ML20069G115
| ML20069G115 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 09/13/1982 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20069G103 | List: |
| References | |
| TAC-10836, NUDOCS 8209280453 | |
| Download: ML20069G115 (2) | |
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UNITED STATES s-g NUCLEAR REGULATORY COMMISSION y
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING A'tENDf1ENT N0. 57 TO FACILITY OPERATIflG LICENSE NO. DPR-72 FLORIDA POWEP, CORPORATION, ET AL CRYSTAL RIVER UNIT NO. 3 NUCLEAR GENERATING PLANT DOCKET NO. 50-302 Introduction By letter dated December 3,1980, as revised January 19, 1982, Florida Power Corporation (FPC) proposed a change to the Crystal River Unit 3 (CR-3) Technical Specifications (TSs) to reflect an expanded Plant Review Committee (PRC) membership, an expanded procedural review and current title designations for CR-3 management.
Evaluation The changes proposed by FPC will expand the PRC by adding the Nuclear Technical Services Superintendent, the QA/QC Compliance Manager and the Performance Engineering Supervisor. The proposed number of PRC members required for a quorum is expanded from four plus the chairman to five plus the chairman. Expanding the membership of the PRC to more technical areas and departments will increase the technical expertise of the PRC and the participation by all FPC departments.
The proposed increase in the number of members required for a quorum will assure that issues are more completely considered with respect to impact on all CR-3 operations. Expanding the number of members on the committee will also assure greater continuity if individual members are absent. Therefore, this change is in the direction of improving the capability of the PRC.
The proposed TSs expand the procedural review requirements of the PRC to specifically require PRC review of the Emergency Plan, Security Plan, Fire Protection Plan and test procedures associated with plant modification. The proposed TSs also specify the review requirements for other procedures including the qualification of reviewers These changes assure that each procedure is reviewed adequately by FPC management i ad technically qualified reviewers prior to implementation.
The revised review process clarifies the review process for procedures and places more review responsibility on lower level management at CR-3 The procedures do, however, retain adequate higher management participation in the review and approval process.
The proposed changes in titles of CR-3 management are administrative only and do not involve any safety issues.
6209280453 820913 PDR ADOCK 05000302 P
. j Environmental Consideration 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 frapact. Having made this determination, we have further concluded that the amendment involves an action which is insignificant from the standpoint of
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environmental impact and, pursuant to 10 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.
Conclusion We have concluded, based on the considerations discussed above, that:
(1) because the amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated, does not create the possibility of an accident of a type different from any evaluated previously, and does not involve a significant reduction in a margin of safety, 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 the issuance of this amendment will not be inimical to the common-defense and security or to the. health and safety of the public.
Dated: September 13, 1982 The following NRC personnel have contributed to this Safety Evaluation:
P. Erickson.
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