ML20066B241

Forwards Application for Amends to Licenses DPR-42 & DPR-60, Changing Tech Spec Tables 3.5-4 & 4.1-1 to Incorporate Feedwater Isolation Specs Per Generic Ltr 89-19 & USI A-47

ML20066B241
Person / Time
Site:	Prairie Island
Issue date:	12/26/1990
From:	Parker T NORTHERN STATES POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20066B244	List: ML20066B241 ML20066B252 ML20066B258
References
REF-GTECI-A-47, REF-GTECI-SY, TASK-A-47, TASK-OR GL-89-19, NUDOCS 9101070015
Download: ML20066B241 (2)

Text

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Northem States Power Company 414 Nicollet Mall Minneapolis, Minnesota 55401 1927 Telephone (612) 330 5500 December 26, 1990 10 CFR Part 50 Section 50.90 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 Reques , Dated December 26, 1990 Feedwater Isolation Limitations Attached is a request for a change to the Technical Specifications, Appendix A of the Operating Licenses, for the Prairie Island Ni e Generating Plant.

This request is submitted in accordance with the provtsions of 10 CFR Part 50, Section 50.90.

Generic Le tte r 89-19, " Request for Action Related to Resolution of Unresolved Safety Issue A-47", recommended that Technical Specifications for all

! Westinghouse plants include provisions to periodically verify the operability l of the main feedwater overfill protection and ensure that the automatic overfill protection-is operable during reactor power operation.

Our response l to Generic Letter 89 19, dated March 15, 1990, committed to submit a License i

Amendment Request to revise Technical Specification Table TS.3.5-4 to include limiting conditions for operations for feedwater isolation.

The NRC closeout of our response to Generic Letter 89-19, transmitted by letter dated July 17, 1990, requested that Technical Specification Surveillance Section 4.0 also be changed to require surveillance of both low l and high steam generator water level instrumentation.

i l

Prairic Island Technical Specification Tables TS.3.5-4 and TS.4.1-1 are being /

revised to incorporate the feedwater isolation specifications requested by /

l Generic Letter 89 19 and the subsequent NRC closcout.

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91010700J5 901226 PDR P

ADOCK 05000282 PDR A 0 ()/

e Northern States Power Company USNRC December 26, 1990 Page 2 l

l Prairie Island Technical Specification Table TS.4.1-1 is also being corrected to remove surveillances related to the low steam generator water level coincident with steam /feedwater mismatch reactor trip which was removed from the Technical Specifications by License Amendments Nos. 87 and 80.

Exhibit A contains a description of the proposed change , the reasons for requesting the changes and the supporti..g 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 Request.

/ v Thomas M Parker Manager Nuclear Support Services c: Regional Administrator-III, NRC NRR Proj ect Manager, NRC Senior Resident Inspector, NRC MPCr\

Attn: J W Ferman J E Silberg Attachments:

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

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