ML20059F161
| ML20059F161 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 01/06/1994 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20059F158 | List: |
| References | |
| NUDOCS 9401130171 | |
| Download: ML20059F161 (3) | |
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WASHINGTON, D.C. 20$55-4001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 85 TO FACILITY OPERATING LICENSE NO. DPR-80 AND AMENDMENT NO. 84 TO FACILIJ" OPERATING _ LICENSE NO. DPR-82 PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON NUCLEAR POWER PLANT. UNITS 1 AND 2 DOCKET NOS, 50-275 AND 50-323
1.0 INTRODUCTION
By letter dated July 7,1993, Pacific Gas and Electric Company (or the licensee) submitted a request for changes to the lechnical Specifications (TS).
The proposed amendment is in support of its plan to implement the revised 10 CFR Part 20, 2.0 Evaluation The licensee has revised the TS to include wording that is consistent with the revised 10 CFR Part 20, Standards for Protection Aaainst Radiation, and will retain the same overall level of effluent control required to meet the design objectives of Appendix I to 10 CFR Part 50.
The proposed TS changes and evaluations follow:
1.
Technical Specification Bases 3/4.11.1.4 The licensee has proposed to revise the Bases to replace the reference to "10 CFR 20, Appendix B, Table II, Column' 2 with "10 CFR 20.1001 -
20.2401, Appendix B, Table 2, Column 2."
This change is administrative in nature to incorporate the corresponding revised 10 CFR Part 20 terminology and is acceptable.
l 2.
Technical Specification 6.8.4 The licensee has proposed to revise item g.3 of this TS to replace the old "10 CFR 20.106" reference with "10 CFR 20.1302."
The change is administrative in nature to incorporate the corresponding revised 10 CFR Part 20 section number and is acceptable.
9401130171 94'0106 PDR ADOCK 05000275 P
. 3.
Technical Specification 6.8.4 The licensee has proposed to revise item g.7 of this specification to read as follows:
" Limitations on the dose rate resulting from radioactive material released in gaseous effluents from the site to areas at or beyond the SITE B0UNDARY shall be limited to the following:
a.
For noble gases: Less than or equal to a dose rate of 500 mrem /yr to the whole body and less than or equal to a dose rate of 3000 mrem /yr to the skin, and b.
For Iodine-131, for Iodine-133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days:
Less than or equal to a dose rate of 15;0 mrem /yr to any organ."
The licensee has proposed this change in order to retain operational flexibility consistent with 10 CFR Part 50, Appendix I, concurrent with the implementation of the revised 10 CFR Part 20.
The current requirements for the content of the licensee's TS concerning radioactive effluents are contained in 10 CFR 50.36a.
10 CFR 50.36a requires licensees to maintain control over radioactive material in gaseous and liquid effluents to unrestricted areas, produced during normal reactor operations, to levels that are as low as reasonably achievable (ALARA).
For power reactors, Appendix I to 10 CFR Part 50 contains the numerical guidance to meet the ALARA requirement.
The dose values specified in Appendix I of 10 CFR Part 50 are small percentages of the implicit limits in 10 CFR 20.106 and the explicit limits in 10 CFR 20.1301.
As secondary controls, the instantaneous dose rates required by this specification were chosen by the staff to help maintain annual average relear.es of radioactive material in gaseous and liquid effluents to within the dose values specified in Appendix I of 10 CFR Part 50.
For purpose of the bases of this TS,10 CFR Part 20 is used as a source of reference values only.
These TS requirements allow operational flexibility, compatible with considerations of health and safety, which may temporarily result in release rates which, if continued for the calendar quarter, would result in radiation doses higher than specified in Appendix I of 10 CFR Part 50.
However, these releases are within the limits specified in 10 CFR 20.106 (10 CFR 20.1302).
This specification, which is based on guidance contained in NUREG-0133, is acceptable as a TS limit for gaseous effluents, which applies at all times as an assurance that the values in Appendix I of 10 CFR Part 50 are not likely to be exceeded.
i
- 1 i
The licensee states that the use of the proposed TS will not have a i
negative impact on the ability to continue to operate within the design i
objectives in Appendix I of 10 CFR Part 50.
i Based on the above, it is acceptable that the gaseous release rate TS for radioactive material be based on the stated dose rates, i
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the California State official was notified of the proposed issuance of the amendments.
The State official had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
A Notice of Issuance of Environmental Assessment and Finding of No Significant Impact relating to the proposed amendments revising the limitations on the dose rate resulting from radioactive material released in gaseous effluents, and reflecting the relocation of the prior 10 CFR 20.106. requirements to the new 10 CFR 20.1302 for the Diablo Canyon Power Plant was published in the Federal Reaister on January 5, 1994 (59 FR 606).
5.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor:
Stephen Klementowicz Date: January 6, 1994 t