ML20095A787
| ML20095A787 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 08/10/1984 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20095A776 | List: |
| References | |
| TAC-49988, NUDOCS 8408210582 | |
| Download: ML20095A787 (2) | |
Text
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- NUCLEAR REGULATORY COMMISSION WASHINGr_ N, D. C. 20555 l
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j SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT N0.70 TO FACILITY OPERATING LICENSE NO. DPR-72 FLORIDA POWER CORPORATION, ET AL.
l CRYSTAL RIVER UNIT NO. 3 NUCLEAR GENERATING PLANT DOCKET NO. 50-302 Introduction 4
By letter, dated March 18, 1983, and as subsequently revised by letter dated January 17, 1984, Florida Power Corporation (FPC or the licensee) proposed vchange to the Crystal River Unit 3 (CR-3) Technical Specifications (TSs).
This change specifies positive controls required to control personnel entry 4
into high radiation areas of greater than 1,000, millirem per hour (mrem /hr) which;are located in large areas where no enclosureccan be reasonably constructed around the individual area.
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Background===
ntry into high radiation. areas requires positive control of person *nel within those areas. Conditions for entry should be based on good radiation protection practices and should provide reasonable protection of personnel.
.The Standard Technical Specifications (STSs) for high radiation area access
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control clearly address the manner in which positive control for entiy into o
high radiation eNas should be exercised.
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The' licensee proposed amending.Secti'on 6.12.1(b) of the TSs in accordance with the STSs to, address procedures, for entry into high radiation areas (those areas
-having radiation levels of greater than 1000 mrem /hr) which are located in large areas where no. enclosure can be.. reasonably constructed.
Heretofore, no provision ~ existed in'the CR-3 TSs, thereby requiring all such high radiation areas
-to be controlled by locked doors. This requirement is impractical and could result in unwarranted radiation exposure to personnel as the result of building i
temporary enclosures that can be locked.
The licenkee', in the March 18, 1983 application, requested inclusion of the STS provisions in lieu of certain administrative and monitoring requirements presently in.the TSs. To provide a higher degree of protection to personnel and to be more consistent with the STSs, we required the licensee to maintain the previous requirements and implement the alternatives to locking these areas in addition to the administrative and monitoring requirements. The licensee agreed to this modified version of the proposed TS change. A Notice of Consideration of Issuance of Amendment to Facility Operating License and Proposed No Significant Hazards Consideration Determination and Opportunity for Hearing was published in the Federal Register on December 21, 1983 The licensee documented the modified version of the request in their January 17, 1984,. submittal.
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Evaluation As provided by the amended TSs, areas with radiation levels greater than 1,000 mrem /hr which are located within large areas, such as the Reactor Building, where no enclosure exists for purposes of locking, and for which no enclosure can be reasonably constructed around the individual area, will be roped off, conspicuously posted, and a flashing light will be activated as a warning device.
Entrance to such areas shall be controlled by issuance of a Radiation Work Permit (RWP).
In addition, any individual or group of individuals permitted to enter such areas shall be provided with a radiation monitoring device which continuously indicates the radiation dose rate in the
.t rea. This proposed change will provide controls equivalent to those contained in the STS. The Crystal River 3 TSs, as amended, provide clear, definitive conditions for positive access control for entry into high radiation areas, and therefore, are acceptable.
Environmental Consideration 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.
We have determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents 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.
Conclusion We have concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of-the will not be endangered by operation in the proposed manner, and (2) public 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: August 10, 1984 Principal Contributors:
C. Hinson, R. Hernan
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