ML19249A500
| ML19249A500 | |
| Person / Time | |
|---|---|
| Site: | Zimmer, 07002838 |
| Issue date: | 06/26/1978 |
| From: | Delaney J NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19249A479 | List: |
| References | |
| NUDOCS 7908230157 | |
| Download: ML19249A500 (3) | |
Text
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E ; c m3 SAFETY EVALUATIO!! REPORT - cit'CIN"ATI CAS & ELECTRIC COMPANY (CG&E)
COLUMBUS AND SOUfHERN CHIO LtECTRIC COMP /d1Y (C50)
THE DAYi0fl POWER /.ND LIGHT CCMPANY (DPL)
APPLICAT0fl DATED MARCH 8, 1973, /,!!D SUPPLEMENT THERETO TRAN5MITTED BY LETTER DATED " ARCH 31, 1978, FOR A STORAGE LICENSE FCR FUEL AND ACCESSORIES FOR THE WM. H. ZIl'MER HUCLLAR POWER STATION, UNIT 1 DOCKET NO. 70-2838 The subject application and supplement thereto submitted by CG&E on behalf of itself and as agent for CSO and DPL requests a license to receive approximately 2000 kilograms of U-235 as uranium enriched up to 1.95% in the U-235 isotope contained in reactor fuel assemblies, and 5 grams of U-235 at any enrichment contained in neutron detectors.
The fuel assemblies which the applicants wish to receive contain uranium enriched to a maximum of 1.95% in the U-235 isotope.
The fuel is con-tained in up to 560 fuel assemblies.
Because of measurement and enrich-ment variatione n;<' ally encountered, it is proposed that a maximum U-235 enrichment of 2.0% be authorized.
The reactor in which the fuel assemblies will be used is a General Electric Boiling Water Reactor.
The weignt of uranium contained in a single fuel assembly is 186.214 kilograms and the weight of U-235 in a single assembly is 3.537 kilograms.
The fuel assemblies will be stcred in their shipping containers and in the spent fuel storage racks located in the spent fuel pool.
Each storage rack holds 20 assemblies in two rows.
Assemblies in a row are stored 6.625" center-to-center spacing.
The safety of these spacings have been previously established, for both the flooded and ary cases.
These spacings are currently used at reveral operating reactors (see Dockets 70-1072 and 70-1247).
Further, the fuel is to be stored dry.
Uranium enriched to 2%
in the U-235 isotope canlot be made accidentally critical unless a moderator such as water is present.
Conservative calculations by the staff have shown that four or more of these fuel assemblies are cequired in order to attain criticality.
A license condition has been added restricting the number of fuel assemblies which can be out of approved shipping containers or storage location at any one time to three assemblies.
In addition the Staff has added a condition requiring that fuel assemblies be stored in such a manner that would allow water to drain freely from the assemblies in the event of flooding and subsequent draining of a storage area.
This prevents a h
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, condition where individual fuel ass <mblies could he water moderated without providing shieldinn between ass m; lies.
As secondary controls, the applicants have caused water hoses in the area to be valved off and safety tagged, have provided a waterrroof and fire resistant cover for the fuel assemblies, and have limited tim amount af con:bustible mater als i
in the area.
It is the Staff's opinion that under these conditions tiie applicants have established reasonable and satisfactory precautions to avoid accidental criticality.
The applicant's industrial security program has been reviewed and it is the Staff's opinion that the program is satisfactory.
The applicants have also described the basic aspects of their radiat:aa safety control program, including a description of the training ana experience of personnel responsible for administering the program.
The Staf f has concluded that the applicant's radiation safety program and personnel are adequate to allow them to reasonably tarry out the activi-ties for which a license is requested.
The applicants have 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 contain-ing 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 endanger life or property or the common defense and security, and is in the public interest.
This exemp-tion 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 requrements 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 (a)(4),
no environmental impact statement, negative declaration, or environmental appraisal need be prepared.
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. The Staff recommends approval of the application with the ac'dition of the above license conditions, and exemption of the licensee from the require-ments of 10 CFR 70.24.
b5 huit.tu J. C. Delaney
. Fuel Processing and Fabrication Branch Division of Fuel Cycle and Material Safety Approved:
'k L. C. Rouse D0
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