ML20100K377
| ML20100K377 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 04/03/1985 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20100K375 | List: |
| References | |
| NUDOCS 8504150295 | |
| Download: ML20100K377 (5) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION g
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WASHINGTON D.C.20555
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 86 TO FACILITY OPERATING LICENSE NO. DPR-40 FORT CALHOUN STATION OMAHA PUBLIC POWER DISTRICT Docket No. 50-285
1.0 INTRODUCTION
To comply with Section V of Appendix I of 10 CFR Part 50, the Omaha Public Power District (0 PPD) has filed with the Comission plans and proposed tech-nical specifications developed for the purpose of keeping releases of radio-active materials to unrestricted areas during nonnal operations, including expected operational occurrences,'as low as is reasonably achievable. OPPD i
filed this information with the Comission by letter dated October 18, 1984, which requested changes to the Technical Specifications appended to Facility Operating License No. DPR-40 for Fort Calhoun Station. The proposed technical specifications update those portions of the technical specifications addressing radioactive waste management and make them consistent with the current staff positions as expressed in NUREG-0472. These revised technical specifications
.would reasonably assure compliance, in radioactive waste management, with the 50, with 10 CFR Parts 20.105(c),106(g)pplemented by Appendix I to 10 CFR Part provisions of 10 CFR Part 50.36a, as su, and 405(c); with 10 CFR Part 50, Appendix A, General Design Criteria 60, 63 and 64; and with 10 CFR Part 50, l
Appendix B.
2.0 BACKGROUND
AND DISCUSSION i
l 2.1 Regulations 10 CFR Part 50, " Domestic Licensing of Production and Utilization Facilities,"
l Section 50.36a, " Technical specifications on effluents from nuclear power reactors,"
provides that each license authorizing (operation of a nuclear power reactor will l
include technical specifications that 1) require compliance with applicable rovisions of Part 20.106, " Radioactivity in effluents to unrestricted areas;"
l p(2) require that operating procedures developed for the control of effluents be waste system be maintained and used; and (4)quipment installed in the radioacti established and followed; (3) require that e 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 Comission to estimate maximum potential radiation dose to the public resulting from the effluent releases.
8504150295 850403 PDR ADOCK 05000285 P
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 licen-sees 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.
General Design Criteria for Nuclear Power Plants, contains Criterion 60, Control of releases of 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 con-
' trol suitably the release of radioactive materials in gaseous and liquid effluents and to handle-radioactive solid wastes produced during nornal 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, 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 specifi-cations for limiting conditions for operation for light-water-cooled nuclear power reactors licensed under 10 CFR Part 50.
~
3 2.2 Standard Radiological Effluent Technical Specifications NUREG-0472 provides radiological effluent technical specifications for pres-surized water reactors which the staff finds to be an acceptable standard for licensing actions.
Further clarification of these acceptable methods is pro-vided in NUREG-0133, " Preparation of Radiological Effluent Technical Specifica-tions for Nuclear Power Plants." NUREG-0133 describes methods found acceptable 1
to the staff of the NRC 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 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 released release of radioactive materials in effluents and on the administrative control 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 e
_provided by the regulations previously cited. However, alternative approaches F
to the preparation of radiological effluent technical specifications and alter-native 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:
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(1 Instrumentation Radioactive effluents Radiological environmental monitoring 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 require-ments. The limiting condition for operation provides a statement of the limi-ting 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 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 con-ditions. Otherwise, the facility is required to effect approved shutdown pro-cedures.
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, alter-native means of operation are to be employed, and certain reports are to be sub-mitted to the NRC describing these conditions and actions.
The specifications concerning design features and administrative controls con-tain no limiting conditions of 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, 3.0 EVALUATION The attached report (EGG-PBS-6765) was prepared for us by EG&G Idaho, Inc. as part of our technical assistance contract program. Their report provides their technical evaluation of the compliance of the licensee's submittal with NRC-pro-vided 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 Fort Calhoun Station 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 (Fort Calhoun Station is a pressurized water reactor) and thereby fulfill all the requirements of the r.egulations related to radiological effluent technical specifications. The proposed changes will not remove or relax any existing requirement related to the probability or con-sequences 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 staff, therefore.
finds the proposed changes acceptable.
O
D 4.0 ENIRONMENTAL CONSIDERATION This amendment involves changes in the installation or use of a facility com-ponent 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 signi-ficant change in the types, of any effluents that may be released offsite and that there is no significant increase in individual or cumulative occupational radia-tion 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 eli lity criteria for categorical exclusion set forth in 10 CFR Section 51.22(gibi-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 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 Commission'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.
Attachment:
INEL Technical Evaluation Report Date: April 3, 1985 Principal Contributor:
C. Miller, DSI
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