ML20053D322
| ML20053D322 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 06/01/1982 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Fiedler P JERSEY CENTRAL POWER & LIGHT CO. |
| References | |
| TASK-09-01, TASK-9-1, TASK-RR LSO5-82-06-001, LSO5-82-6-1, NUDOCS 8206040296 | |
| Download: ML20053D322 (4) | |
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- t June 1,1982 Docket No. 50-219 LS05-82-06-001 4
Mr. P. B. Fledler Vice President and Director - Oyster Creek Oyster Creek Nuclear Generating Station Post Office Box 388 Forked River, New Jersey 08731
Dear Mr. Fledler:
SUBJECT:
SEP TOPIC IX-1, FUEL STORAGE OYSTER CREEK NUCLEAR GENERATING STATION Enclosed is the staff's evaluation of SEP Topic IX-1, " Fuel Storage" for the Oyster Creek facility. This assessment compares your facility as described in Docket No. 50-219 with the criteria current-ly used for licensing new facilities.
This evaluation will be a basic input to the integrated safety asses-ment for your facility unless you identify changes needed to reflect the as-built conditions at your facility. This assessment may be re-vised in the future if your facility design is changed or if NRC criteria relating to this subject are modified before the integrated assessment is completed.
Sincerely.
Crisinel cicnenyi i
Dennis M. Cr6tchfield, Chief Operating Reactors Branch No. 5 Division of Licensing As stated g
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SYSTEMATIC EVALUATION PROGRAM TOPIC IX-1 OYSTER CREEK TOPIC:
IX-1, Fuel Storage I.
INTRODUCTION The purpose of SEP Topic IX-1 is to review the storage facility for new and irradiated fuel, including the cooling capability and seismic classification of the fuel pool cooling system of the spent fuel storage pool in order to assure that new and irradiated fuel are stored safely with respect to criticality, cooling capability; shield-ing, and structural capability.
II.
REVIEW CRITERIA The plant design was reviewed with regard to Section VI, " Fuel and Radioactivity Control"of' Appendix A to 10 CFR Part 50, General Design Criteria for Nuclear Power Plants" which requires that the fuel stor-age systems shall be designed to assure adequate safety under normal and postulated accident conditions.
III. RELATED SAFETY TOPICS SEP Topic II-3.B. " Flooding Potential and Protection Requirements" identifies the design basis flood for which the plant must be ade-quately designed.
SEP Topic III-1, " Classification of Structures, Components and Systems (Seismic and Quality)" is intended to assure that structures, systems and components important to safety are of the quality level commensur-ate with their safety function.
SEP Topic III-4. A " Tornado Missiles" covers tornado missile protection of a number of structures and systems including fuel storage areas and support systems.
SEP Topic III-6, " Seismic Design Considerations" will ensure the capa-bility of the plant to withstand the effects of earthquakes.
SEP Topic IX-2, " Overhead Handling Systems-Cranes" covers the potential for dropping heavy objects onto spent fuel.
This topic has been deleted since the review criteria is identical to that of Unresolved Safety <
Issue A-36 " Control of Heavy Loads Near Spent Fuel."
SEP Topic IX-5, " Ventilation Systems" assures that the ventilation systems have the capability to provide a safe environment for plant personnel and engineered safety features equipment.
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, IV.
REVIEW GUIDELINES Current guidance for the review of spent fuel storage is provided in Standard Review Plan Section 9.1.0 New Fuel Storage, Section 9.1.2 Spent Fuel Storage, Section 9.1.3 Spent Fuel Pool Cooling and Clean-up System, Section 9.1.4 Fuel Handling System and Regulatory Guides 1.29 Seismic Design Classification,1.13 Fuel Storage Facility Design Basis,1.26 Quality Group Classificat, ion and Standards for Water-Steam and Radioactive Waste-Containing Components of Nuclear Power Plants as well as the guidance contained in the April 14, 1978 generic letter -
OT Position for Review and Acceptance of Spent Fuel Storage and Handl-ing Applications (i.e., D0R Technical Activities Category A Item 27, Increase in Spent Fuel Storage Capacity).
Those portions of the topic which have been previously reviewed to current criteria have not been reevaluated.
V.
EVALUATION By letter dated March 18, 1976, as supplemented by letters dated August 11, 1976, November 30, 1976, January 18, 1977, and February 23, 1977, the licensee requested an amendment to their operating license.to allow for increased on-site storage of spent fuel. On March 30,1977 the staff issued Ammendment 22 to Provisional Operating License No. DPR-16 allowing the increased spent fuel storage capacity and included a Safety Evaluation (SE) supporting the proposed facility modifications.
Since the existing fuel rack design remains the same as that reviewed and approved in the previous NRC safety evaluation our ccnclusions con-cerning the criticality analysis, rack, mechanical and material review, radiation level, nuclear; thermal and hydraulic aspects and heat removal capability of the spent ft.al pool cooling system remain valid.
Since the staff analysis was performed in accordance with current licens-ing criteria, we conclude that the March 30, 1977 SE satisfies the re-quirements of SEP Topic IX-1.
The structural response of the Oyster Cieek facility with respect to seismic capability is being evaluated as part of SEP Topic III-6, " Seismic Design Consfderations."
In addition, the March 30, 1977 SE states that the spent fuel storage racks, lined spent fuel pool and fuel pool gates are designed as Seismic Category I and.are therefore, acceptable.
, Regarding new fuel storage, the new fuel storage vault is located within the reactor building. The fuel is stored within a subcritical array which will ensure Keff < 0.95 if the vault were flooded.
The vault has concrete covers which wT11 prevent the introduction of aqueous mists or foams and will also limit water leakage into the vault. Vault drainage is provided to prevent water accumulation. Therefore, no moderator conditions between 100% and 0% water can reasonably be expected to occur and Keff will be <.95.
The fuel storage vault is covered by concrete covers which protect the stored fuel bundles from damage due to dropped objects. Based on the above considerations, we conclude that the new fuel storage facility meets the guidance of Standard Review Plan 9.1.1.
VI.
CONCLUSION Based on the above considerations, we conclude that the Oyster Creek fuel storage systems meet current acceptance criteria. We further conclude that SEP Topic IX-1 is complete.
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