ML20101F455: Difference between revisions

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| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 2
| page count = 2
| project =  
| project = TAC:56614, TAC:56615
| stage = Withdrawal
| stage = Withdrawal
}}
}}

Latest revision as of 01:23, 24 September 2022

Forwards Application for Amends to Licenses DPR-42 & DPR-60. Amends Change Sections 3.8 & 5.6 of Tech Specs Re Insertion & Withdrawal of Pool 1 Spent Fuel Shipping Cask,Eliminating Restriction of Assemblies Stored Onsite.Fee Paid
ML20101F455
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 12/21/1984
From: Musolf D
NORTHERN STATES POWER CO.
To:
Office of Nuclear Reactor Regulation
Shared Package
ML20101F457 List:
References
TAC-56614, TAC-56615, NUDOCS 8412270175
Download: ML20101F455 (2)


Text

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r-cm ,s Northem States Power Company 414 Niconet Vxt Minneapons Mennesota 55401 Teephone q612) 330 5500 December 21, 1984 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 50-305 DPR-60 License Amendment Request dated December 21, 1984 Removal of Restriction on Use of 266 Existing Spent Fuel Storage Spaces Attached are three originals and 37 conformed copies of a request for a change of Technical Specifications, Appendix A, of Operating Licenses DPR-42 and 60. Also enclosed is a check in the amount of $150.00 in accordance with 10 CFR Part 170 as the required application fee.

This submittal proposes changas to Sections 3.8 and 5.6 of the Prairie Island Technical Specifications. The requested changes will allow the insertion and withdrawal of a Spent Fuel Shipping Cask in Pool No. I thereby eliminating the temporary restriction on the number of assemblies that can be stored onsite.

Exhibit A contains a description of the proposed changes, the reason for these changes, and a significant hazards evaluation. Exhibit B contains the revised Technical Specification pages. Exhibit C contains Report No.

Quad-1-83-017 prepared by Quadrex Corporation entitled " Licensing Report for Prairie Island Nuclear Generating Plant Units 1 and 2 Spent Fuel Cask Drop Evaluation".

The crash pad depicted in Exhibit 0 is intended to be a typical crash l pad design only. This report ' describes the method which would be used to evaluate energy absorbing capabilities of crash pads. Other materials and designs are available which could be substituted.

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8412270175 841221 p DR ADOCK 05000282 i p PDR g0k M

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l 1 Dir of NRR December 21, 1984

.- Page'2 Northem States Power Company Please contact us if you have any questions related to our request.

D David Mucoif Manager - Nuclear Su t Services DMM/ TAP / dab c: Regional Administrator-III, NRC NRR Project Manager, NRC Resident Inspector, NRC MPCA Attn: J W Ferman G Charnoff Attachments

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