ML20209G693

Forwards Request for Addl Info Re Spent Fuel Storage Capacity Expansion

ML20209G693
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	07/14/1999
From:	Croteau R NRC (Affiliation Not Assigned)
To:	Wanczyk R VERMONT YANKEE NUCLEAR POWER CORP.
References
TAC-MA3490, NUDOCS 9907190226
Download: ML20209G693 (5)

Text

9-t Mr. Robert J. Wanczyk July 14, 1999 Acting Director of Operations Vermont Yankee Nuclear Power Corporation 185 Old Ferry Road Brattleboro, VT 05301

SUBJECT:

VERMONT YANKEE NUCLEAR POWER STATION, REQUEST FOR h

ADDITIONAL INFORMATION REGARDING SPENT FUEL STORAGE CAPACITY v

EXPANSION (TAC NO. MA3490)

.>e 6r Mr. Vlanczyk:

The Mechanical and Civil Engineering Branch has completed its review of your September 4,1998, submittal, as supplemented on February 8 and April 16,1999, concerning the proposed increase in the spent fuel pool storage capacity. We require additional information in order to complete our review. Please provide responses to the enclosed request for additional information within 60 days of receipt of this letter, as agreed to by Mr. Thomas Silko of your staff on May 19,1999.

Sincerely, ORIGINAL SIGNED BY:

Richard P. Croteau, Project Manager, Section 2 Project Directorate l Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-271

Enclosure:

Request For Additional Information cc w/ encl: See next page DISTRIBUTION Docket File PUBLIC E. Adensam T. Clark PDI-c 3dg.

K. Manoly S. Black C. Anderson, RI R. Croteau OGC ACRS DOCUMENT NAME: G:\\PDI-2Wermont\\RAl3490.wpd To receive a copy of this document, indicate 8:n the box: "C" = Copy without attachment / enclosure "E" = Copy with rttachment/ enclosure "N" = No copy OFFICE PM:PDl-2 LA:PDI-2 l EMEB 6 SC@lf l l

NAME RCroteathP TClarKjdL KManloyAT JCliff'o'P r

DATE 07/d/99 07/9/99 7//t/99 1/0 /99 l

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July 14, 1999

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Mr. Robert J. Wanczyk Acting Director of Operations Vermont Yankee Nuclear Power Corporation 185 Old Ferry Road Brattleboro, VT 05301 j

SUBJECT:

VERMONT YANKEE NUCLEAR POWER STATION, REQUEST FOR ADDITIONAL INFORMATION REGARDING SPENT FUEL STORAGE CAPACITY

{

EXPANSlON (TAC NO. MA3490)

Dear Mr. Wanczyk:

i The Mechanical and Civil Engineering Branch has completed its review of your September 4,1998, submittal, as supplemented on February 8 and April 16,1999, concerning l

the proposed increase in the spent fuel pool storage capacity. We require additional information in order to complete our review. Please provide responses to the enclosed request for additional information within 60 days of receipt of this letter, as agreed to by Mr. Thomas Silko of your staff on May 19,1999.

Sincerely, 7

Af /g Richard P. Croteau, Project Manager, Section 2 j

Project Directorate i Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-271

Enclosure:

Request For AdditionalInformation cc w/enci. See next page 1

4

}

Vermont Yankee Nuclear Power Station cc:

Regional Administrator, Region i Mr. Raymond N. McCandless U. S. Nuclear Regulatory Commission Vermont Department of Health 475 Allendale Road Division of Occupational King of Prussia, PA 19406 and Radiological Health 108 Cherry Street Mr. David R. Lewis Burlington, VT 05402 Shaw, Pittman, Potts & Trowbridge 2300 N Street, N.W.

Mr. Gautam Sen Washington, DC 20037-1128 Licensing Manager Vermont Yankee Nuclear Power Mr. Richard P. Sedano, Commissioner Corporation Vermont Department of Public Service 185 Old Ferry Road 112 State Street Brattleboro, VT 05301 Montpelier, VT 05620-2601 Resident inspector Mr. Michael H. Dworkin, Chairman Vermont Yankee Nuclear Power Station Public Service Board U. S. Nuclear Regulatory Commission State of Vermont P.O. Box 176 112 State Street Vernon, VT 05354 Montpelier, VT 05620-2701 Director, Massachusetts Emergency Chairman, Board of Selectmen Management Agency Town of Vernon ATTN: James Muckerheide P.O. Box 116 400 Worcester Rd.

