ML19320B265
| ML19320B265 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 06/18/1980 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19320B258 | List: |
| References | |
| TAC-13056, NUDOCS 8007100118 | |
| Download: ML19320B265 (2) | |
Text
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w SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACiOR REGULATION SUPPORTING AMENDMENT NO. 31 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 November 21, 1977, as revised and supplemented Febr.uar.y.15,1980, and May 14, 1980, the Florida Power Corporation (FPC) requested a change to the Crystal River Unit No. 3 (CR-3) Technical Specifications (TSs) to delete requirements for maintaining a containment test pressure when inspecting tendon end anchorages and adjacent concrete surfaces.
In our letter and amendment of April 3,1980, we took action on some of the other issuec of the FPC November 21, 1977, request. Our review of the remaining part of FPC's application is continuing.
Evaluation As presently written the CR-3 TSs require visual inspection of tendon end anchorages and adjacent concrete surfaces while the containment is at its maximum test pressure of 50 psig. The containment building must, therefore, be held at 50 psig for a period of time that exceeds the time required for containment integrated leakage rate testing.
The visual inspections of anchoring points with containment under pressure would not be expected to detect any difference in appearance than without containment pressure.
In aadition, proposed Regulatory Guide 1.35, " Inservice Inspection of Ungrouted Tendons in Prestressed Concrete Containments", Revision 3, reflects a revised NRC staff posi-tion that allows these visual inspections of tendon end anchorages without any pres-surization of containment.
Therefore, for the above reasons, we have determined that we may delete requirements for maintaining containment pressure during examination of tendon end anchors and adjacent concrete surfaces.
Environmental Consideratior We have detennined 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 insignificant from the standpoint of environmental impact and, pursuant to 1C CFR 551.5(d)(4), that an environmental impact statement, or negative declaration and environ-mental impact appraisal need not be prepared in connection with the issuance of this amendment.
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Crystal River-3 Conclusion We have concluded, based on the censiderations discussed above, that:
(1) because the amendment does not involve a significant increase in the probability or consequences of accidents previously considered and does not involve a significant decrease in a safety margin, the amendment does not involve a significant hazards consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (3) such activities will be conducted in compliance with the Commission's regulations and tr,e issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
Dated: June 18, 1980
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