ML20148G660
| ML20148G660 | |
| Person / Time | |
|---|---|
| Site: | 07002858 |
| Issue date: | 10/04/1978 |
| From: | Delaney J NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20148G636 | List: |
| References | |
| NUDOCS 7811130131 | |
| Download: ML20148G660 (3) | |
Text
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Safety Evaluation Report Public Service Electric and Gas Company (PSEG)
Application Dated April 12, 1978, and the Supplements Thereto Dated April 28, June 22, July 19, and September 6 and 22, 1978 For a Storage License for Fuel and Accessories for the Salem Nuclear Generating Station, Unit 2 Docket No. 70-2858 Public Service Electric and Gas Company on behalf of itself and Phila-delphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company requests a license to receive 2428 kilograms of U-235 as uranium enriched up to 3.1% in the U-235 isotope continued in reactor fuel assemblies, up to 120 milligrams of U-235 at any enrichment contained in incore detectors,12 milligrams of U-238 and 18 milligrams of Np-237 in flux dosimeters, and up to 500 mil 11 curies of Cf-252 and associated isotopes in encapsulated neutron sources.
The neutron sources, reactor vessel flux dosimeters, and incore detectors are to be stored in the Unit 2 fuel handling building storage area which is a completely segregated area from the remainder of the fuel handling building. The only entrance to the storage area is by two exterior doors ,
which are locked at all times. All sources are to be stored in their shielded shipping containers. PSEG states that periodic surveys will be performed to assure the integrity of the shipping containers and sources.
The standard license condition regarding leak testing of sealed sources is being made a part of the license in accordance with standard operating procedure. Prior to loading of fuel in the core, as may be authorized by a facility operating license, the neutron sources will be installed it.
their respective fuel assemblies.
The fuel assemblies which the applicant wishes to revise contain uranium enriched in the U-235 isotope. Nominal enrichments are 2.10, 2.60, and 3.10% U-235. Because of measurements and enrichment variations usually encountered, it is proposed that a maximum U-235 enrichment of 3.15% be authorized. The reactor in which the fuel assemblies will be used is a Westinghouse pressurized water reactor. The maximum weight of U-235 in a fuel assembly is approximately 14.3 kilograms.
The fuel assemblies will be stored in their shipping containers, in the new fuel storage rack, and the storage racks in the spent fuel storage pool. The minimum center-to-center spacing provided by the racks are 21" in both the new and the spent fuel storage racks. A license condition requiring a 21" center-to-center spacing between fuel assemblies has been made a part of the license. The nuclear safety of a 21" center-to-center spacing has been previously established (see NR-FM-003, dated November 10, 1975).
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Conservative calculations by the staff have shown that two or more fuel assemblies are required in order to attain criticality. Accordingly a license condition has been added restricting the number of fuel assemblies !
which can be out of approved shipping containers or storage locations to one assembly.
The applicant has requested authorization to use one fuel assembly for the following purposes:
A. Indexing the manipulator crane in the containment building.
B. Preoperational testing of the RCC change fixture in the containment building.
C. Preoperational testing of the burnable poison rod assembly and handling tool.
D. Preoperational testing of the RCC handling tool.
E. Preoperational testing of the thimble plug handling tool.
F. Indexing the fuel handling crane.
G. Preoperational testing of the source rod tools.
All activities will be performed in accordance with written procedures which have been reviewed by the Station Operations Review Committee and ,
approved by the Station Chief Engineer and Manager. Assemblies will not be handled during severe weather conditions, for example when a hurricane or tornado watch is in effect.
It is the staff's opinion that under these conditions the applicant has established reasonable and satisfactory precautions to avoid accidental criticality.
The applicant's industrhl security program has been reviewed and it is the staff's opinion that the program is satisfactory.
The applicant has also described the basic aspects of its radiation safety control program, including a description of the training and experience of personnel responsible for administering the program. The staff has concluded that the applicant's radiation safety program and personnel are adequate to allow them to reasonably carry out the activities for which a license is requested.
The applicant has requested, pursuant to 10 CFR 70.24(b), an exemption from the provisions of 10 CFR 70.24. Because of the inherent features associated with the storage and inspection of unirradiated fuel containing uranium enriched to less than 5% in the U-235 isotope when no fuel
processing activities are to be performed, the staff hereby determines that granting such an exemption will not enganger life or property or the common defense and security, and is in the public interest. This exemption is authorized pursuant to 10 CFR 70.14.
Conclusion Based on the above statements, the staff believes that the proposed activities can be performed without undue risk to the health and safety of the public. It has been determined by the staff that the application fulfills the requirements of 10 CFR 70.23(a). Further, the issuance of this license is not a major Federal action significantly affecting the quality of the human environment and thus, pursuant to 10 CFR 51.5(d)(4),
no environmental impact statement, negative declaration, or environmental appraisal need be prepared. The reactor licensing project manager Mr. A. Dromerick states that he has no objection to the issuance of the license provided fuel is stored on 21-inch or greater centers.
The staff recommends approval of the application with the addition of the above license conditions, and the exemption of the licensee from the requirements of 10 CFR 70.24.
J. C. Delaney Fuel Processing and Fabrication Branch Division of Fuel Cycle and Material Safety Approved h L. C. Rouse IM
,C Fuel Processing and Fabrication Branch Division of Fuel Cycle and ;
Material Safety i
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