ML20129J049
| ML20129J049 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 06/28/1985 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20127C329 | List: |
| References | |
| TAC-08043, TAC-08095, TAC-49090, TAC-49091, TAC-8043, TAC-8095, NUDOCS 8507220182 | |
| Download: ML20129J049 (5) | |
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENTS NOS.110 AND 48 TO FACILITY OPERATING LICENSE NO. NPF-5 GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA EDWIN I. HATCH NUCLEAR PLANT, UNITS NOS. 1 AND 2 s
DOCKETS NOS. 50-321 AND 50-366 s
1.0 INTRODUCTION
To comply with Section V of Appendix I of 10 CFR Part 50, the Georgia Power Company (GPC) has filed with the Comission plans and proposed technical specifications developed for the purpose of keeping releases of radioactive materials to unrestricted areas during normal operations, including expected operational occurrences, as low as is reasonably achievable. This Safety Evaluation (SE) is in response to GPC's application dated December 21, 1978 as supplemented and revised by letters dated October 30, 1979, August 1, and October 1, 1984, which requested changes to the technical specifications appended to Facility Operating License Nos. DPR-57 and NPF-5 for Hatch, Units Nos. I and 2.
The proposed technical specifications update those portions of the technical specifications addressing radioactive waste management and make them consistent with the current staff positions, as expressed in NUREG-0473. These revised technical specifications would reasonably assure compliance, in radioactive waste management, with the provisions of 10 CFR Part 50.36a, as supplemented by Appendix I to 10 CFR Part 50, with 10 CFR Parts 20.105(c),106(g),(GDC) 60, 63, and 64; and with and 405(c); with 10 CFR Part 50, Appendix A General Design Criteria 10 CFR Part 50, Appendix B.
2.0 BACKGROUND
AND DISCUSSION l
2.1 Regulations 10 CFR Part 50, " Domestic Licensing of Production and Utilization Facilities," Section 50.36a, " Technical Specifications on Effluents from Nuclear Power Reactors," provides that each license authorizing operation of a nuclear power reactor will include technical I
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specifications that (1) require compliance with applicable provisions of part 20.106, " Radioactivity in Effluents to Unrestricted Areas"; (2) require that operating procedures developed for the control of effluents be established and followed; (3) require that equipment installed in the radioactive waste system be maintained and used; and (4) require the periodic submission of reports to the NRC specifying the quantity of each of the principal radionuclides released to unrestricted areas in liquid and gaseous effluents, any quantities of radioactive materials released that are significantly above design objectives, and such other infomation as may be required by the Commission to estimate maximum potential radiation dose to the public resulting from the effluent releases.
10 CFR Part 20 " Standards for Protection Against Radiation,"
paragraphs 20.105(c), 20.106(g), and 20.405(c), require that nuclear power plant and other licensees comply with 40 CFR part 190,
" Environmental Radiation Protection Standards for Nuclear Power Operations," and submit reports to the NRC when the 40 CFR Part 190 limits have been or may be exceeded.
10 CFR Part 50, Appendix A. " General Design Criteria for Nuclear Power Plants," contains GDC 60, Control of releases for radioactive
. materials to the environment; GDC 63 Monitoring fuel and waste storage; and GDC 64, Monitoring radioactivity releases. GDC 60 requires that the nuclear power unit design include means to control suitably the release of radioactive materials in gaseous and liquid effluents and to handle radioactive solid wastes produced during normal reactor operation, including anticipated operational occurrences. GDC 63 requires that appropriate systems be provided in radioactive waste systems and associated handling areas to detect conditions that may result in excessive radiation levels and to initiate appropriate safety actions. GDC 64 requires that means be provided for monitoring effluent discharge paths and the plant-environs for radioactivity that may be released from nomal operations, including anticipated operational occurrences and postulated accidents.
10 CFR Part 50, Appendix B, establishes quality assurance requirements for nuclear power plants.
10 CFR Part 50, Appendix I, Section IV, provides guides on technical specifications for limiting conditions for operation of light-water-cooled nuclear power reactors licensed under 10 CFR Part 50.
! The standard radiological effluent technical specifications can be grouped under the following categories:
(1)
Instrumentation (2) Radioactive effluents
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(3) Radiological environmental monitoring l
(4) Design features (5) Administrative controls.
Each of the specifications under the first three categories is comprised of two parts: the limiting condition for operation and the surveillance requirements. The limiting condition for operation provides a statement of the limiting condition, the times when it is applicable, and the actions to be taken in the event that the limiting condition is not met.
In general, the specifications established to assure compliance with 10 CFR Part 20 standards provide, in the event the limiting conditions of operation are exceeded, that without delay, conditions are restored to within the limiting conditions. Otherwise, the facility is reqt. ired to effect approved shutdown procedures.
In general, the specifications established to assure compliance with 10 CFR Part 50 provide, in the event the limiting conditions of operation are exceeded, that within specified times corrective actions are to be taken, alternative means of operation are to be employed, and certain reports are to be submitted to the NRC describing these conditions and actions.
The specifications concerning design features and administrative controls contain no limiting conditions of operation or surveillance requirements.
Table 1 indicates the standard radiological effluent technical specifications that are needed to assure compliance with the particular provisions of the regulations described in Section 1.0.
3.0 EVALUATION The enclosed technical evaluation report (TER), EGG-PBS-6742, was prepared for us by EG&G Idaho, Inc., as part of our technical assistance
. contract program. Their report provides their technical evaluation of the compliance of the licensee's submittal with NRC-provided criteria.
The staff has reviewed this TER and agrees with the evaluation.
3.1 Suninary The proposed changes to the radiological effluent technical specifications for Hatch, Units Nos. 1 and 2, have been reviewed, evaluated, and found to be in compliance with the requirements of
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the NRC regulations and with the intent of NUREG-0133 and NUREG-0473 (Hatch, Units Nos. I and 2, are BWRs) and thereby fulfill all the requirements of the regulations related to radiological effluent technical specifications.
The proposed changes will not remove or relax any existing requirement related to the probability or consequences of accidents previously considered and do not involve a significant hazards consideration.
The proposed changes will not remove or relax any existing requirement needed to provide reascnable assurance that the health and safety of the public will not be endangered by operation in the proposed manner. The staff, therefore, finds the proposed changes acceptable.
4.0 ENVIRONMENTAL CONSIDERATION
S The 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 and a change to a surveillance requirement. We have detennined 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, the 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 the amendment.
5.0 CONCLUSION
We have 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, and (2) such activities will be conducted in compliance with the Consnission's regulations and the issuance of this amendment v 111 not be inimical to the comon defense and security or the health and safety of the public.
Principal Contributor:
C. Miller Dated: June 28,1985
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