ML20129F373

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Safety Evaluation Supporting Amend 92 to License DPR-46
ML20129F373
Person / Time
Site: Cooper Entergy icon.png
Issue date: 05/20/1985
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20129F366 List:
References
TAC-56090, NUDOCS 8506060756
Download: ML20129F373 (3)


Text

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NUCLEAR REGULATORY COMMISSION

.j WASHINGTON, D. C. 20555

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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT N0. 92 TO FACILITY OPERATING LICENSE N0. DPR-46 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION DOCKET NO. 50-298

1.0 INTRODUCTION

This amendment modifies the Cooper Nuclear Station (CNS) Technical Specifications to (1) delete the tables listing the individual hydraulic and mechanical snubbers which are required to be operable, and (2) delete requirements to verify operability of valves in the recirculation pumps discharge valve four-inch bypass lines. These Technical Specification changes were proposed by the Nebraska Public Power District, the licensee for CNS, in an application dated October 5, 1984, as supplemented by a submittal dated October 29, 1984 2.0 EVALUATION 2.1 Snubbers The licensee proposed to delete from the Cooper Technical Specifications Tables 3.6.1, 3.6.2, 3.6.3, and 3.6.4 which list the hydraulic and mechanical snubbers which are required to be operable. The proposed change would also delete the references to these tables in Section 3/4.6.H and 6.4.2.G of the Technical Specifications.

In lieu of listing the individual snubbers, Section 3.6.H.1 would be changed by this amendment to specify the types of snubbers which are required to be operable. One result of these changes would be to eliminate the need for frequent amendments to incorporate changes in the snubber tables. Any future changes in snubber quantities, types or locations would be a change to the facility and as such would be subject to the provisions of 10 CFR Part 50.59.

We have reviewed the proposed amendment and have determined that it would not change the intent of the Technical Specifications for snubbers. Previously the staff had evaluated the inclusion of snubber listings in Technical Specifi-cations and concluded that such listings are not necessary provided the snubber Technical Specifications are modified to specify which snubbers are required to be operable. This guidance was provided to licensees by Generic Letter 13. " Technical Specifications for Snubbers" dated May 3,1984. Since the changes proposed by the licensee for Cooper would not change the existing requirements for recorckeeping and operability of safety-related snubbers, the proposed amendment meets the guidelines of Generic Letter 84-13. We, therefore, find that the proposed changes to snubber Technical Specifications are acceptable.

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  • 2.2 Four-Inch Recirculation Bypass Lines By letter dated October 5, 1984, the licensee proposed to delete the require-ments in Section 3/4.5.A of the Cooper Technical Specifications to verify the operability of the valves in the recirculation pump discharge valve four-inch bypass lines. This proposed amendment is related to the licensee's plans to pennanently remove these bypass lines and valves during the present refueling outage because of the occurrence of bypass line cracking in other boiling water reactor plants.

We have reviewed the licensee's proposal and have determined that removal of the bypass lines and valves will not edversely affect the safety of the plant.

The bypass lines and valves are not required for normal operation. These four-inch lines were originally included in the recirculation system to be used during startup and when a recirculation loop is returned to service.

That is, when the recirculation pump is started or returned to service, it is started at slow speed with the main discharge valve closed and the bypass valve open. Pump speed is not increased until after the main discharge valve has been opened. However, other means of loop heat-up are available which do not require use of the bypass lines. The proposed removal of the bypass lines does not compromise the safety margin of the plant. Therefore, we find that the removal of the bypass lines and valves, and the deletion of the associated bypass valve operability requirements from the Technical Specifications are acceptable.

3.0 ENVIRONMENTAL CONSIDERATION

S This amendment involves a change in the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes in surveillance requirements. The staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluent s that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that this amendment involves no significant hazards consideration and there has been no public comment on such finding. Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).

Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.

4.0 CONCLUSION

S We have concluded, based on the co'isiderations 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

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'and the issuance of the amendment will not be inimical to the comon defense and security or to the health and safety of the public.

Principal Contributors: H..Shaw, G. Thomas

. Dated: May'20,'1985 i

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