the changes and the supporting safety evaluation /significant hazardr determination. Exhibit B contains current Prairie Island Technical Specification r
pages marked up to show the proposed changes.
Exhibit C contains the revised Technical Specification pages.
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i-Northern States Power Company USNRC May 7, 1992 s
Page 2 Please contact us if you have any questions related to these License Amendment
- Requests,
'550 $1
/Thomas M Parker Manager c
Nuclear Support Services 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 Chenges to the Technical Specifications Exhibit B - Proposed Changes Marked Up on Existing Technical Specification Pa60s Exhibit C - Revised Technical Specification Pages c
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