ML20085C993

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Forwards Rev to 900831 Application for Amends to Licenses DRP-42 & DPR-60,modifying Auxiliary Bldg Crane Per Single failure-proof Criteria in Section 5.1.6 & App C of NUREG-0612
ML20085C993
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 10/04/1991
From: Parker T
NORTHERN STATES POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20085C994 List:
References
RTR-NUREG-0612, RTR-NUREG-612 NUDOCS 9110150178
Download: ML20085C993 (2)


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Northem States Power Cornpany 414 tecoilei Mall M.nnea; ohs. Minnesota f64011927 Telephone (61P) 3X) 5500 October 4, 1991 10 CFR Part 50 Section 50.9d U S Nuclear Regulatory Commission Attn: Document Control Desk Vashington, DC 20555 PRAIRIE ISINiD NUCLEAR CENERATING l'1 ANT Docket Nos. 50-282 License Nos. DPP 42 50 306 DPR-60 License Amendment Request Dated October 4, 1991 Single-Failure-Proof Crane Upgrade 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 5 0 . i> 0 .

In an application dated August 31, 1990, Northern States Power Company applied for a license to conctruct and operate a Dry Cask Independent Spent Fuel Storage Installation to be located on the Prairie Irland Site. The license was requested for the storage of spent fuel from the Prairie Island Nuclear Generating Plant in Transnuclear TN 40 stornge casks.

liowever, because of the height of the TN 40 storage casks, it is not practical to use an impact lirtiter or crash pad, as prescribed by Technical Specification 3.8.11.1.b.2, during the handling and loading of those casks. Therefore, Northern States Power has contracted ;ith Ederer Incorporated to modliy the auxiliary building arane in accordance with the single-tailure-r, roof criteria of Section 5.1.6 and Appendix C of NUREC 0612. This modification consists of replacement of the existing bridge trolley with an Ederer designed trolley and associated hoists. The upgrade of the auxiliary building crane to 4. single-failure proof-design is scheduled to be completed in 1992.

The Technical Specification changes described in the attached License Amendment Request eliminate the cask handling restrictions imposed by the current Technical Specifications and replace them with requirements for the use of a single-failure-proof handling system in the handling of heavy loads. The changes t 911r:1 %1/s vt1004 von nonce wooo m h

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Northern States Power Cornpany October 4, 1991 Page 2 include the addition of requirements in Section 5.6 requiring the use of a single-failure proof handling system for handling spent fuel casks and new surveillance requirements on lif ting devices to be used f.or handling heavy loads by the auxiliary building crane over safe shutdown equipment or spent fuel in the spent fuel pool.

Exhibit A contains a description of the proposed changes, the reasons for requesting the changes and the supporting 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.

As noted in Exhibit A, the plant specific design details of the auxiliary building cane uPbrade are still under preparation. Based on the current schedule, the plant specific design information should be provided for NRC Staf f review in December of 1991.

Please contact un if you have any questions related to this License Amendnient Request.

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'ker Manager Nuclear Support Services c: Regional Administrator III, NRC NRR Project Manager, NRC Senior Resident inspector NRC MPCA Attn: J V Ferman J E Silberg Independent Spent Fuel Storage Installation Service List 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