ML20235M466

Safety Evaluation Supporting Amend 101 to License DPR-36

ML20235M466
Person / Time
Site:	Maine Yankee
Issue date:	09/29/1987
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20235M442	List: ML20235M441 ML20235M459 ML20235M466
References
NUDOCS 8710060204
Download: ML20235M466 (4)

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i SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATING TO AMENDMENT N0.101 TO FACILITY OPERATING LICENSE NO. DPR-36 l

MAINE YANKEE ATOMIC POWER COMPANY l

MAINE YANKEE ATOMIC POWER STATION DOCKET NO. 50-309 1

1.0 INTRODUCTION

To comply with Section V of Appendix I of 10 CFR Part 50, the Maine Yankee Atomic Power Company filed with the Coninission plans and proposed technical specifications developed for the purpose of keeping releases of radioactive materials to unrestricted areas during nonnal operations, including expected operational occurrences, as low as is reasonably l

achievable.

Those technical specifications were approved as Amendment No.

86 of Maine Yankee Atomic Power Station License (No. DPR-36). The proposed technical specifications update those portions of the technical specifications addressing radioactive waste management and make them i

consistent with the current staff positions as expressed in NUREG-0472, These revised technical specifications 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 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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However, to assure tbat the radioactive waste at Maine Yank'ee Atomic Power.

Station is processed for shipment in accordance with existing,-

reviewed / approved plant procedures, Maine Yankee Atomic Power Company has

.q submitted a proposed technical specification change to require that such l

t procedures be generated.

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2.0 BACKGROUND

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 ir.clude technical specifications that require, among other things, operating procedures developed for the control of radioactive wast:s be established and

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followed.

3.0 EVALUATION

.1 The proposed change is administrative in nature formally requiring in the technical specifications the implementation of existing procedures.

3.1

SUMMARY

The proposed changes to the radiological effluent technical specifications for Maine Yankee Atomic Power Station have been reviewed, evaluated, and found to be in compliance-with' the requirementsiof the NRC regulations and with the intent of NUREG-0133 and NUREG-0472 '(the Maine Yankee Plant is a pressurized water reactor) and thereby fulfill-all the requirements of the regulations related to radiological effluent technical specifications.

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nr 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 i

staff, therefore, finds the proposed changes acceptable.

4.0 ENVIRONMENTAL CONSIDERATION

l 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 and changes in inspection and surveillance requirements. The staff has a

determined that the amendment involves no significant increase in the j

amount and no significant change in the types of any effluents that may j

l be released offsite and that there is no significant increase in j

individual or cumulative occupational radiation exposure.

The Comission 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 i

issuance of this amendment.

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'i 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 Comission'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.

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Principal Contributor:

P. Sears I

Dated: August 12, 1987 8

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