ML20138R226
| ML20138R226 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 10/01/1985 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20136G192 | List: |
| References | |
| NUDOCS 8511180498 | |
| Download: ML20138R226 (6) | |
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- UNITED STATES p
i NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20655
\\.....l SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR PEG SUPPORTING AMENDMENT NO.106 TO PROVISIONAL OPERAT a
NORTHEAST NUCLEAR ENERGY COMPANY MILLSTONE NUCLEAR POWER STATION, UNIT NO. I DOCKET NO. 50-245
1.0 INTRODUCTION
To comply with Section V of Appendix I of 10 CFR Part 50, the Northeast Nuclear Energy Company (NNECO) 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.
which requested changes to the Technical 29, 1985 by letter dated MaySpecifications appended to Facility Operating License No.
The proposed technical Millstone Nuclear Power Station, Unit No.1.
specifications would delete Appendix B in its entirety and provide new Appendix A Technical Specifications defining limiting conditions for operation and surveillance requirements for radioactive liquid and gaseous effluent monitoring; concentration, dose, and treatment of liquid and gaseous wastes; and total dose. The proposed technical specifications would also update those portions of the technical specifications addressing radioactive waste management a These revised technical specifications reasonably assure compliance, in radioactive waste manaaement, with the provisions of 10 CFR Part 50.36a, as supplemented by Appendix I to 10 CFR Part 50, with 10 Design Criteria 60, 63 and 64; and with 10 CFR Part 50, Appendix B.
A Notice of Consideration of Issuance of Amendment to License and Proposed No Significant Hazards Consideration Detemination and Opportunity for Hearing related to the requested action was published in the FederalNo cons Register on August 14,1985(50FR32798).
hearing were received.
2.0 BACKGROUND
AND DISCUSSION 2.1 Peoulations 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 te hnical specifications that (1) require compliance with applicable provisions of Part 20.106,
" Radioactivity in Effluents to Unrestricted Areas;" (2) require that 5
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2-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 reautred 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 Criterion 60, Control of releases of 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 that 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 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 for light-water-cooled nuclear power reactors licensed under 10 CFR Part 50.
2.2 Standard Radiological Effluent Technical Specifications NUREG-0473 provides radiolooical effluent technical specifications for boiling 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 acceptGble to the staff of the NRC for the calculation of certain key v6ues required in the preparation of proposed radiological efflv.:nt technical specifications for light-water-
cooled nuclear power plants. NUREG-0133 also provides guidance to licensees in preparing requests for changes to existing radiological effluent technical specifications for operating reactors.
It also describes current staff 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 requirements provided by the regulations previously cited. However, alternative approaches to the preparation of radiological effluent technical specifications and alternative radiological effluent technical specifications 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 radiological effluent technical 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 apprnved shutdown procedures.
In peneral, the specifications established to assure compliance with 10 CFR Part 50 provide, in the event the limiting conditions of operation l
are exceeded, that within specified tines, corrective actions are to be taken, alternative means of operation are to be employed, and certain reports are 4
to be submitted to the NRC describing these conditions and actions.
I The specifications concerning desian features and adninistrative 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.
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e 3.0 EVALUATION The enclosed report (TER-C5506-98) was prepared for the staff by Franklin Research Center as part of a technical assistance contract program.
The report provides the 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
SUMMARY
The proposed changes to the radiological effluent technical specifications for Millstone Nuclear Power Station, Unit No. I 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-0437 (Millstone-1 is a boiling water reactor) and thereby fulfill all the requirements of the regulations related to radiological effluent technical specifications.
4 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 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 changes to requirements with respect to the installation or use of facility components located within the restricted area as defined in-10 CFR Part 20 and changes in inspection and surveillance requirements.
The staff has determined that the amendment involves no significant increase in the amount 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, this amendment meets the eligibilit categorical exclusion set forth in 10 CFR Section 51.22(c)y criteria for (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.
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N 5-5.0 GENERAL CONCLUSION We have concluded, based on the considerations discussed above, that:
will not be endangered by operation in the proposed narrer; and (2) public (1) there is reasonable assurance that the health and safety of the such activities will be conducted in compliance with the Commission's reculations and the issuance of this amendment will not be infrical to the cokmon defense and security or the health and safety of the public.
6.0 ACKNOWLEDGEMENT Principal contributor:
W. Meinke Dated: October 1,1985 e
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