ML20101P107

From kanterella
Jump to navigation Jump to search
Forwards Application for Amends to Licenses DPR-42 & DPR-60, Changing TS Re Applicability of Surveillance Requirements Per Generic Ltr 87-09 & Incorporating Sts,Section 4.0.3,per Generic Ltr,Into TS
ML20101P107
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 06/15/1992
From: Parker T
NORTHERN STATES POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20101P110 List:
References
GL-87-09, GL-87-9, NUDOCS 9207100290
Download: ML20101P107 (1)


Text

- - _ - _ _ _

Northem States Power Company 414 Nicollst Mall Moneapolis Mmnesota 55401 1927 Telephone (612) 3D5500 June 15,1992 10 CFR Part 50 Section 50.90 U S Nuclear Regulatory Commission Attn; Document Control Desk Vashington, DC 20555 PRAIRIE IS1AND NUCLEAR GENERATING PLANT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 License Amendment Request Dated June 15, 1992 Surveillance Recuirements Aeolicability Section 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.

Generic Letter 87-09, " Sections 3.0 and 4.0 of the Standard Technical

~

Specifications (STS) on the App icability of Limiting Conditions for Operation and Surveillance Requirements", provided guidance on improvements to Section 4.0 of the Standard Technical Specifications which could be voluntarily adopted by licersees. One of the improvements described in Generic Letter 87-09 revised Standard Technical Specification 4.0.3 to clarify when a missed surveillance constitutes a violation of the operability requirements of a Limiting Condition for Operation and,to clarify the applicability of the action requirements and the time during which the limits apply.

TLis License Amendment Request proposee the incorporation of Standard Technical Specification Section 4.0.3, as modified by Generic Letter 87-09, into the Prairie Island Technical Specifications.

Evhibit A contains a description of the proposed changes, the reasons for requesting the changes and the supporting safety evaluation /significant hazards determination. Exhibit B contains current Prairie Island Technical Specification pages marked up to show the proposed changes.

Exhibit C contains the revised Technical Specification pages.

,, n.m 11iiU U d 4 82 g/

P PDR

' II

)

Northem States Power Company June 15, 1992 Page 2 Please contact us if you have any questions related to these License Amendment Requests.

Thomas M Parker Manager Nuclear Support Services c: Regional Ad.ninistrator-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 l

l Exhibit B - Proposed Changes Marked Up on Existing Technical Specification Pages Exhibit C - Revised Technical Specification Pages 1

l l

N