ML20056E010
| ML20056E010 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 07/29/1993 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20056E011 | List: |
| References | |
| NUDOCS 9308190186 | |
| Download: ML20056E010 (4) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 ENVIRONMENTAL ASSESSMENT AND FINDING OF NO SIGNIFICANT IMPACT The U.S. Nuclear Regulatory Commission is considering issuance of an exemption from the requirements of Appendix J of 10 CFR Part 50 to the Power Authority of the State of New York (PASNY, the licensee), for the James A.
FitzPatrick Nuclear Power Plant located in Oswego County, New York.
ENVIRONMENTAL ASSESSMENT Identification of Proposed Action:
The licensee would be exempted from the requirements of Section IV.A. of Appendix J, to 10 CFR Part 50, to the extent that a Type A, B, or C leak rate test would not have to be performed following the replacement of certain piping and welds in the Core Spray system minimum flow lines during the fall 1993 maintenance outage, currently scheduled for September 1993. The replacement piping and welds would be subject to a Type A primary containment integrated leak rate test prior to startup from the next refueling outage, currently scheduled to start in January 1995.
The Need for the Proposed Action:
In accordance with Section IV.A. of Appendix J to 10 CFR Part 50, a Type A, B, or C test (as applicable) is required to be performed following any major modification or replacement of a component which is part of the primary j
containment boundary. Augmented erosion / corrosion inspections conducted
$0 OoN O 3
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. during the 1992 refueling outage revealed the presence of pipe wall thinning in Core Spray system minimum flow lines (3"-W23-152-7A, 8), which the licensee believes to be cavitation induced pitting due to the location of the restricting orifice in each of these lines.
PASNY intends to replace approximately 5 feet of piping in each of these lines during the fall 1993 maintenance outage. The sections of piping scheduled to be replaced include the restricting orifices (14R0-27A, B) and the Core Spray minimum flow valves (14MOV-5A/5B). The planned repair constitutes a replacement of a component that is part of the primary containment boundary and would be performed in accordance with the requirements of ASME Section XI and ANSI B-31.1-1967 (the construction code for the FitzPatrick plant).
The licensee has determined that the requirement to conduct a Type A, B, or C test following repairs is applicable. However, the licensee has determined that, because of the locations of the sections of minimum flow line piping to be repaired, isolatable volumes cannot be practicably obtained. Therefore, pressure testing can only be accomplished by performing a Type A primary containment integrated leak rate test.
Further, the licensee has determined that performance of a Type A test would not be feasible during the 3-week maintenance outage, since it would lengthen the outage by a minimum of 3 to 4 weeks. Therefore, the licensee has requested an exemption from Section IV.A. of Appendix J to 10 CFR Part 50.
In lieu of a Type A, B, or C test, the licensee has proposed an alternate inspection program, including 100% radiography of the new welds, surface examination on new welds that form a portion of the primary containment boundary, and a system leakage test (in accordance with ASME Section XI,
_3_
1980 Edition through Winter 1981 Addenda, paragraph IWA-5213) to ensure structural integrity and leak tightness. These nondestructive examinations will ensure that the intent of Section IV.A. of Appendix J to 10 CFR Part 50 i
is met, which is to assure that modifications to the containment pressure boundary are leak-tight.
Environmental Imoact of the Proposed Action:
The proposed alternate inspection program would ensure that excessive leakage from the primary containment from the repaired areas of the Core Spray-minimum flow lines does not exist and would provide a level of safety at least equivalent to that attained by compliance with Section IV.A. of Appendix J to 10 CFR Part 50. On this basis, the Commission concludes that there are no significant radiological impacts associated with this proposed exemption.
With regard to potential nonradiological impacts, the proposed exemption involves features located entirely within the restricted areas as defined in 10 CFR Part 20.
It does not affect nonradiological plant effluents and has no other environmental impact. Therefore, the Commission concludes that there are no significant nonradiological environmental impacts associated with the proposed exemption.
t Alternative to the Proposed Action:
As an alternative to the proposed action, the staff considered denial of the proposed action. Denial of the application would result in no change in current environmental impacts. The environmental impacts of the proposed action and the alternative action are similar. This alternative would also result in an unwarranted extension of the fall 1993 maintenance outage beyond the planned 3 weeks.
m-
Alternative Use of Resources:
The actions associated with the granting of the proposed exemption as detailed above do not involve the use of resources not previously considered in connection with the " Final Environmental Statement Related to Operation of the James A. FitzPatrick Nuclear Power Plant," dated March 1973.
Acencies and Persons Contacted:
The Comission consulted with the State of New York regarding the environmental impact of the proposed action.
FINDING OF NO SIGNIFICANT IMPACT The Comission has determined not to prepare an environmental impact statement for the proposed exemption.
Based on the foregoing environmental assessment, the Comission concludes that the proposed action will not have a significant effect on the quality of the human environment.
For further details with respect to this action, see the licensee's application for exemption dated June 28, 1993. This document is available for public inspection at the Comission's Public Document Room, 2120 L Street, NW., Washington, DC 20555 and at the Reference and Documents Department, Penfield Library, State University of New York, Oswego, New York.
Dated at Rockville, Maryland, this 29th day of July 1993.
FOR THE NUCLEAR REGULATORY COMMISSION 0.
Robert A. Capra, Director Project' Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear. Reactor Regulation