ML20214K001

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Submits Addl Info Re Par Rack Lifting Rig Design Associated W/Proposed Tech Spec Change 133 Re Spent Fuel Pool Expansion,In Response to Request.Lifting Device Designed Per NUREG-0612 Criteria.W/One Oversize Drawing
ML20214K001
Person / Time
Site: Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date: 05/22/1987
From: Capstick R
VERMONT YANKEE NUCLEAR POWER CORP.
To: Rooney V
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM), Office of Nuclear Reactor Regulation
Shared Package
ML20214K005 List:
References
RTR-NUREG-0612 FVY-87-57, NUDOCS 8705280286
Download: ML20214K001 (2)


Text

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VERMONT YANKEE NUCLEAR POWER CORPORATION RD 5. Box 169. Ferry Road, Brattleboro, VT 05301

,3,g 70 g

ENGINEERING OFFICE

%t1 WORCESTER ROAD FRAM:NGHAM, MASSACHUSETTS 01701 TELEPHONE 617 872-8100 May 22, 1987 FVY 87-57 United States Nuclear Regulatory Commission Document Control Desk l

Washington, DC 20555 Attention:

Office of Nuclear Reactor Regulation Mr. V. L. Rooney, Senior Project Manager BWR Project Directorate No. 2 l

Division of BWR Licensing l

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References:

(a) License No. DPR-28 (Docket No. 50-271) l (b) Letter, VYNPC to USNRC, FVY 86-34, " Proposed Technical Specification Change for Spent and New Fuel Storage,"

dated April 25, 1986 (c) Letter, VvNPC to USNRC, FVY 87-42, " Vermont Yankee Proposed Change No. 133, Spent Fuel Pool Expansion -

Responsri to Request for Additional Information (Rack Lifting Rig Designs)," dated April 13, 1987

Subject:

Vermont Yankee Proposed Change No. 133, Spent Fuel Pool Expansion - Response to Request for Additional Information (par Rack Lifting Rig Designs)

I

Dear Sir:

In response to your recant request, Vermont Yankee herein providos the additional information concerning the par rack lifting rig design associated with our proposed spent fuel pool expansion Technical Specification change submittal [ Reference (b)].

A conceptual design drawing of the par lifting fixture device is enclosed with this letter.

The par lifting device will be designed and verified to meet the stress and redundancy criteria of NUREG-0612.

The preoperational load test for each lift system will consist of 150% of the empty spent fuel rack weight.

The lifting tool for removing the par-designed spent fuel racks utilizes four lifting arms which protrude downward from the strongback through four h

open cells in the racks. These directly engage the rack base plate. The design will provide redundant load paths to the Reactor Building crane.

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8705280286 870522 O gDR ADOCK 05000271 PDR 3

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_ United States Nuclear Regulatory Commission May-22, 1987 Attention:

Mr. V. L. Rooney Page 2' j

We trust that:the information contained with this letter is satisfactory; however, should.you have any questions, or ret.uire further information regarding this matter, please contact this office.

'Very truly yours VERMONT YANKEE. NUCLEAR POWER CORPORATION

.h As R. W. Capstick Licensing Engineer

- RWC/dlb Enclosure j.

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