Vernon, VT 05354-0116 P.O. Box 1496 Framinghani, MA 01701-0317 Mr. Richard E. McCullough Operating Experience Coordinator Jonathan M. Block, Esq.

Vermont Yankee Nuclear Power Station Main Street P.O. Box 157 P. O. Box 566 Governor Hunt Road Putney, VT 05346-0566 Vernon, VT 05354 G. Dana Bisbee, Esq.

Deputy Attorney General 33 Capitol Street Concord, NH 03301-6937 Chief, Safety Unit Office of the Attorney General One Ashburton Place,19th Floor Boston, MA 02108 Ms. Deborah B. Katz Box 83 Shelburne Falls, MA 01370

4 REQUEST FOR ADDITIONAL INFORMATION ON THE SPENT FUEL POOL STORAGE RACK MODIFICATION AT VERMONT YANKEE NUCLEAR POWER STATION The regulatory basis for these questions is to determine conformance with (1) the general design criteria for Vermont Yankee Nuclear Power Station (VYNPS) as specified in Appendix F of the VYNPS Final Safety Analysis Report, (2) the guidance of Standard Review Plan (SRP) 3.8.4 and 3.7.1, and (3) American Concrete Institute (ACl) 349-80.

.1. 'You indicated that the calculated seismic loading stresses in a fully-loaded rack will not exceed that of SRP Section 3.8.4 which was used as a guide. With respect to your stress calculations using the DYNARACK computer code presented in Chapter 6 of the submittal, provide the following:

a) Explain how the simple stick model used in the dynamic analyses can represent accurately and realistically the actual highly-complicated nonlinear hydrodynamic fluid-rack structure interactions and behavior of the fuel assemblies and the box-type rack structures. Discuss whether or not a finite element (FE) model with 3-D plate, beam and fluid elements together with appropriate constitutive relationships would be a more realistic, accurate approach to analyze the fluid-structure interactions in contrast to the stick model.

b) Provide the results of any prototype experimental study that verifies the correct or adequate simulation of the fluid coupling utilized in the numerical analyses for the fuel assemblies, racks and walls, if there is no such experimental study available, provide justification that the current level of the DYNARACK code verification is adequate for engineering application without further experimental verification work.

c) Provide the stiffness calculations for the rack used in the single rack analysis for the three (North-South, East-West and vertical) directions.

d) Provide the physical dimensions of the racks, and gaps between the racks, and the racks and the walls, e) Demonstrate that the artificial seismic time histories used in the analyses satisfy the

• 2 power spectral density (PSD) requirement of SRP 3.7.1.

2. _ You indicated that the design conditions described in SRP Section 3.8.4 and ACI 349-80 were userf as a guidance in the calculations of spent fuel pool (SFP) capacity. With respect to the SFP capacity calculations using the ANSYS computer code presented in Chapter 8 of the submittal:

a) Provide physical dimensions of the reinforced concrete slab and walls, liner plate and liner anchorage.

b) Provide the mesh used in the analysis, c) Identify and describe the boundary conditions used in the mesh.

Enclosure

.a

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. d) Provide the material properties used in the analysis.

e) Describe the applied loading conditions including the magnitudes, and indicate their i

locations in the mesh.

f) Explain how the interface between the liner and concrete slab is modeled, and also, how the liner anchors are modeled. Provide the basis for using such modeling with respect to how they accurately represent the real structural behavior; g) Provide the calculated governing factors of safety in a tabular form for the axial, shear, bending, and combined stress conditions.

h) What is the maximum bulk pool temperature at a full-core offload during a refueling outage? If the temperature exceeds 150 'F, provide the following:

i) Describe the details of the SFP structural analysis including the material properties (i.e., modulus of elasticity, shear modulus, poisson's ratio, yield stress and strain, ultimate stress and strain, compressive strength) used in the analysis for the reinforced concrete slab and walls, liner plato, welds and anchorages in the analysis.

ii) ACI Code 349 limits a concrete temperature up to 150 'F for normal operation or any other long-term period. Provide technical justifications for exceeding the required temperature of 150 *F.

l