ML20134K198

Safety Evaluation Supporting Amend 77 to License DPR-6 Re Radiological Effluent Tech Specs

ML20134K198
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	08/26/1985
From:	Office of Nuclear Reactor Regulation
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ML20132C980	List: ML20132C977 ML20134K169 ML20134K189 ML20134K198 ML20134K220 ML20134K254 ML20134K266
References
NUDOCS 8508300068
Download: ML20134K198 (5)

Text

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j NUCLEAR REGULATORY COMMISSION WASHWGTON, D. C. 20555

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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION

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SUPPORTING AMENDHENT NO. 77 TO FACILITY OPERATING LICENSE NO. DPR-6 CONSUMERS POWER COMPANY i BIG ROCK POINT PLANT 1 DOCKET NO. 50-155 i

RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS (RETS)_

1.0 INTRODUCTION

To comply with Section V of Appendix I, of 10 CFR Part 50, Consumers Power Company has filed the subject application with the Commission. In general, it contains the plans and proposed technical specification changes related to the RETS. ~These documents were developed for the purpose of keeping releases of radioactive materials, in unrestricted areas during normal -

operations, including expected operational occurrences, as low as

reasonably achievable. This information was filed with the Commission via letter dated January 7,1985 as revised March 14, 1985. The proposed technical specifications update those portions of the Technical Specificetions '

addressing radioactive waste management and make theri consistent with the current staff positions as expressed in NUREG-0473, " Radiological Effluent

- Technical Specifications for BWRs." These revised Technical Specifications would reasonably assure compliance, in radioactive waste management, with the provisions of 10 CFR 50.36a, as supplemented by Appendix I to 10 CFR Part 50, with 10 CFR 20.105(c),106(g), and a05(c); with 10 CFR Part 50, Appendix A, General 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 Determination and Opportunity for Hearing related to the requested action was published in the Federal Register on June 4, 1985 (50 FR 23546). No public coments or requests for hearing were received.

2.0 BACKGROUND

AND DISCUSSION I 2.1 Reculations 10 CFR Part 50, " Domestic Licensing of Production and Utilization Facilities",

4- Section 50.36a, " Technical Specifications on Effluents from Nuclear Power i

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"; (2) require that operating procedures I developed for the control of effluents be established and followed; (3) require 850830 e50826 PDR A 05000155 P PDR

I 2-that equipment installed in the radioactive waste systen be maintained and used; and (4) recuire the periodic submission of reports to NRC specifying the quantity of each of the principal radionuclides released to unrestricted areas in liquid and gasecus effluents, and quantities of radioactive materials released that are significantly above c'esion ob,iectives, and such other information as may be recuired by the Commission to estimate maximun 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.dO5(c), require that nuclear power plant and other licensees comply with 40 CFR Part 190, "Fnvironmental Radiation Protection Standards for Fuclear 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 environnent; 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 radioective solid wastes produced during normal reactor operation, including anticipated operational occurrences. Criterion 63 reouires that appropriate systens 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 reouf res that neans 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 nucleer power reactors licensed under 10 CFR Part 50.

2.2 Standard Radiological Effluent Technical Specifications NUREG-0473 provides RETS for boiling veter 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 rethods found acceptable to the staff of the NRC for the calculation of certain key values reouired in the oreparation of proposed RETS 'or light-water-cooled nuclear power plants. NUREG-0133 also provides guidance to licensees in precaring reauests for changes to existing RETS 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 apptuaches to the preparation of radiological effluent technical specifications and alternative radiological effluent technical specifications rey be acceptable if the staff determines that the alternatives are in compliance with the regulations and with the intent of the regulatory cuidance.

The standard RETS can be grouped under the following ca'tegories:

(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 corprised of two perts: the limiting condition for operation and the surveillance reouirements. The limiting condition for operation provides a statenent 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 ret.

In general, the specifications established to assure compliance with 10 CFR Part 20 standards provide, in the event the limiting conditfors for operation are exceeded, that without deley, 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 for operations 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 cortein 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.

3.0 EVALUATION The attached report (TER-C5506-PA) was prepared for the staff by Franklin Research Center, as part of a technical assistance contract program.

Their report provides a technical evaluation of the compliance of Consumers Power Company's submittal with NRC provided criteria. The staff has reviewed this technical evaluation report, agrees with the evaluation, and incorporates it herein as a part of this safety evaluation.

3.1 Sumary The proposed changes to the RETS for Big Rock Point have been reviewed, evaluated, and found to be in compliance with the recuirements of the NRC regulations and with the intent of NUREG-0133 and NUREG-0473 (Big Rock Point is a boilina water reactor) and thereby fulfill all the requirements of the regulations related to RETS.

Several administrative chances tiere necessary in order to accommodate the new RETS. These affected technical specifications were either relocated and/or reformatted. These changes have also been evaluated in the attached safety evaluation.

4.0 ENVIRONMENTAL CONSIDERATION

This amendnent involves a change to a reouirenent with respect to the installation or use of facility components located within the restricted area as defired in 10 CFR Part 20 and changes to the surveillance requirements. The staff has determined that the amendment involves 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 Commission has previously issued a proposed finding that this amendment irvolves 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 CFP. 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuarce of this amendment.

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 erdangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Connission's regulations and the issuance of this anendment will not be inimical to the common defense and security or to the health and safety of the pubitc.

6.0 ACKN0l!LEPCFFENT This Safety Evaluation has been prepared by Kayre Feinke and Thomas S. Rotella.

Dated: August 26, 1985

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