ML20093D013
| ML20093D013 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 06/27/1984 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20093D011 | List: |
| References | |
| TAC-08985, TAC-8985, NUDOCS 8407160069 | |
| Download: ML20093D013 (6) | |
Text
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o UNITED STATES
'[ g(ffgg NUCLEAR REGULATORY COMMISSION
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i WASHINGTON, D. C, : 0555
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT N0.69 TO FACILITY OPERATING LICENSE NO. DPR-72
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FLORIDA POWER CORPORATION, ET AL l
CRYSTAL RIVER UNIT NO. 3 NUCLEAR GENERATING PLANT DOCKET NO. 50-302
1.0 INTRODUCTION
To comply with Section V of Appendix I of 10 CFR Part 50, the Florida Power Corporation (the licensee) has filed with the Connission plans and proposed technical specifications developed for the purpose of keeping i
releases of radioactive materials to unrestricted areas during nonnel 1
operations, including expected operational occurrences, as low as is -
reasonably achievable. The Florida Power Corporation filed this infonnation with the Connission by letter dated January 17, 1983, as supplemented by letters dated November 1, and December 16, 1983, and March 22, 1984, which requested changes to the Technical Specifications appended to Facility Operating License No. DPR-72 for Crystal River Unit 3.
The proposed Technical Specifications update those portions of the Technical Specifications addressing radioactive waste management and make them consistent with the current NRC staff positions'as expressed in NUREG-0472. The supplemental revisions to the January 17, 1983, change request were, for the most part, requested by the staff to make the new Technical Specifications more consistent with staff positions.
.with other nuclear power plants in the State of Florida and with certain items implemented by NUREG-0737. These revised Technical
>j Specifications will reasonably assure compliance, in radioactive waste management, with the provisions of 10 CFR Part 50.36a, as supplemented i
by Appendix I to 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, j
and 64; and with 10 CFR Part 50, Appendix B.
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2.0 BACKGROUND
AND DISCUSSION
.l, 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 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 l
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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 i
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), 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 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 1
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 radioactive solid wastes produced during normal reactor operation, including anticipated operational occurrences.
Criterion 63 requires that appropriate systems be prwided 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 prwided for monitoring effluent discharge paths and the plant environs for radioactivity that i
may be released from normal operations, including anticipated operational 1
occurrences and postulated accidents.
10 CFR Part 50, Appendix B, establishes quality assurance requirements
- 4 for nuclear power plants.
!I Ji 10 CFR Part 50, Appendix I, Section IV, prwides guides on technical i'
specifications for limiting conditions for operation for light-water-3 cooled nuclear power reactors licensed under 10 CFR Part 50.
2.2 Standard Radiological Effluent Technical Specifications 3
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!1 NUREG-0472 prwides radiological effluent technical specifications for l}
pressurized water reactors which the staff finds to be an acceptable standard for licensing actions. Further clarification of these accept-lf'.
able methods is prwided in NUREG-0133, " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants." NUREG-lj 0133 describes methods found acceptable to the staff of the NRC for l.
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! i the calculation of certain key values required in the preparation of proposed radiological effluent technical speci fications for light-water-cooled nuclear power plants. NUREG-0133 also prwides 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 abwe NUREG documents address all of the radiological effluent technical specifications needed to assure compliance with the guidance and requirements prwided 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 following categories:
(1 Instrumentation Radioactive effluents Radiological environmental monitoring Design features
- 5) Administrative controls, a
l' Each of the specifications under the first three categories is comprised of two parts: the limiting condition for operation and the surveillance 1
requirements. The limiting condition for operation prwides a statement of the limiting condition, the times when it is applicable, and the i
actions to be taken in the event that the limiting condition is not met.
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In general, the specifications established to assure compliance with 10 2
CFR Part 20 standards prwide, in the event the limiting conditions of j
operation are exceeded, that without delay conditions.are restored to
.j within the limiting conditions. Otherwise, the facility-is required to effect approved shutdown procedures.
In general, the specifications
.i established to assure compliance with 10 CFR Part 50 prwide, in the
!I event the limiting conditions of operation are exceeded, that within If specified times corrective actions are to be taken, alternative means of j
operation are to be employed, and certain reports are to be submitted to the NRC describing these conditions and actions.
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i The specifications concernino desian features and administrative controls concein no iinniting conditivos fur operacion 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.
3.0 EVALUATION A Technical Evaluation Report (EGG-PHYS-6171) was prepared for us by EG&G Idaho, Inc. (EG&G) as part of our technical assistance contract program.
Their report provides their Technical Evaluation of the compliance of the licensee's submittal.with NRC provided criteria. The staff has revi'ewed this TER and agrees with the evaluation with the following exceptions. Because of the location of the plant, the staff considers j
that the licensee's commitment to extra airborne radioiadine samples provides a sufficient supplement to their proposed ingestion samples to meet the intent of NUREG-0472. In relation to the PCP, the licensee is presently operating under a Process Control Program (PCP) that is available for review by the NRC at any time. This is acceptable under NRC guidelines. A copy of the TER, minus the detailed Appendix, is enclosed.
3.1 SAFETY CONCLUSIONS The proposed radiological effluent technical specifications for Crystal River Unit No. 3 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 (Crystal River 3 is a pres-surized water reactor) and thereby fulfill all the requirements of the
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regulations related to radiological effluent technical specifications, c
The proposed changes will not remove or relax any existing requirement related to the probability or consequences of accidents previously considered or needed to provide reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner.
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4.0 ENVIRONMENTAL CONSIDERATION
l This amendment involves a change in the installation or use of a facility component located within the restricted area. We have determined that the amendment involves no significant increase in the amounts of any effluents that may be released offsite and that there is no significant lj increase in individual or cumulative occupation radiation exposure. The l
Commission has previously issued a proposed finding that this amen &nent involves no significant hazards consideration and there has been no public l,
consent on such finding. Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
l.
Pursuant to 10 CFR 51.22(b) no environmental impact statement or
! l environmental assessment need be prepared in connection with the issuance of this amendment.
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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 p0blic 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 common defense and security or to the health and safety of the public.
Datedi June 27, 1984
Attachment:
TER No. EGG-PHYS-6171 dated May 1983 Principal Contributors:
C. Willis, W. Meinke.
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