ML20140A711

Forwards Application for Amends to Licenses DPR-42 & DPR-60, Authorizing Tech Spec Revs for Cycle 11 Operations Including Temp Coefficient,Accumulator Spec & Peaking Factor Changes.Fee Paid

ML20140A711
Person / Time
Site:	Prairie Island
Issue date:	01/13/1986
From:	Musolf D NORTHERN STATES POWER CO.
To:	NRC COMMISSION (OCM)
Shared Package
ML20140A716	List: ML20140A711 ML20140A718 ML20140A731 ML20140A747 ML20140A751 ML20140A775 ML20140A781
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.K.3.31, TASK-TM NUDOCS 8601230353
Download: ML20140A711 (2)

Text

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4 o Northern States Power Company 414 Nicollet Mall Minneapohs, Minnesota 55401 Telephone (612) 330-5500 January 13, 1986 Director Office of Nuclear Reactor Regulation U S Nuclear Regulatory Commission Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket Nos. 50-282 License Nos. DPR-42

• 50-306 DPR-60 License Amendment Request dated January 13, 1986 Change to Westinghouse Fuel and Miscellaneous Changes

Reference:

Meeting Minutes prepared by the NRC dated July 31, 1985 entitled, " Summary of June 26, 1985 Meeting Associated with Upcoming Changes to the Reactor Internals and Impact on the Technical Specifications" Attached are three originals and 37 conformed copies of a request for change to the Technical Specifications, Appendix A, of Operating Licenses DPR-42 and DPR-60. In accordance with 10 CFR Part 170, a check in the amount of $150.00 is enclosed. 3 This change proposes the Technical Specification changes necessary for the operation of Unit 1 Cycle 11. A change in fuel suppliers has been made for Unit 1 Cycle 11. Westinghouse will supply fuel for Unit 1 Cycle 11 and subsequent cycles. Two hardware changes will be incorporated in Unit 1 Cycle 11. The upper internals are being replaced with new internals of the " inverted top hat" des i gn. Also, thimble plugs will be removed from fuel assemblies for the irst time for Unit 1 Cycle 11. A safety evaluation of the change to the new upper internals will be submitted for year information in the near future. A safety evaluation for the thimble plug removal has been submitted and approved by the NRC Staff in an SER dated October 18, 1985. These hardware changes do not affect the Technical Specifications, but have been accounted for in the supporting analyses, where appropriate.

Changes incorporated in this submittal are: 1) referencing the WRB-1 DNB correlation, 2) temperature coefficient changes, 3) accumulator specification changes, 4) peaking factor changes, and 5) deletion of the third line segment of the K(z) curve.

f, Exhibit A describes the proposed changes, provides the reasons for the 8601230353 860113 PDR P

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changes, and provides the supporting significant hazards evaluation.

Exhibit B contains the proposed changes marked up on the existing Technical Specification pages. Exhibit C contains the revised Technical Specifica-tion pages.

The information contained in Exhibit D was requested by the NRC Staff at the. referenced June 26, 1985 meeting discussing this submittal. Exhibits E thtu H support the evaluations in Exhibit A.

In addition to supporting this amendment, Exhibit F. and G, the small break LOCA analyses for Westinghouse and Exxon fuel, are being submitted to '

satisfy the requirements of NUREG 0737, Item II.K.3.31.

Please contact us if you have any questions concerning this License Amendment Request. NRC Staff review and approval of these changes is requested prior to April 15, 1986 to support the operation of Unit 1 Cycle 11.

David Musolf kw Manager - Nuclear Suppor Services DMM/TMP/tp t

c: Regional Administrator-III, NRC NRR Project Manager, NRC -

Resident Inspector, NRC MPCA Attn: J W Ferman G Charnoff Attachments:

Affidavit l Exhibit A - Evaluation of Proposed Changes to the Technical' Specifications i Exhibit B - Proposed Changes Marked Up on Existing Technical Specification

'l Pages Exhibit C - Revised Technical' Specification Pages-

< Exhibit D - Prairie Island Unit 1 Westinghouse OFA Transition Reloads Exhibit E - Demonstration of the Conformance of the Prairie Island Units to l . Appendix K and 10CFR50.46 for Large, Break LOCAs Exhibit F - Demonstration of the Conformance 'of the Prairie Island Units to j Appendix K and 10CFR50.46 for Small Break LOCAs l Exhibit G - Demonstration of the Conformance of the Prairie Is1. nd Units with l ' Exxon Fuel Assemblies to Appendix K and 10CFR5Cate for Small Breok LOCAs l Exhibit H - Safety Evaluation of Increased FQ, FdH and Isothermal

Temperature Coefficient-

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