ML20205D775
| ML20205D775 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 10/03/1985 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20205B020 | List: |
| References | |
| NUDOCS 8510170087 | |
| Download: ML20205D775 (9) | |
Text
Ja nog'o UNITED STATES g
NUCLEAR REGULATORY COMMISSION y
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WASHINGTON, D. C 20555 E
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATtU TO AMENDMENT N05.97 AND101TO FACILITY OPERATING LICENSE N05. DPR-24 AND DPR-27 WISCON5IN ELEGINIC POWER COMPANY POINT BEACH NUCLEAR PLANT, UNIT N05. 1 AND 2 DOCKET N05. 50-266 AND 50-301
1.0 INTRODUCTION
To comply with Section V of Appendix I of 10 CFR Part 50, the Wisconsin Electric Power Company 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. Wisconsin Electric Power Company filed this information with the Comission by letter dated December 20, 1984, and modified by letter submittals dated March 11, 1985, and April 12, 1985, which requested changes to the Technical Specifications appended to Facility Operating License Nos. OPR-24 and DPR-27 for the Point Beach Plant. 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-0472.
These revised technical specifications would reasonably assure compliance, in radioactive waste nianagement, 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), and 405(c); with 10 CFR Part 50, Appendix A, General Design Criteria 60, 63 and 64; and with 10 CFR Part 50, Appendix B.
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1 2.0 BACKGROLND AND DISCUSSION 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 specifications that (1) require compliance with applicable provisions of 10 CFR 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 i
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 Part 20. " Standards for Protection Against Radiation,"
paragraphs 20.105(c), 20.106(g), and 20.405(c), require that nuclear power i
plant and other licensees comply with 40 CFR Part 190 " Environmental Radiation Protection Standards for Nuclear Power Operations" and submit J
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. e reports to the NRC when the 40 CFR Part 190 limits have been or may be 10 CFR Part 50, Appendix A - General Design Criteria for Nuclear exceeded.
Power Plants, contains Criterion 60, Control of releases of radioactive i
materials to the environment; Criterion 63, Monitoring fuel and waste Criterion 60 storage; and Criterion 64, Monitoring radioactivity releases.
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 that may result in excessive radiation levels and to initiate appropriate safety Criterion 64 requires that means be provided for monitoring actions.
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 Part 50, Appendix B, establishes quality assurance requirements for nuclear power plants.
i 10 CFR Part 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 Part 50.
Standard Radiological Effluent Technical Specifications 2.2 NUREG-0472 provides radiological effluent technical specifications for pressurized water reactors which the staff finds to be an acceptable Further clarification of these acceptable standard for licensing actions.
methods is provided in NUREG-0133, " Preparation of Radiological Effluent NUREG-0133 describes Technical Specifications for Nuclear Power Plants."
methods found acceptable to the staff of the NRC for the calculation of certain key values required in the preparation of proposed radiological effluent technical specifications for light-water-cooled nuclear power NUREG-0133 also provides guidance to licensees in preparing plants.
requests for changes to existing radiological effluent technical It also describes current staff specifications for operating reactors.
positions on the methodology for estimating 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 radiological effluent technical specifications needed to assure compliance with the guidance and
- However, requirements provided by the regulations previously cited.
alternative approaches to the preparation of radiclogical effluent technical specifications and alternative radiological effluent technical specifications may be acceptable if the staff detennines that the alternatives are in compliance with the regulations and with the intent of l
the regulatory guidance.
l
. The standard radiological effluent tech..ical specifications 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 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 required 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 att&ched report (EGG-PBS-6863) 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 l'censee's
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3.1
SUMMARY
The proposed changes to the radiological effluent technical specifications I
for Point Beach Nuclear Plant, Unit Nos.1 and 2,have been reviewed, evaluated, and found to be in compliance with the requirements of the NRC regulationsandwiththeintentofNUREG-0133andNUREG-0472(thePoint BeachPlantconsistsoftwopressurizedwaterreactors)andthereby fulfill all the requirements of the regulations related to radiological effluent technical specifications.
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The proposed changes will not remove or relax any existing rr,quirement related to the probability & 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 provice reasonable assurance that the health and safety of the pubi k will not be endangered by operation in the proposed manner. The staff, therefore, finds the proposed changes acceptable.
4.0 ENVIRONMENTAL CONSIDERATION
These amendments involve a change in the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes in the inspection, surveillance and reporting requirements.
The staff has determined that the amendments involve 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 d
Comission has previously published a proposed finding that these amendments involve no significant hazards consideration and there has been no public coment on such finding. Accordingly, these amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 951.22(c)(9) and10CFR651.22(c)(10). Pursuantto10CFR651.22(b),noenvironmental impact statement or environmental assessment need be prepared in connection with the issuance of these amendments.
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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 Commission's regulations, and the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
Date: October 3, 1985 i
Principal Contributor:
C. Miller, DSI
Attachment:
" Radiological Effluent Technical Specifications (RETs) Implementation -
Point Beach Nuclear Plant," EGG - PBS - 6863, May 1985.
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