ML20059B505
| ML20059B505 | |
| Person / Time | |
|---|---|
| Site: | Millstone |
| Issue date: | 10/26/1993 |
| From: | Vissing G Office of Nuclear Reactor Regulation |
| To: | Opeka J CONNECTICUT YANKEE ATOMIC POWER CO., NORTHEAST NUCLEAR ENERGY CO. |
| References | |
| TAC-M86361, NUDOCS 9310280239 | |
| Download: ML20059B505 (4) | |
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October 26, 1993 Docket No. 50-336 Mr. John F. Opeka Executive Vice President, Nuclear Connecticut Yankee Atomic Power Company Northeast Nuclear Energy Company Post Office Box 270 Hartford, Connecticut 06141-0270
Dear Mr. Opeka:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION CONCERNING TECHNICAL SPECIFICATIONS FOR SPENT FUEL STORAGE POOL MODIFICATIONS -
MILLSTONE 2 (TAC NO. M86361)
In our review of your application for amendment dated May 14, 1993, concerning
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the technical specifications related to the proposed modification of the Millstone 2 Spent Fuel Storage Pool, we have identified the need for 1
additional information. The enclosure provides details concerning the information that is needed.
Please provide a quick response to accommodate your schedule for implementation.
This requirement affects one respondent and, therefore, is not subject to Office of Management and Budget review under P.L.96-511.
Sincerely, t
Original signed by Guy S. Vissing, Senior Project Manager Project Directorate I-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosure:
Request for Additional Information cc w/ enclosure:
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.0ctober 26, 1993 Docket No. 50-336 Mr. John F. Opeka Executive Vice President, Nuclear Connecticut Yankee Atomic Power Company Northeast Nuclear Energy Company Post Office Box 270 Hartford, Connecticut 06141-0270 D"at Mr. Opeka:
SUE,... i:
REQUEST FOR ADDITIONAL INFORMATION CONCERNING TECHNICAL SPECIFICATIONS FOR SPENT FUEL STORAGE POOL MODIFICATIONS -
MILLSTONE 2 (TAC NO. M86361)
In our review of your application for amendment dated May 14, 1993, concerning the technical specifications related to the proposed modification of the M111 stone' 2 Spent Fuel Storage Pool, we have identified the need for additional information. The enclosure provides details concerning the information that is needed.
Please provide a quick response to accommodate your schedule for implementation.
This requirement affects one respondent and, therefore, is not subject to Office of Management and Budget review under P.L.96-511.
Sincerely, Guy S. Vissing, Senior Project Manager Project Directorate I-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosure:
Request for Additional Information cc w/ enclosure:
See next page d
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y Mr. John F. Opeka Millstone Nuclear Power Station Northeast Nuclear Energy Company Unit 2 cc:
Gerald Garfield, Esquire R. M. Kacich, Director Day, Berry and Howard Nuclear Licensing Counselors at Law Northeast Utilities Service Company City Place Post Office Box 270 Hartford, Connecticut 06103-3499 Hartford, Connecticut 06141-02'/0 W. D. Romberg, Vice President J. P. Stetz, Vice President
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Nuclear Operations Services Haddam Neck Plant Northeast Utilities Service Company Connecticut Yankee Atomic Power Company Post Office Box 270 362 Injun Hollow Road Hartford, Connecticut 06141-0270 East Hampton, Connecticut 06424-3099 Kevin T. A. McCarthy, Director Regional Administrator Monitoring and Radiation Division Region I Department of Environmental Protection U.S. Nuclear Regulatory Commission 79 Elm Street 475 Allendale Road
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Post Office Box 5066 King of Prussia, Pennsylvania 19406 Hartford, Connecticut 06102-5066 Allan Johanson, Assistant Director First Selectmen Office of Policy and Development Town of Waterford i
Policy Development & Planning Division Hall of Records l
80 Washington Street 200 Boston Post Road Hartford, Connecticut 06106 Waterford, Connecticut 06385 S. E. Scace, Vice President P. D. Swetland, Resident Inspector Millstone Nuclear Power Station Millstone Nuclear Power Station Northeast Nuclear Energy Company c/o U.S. Nuclear Regulatory Commission Post Office Box 128 Post Office Box 513 Waterford, Connecticut 06385 Niantic, Connecticut 06357 G. H. Bouchard, Nuclear Unit Director Charles Brinkman, Manager Millstone Unit No. 2 Washington Nuclear Operations Northeast Nuclear Energy Company ABB Combustion Engineering Post Office Box 128 Nuclear Power Waterford, Connecticut 06?85 12300 Twinbrook Pkwy, Suite 330 Rockville, Maryland 20852 Nicholas S. Reynolds Winston & Strawn J. M. Solymossy, Director 1400 L Street, NW Nuclear Quality and Assessment Services Washington, DC 20005-3502 Northeast Utilities Service Company Post Office Box 270 Hartford, Connecticut 06141-0270
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a Recuest for Additional Information i
Millstone Unit 2 Spent Fuel Storace Pool Modifications Docket No. 50-336 1.
The seismic and structural reports provided in the June 10, 1993, and July 16, 1993 submittals did not provide sufficient information to independently verify that the original analysis bounds the proposed Region C storage capacity expansion.
Please provide the following additional information:
a)
A complete list and description of all the seismic load cases for which a CESH0CK or SAP IV analysis was performed.
i b)
A complete set of results for each load case. This should include displacements, loads and stresses.
c)
A detailed description of the ESHOCK fuel rack models for both normal and consolidated fuel.
Provide quantitative information that highlights the differences between the models including weight, stiffness, natural frequencies, fuel to rack cell gaps, and hydrodynamic mass and coupling parameters, d)
How were the cell blocking devices considered in the analyses?
Did the analysis of a fully loaded rack with standard fuel consider that only 75 percent of the total number of cells would be used?
e)
When poison rods are added to standard fuel assemblies, what is the percentage weight increase to a sir 31e fuel assembly and to the fuel rack?
2.
The stress results given in the spent fuel rack structural report provided in the June 10, 1993 submittal indicated that the smallest stress margin occurs in a weld (maximum stress of 23,353 psi compared to an allowable of 24,000 psi).
Please provide a copy of the weld stress calculation for review. The calculation should indicate the load case and load combination that was considered, how the loads were determined, and the location of the maximum weld stress.
3.
The stress results given in the spent fuel rack structural report provided in the June 10, 1993 submittal did not discuss fuel to rack i
storage cell impact loads or their evaluation.
Please include a summary of maximum impact loads for each load case in the response to question 1(b). Describe how the impact loads are evaluated for local as well as overall effects considering local stresses in the cell walls and inter-cell welds and potential damage to the fuel.
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