ML20132A849
| ML20132A849 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 09/16/1985 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20132A847 | List: |
| References | |
| TAC-49588, NUDOCS 8509260037 | |
| Download: ML20132A849 (5) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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- j WASHING TON. D. C. 20555
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR RE RELATED TO AMENDMENT NO.104T0 FACILITY OPERATING LICEN NORTHEAST NUCLEAR ENERGY COMPANY, ET AL.
MILLSTONE NUCLEAR POWER STATION, UNIT NO. 2 DOCKET NO. 50-336
1.0 INTRODUCTION
To comply with Section V of Ap Nuclear Energy Company (NNECO)pendix I of 10 CFR Part 50, the Northeast has filed with the Comission plans and proposed technical specifications developed for the purpose of keeping releases of radioactive materials to unrestricted areas during nortnal operations, including expected operational occurrences, as low as is reasonably achievable. NNEC0 filed this infomation with the Commission by letter dated May 29, 1985, which requested changes to the Technical Specifications appended to Facility Operating License No. DPR-65 for the Millstone Nuclear Power Station, Unit No. 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-0472.
These revised technical specifications would reasonably assure compliance, in radioactive waste Appendix I to 10 CFR Part 50, with ~10 CFR Parts 20.10 405(c); with 10 CFR Part 50, Appendix A, General Design Criteria 60, 63 and 64; and with 10 CFR Part 50, Appendix B.
2.0 BACKGROUND
AND DISCUSSION 2.1 Regulations Section 50.36a, " Technical Specifications on Effluent Reactors," provides that each license authorizing operation of a nuclear power reactor will include technical ~ specifications that (1) require Effluents to Unrestricted Areas;" (2) require that opera developed for the control of efflupnts be established a maintained and used; and (4) require the periodic submission of reports to the NRC specifying the quantity of each of the principal FFdionuclides released to unrestricted areas in liquid and gaseous effluents, any design objectives, and such other information as may Commission to estimate maximum potential radiation dose to the public resulting from the effluent releases.
8509260037 850916 DR ADOCK O g6
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j-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 diceeded.
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10 CFR Part 50, Appendix A - Seneral Design Criteria for Nuclear Power i
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 i
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 j
handling areas to detect conditions that may result in excessive radiation levels and to initiate appropriate safety actions. Criterion 64 requires t
that means be provided for monitoring effluent discharge paths and the plant environs for radioactivity that may be released from normal operations, i
including anticipated operational occurrences and postulated accidents.
10 CFR Part 50, Appendix B, establishes quality assurance requirements for i
nuclear power plants.
10 CFR Part 50, Appendix I, Section IV, provides guides on technical 4
specifications for limiting conditions for operation for light-water-cooled j
nuclear power reactors licensed under 10 CFR Part 50.
4 2.2 Standard Radiological Effluent Technical Specifications 4
i NUREG-0472 provides radiological effluent technical specifications for pressurized water reactors which the staff finds to be an acceptable stan,dard for licensing actions.
Further clarification of these acceptable methods is provided in NUREG-0133, " Preparation of Radiological Effluent Technical l
Specifications for Nuclear Power Plants." NUREG-0133 describes methods
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found acceptable to the staff of the NRC for the calculation of certain key values required in the preparation of proposed radiological effluent i
technical specifications for light-water-cooled nuclear power plants.
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NUREG-0133 also provides guidance to licensees in preparing requests for -
l 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 i
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 speciffntions and i
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.
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, _ _ _ _.. ~ _ _ _.. - _. _.,,,. _ -.
. 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 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 th_e regulatfor.s described in Section 1.0.
3.0 EVALUATI0h The attached report (TER-C5506-99) was prepared by Franklin Research Center as part of the technical assistance contract program. This report provides a technical evaluation of NNECO's submittal relative to NRC-provided criteria.
The staff nas 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. 2 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 Millstone-2 is a pressurized water. reactor) and thereby fulfill all the requirements of the regulations
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related to radiological effluent technical specifications.
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. The proposed changes will not remove or relax any existing requirement related to the probability or c'onsequences 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 in the-installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20.
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 Conmission 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 Section 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.
5.0 GENERAL 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 this amendment will not be inimical to the common defense and security or the health and safety of the public.
Attachment:
FRC TER Date: September 16, 1985 Principal Contributors:
W. Meinke F. Congel C. Willis e ee e
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