ML20136C105
| ML20136C105 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 11/12/1985 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20136C098 | List: |
| References | |
| NUDOCS 8511210023 | |
| Download: ML20136C105 (2) | |
Text
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UNITED STATES 8
NUCLEAR REGULATORY COMMISSION o
g E-WASHINGTON, D. C. 20555
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. 96 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 t
1.0 INTRODUCTION
In the Fall of 1976, the NRC staff sent guidance to all licensees of power reactors concerning the implementation of 10 CFR 50.55a(g), inservice Inspection-(ISI) Requirements. In that guidance, licensees were requested 4
to submit, at least 6 months before the end of their first 120-month inspection interval, proposed Technical Specification (TS) changes to reflect more recent editions of Section XI of the ASME Boiler and Pressure Vessel Code, as required by 10 CFR 50.55a(g)(4)(11) and (5)(1). These i
revisions to the inservice inspection program TS would allow the incorporation of improved examination techniques as well as expanded and more clearly defined sampling plans that may have been developed during the previous 120-month interval for pressure-retaining components and their j
supports.
2.0 EVALUATION The staff has reviewed the licensee's request for amendment dated January 28, 1985. The proposed TS changes ensure that inservice inspection i
of components and piping will te performed in accordance with periodically 1
I updated editions and addenda of Section XI of the ASME Boiler and Pressure i
Vessel Code. The inspection and testing programs include ASME Code Class i
1, 2 or 3 components and piping and will provide assurance that the structural integrity of these components and piping will be maintained at an acceptable level throughout the life of the plant. We conclude that the proposed changes conform to the above-mentioned staff guidance and, therefore, are acceptable.
3.0 ENVIRONMENTAL CONSIDERATION
S This amendment involves a change in the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20.
The staff has determined that the amendment involves no significant increase i
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 i
significant hazards consideration and there has been no public comment on such finding. Accordingly, this amendment meets the eligibility criteria 8511210023 051112 DR ADOCK O 33
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.
4.0 CONCLUSION
We have concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the will not be endangered by operation in the proposed manner, and (2) public 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.
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" Principal Contributor:
B. Turovlin Dated: November 12, 1985 I
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