ML20099K774
| ML20099K774 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 02/22/1985 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20099K761 | List: |
| References | |
| NUDOCS 8503200368 | |
| Download: ML20099K774 (4) | |
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- g UNITED STATES p,
NUCLEAR REGULATORY COMMISSION
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j wAsHWGTON, D. C. 20665
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NOS.100 AND 82 TO FACILITY OPERATING LICENSE NOS. DPR-53 AND DPR-69 BALTIMORE GAS AND ELECTRIC COMPANY CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-317 AND 50-318
1.0 INTRODUCTION
To comply with Section V of Appendix I of 10 CFR Part 50, the Baltimore Gas &
Electric Company (BG&E) has filed with the Commission plans and proposed
' technical-specifications (TS) 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. BG8E filed this information with the Commission by letter dated October 11, 1984 which requested changes to the Technical Specifications appended to Facility Operating License Nos. DPR-53 and DPR-69 for the Calvert Cliffs Nuclear Power Plant, Unit Nos. I and 2.
The proposed TS update those portions of the TS addressing radioactive waste management and make them consistent with the current staff positions as expressed in NUREG-0472.
These revised TS 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 20.105(c),106(g), and 405(c);
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with 10 CFR Part 50, Appendix A, General Design Criteria 60, 63, and
'6A; and with 10 CFR Part 50, Appendix B.
At the request of the licensee, the Technical Specifications associated with
. the radiological environmental monitoring program will be issued at this time.
The. existing program requirements in the Appendix B Technical Specifications will'be deleted since they are no longer needed. The remaining radiological effluent technical specifications.will be issued by' July 1, 1985.
2.0 BACKGROUND
AND DISCUSSION 2.1 Reculations i
10 CFR Part 50, " Domestic Licensing of Production and Utilization Facilities",10 CFR 50.36a, " Technical specifications on effluents from nuclear power re1ctors", 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 20.106,
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" Radioactivity in ~ effluents to unrestricted areas"; (2) require that 8503200368 850222 PDR ADOCK 05000317 P
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. l operating procedures developed for the control of effluents be established e
and followed; (3) reouire that equipment installed in the radioactive waste system be maintained and used; and (4) require the periodic submission of i
reports to the NRC specifying the quantity of each of the principal
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radionuclides released to unrestricted areas in liquid and gaseous effluents, 1
any quantities of radioactive materials released that are significantly above
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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," 10 CFR 20.105(c), 20.106(g), and 20.405(c), reouire that nuclear power plants and 3
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.
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10 CFR Part 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 i
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 i
radioactive solid wastes produced during nonnal reactor operation, including r
anticipated operational occurrences. Criterion 63 requires that appropriate i
systems be provided in radioactive waste systems and associated handling 5
areas to detect conditions that may result in excessive radiation levels and 2
to initiate appropriate safety actions. Criterion 64 requires that means be ti provided for monitoring effluent discharge paths and the plant environs for i'
radioactivity that may be released from normal operations, including anticipated operational occurrences and postulated accidents.
d 10 CFR Part 50, Appendix B, establishes quality assurance requirements for nuclear power plants, f
a 10 CFR Part 50, Appendix I, Section IV, provides guides on technical 3
specifications for limiting conditions for operation for light-water-cooled g
nuclear power reactors licensed under 10 CFR Part 50.
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2.2 Standard Radiolooical Effluent Technical Specifications NUREG-0472 provides radiological effluent technical specifications for l
pressurized water reactors that the staff finds to be an acceptable
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standard for licensino actions.
Further clarification of these acceptable methods is'provided in NUREG-0133, " Preparation of j
Radiological Effluent Technical Specifications for Nuclear Power Plants."
P NUREG-0133 describes methods found acceptable to the staff of the NRC a
for the calculation of certain key values required in the preparation of proposed radiological effluent technical specifications for light-water-cooled nuclear power plants. NUREG-0133 also provides guidance to g
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. 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 complian:e with the guidance and requirements provided by the regulations previously cited. However, alternative approaches to the preparation of radiological effluat 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 l
CFR Part 20 standards provide, in the event the limiting conditions of operation are exceeded, that without delay conditions are restored to l
within the limiting conditions. Otherwise, the facility is reouired 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 for 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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. ~3.0 EVALUATION
.The enclosed report (TER-C5506-87/88) was prepared for the staff by Franklin Research Center (FRC) as part of a technical assistance contract program. The FRC 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 the Calvert Cliffs Plant, Unit Nos. I and 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 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 needed to provide reasonable assurance that the health and safety of the public will not be endanoered by operation in the proposed manner. The staff, therefore, finds the proposed changes acceptable.
4.0 ENVIRONMENTAL CONSIDERATION
These amendments involve changes in 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 detennined that the amendments involve 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 these amendments involve no significant hazards consideration and there has been~no public comment on such finding. Accordingly, the amendments meet 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 assess-ment need be prepared in connection with the issuance of the amendments.
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 these amendments will not be inimical to the convron defense and security or to the health and safety of the public.
Enclosure:
Franklin Research Center Technical Evaluation Report Principal Contributors:
W. Meinke D. Jaffe
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Date: February 22, 1985
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