ML15218A097

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Forwards Request for Addl Info Re 830310 Proposed Amend to License DPR-55 & Proposed Rev to Tech Spec on Expansion of Storage Capacity of Spent Fuel Pool.Info Requested within 30 Days of Ltr Receipt
ML15218A097
Person / Time
Site: Oconee Duke Energy icon.png
Issue date: 05/23/1983
From: Stolz J
Office of Nuclear Reactor Regulation
To: Tucker H
DUKE POWER CO.
References
NUDOCS 8306150504
Download: ML15218A097 (3)


Text

IAY.

231983

'DISTRIBUTION J)Jc NRFU L PDR ORB#4 reading Docket No. 50-287 DEisenhut OELD EJordan JSuermann RIngram Mr. H. B. Tucker, Vice President NSIC Nuclear Production Department JTaylor Duke Power Company ACRS, 10 P. 0. Box 33189 Gray file 422 S. Church Street Charlotte, North Carolina 28242

Dear Mr. Tucker:

We have been reviewing your proposed amendment to the Oconee Nuclear Station Facility Operating License and proposed revision to the Oconee Technical Specifications dated March 10. 1983.

This submittal concerns the expansion of the storage capacity of the Oconee Unit 3 spent fuel pool from 474 to 825 spaces. In order to complete our structural review, the staff requires additional information. In this regard, please provide a repponse to the enclosed request for additional information within 30 days after receipt of this letter.

This request for additional information affects fewer than ten respondents; therefore, OMB clearance is not required under Public Law 96-511.

Sincerely, John F. Stolz, Chief Operating Reactors Branch #4 Division of Licensing

Enclosure:

As stated cc w/enclosure:

See next page 8306150504 830523 PDR ADOCK 05000287 P

PDR OFFICE)

ORB#4:DL 4DLII OFIEO.................................

JSuermann z

5/,O/83 _

5 NRC FORM 318 (10-80) NRCM 0240 OFFICIAL RECORD COPY USGPO: 1981-335-960

Duke Power Company cc w/enclosure(s):

Mr. William L. Porter Duke Power Company P. 0. 3ox 33189 422 South Church Street Office of Intercovernmental Relations Charlotte, North Carolina 28242 116 West Jones Street Raleigh, North Carolina 27603 Honorable James M. Phinney County Supervisor of Oconee County Walhalla, South Carolina 29621 Mr. James P. O'Reilly, Regional Administrator U. S. Nuclear Regulatory Commission, Region II 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 Reqional Radiation Representative EPA Region IV 345 Courtland Street, N.E.

Atlanta, Georgia 30308 Mr. J. C. Bryant Senior Resident Inspector U.S. Nuclear Regulatory Commission Route 2, Box 610 Seneca, South Carolina 29678 Mr. Robert B. Borsum Babcock & Wilcox Nuclear Power Generation Division Suite 220, 7910 Woodmont Avenue Bethesda, Maryland 20814 Manager, LIS NUS Corporation 2536 Countryside Boulevard Clearwater, Florida 33515 J. Michael McGarry, III, Esq.

DeBevoise & Liberman 1200 17th Street, N.W.

Washington, 0. C. 20036

ENCLOSURE DOCKET NO.

50-287 Recuest 1 rve sructural rwings of the pool and liner showing reinforcement of the walls and floor and attachment of the liner to the concrete.

2.

How are seismic effects modeled to account for a three-dimensional earthquake input for the sliding/tipping analysis?

- rvidae results of key structural calculations and comparison with allowable values for the design of the racks.

A Provide results of key structural calculations and comparison with allowable values for the analysis of the pool structure under the new rack loads.

5.

Describe the methods used to account for fluid inertia effects in the following analyses:

a. fuel bundle/rack impact analysis I-I I. -'

I LJ ~ Y ii

-'~

.Y

-a---I-J rd ac sI b

ildi t.i py i ng gliia Ifals C. seismic design of the rack structure

d.

seismic analysis of the pool structure

.Provide numerical results of the sliding/tipping analys-iswhich indicates minimum gaps between racks and/or pool structure for worst sliding and tioping compared to nominal caps for the racks as PIaced in the pool.

7. Describe the potential structural consequences of a cask drop accident on the pool structure including the pool floor, walls and liner. Provide results of computations showing comparisons of calculated and allowable values for pool structural components including the liner.
8. For the design of the rack ce-ls, describe the calculation procedure and acceptance criteria for local buckling of the thin gage material.