ML20003B779

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Application for Amend to License DPR-28 to Approve Cask Lifting Device.Design of Proposed Lifting Device Adequate to Withstand Dynamic Loads Imposed by Overhead Handling Sys Under Postulated Conditions
ML20003B779
Person / Time
Site: Vermont Yankee Entergy icon.png
Issue date: 02/11/1981
From: Rich Smith
VERMONT YANKEE NUCLEAR POWER CORP.
To: Ippolito T
Office of Nuclear Reactor Regulation
References
FVY-81-30, NUDOCS 8102250488
Download: ML20003B779 (2)


Text

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VERMONT Y AN K EE NUCLEAR POWER CORPORATION

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}a T EL E PH O Pe E 517-572-8100 E t - February 11, 1981 t

9 United States Nuclear Regulatory Commission Washington , D. C. 20555 Attention: Office of Nuclear Reactor Regulation Mr. T. A. Ippolito, Chief Operating Reactors Branch #2 Division of Licensing

References:

(a). License No. DPR-28 (Docket No. 50-271)

(b) Letter, R. W. Reid to -R. H. Groce, dated January 28, 1977: Amendment No. 29 'to Facility Operating License No. DPR-28 (c) Certificate of Compliance No. 6375, Rev.10, Docket No.

71-6375, Chem-Nuclear Systems, Inc. Cask CNS 4 45

Subject:

Request for NRC Review- and Approval of Cask Lifting Device

Dear Sir:

Vermont Yankee currenty has an inventory of activated - reactor components which have served their useful life and now require disposal. Due to the radiation ' levels associated with these components, a shielded cask of the spent fuel type will be required to provide adequate shielding for transportation to a licensed disposal site. Vermont Yankee has investigated the availability and suitability. of existing casks and has determined that the Chem-Nuclear Systems, Inc, cask (CNS 4-45 cask) is adequate for this purpose.

l Reference (b) requires that any cask being used over the fuel pool at Vermont Yankee be evaluated to provide assurance that the redundancy of the

. Vermont Yankee Reactor Building crane will be maintained and that there will l

be nil ' displacement of the load in the event of a single failure in the lifting system. Reference (b) also requires that all such evaluations be l

l reviewed and approved by'the NRC prior to 'any movement of the cask.

l . .

i Accordingly, Verer.t Yankee herewith, submits supporting information on

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, the lifting devices to be used by Vermont Yankee for this application and requests NRC approval of their use.

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United States Nuclear Regulatory Commission February 11, 1981 I Washington, D. C. 20555 Page 2 The proposed lifting device is fully redundant and compatible with both the CNS 4-45 cask and the Vermont Yankee redundant crane hook. The cask is equipped with four (4) li fting trunnions , two (2) at the top and two (2) at

'. the bottom. The lif ting device consists of a primary lifting rig coupling the top cask trunnions to the redundant block of the reactor building crane and a secondary lifting rig cou? ling the bottom cask trunnions to the sister hook of the reactor building creae. During lifting, both lifting rigs share the load, therefore, in the event of a failure of one rig, there would be no load dis pla cement .

The lifting device is designed to meet the loading requirements of HUREG 0554. Each lifting rig is designed dynamically for a minimum load rating of three (3) times the maximum loaded cask weight (3x70,000 pounds; note that the loaded cask weighs 67,050 pounds) based on yield point. The preoperational test load for each rig will consist of 130% of the loaded cask weight or 87.500 pounds.

Using these conservative conditions, Vermont Yankee has determined that the design of the proposed lifting device is adequate to withstand the dynamic loads imposed by the overhead handlilg system under the postulated conditions.

The NRC review of this submittal involves a single safety issue and does not involve a significant hazards consideration. For these reasons, Vermont Yankee Nuclear Power Corporation proposes this submittal as a Class III application. A payment of $4,000.00 is enclosed.

We trust that the information provided above is sufficient for your review of this lifting device. We respectfully request your immediate attention to this matter because our current plans entail commencement of shipping of the irradiated material mentioned during the first quarter of 1981.

Should you require additional clarification or information, please feel free to contact us.

Very truly yours, VERMONT YANKEE NUCLEAR POWER CORPORATION sd?.5 a-R. L. Smith Licensing Engineer

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