ML20045C137

Forwards Application for Amend to Licenses DPR-42 & DPR-60, Revising TS for Increase in Fuel Enrichment Limits to Support Longer Fuel Cycles. Criticality Analysis of Prairie Island Units 1 & 2 Fresh & Spent Fuel Racks Encl Also

ML20045C137
Person / Time
Site:	Prairie Island
Issue date:	06/11/1993
From:	Richard Anderson NORTHERN STATES POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20045C138	List: ML20045C137 ML20045C151 ML20045C171 ML20045C184
References
NUDOCS 9306220122
Download: ML20045C137 (2)

Text

P 14 Northem States Power Company 414 Nicollet Mall Minneapolis, Minnesota 55401-1927 Telephone (012) 330-5500 June 11, 1993 10 CFR Part 50 Section 50.90 U S Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 PRAIRIE ISIAND NUCLEAR GENERATING PLANT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 License Amendment Request Dated June 11, 1993 Increased Fuel Enrichment Limit Channes 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.

Prairie Island Technical Specifications currently limit fuel in the . spent fuel pool and new fuel storage racks to a maximum enrichment of 4.25 weight percent U-235. In order to support longer fuel cycles at Prairie Island, it is necessary to increase fuel enrichments beyond the 4.25 weight percent limit and to revise the Technical Specification enrichment limits. Based on the results of a criticality analysis included as Exhibit D to this request, the Prairie Island Technical Specifications are being revised to allow the storage of 5.0 weight percent U-235 fuel in the new fuel vault and the spent fuel pool.

Prairie Island Technical Specifications set the minimum Refueling Water Storage Tank (RUST) boron concentration at 1950 ppm. The RWST boron concentration requirements for recent core reload designs using 4.2 weight percent U-235 fuel assemblies have approached the current 1950 ppm limit. It is expected that future core reload designs utilizing 5.0 weight percent U-235 fuel will require minimum RWST boron concentrations in excess of the current 1950 ppm limit in order to maintain reactor suberiticality following a LOCA.

Therefore, Technical Specifications are being revised to increase the minimum RWST boron concentration to 2500 ppm.

1800.92

- 6g 9306220122 930611 PDR ADOCK 05000282 liN i a lI k

P PDR y

I.

USNRC June 11, 1993 Nodhem States Power Company Page 2 The attached license amendtent request also revises Technical Specifications to incorporate references to natural uranium and ZIRLD clad material into the reactor core design description.

Exhibit A contains a description of the proposed changes, the reasons for l requesting the changes, the supporting safety evaluations and significant hazards determinations. Exhibit B contains current and new Prairie Island Technical Specification pages marked up to show the proposed changes. . Exhibit C contains the revised Technical Specification pages. Exhibit D contains a Westinghouse report describing the criticality analysis performed on the Prairie Island new and spent fuel storage facilities.

Because the proposed changes to increase the fuel enrichment limitations in the Prairie Island Technical Specifications must be in place prior to the ,

receipt of new fuel for the Fall 1993 Unit 2 refueling outage, we request that the proposed license amendment request be issued by September 1, 1993.

Please contact Gene Eckholt (612-388-1121, ext 4663) if you.have any questions related to this License Amendment Request.

1

/"

f;Y X Y 4fy l Roger 0 Anderson  ;

Director Licensing and Management Issues c: Regional !.dministrator-I 3, 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 Exhibit B - Proposed Changes Marked Up on Existing and New Technical Specification Pages Exhibit C - Revised Technical Specification Pages Exhibit D - Criticality Analysis of Prairie Island Units 1 and 2 Fresh and Spent Fuel Racks

I UNITED STATES NUCLEAR REGULATORY COMMISSION NORTHERN STATES POWER COMPANY PRAIRIE ISIAND NUCLEAR GENERATING PLANT DOCKET NO. 50-282 50-306 REQUEST FOR AMENDMENT TO OPERATING LICENSES DPR-42 & DPR-60 LICENSE AMENDMENT REQUEST DATED JUNE 11, 1993 Northern States Power Company, a Minnesota corporation, requests authorization for changes to Appendix A of the Prairie Island Operating License as shown on the attachments labeled Exhibits A, B, C and D. Exhibit A describes the proposed changes, reasons for the changes, safety evaluation and a significant hazards evaluation. Exhibits B and C are copies of the Prairie Island Technical Specifications incorporating the proposed changes. Exhibit D is a report supporting the requested changes.

This letter contains no restricted or other defense information.

NORTHERN STATES POWER COMPANY

,1

,sq ,1 By '/  ?/ / ( l(h Mf}&

Re'ger 0 Anderson Director Licensing and Management Issues OnthisN ay of MS /fkhbeforemeanotarypublicinandforsaid County, personally aVpeared Roger 0 Anderson, Director Licensing and Management Issues, and being first duly sworn acknowledged that he is authorized to execute this document on behalf of Northern States Power Company, that he knows the contents thereof, and that to the best of his knowledge, information, and belief the statements made in it are true and that it is not interpo ed elay.

g*ng

\/~

m ::::::.v::::::::::,v:::::::::::::: m MARCIA K. LaCORE NOTARY PUBLIC--M:NNESOTA HENNEPIN COUNTY My Commeon Expnes Sept 24.1933 wvw:::::::::::::::::::::::::::::::n

-