ML20092A623

Forwards App B Suppl to Generic Licensing Topical Rept EDR-1, Summary of Plant Specific Crane Data Supplied by Ederer Inc for NSP Co Praire Island Nuclear Generating Plant Units 1 & 2 Auxiliary Bldg Crane

ML20092A623
Person / Time
Site:	Prairie Island
Issue date:	02/03/1992
From:	Parker T NORTHERN STATES POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20092A626	List: ML20092A623 ML20092A667 ML20092A679
References
NUDOCS 9202100205
Download: ML20092A623 (3)

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Northem States Power Company 414 Nicollet Mall Minneapolis IAnnesota $54011927 Telephone (612) 330 5500 February 3, 1992 10 CPR part 50 Section 50.90 U S Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 PRAIRIE ISLAND NUCLEAR CENERATING PLANT Docket Nos. 50-282 License Nos. DpR 42 50 306 DpR 60 Supplemental Information to Support the License Amendment Request Dated October 4, 1991 Sipcle Failure pIoof Crane Uncrade In our License Amendment Request dated October 4,1991 ve submitted proposed Technical Specification changes which elininate cask handling restrictions and replace them with requirements for the use of a single failure proof handling system in the handling of heavy loads. The propose of this letter is to provide supplemental information in support of the October 4, 1991 License Amendment Request. This supplemental information includes plant design details for the auxiliary building crane upgrade and design '1 formation on the i

special lifting devices to be utilized in handling the TN 40 spent fuel storage casks.

As stated in the October 4, 1991 1 icense Amendatnt Request, Northern States I power has contracted with Ederer Incorporated to modify the auxiliary building crano in accordance with the single failure proof criteria of NUREC 0612.

This modification will consist of the replacement of the existing bridge trolley with an Ederer designed trolley and asrcciated hoists which are comparable to that described in Revision 3, Amendment 3 of the Ederer l Incorporated Generic Licensing Topical Report EDR 1(p)-A, "Ederer Nuclear l Safety-Related Extra Safety and Monitoring (X-SAM) Cranes", dated October 8, 1982. The report describes the design and testing of the single failure proof features which are included in Ederer's X SAM cranes intended for handling spent fuel casks and other safety related loads in a nuclear power plant. NRC Staff approval of the report was documented in a Safety Evaluation transmitted l by NRC letter dated August 26, 1983.

The Appendix B and Appendix C Supplements to Topical Report EDR 1 are provided for NRC_ Staff review by Attachments 1 and 2 to this letter. The Appendix B supplement to Topical Report EDR 1 provides a summary of plant specific crane data supplied by Ederer Incorporated for the prairie Island auxiliary building crane. The Appendix C supplement to Topical Report EDR 1 providen a summary of plant specific data supplied by Northern States power for the prairie Island auxiliary building crane _ modifications.

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USNRC February 3, 1992 Northern States Power Company Page 2 The design criteria for the special lifting device to be utilized in handling the TN 40 spent fuel storage casks at Prairie Island is provided for NRC Staff review by Attachment 3 to this letter.

Ir performing the seismic qualification of the modified Prairie Island auxiliary building crane Northern States Power has followed the guidance of Section 2.5 of NUREG 0554. The evaluation of the modified auxiliary building crane took into account the increased weight of the new trolley, the actual bridge weight and the maximurn critical load on the crane book.

The resultant lateral seismic loads imparted on the auxiliary building runway girders has increased from the original design. Northern States Power has chosen to modify the existing runway girders by providing additional stiffness / strength in order to meet American Institute of Steel Construction (AISC) structural code requirements.

Please contact u if you have any questions related to the information provided. ,

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/l) Y Thomas M Parker Manager Nuclear Support Services c: Regional Administrator Region III, NRC Senior Resident inspector, NRC NRR Project Manager, NPC J E Silberg Attachments:

1. Appendix B Supplerent to Generic Licensing Topical Report EDR.1.

2. Appendix C Supplement to Generic Licensing Topical Report EDR.1.

L 3. Design Criteria for Lifting System for TN.40 Dry Storage Cask.

l'RA1RIE IS!.AND NUCI.1%R CENERATING PLANT i

ATTACllMENT 1

. Appendix B Suppleinent to Generic Licensing Topical Report EDR.1 P

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