ML13326A691
| ML13326A691 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 08/11/1982 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML13326A689 | List: |
| References | |
| NUDOCS 8208170262 | |
| Download: ML13326A691 (2) | |
Text
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o UNITED STATES 0
aNUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. 61 TO PROVISIONAL OPERATING LICENSE NO. DPR-13 SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS & ELECTRIC COMPANY SAN ONOFRE UNIT NO. 1 DOCKET NO. 50-206
1.0 INTRODUCTION
By letter dated April 22, 1982, Southern California Edison Company (the licensee) proposed changes to the San Onofre Nuclear Generating Station, Unit No. 1, Technical Specifications. These changes would modify Section 6.11, "Radiation Protection Program" of the Technical Specifications to adopt the wording of the "Standard Technical Specifi cations for Westinghouse Pressurized Water Reactors," NUREG-0452, Revision 4, with one modification.
2.0 DISCUSSION AND EVALUATION Positive control of personnel access into high radiation areas is required in accordance with 10 CFR Part 20. Each entry must be con trolled unambiguously in a manner which is consistent with good radiation protection practice. The Standard Technical Specifications for high radiation area access control have been written to express clearly the manner in which positive control for entry into high radiation areas will be exercised.
The licensee's proposed Technical Specifications adopt the wording of the Standard Technical Specifications with one modification. In item 6.11.2, the licensee has added to the Standard Technical Specification that, where dose rates are in excess of 1,000 mrem/hr, either flashing lights will be used to identify such areas, or a health physics technician will be in continuous attendance. Based on our review, we find that this change should provide controls equivalent to the StandardTechnical Specifications.
Based on our review of the licensee's submittal of April 22, 1982, we find that the proposed modification establishes improved physical. and administrative methods for access control.
It also, updates the Unit 1 technical specifications to be the same as Unit 2's specifications.
We also find that the proposed technical specifications provide clear, definitive conditions for positive access control for entry into high radiation areas.
We conclude that the proposed changes are in accordance with 10 CFR Part 20, Section 20.203(c)(5) and are, therefore, acceptable.
9208170262 820811 PDR ADOCK 05000206 P
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3.0 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 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 10 CFR §51.5(d)(4), that an environmental impact state ment or negative declaration and environmental impact appraisal need not be prepared in connection with the issuance of this amendment.
4.0 CONCLUSION
We also conclude, based on the considerations discussed above, that:
(1) because the amendment does not involve a significant increase in the probability or consequences of accidents previously considered, does not involve a significant decrease in a safety margin, and does not create the possibility of an accident of a type different from any evaluated previously, 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 the health and safety of the public.
5.0 ACKNOWLEDGEMENTS The following individuals contributed to this evaluation:
J. Minns W. Paulson Date:
August 11, 1982