ML19294B374

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Safety Evaluation Supporting Amend 28 to License DPR-72
ML19294B374
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 02/15/1980
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML19294B370 List:
References
NUDOCS 8002280256
Download: ML19294B374 (2)


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%% f SAFETY EVALUATION SY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORT'.dG AMENDMENT NO. 28 TO FACILITY OPERATING LICENSE NO DPR-72 FLORIDA POWER CORPORATION, ET AL CRYSTAL RIVER UNIT NO. 3 NUCLEAR GENERATING PLANT DOCKET NO. 50-302 Introduction By letter dated February 14, 1980, Florida Power Corporation (FPC or the licensee) requested an amendment to the Crystal River Unit No. 3 Nuclear Generating Plant Technical Specifications (TS's). This TS change would delete a blind flange inside containment on penetration 116 and replace it with an isolation valve outside containment.

In addition, two existing valves would be designated as isolation valves and made part of the Appendix J inspection program. These cnanges are required to implement the Commission's January 2,1980 Show Cause Order in the area of post-accident sanpling capability.

Evaluation FPC proposes to remove a blind flange on penetration 116 inside containment and replace it with an isolation valve, to be designated LRV-46, on the out-side of containment. The flange will not be removed until the outside valve is installed.

This change is acceptable as the valve LRV-46 will meet all the criteria of isolation devices in the Final Safety Analysis Report (FSAR) within the containment boundary, and the change will still provide redundant isolation devices as required by General Design Criterion (GDC) 54 of 10 CFR 50, Appendix A.

An additional proposal is to redefine two existing valves as containment boundary valves and add them to Table 3.6-1, Containment Isolation Valves, in the TS's.

These valves are designated SAV-23 and SAV-122. These two valves were orginally designed as containment boundary isolation valves and are so designated in the FSAR. The valves were not included in the original TS test program as there were already two isolation devices in series that ade-quately met minimum Appendix J requirements and GDC 54.

For the above reasons, the addition of SAV-23 and SAV-122 to Table 3.6-1 is acceptable.

These changes provide the licensee with the capability of installing, if needed, a containment atmosphere sampling system.

This system would be installed post-accident as required by Item 2.1.8.a of NUREG-0578, Short-Term Lessons Learned Recommendations. We conclude that the changes to TS Table 3.6-1 are acceptable in that they provide the means to meet Item 2.1.8.a and meet both 10 CFR 50, Appendix J and Appendix A requirements.

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2 Env'ronmental tensideration We have determined that the amendment does not authorize a change in effluent types'or total amounts nor an increase in power level and will not result in any significant environmental impact.

Having made this determination, we have further concluded that the amendment involves an action which is insienificant from the standpoint of environmental impact and, pursuant to 10 CFR 551.5(d)(4), that an environmental impact statement, or necative declaration and environ-mental impa:t appraisal need not be prepared in connection with the issuance of this amendment.

Con:lusion We hava concluded, based on the considerations discussed above, that:

(1) be:ause the amencmant does not involve a significant increase in the probability or consequences of accidents previously considered and coes not inv 1ve a sienificant decrease in a safety margin, the amencment does not invcive a significant ha:ards consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the pro:csed manner, and (3) such activities will be concutted in compliance with the Cc==ission's regulations and the issuance of this amendment will net be inimical tc :ne : m cr defea.se and secu-ity er to the health and safety of the public.

Cated: Feoraa ry 15,19E:

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