ML20141A023

Forwards Application for Amends to Licenses DPR-42 & DPR-60, Maintaining Limitations on Spent Fuel Handling Re Spent Fuel Pool Special Ventilation Sys Operability

ML20141A023
Person / Time
Site:	Prairie Island
Issue date:	05/07/1997
From:	Richard Anderson NORTHERN STATES POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20141A029	List: ML20141A023 ML20141A075 ML20141A087
References
NUDOCS 9705140139
Download: ML20141A023 (3)

Text

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Northern states Power Company ,

1717 Wakonado Dr. E.

Welch, MN 55089 I Telephone 612-38&1121 l

May 7,1997 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 Request Dated May 7,1997 Amendment of Spent Fuel Pool Special Ventilation System Specifications Attached is a request for changes 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.

These requested amendments will maintain limitations on spent fuel handling relating to spent fuel pool special ventilation system operability. Limitations on crane operations in the spent fuel pool enclosure relating to spent fuel pool special ventilation system operability will be removed from the Technical Specifications.

These changes are necessary to allow movement of loads over spent fuel stored in the spent fuel pool enclosure with the spent fuel pool special ventilation system inoperable.

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

Recently the Prairie Island plant staff reviewed the technical specification interpretations to assure that plant operations were in compliance with the technical specifications. Difficulties were identified with verbatim compliance with TS.3.8, 9705140139 970507

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USNRC 5/7/97 Page2 of 3 Applicability and Objectives and TS.3.8.D. It is our understanding that the underlying purpose of these specifications is to assure that the spent fuel pool special ventilation system is operable when heavy loads preserW a potential for damaging irradiated fuel stored in the spent fuel pools. License Amendments 91/84 incorporated these limitations into the Prairie Island Technical Specifications on October 27,1989. Since License Amendments 91/84 were issund, NSP has installed single-failure-proof cranes and implemented precedures which implement the requirements of NUREG-0612, " Control of Heavy Loads at Nuciear Plants," for handling heavy loads over the spent fuel pools. Prairie Island wR a 7sure that heavy loads do not present a potential for damaging irradiated fuel througn use of: 1) a single-failure-crane with rigging and procedures which implement Prairie Island commitments to NUREG-0612; or, 2) spent fuel pool covers and theirimplementing plant procedures. Compliance with the requirements of NUREG-0612, through use of a single-failure-proof crane, associated rigging and procedures, or through use of spent fuel pool covers, eliminates the necessity of crane operating limitations in TS.3.8.

In general, crane operating limitations are the subject of plant operating procedures and commitments, and are not contained in the Technical Specifications. Removal of crane operating restrictions from this Technical Specification will make this specification consistent with other Prairie Island Technical Specifications and consistent with NUREG-1431, Standard Technical Specifications, Westinghouse Plants.

Movement of heavy loads through the spent fuel pool enclosure is required to prepare for and implement the Unit 1 refueling outage scheduled to commence on October 18,1997. Therefore, NSP requests that the proposed license amendment request be issued by October 11,1997 in order to allow for movement of heavy loads over spent fuel stored in the spent fuel pool enclosure in preparation for the Unit 1 refueling outage.

In this submittal, NSP has made new Nuclear Regulatory Commission commitments which are identified in italics. If you have any questions related to this information in support of the subject license amendment request, please Dale Vincent at 612-388-1121.

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0h 6&n u Roger O. Anderson Director, Licensing end Management issues (attachments and copies listed on page 3)

USNRC

• 5/7/97.

Page 3 of 3 Attachments:

Affidavit Exhibit A, Description of the Proposed Changes, The Reasons for Requesting the Changes, and the Supporting Safety Evaluation /Significant Hazards Determination.

Exhibit 8, Marked Up Technical Specification Pages Exhibit C, Revised Technical Specification Pages c: Regional Administrator-lli, NRC NRR Project Manager, NRC Senior Resident inspector, NRC State of Minnesota Attn: Kris Sanda J E Silberg

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