ML13316A686
| ML13316A686 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 08/27/1984 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML13316A684 | List: |
| References | |
| TAC-08101, TAC-8101, NUDOCS 8409040007 | |
| Download: ML13316A686 (6) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. 79 TO PROVISIONAL OPERATING LICENSE NO. DPR-13 SOUTHERN CALIFORNIA EDISON COMPANY SAN ONOFRE NUCLEAR GENERATING STATION, UNIT NO. 1 DOCKET NO. 50-206
1.0 INTRODUCTION
To comply with Section V of Appendix I of 10 CFR Part 50, Southern California Edison Company has filed with the Commission 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. Southern California Edison Company filed this information with the Commission by letter dated December 12, 1983 and supplemented by a letter dated March 20, 1984, which requested changes to the Technical Specifications appended to Provisional Operating License No. DPR-13 for San Onofre Nuclear Generating Station, Unit No. 1. The proposed Technical Specifications (TSs) update those portions of the TSs addressing radioactive waste management and make them consistent with the current staff positions as expressed in NUREG-0472. These revised TSs would reasonably assure compliance, in radioactive waste management, with the provisions of 10 CFR 50.36a, as supplemented by Appendix I to 10 CFR 50, with 10 CFR 20.105(c), 106(g), and 405(c); with 10 CFR 50, Appendix A, General Design Criteria 60, 63, and 64; and with 10 CFR 50, Appendix B.
A Notice of Consideration of Issuance of Amendment to License and Proposed No Sionificant Hazards Consideration Determination and Opportunity for Hearing related to the requested action was published in the Federal Register on May 23, 1984 (49 FR 21839). A request for hearing and public comments were not received.
2.0 BACKGROUND
AND DISCUSSION 2.1 Regulations 10 CFR 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 Specifications that (1) require compliance-with applicable provisions of Part 20.106, "Radioactivity in Effluents to Unrestricted Areas;"
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-2 (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 information as may be required by the Commission to estimate maximum potential radiation dose to the public resulting from the effluent releases.
10 CFR 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 190, "Environmental Radiation Protection Standards for Nuclear Power Operations," and submit reports to the NRC when the 40 CFR 190 limits have been or may be exceeded.
10 CFR 50, Appendix A - General Design Criteria for Nuclear Power Plants, contains Criterion 60, Control of releases for radioactive materials to the environment; Criterion 63, Monitoring fuel and waste storage; and Criterion 64, Monitoring radioactivity releases.
Criterion 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. Criterion 63 requires that appropriate systems be provided in radioactive waste systems and associated handling areas to detect conditions thay may result in excessive radiation levels and to initiate appropriate safety actions. Criterion 64 requires that means be provided for monitoring effluent discharge paths and the plant environs for radioactivity that may be released from normal operations, including anticipated operational occurrences and postulated accidents.
10 CFR 50, Appendix B, establishes quality assurance requirements for nuclear power plants.
10 CFR 50, Appendix I,Section IV, provides guides on Technical Specifications for limiting conditions for operation for light-water cooled nuclear power reactors licensed under 10 CFR 50.
2.2 Standard Radiological Effluent Technical Specifications NUREG-0472, "Standard Radiological Effluent Technical Specifications for Pressurized Water Reactors," provides radiological effluent Technical Specifications for pressurized water reactors which the staff finds to be an acceptable standard for licensing actions. Further clarification of these acceptable methods is provided in NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants."
NUREG-0133 describes methods found acceptable to the staff of the NRC for the calculation of certain key values required in the
-3 preparation of proposed radiological effluent technical specifications (RETS) for light-water-cooled nuclear power plants. NUREG-0133 also provides guidance to licensees in preparing requests for changes to existing RETS for operating reactors. It also describes current staff positions on the methodology for estifmating radiation exposure due to:
the release of radioactive materials in effluents and on the administrative control of radioactive waste treatment systems.
The above NUREG documents address all of the RETS needed to assure compliance with the guidance and requirements provided by the regulations previously cited. However, alternative approaches to the preparation of RETS and alternative RETS may be acceptable if the staff determines that the alternatives are in compliance with the regulations and with the intent of the regulatory guidance.
