ML20246M373
| ML20246M373 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 05/09/1989 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20246M357 | List: |
| References | |
| NUDOCS 8905190109 | |
| Download: ML20246M373 (2) | |
Text
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>1 KEG UNITED STAMS NUCLEAR REGULATORY COMMISSION o
y E
WASHINGTON, D. C. 20555
/
SAFETY EVALUATION BY THE OFFICE OF NJCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 128 TO FACILITY OPERATING LICENSE NO. DPR-59 POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 INTRODUCTION letter dated April 11, By letter dated December 7, 1987 and supplemented by(PASNY) requested changes 1989, the Power Authority of the State of New York-to Facility License No. DPR-59 for the James A. Fif 1 trick Nuclear Power Plant. The changes would modify the license sectiv.s dealing with byproduct material by removing the limit on the receipt, possession, and use of radioactive apparatus, components and tools, and removing the limit on possession of source and special nuclear material by expressly permitting the possession of radioactive material which is produced by the operation of the plant.
EVALUATION The purpose of the proposed changes is to clarify the license conditions governing on-site receipt, possession and use of radioactive materials. The current license does not explicitly address the receipt, possession and use of radioactive equipment such as apparatus, components and tools and does not reflect the amount of byproduct, source and special nuclear material already existing in the plant. This material is being used for check sources, sampling and instrument calibration, or resultt from normal plant operation, or is used to support normal plant operation. The quantity currently noted in the operating license was a limiting value initially used for sampling analysis and/or for laboratory and portable instrument calibration prior to issuance of the operating license.
The ability to receive, possess and use byproduct, source and special nuclear material, radioactive apparatus, components, and tools, without restriction to chemical or physical form to support various plant activities, is implicitly granted by the operating license, subject to 10 CFR Parts 30, 40 and 70 conditions. Clarifying the license in this area will, among other things, eliminate difficulties which have been encountered in the past during transfer of radioactive tools frosa other utilities to the licensee. The proposed license change will also clarify the ability of the licensee to possess the byproduct and special nuclear material, such as fission byproducts and activated equipment, resulting from plant operation, the principle source of such material.
8905190109 890509 gDR ADOCK 05000333 PUC
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. l The licensee has been handling byproduct, source and special nuclear material in accordance with 10 CFR Parte 30, 40 and 70. These sections specify the rules for handling such materials, but do not limit the amount a licensee may possess. At the site, this material is controlled by the Radiological &
Environmental Services and Operations Departments and procedures are in effect for handling, storage, and inventory control. Also, the NRC Safety Evaluation Report, Supplement 1, dated February 1,1973, determined that the personnel qualifications, facilities, equipment, and procedures for handling this material meet the applicable radiation protection provisions of 10 CFR Parts 20 and 30.
Additionally, the licensee's technical specifications contain provisions for leakage testing and related surveillance and reporting requirements for applicable radioactive material sources at the plant.
The proposed license changes are clarifying in nature and do not affect the original authorization in the license to possess nuclear materials necessary for plant operation. They have no significant impact on the types or quantities of radioactive materials on hand at the plant. The proposed change does not change any s, stem or subsystem and will not alter the conclusions of either the FSAR or SER accident analysis.
ENVIRONMENTAL CONSIDERATION The amendment involves a change in the installation or use of a facilit.v component located within the restricted area as defined in 10 CFR Part L.
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 Sec 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.
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 b-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 scfety of the public.
Dated:
May 9, 1989 PRINCIPAL CONTRIBUTOR:
D. LaBarge
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