ML20205T364
| ML20205T364 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 11/10/1988 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20205T367 | List: |
| References | |
| NUDOCS 8811140226 | |
| Download: ML20205T364 (4) | |
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7590-1 UNITEDSTATESNUCLEARREGULATORYCOMMISSig POWER AUTHORITY OF THE STATE OF NEW YORK 00CKET NO. 50-333 ENVIRONMENTAL ASSESSMENT AND FINDING OF NO $1GNIFICANT IMPACT The U.S. Nuclear Regulatory Comission (NRC/the Comission) is considering issuance of an exemption from the requirements of Appendix J of 10 CFR Part 50 to the Power Authority of the State of New York (PASNY/the licensee),
for the James A. FitzPatrick Nuclear Power Plant located in Oswego County, New
- York, j
ENVIRONMENTAL ASSESSMENT Identification of proposed Action:
The licer,ee would be exempted from the requirements of Section III. A.6(b) of Append x J to 10 CFR Part 50 to the extent that a Type A Primary Containment Int cgrated Leak Rate Test (PCILRT) would not have to be perforined during the Reload 8/ Cycle 9 refueling outage (which connenced in August 1988) and that the normal PCILRT retest schedule specified in Section !!!.0(a) of Appensix J would be restored.
In addition, the 'iicensee would be exempted from the requirements of Section IV. A of Appendix J tc the extent that a Type C test would not be perforred during the Reload 8/ Cycle 9 refueling outage on the welds of a containment isolation valve located on the High Pressure Coolant injection (HPCI) turbine exhaust line. This valve is to be replaced during the outage, h$kI $0bN:
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The Need for the Proposed Action:
The PCILRTs performed during the 1982, 1985, i
and 1987 refueling outages were deemed failures in the "as-found" condition, i
Sei; tion III. A.6(b) of Appendix J states that, should two consecutive PCILRTs fail to meet the applicable acceptance criteria, a retest must be perfonaed l
during each subsequent refueling outage until two consecutive tests are deemed l
acceptable, after which time the retest schedule specified in Section !!!.D(a) may be resumed. Accordingly, tr a licensee would be required to perform a l
t PCILRT during the August 1988 refueling outage. As an alternative to performing i
this test the licensee has submitted a Corrective Action Plan which entails
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the replacement of 33 containment isolation valves which previously were identified as having excessive leakage.
Replacerent of 21 of these valves would take place during the Reload 8/ Cycle 9 cutage.
Implementation of the j
Corrective Action Plan will ensure that the intent of Section III.A.6(b) is met.
i in that unacceptable containment leakage is identified and corrected.
i In accordance with Section IV. A of Appendix J. a Type A. B or C test (as applicable) is required to be perfonned following any major modification or l
replar.ement of a component which is part of the primary reactor iontain:nent boundary. The licensee has deter: tned that the welds of one of the valves to be t
repleced, located on the HPCI turbine exhaust line, cannot be pressure tested.
Also, since the replaced manual valve is not used for containment isolation, it is not subiect to PCILRT requirements. Accordingly, the licensee has requested an exemption from Section IV.A.
In lieu of a Type A 8 or C test, the licensee I
i has proposed 100 percent radiography of the affected weld as well as dye t
i penetrant or magnetic particle tests. This will ensure that the intent t
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of Section IV. A. (the identification of leakage resulting from replacement of i
a component which is part of tFe primary containment boundary) is met, j
Environmental impact of the proposed Action:
The proposed action would ensure I
that excessive leakage from containment isolation valves is identified and 1
l corrected and would provide a level of safety at least equivalent to that I
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attained by compliance with Sections !!!.A.6(b) and IV.A of Appendix J to 10 CFR Part 50.
On this basis, the Commission concludes there are no sigaificant i
radiological environmental impacts associated with this proposed exemption.
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1 With regard to potential nonradiological impacts, the proposed exemption irvolves features located entirely within the restricted areas as defined in 4
It does.iot affect nonradiological plant effluents and has no i
other environrental impact. There' ore, the Commission u,ncludes that there
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are no significant nonradiological environmental impacts associated with the
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proposed exemption.
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Alternattu Use of Rescurces: This action involves no ese of resources not
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I previously' considered in the Final Environments 1 Statement (construction permit i
l and operating license) for the James A. FitzPatrick Nuclear Power Plant.
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Agencies and Persons Consulted:
The NPC staff reviewed the licensee's request j
and did not consult other agencies or persons, j
f FINDING OF NO SIGNIFICANT IMPACT 9
k The Consnission has determined tiot to prepare an environmental impact j
t statement for the propos d exemption.
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l Based upon the foregoing environmental assessment. we conclude that the 4
proposed action will not have a significant effect on the quality of the hunan i
i environment, j
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t 4-For further details with respect to this action, see the request for i
exemption dated April 8,1988 and the supplements dated June 17, 1988, i
July 14, 1988 and October 28, 1988, which are available for public inspection at the Cownission's Public Document Room, Gelman Building, 2120 L Street N.W.,
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Washington, D.C., and at the Penfield Library, State University College of Oswego, Oswego, New York.
i Dated et Rockv11*e, Maryland, this loch of Noveneer 1988.
1 FOR THE NUCLEAR REGULATORY CO*ISSION 3 M a-. Cw i
Robert A. Capra, Director 1
Project Directorate I-1 Division of Reactor Projects, I/I!
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