The standard RETS can be grouped under the following categories:
(1) Instrumentation (2) Radioactive effluents (3) Radiological environmental monitoring (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 conditions, the times when it is applicable, and the actions to be taken in the event that the limiting condition is not met.
rn general, the specifications established to assure compliance with 10 CFR 20 standards provide, in the event the limiting conditions for operation are exceeded, that without delay conditions are restored to within the limiting conditions. Otherwise, the facility is required to effect.approved shutdown procedures. In general, the specifications established to assure compliance with 10 CFR 50 provide, in the event the limiting conditions for 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 for operation or surveillance requirements.
Table 1 indicates the standard RETS that are needed to assure compliance with the particular provisions of the regulations described in Section 1.0.
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Table 1. Relation Between Provisions Of the Regulations and the Standard Radiological Effluent Technical Specifications'fur Pressurized Water Reactors and Boiling Water Reactors Staiiar&1T~ioiyica Efluent T-c hn iCaWFSp~hTFi ica~~
Instru-Radioactive Efflients nenta-as Rad.
Envir.
De Si AdiiStrative Contrul Lion Liquid W
PW
[IWR Monitoring Caur Indicate tha 01 Indicate the specifications that are needed L.C to assure compliance with the identified (U 0 c
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3 LE provision of the regulations.
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40 CFR 190I 0Q)
PartA 50 Apeni A
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rovisionso it Code of Federa eaTions active 0 W U c 5.36 mehiatseiiaton he eironents o
Cteinu61 power reactors Remain within limits of 9 20.106 0
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stablish An follow procedurestto control Ctaintain.and use radioactive waste system t*
equ iple n t Submit reports3 semi-annual and other,
- 0 0 0 00OS 40 0 090 0 00
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§9 20.105(c). 20.106(9)-, 20.405(c) Compliance with
- oe Part 50 Appendix A - General Design Criteria aritain Control of releases of radioactive 0 v e0 s
ego.,,,
materials to the environment Esterion 61 - Fuel storage and handling and 0
radioactivity control
)riterion 63 onitoring fuel and waste storage 0
Criterion 64 -
Monitoring radioctivity releases 0
0 Pat 0I iedix B - quality Assurance Criteria 0q-Part 50 AppendIx I -
Guides to eSe "AL R Is Reasonably Achievable (ALARA)'
Maintain releases within design objectives astablish surveillance & monitoring prograo to Rdopiovide data on:
o(1) quantities ofEDrad. matIs. in effluents 0 0 (2) radiation & rad. 'natls. in ' the environment 00 0
(3) changes in use of unresLtricted areas Exert best efforts to keep reledses "ALARA" 00 00 0
a0 0
Submit report if calculated doses exceed the design objective Demotistrate conform.
to des.
obj. by caic proced.
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- Note:
Needed to fully implement other specifications.
-4 3.0 EVALUATION The attached report (EGG-PBS-6569) 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 Technical Evaluation Report (TER) and agrees with the evaluation.
3.1 Summary The proposed changes to the RETS for San Onofre Unit No. 1, have been reviewed, evaluated, and found to be in compliance with the requirements of the NRC regulations and with the intent of NUREG-0133 and NUREG-0472 and thereby fulfill all the requirements of the regulations related to radiological effluent technical specifications., During this review, some minor editorial changes were made, These changes were not substantive and were made to correct typographical errors and to ensure consistency within the specifications.
The proposed changes will not remove or relax any existing requirement needed to provide reasonable 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
This amendment involves a change in the installation or use of a facility component located within the restricted area as defined by 10 CFR 20. The staff has determined that the amendment involves no significant increase in the amounts of any effluents that may be released offsite and that there is no significant increase in individual or cumulative occupation 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.
- Although the Report contains a legend that this is "an informal report intended for use as a preliminary working document," the report in fact represents EG&G's final evaluation of the amendment request for NRC. These statements will be clarified in reports issued in the near future.
5.0 CONCLUSION
The staff 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; and (2) 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.
6.0 ACKNOWLEDGEMENT C. Miller, C. Willis, and W. Meinke contributed to.this evaluation.
Attachment:
EG&G Idaho, Inc., Report (EGG-PBS-6569) dated March 1984.
Dated: August 27, 1984
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