ML17054B197

SER Supporting Amend 66 to License DPR-63

ML17054B197
Person / Time
Site:	Nine Mile Point
Issue date:	11/02/1984
From:	Office of Nuclear Reactor Regulation
To:
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ML17054B196	List: ML17054B195 ML17054B197
References
NUDOCS 8411210467
Download: ML17054B197 (18)

Text

t UNITED STATES NUCLEAR R EGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR PEACTOR REGULATION SUPPORTING AMENDMENT NO.

66 TO FACILITY OPERATING LICENSE NO.

DPR-63 NIAGARA MOHAHK POHER CORPORATION NINE MILE POINT NUCLEAR STATION UNIT NO 1

DOCKET NO. 50-220

1. 0 INTRODUCTION To comply with Section V of Appendix I of 10 CFR Part 50, Niagra Mohawk Power Corporation has filed with the Commission plans and proposed tech-nical 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.

Niagra Mohawk filed this information with the Commission by letter dated February l, 1984, which requested changes to the Tech-nical Specifications appended to Facility Operating License No.

DPR-63 fol Nine Mile Point Unit l.

The proposed technical speci fications update those portions of the technical specifications addressing radioactive waste management and make them consistent with the current staff posi-tions as expressed in NUREG-0473.

These revi sed technical specifications 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 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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2.0 SACKGROUND AND DISCUSSION 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 technical specifications that (1) require compliance with applicable provisions of Part 20.106, "Radioactivity in Effluents to Unrestricted Areas";

(2) require that 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 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," paragraphs 20.105(c),

20. 106(g),

and 20.405(c),

requi re that nuclear power plant and 4

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 for 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'he 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, includin'g 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 Radiolo ical Effluent Technical S ecifications NUREG-0473 provides radiological effluent technical specifications for boiling water reactors which the staff finds to be an acceptable standard for licensing actions.

Further clarification of these accept-able methods is provided in NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants."

NUREG-0133 describes methods found acceptable to the staff of the NRC for

'he 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 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 treat-ment sytems.

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 fo ll owi ng categories:

(1)

Instrumentation (2)

Radioactive effluents (3)

Radi ol ogi cal envi ronmental moni toring (4)

Oesign fe'atures (5)

Admi ni strati ve control s.

Each of the specifications under the first three categories is comprised of two parts:

the limiting condition for operation and the surveil-lance requirements.

The limiting condition for operation provides a statement of the limiting condition, the times when it is applicable, and the actions to he 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'urveillance requirements.

- Table I indicates the standard radiological effluent technical I

specifications that are needed to assure compliance with the particular provisions of the regulations described in Section 1.0.

3.0 EVALUATION The enclosed report (TER-C5506-100) was prepared for us by Franklin Reasearch Center (FRC) as part of our technical assistance contract program.

Their report provides their technical evaluation of the com-pliance of the Licensee's submittal with NRC provided criteria.

The I

staff has reviewed this TER and agrees with the evaluation.

3.1

SUMMARY

,The proposed changes to the radiological effluent technical, specifica-tions for Nine Mile Point Unit 1

have been reviewed, evaluated, and found to be i n compliance with the requi rements of the NRC regulations and with the intent of NUREG-0133 and NUREG-0473 (Nine Mile Point Unit 1

'is a boiling water reactor) and thereby fulfillall the requirements of the regulations related to radiological effluent technical specifications.

I 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.

CP

Table 1.

Relation Between Provisions of the Regulations and the Standard Radiological Effluent Technical Specifications for Pressurized Water Reactors and Boiling Water Reactors I'an ar a io ogica uent ec nica pec>>cat ons nstru-IIenta-tion L1qu id SWW~Wll aseous Radioactive t f uents Had. Envir.

Honitorin Design Features Administrative Control

~ Indicate the specifications that are needed to assure compliance with the identified provision of the regulat1ons.

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4.0 EHYIRONHENTAL 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 and changes in inspection and 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 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 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 CONCLUSION

lie have concluded, based on the considerations discussed above, that (l) 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 to the health and safety of the public.

Attachment:

Technical Evaluation Report Principal Contributors:

W. Meinke C. Hillis Dated:

Nqyegber 2, 1984

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