ML20094P503
| ML20094P503 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 11/21/1995 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20094P501 | List: |
| References | |
| NUDOCS 9511290195 | |
| Download: ML20094P503 (4) | |
Text
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NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 2006H001
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION i
RELATED TO AMENDMENT NOS.194 AND 77 TO FACILITY OPERATING LICENSE NOS. DPR-66 AND NPF-73 DUOVESNE LIGHT COMPANY OHIO EDIS0N COMPANY PENNSYLVANIA POWER COMPANY THE CLEVELAND ELECTRIC ILLUMINATING COMPANY THE TOLED0 EDISON COMPANY BEAVER VALLEY POWER STATION. UNIT NOS. 1 AND 2 DOCKET NOS. 50-334 AND 50-412
1.0 INTRODUCTION
By letter dated September 13, 1995, as supplemented October 16, 1995, the Duquesne Light Company (the licensee) submitted a request for changes to the Beaver Valley Power Station, Unit Nos. 1 and 2, (BVPS-1 and BVPS-2) Technical Specifications (TSs). The requested changes would revise the Administrative Controls section (TSs 6.8.6.a.2), 6.8.6.a.7), and 6.14.a.2)) of the BVPS-1 and BVPS-2 TSs to be consistent with the requirements of the Offsite Dose Calculation Manual (ODCM). The ODCM was recently updated to reflect the radioactive liquid and gaseous effluent release limits and the liquid holdup tank activity limit of BVPS-1 License Amendment No. 188 and BVPS-2 License Amendment No. 70 which were issued June 12, 1995.
By letter dated October 16, 1995, the licensee withdrew proposed changes to TS 6.14.a.2) and the Bases for TS 3/4.11.1.4 because these changes incorrectly referenced superseded sections of 10 CFR Part 20. The NRC staff has approved the licensee's request for withdrawal. The October 16, 1995, letter did not change the initial proposed no significant hazards consideration determination or expand the amendmeat request beyond the scope of the September 22, 1995, Federal Reaister notice.
2.0 EVALUATION The licensee has proposed to revise the TSs 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.
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. f The proposed TS changes and evaluations follow:
TS 6.8.6.a. Radioactive Effluent Controls Procram The licensee has proposed to revise item 2 of this specification to read as follows:
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" Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to 10 times 10 CFR Part 20, Appendix B, Table 2, Column 2,"
The licensee has proposed this change in order to retain operational flexibility consistent with Appendix I to 10 CFR Part 50, concurrent with the implementation of the revised 10 CFR Part 20.
The current requirements for the content of the licensee's TSs concerning radioactive effluents are contained in 10 CFR 50.36a.
Pursuant to 10 CFR 50.36a, licensees are required 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 the old 10 CFR 20.106 and the explicit limits in 10 CFR 20.1301. As secondary controls, the instantaneous concentration release rates required by this TS were chosen by the NRC staff to help maintain annual average releases of radioactive material in gaseous and liquid effluents to within the dose values specified in Appendix I of 10 CFR Part 50.
For the purposes 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 1 of 10 CFR Part 50. However, these releases are within the implicit limits in the old 10 CFR 20.106 and the explicit limits in 10 CFR 20.1302 which references Appendix B concentrations.
These referenced concentrations in the old 10 CFR Part 20 are specific values which relate to an annual dose of 500 mrem. The liquid effluent radioactive effluent concentration limits given in Appendix B, Table 2, Column 2 to 10 CFR 20.1001 - 20.2402 are based on an annual dose of 50 mrem total effective dose equivalent. Since an instantaneous release concentration corresponding to a dose rate of 500 mrem / year has been acceptable as a TS limit for liquid effluents, which applies at all times to assure that the values in Appendix I of 10 CFR Part 50 are not likely to be exceeded, it is not necessary to reduce this limit by a factor of 10.
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. The licensee states that the use of effluent concentration values that are 10 times those listed in Appendix 8, Table 2, Column 2 to 10 CFR 20.1001 -
20.2402 will not have a negative impact on the ability to continue to operate within the design objectives in Appendix I to 10 CFR Part 50 and 40 CFR Part 190.
Based on the above, it is acceptable for the liquid release rate TS, as applied on an instantaneous basis, be based on 10 times the effluent concentration values given in Appendix B, Table 2, Column 2 to 10 CFR 20.1001
- 20.2402.
The licensee has proposed to also revise item 7 of this specification to read as follows:
" Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the SITE B0UNDARY shall be limited to the following:
a.
For noble gases:
Less than or equal to 500 mrem / year to the total body and less than or equal to 3000 mrem / year 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 1500 mrem / year 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.
Pursuant to 10 CFR 50.36a, licensees are required 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 the old 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 NRC staff to help maintain annual average releases of radioactive material in gaseous 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 operations! 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 the old 10 CFR 20.106 and the current 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.
The licensee states that the proposed TS change will not have a negative impact on the ability to continue to operate within the design objectives in Appendix I of 10 CFR Part 50 and 40 CFR Part 190.
Based on the above, it is acceptable that the gaseous release rate TS for radioactive material be based on the stated dose rates.
The licensee has proposed to revise item 3 of this TS to delete a reference to the old 10 CFR Part 20.
The proposed change is administrative in nature and is acceptable.
3.0 STATE CONSULTATION
In' accordance with the Commission's regulations, the Pennsylvania State official was notified of the proposed issuance of the amendments.
The State official had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
The amendments relate to changes in recordkeeping, reporting, or administrative procedures or requirements. Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10).
Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
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 amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor:
S. Klementowicz Date: November 21, 1995
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