ML20197D462
| ML20197D462 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 03/26/1987 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20197D452 | List: |
| References | |
| TAC-62173, NUDOCS 8704100010 | |
| Download: ML20197D462 (2) | |
Text
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. inc; TO FACILITY OPERATING LICENSE NO. DPR-40 OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION, UNIT NO. 1 DOCKET NO. 50-285 INTRODUCTION:
By letter dated August 19, 1986, OmahaPublicPowerDistrict(OPPD)sub-mittedanapplicationtochangetheTechnicalSpecifications(TS)for Fort Calhoun Station, Unit No. 1.
The changes would delete the tabular listing (Tables 2.6(a) and (b)) of snubbers and add the criteria speci-fying which snubbers are required to be operable and which snubbers are exempted from the requirements of Specification 2.18. The licensee's application was made in response to the NRC staff's Generic Letter 84-13
" Technical Specifications for Snubbers," dated May 3,1984. These changes are expected to eliminate the need for frequent TS amendments to incor-porate changes in the snubber listings.
EVALUATION
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The NRC staff indicated in the aforementioned Generic Letter that it had reassessed the inclusion'of snubber listings within the TS and concluded that such listings were not necessary provided the snubber TS are modified to specify which snubbers are required to be operable. The licensee's requested changes to the TS will delete the tabular listings of snubbers and references to those listings, and specify which snubbers are required to be operable.
In addition, the licensee has also provided clarification on the methodology for selecting the sample size for hydraulic and mechanical snubbers.
The staff reviewed the current TS together with the proposed changes and clarification and compared these changes with model TS provided in the Generic Letter. From the review,- the staff finds that the proposed changes are administrative in nature and do not authorize any physical change to the plant's safety-related structures, systems, or components. Any physical changes in snubber quantities, types, or location would be subject to the provisions of 10 CFR 50.59 under the proposed changes. Therefore, the proposed changes would not in any way reduce availability of those snubbers which are provided to ensure that the structural integrity of the reactor coolant system, and all other safety-related systems, is maintained during and following a seismic or other event which induce dynamic loads.
I 8704100010 870326 PDR ADOCK 05000285 l
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. Based an the above discussions and the fact that the proposed changes and the melnodology for selecting the sample size are consistent with guidance provided in the Generic Letter, the staff has determined that the proposed changes are acceptable.
ENVIRONMENTAL CONSIDERATION This amendment relates to changes in recordkeeping, reporting, er administra-tive procedures or requirements. Accordingly, the amendeant meets tha eli bility criteria for categorical exclusion set forth in 10 CFR 951.22(c)(9)gi-Pursuant to 10 CFR 951.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
CONCLUSION We have concluded, based on the considerations discussed above, that (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Commission's regulations, and the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Date: March 26, 1987 Principal Contributor:
M. Hartzman l
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