ML20077H091

Forwards Application for Amend to Licenses DPR-42 & DPR-60, Requesting Revs to Tech Specs,In Response to Generic Ltr 90-06, Resolution of Generic Issue 70, 'Porv & Block Valve Relief Valves...& Generic Issue 94....'

ML20077H091
Person / Time
Site:	Prairie Island
Issue date:	06/25/1991
From:	Parker T NORTHERN STATES POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20077H092	List: ML20077H091 ML20077H096 ML20077H099
References
REF-GTECI-070, REF-GTECI-094, REF-GTECI-NI, TASK-070, TASK-094, TASK-70, TASK-94, TASK-OR GL-90-06, GL-90-6, NUDOCS 9107050152
Download: ML20077H091 (2)

Text

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Northeni States Power Company 414 Nicollet Mati Mint'eapolis, Minnesota $$4011927 lelephone (612) 330 5500 June 25, 1991 10 CFR Part 50 Section 50.90 U S Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PIANT Docket Nos. 50 282 License Nos. DPR 42 50-306 DPR 60 License Amendment Request Dated June 25, 1991 frggggriter Power Operated Relief Valve Changes Attached is a 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.

Generic Letter 90 06, " Resolution of Generic Issue 70, " Power-operated Relief Valve and Block Valve Reliability", and Generic Issue 94, " Additional Low.

Temperature Overpressure Protection for Light Water Reactors", Pursuant to 10 CFR 50.54(f)", provided NRC Staff guidance on Technical Specification changes that should be implemented to improve the reliability of the Pressurizer Power Operated Relief Valves (PORVs) and the availability of the low temperature overpressure protection system.

This license amendment request proposes changes to the Prairie Island Technical Specifications provided in response to Generic Letter 90 06. The Technical Specification changes proposed by this License Amendment Request are cor 1 stent with the recommendations of Generic Letter 90-06 except as noted below and in our response to Generic Letter 90-06, dated December 21, 1991.

In that response we addressed each of Technical Specification modifications recommended by the NRC Staff in Generic Letter 90-06 and provided justification where our proposed changes to the Prairie Island Technical Specifications would differ from the NRC Staff guidance.

Not addressed in our December 21, 1991 response was the PORV lift setting included in the Limiting Condition for Operation. for the low temperature overpressure protection system shown in Attachment L 1 to Generic Letter 90-

06. The current Prairie Island low temperature overpressure protection system specification does not include the PORV li f t setting. Because this lift 9107050152 910625 PDR P

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Nodhem States Power Company USNRC June 25,1991 Page 2 setting is periodically revised, and would require periodic license amendment requ'sts to be maintained current, it is not being incorporated into the Prairie Island Technical Specifications. Instead a discussion of the basis for the POR7 lift setpoint and when it will be updated is being incorporated into the bases for the low tenperature overpressure protection Technical Specifications.

Additionally, Generic Letter 90 06 stated that for plants with existing Technical Specifications for PORVs used for low temperature overpressure protection, only certain portions of the modified Technical Specifications in Attachment B-1 to the Generic Letter were required to be incorporated. All other changes that would result from the implementation of Attachment B 1 were stated to be voluntary. The PORV lift settings were included in a portion of the modified Technical Specifications that was considered voluntary.

Exhibit a contains a description of the proposed changes, the reasons for requesting the changes and the supporcing 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.

Please contact us if you have any questions related to this License Amendment Roquest.

,e lnw)n Thomas M Parker Manager Nuclear Support Services c: Regional Administrctor III, NRC NRR Project Manager, NRC Senior Resident Inspector, NRC MFCA Attn: J W Ferman J E Silberg Attachments:

Affidavit Exhibit A - Evaluation of Proposed Cheuges to the Technical Specifications Exhibit B - Proposed Changes Marked Up on Existing Technical Specification Pages Exhibit C - Revised Technical Specificatiott Pages l

l l

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