[Federal Register Volume 59, Number 192 (Wednesday, October 5, 1994)]
[Unknown Section]
[Page 0]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 94-24598]


[[Page Unknown]]

[Federal Register: October 5, 1994]


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NUCLEAR REGULATORY COMMISSION
[Docket No. 50-333]

 

Power Authority of the State of New York; Notice of Issuance of 
Amendment to Facility Operating License

    The U.S. Nuclear Regulatory Commission (Commission) has issued 
Amendment No. 217 to Facility Operating License No. DPR-59 issued to 
Power Authority of the State of New York, which revised the Technical 
Specifications (TSs) for operation of the FitzPatrick Nuclear Power 
Plant located in Oswego County, New York.
    The amendment modifies the Safety/relief Valve (SRV) performance 
limits. Specifically, the requested changes: (1) Modify TS 2.2.1.B, and 
its associated Bases, to establish a single nominal SRV setpoint of 
1110 psig; (2) modify TS 4.6.E, and its associated Bases, to increase 
the SRV setpoint tolerance to 3%; and (3) modify TSs 3.5.D, 3.6.E and 
4.5.D, and their associated Bases, to allow for two SRVs (or automatic 
depressurization system (ADS) valves) to be inoperable during 
continuous power operation.
    In addition, the amendment clarifies terminology, corrects 
typographical errors, removes a surveillance requirement which should 
have been deleted as part of Amendment No. 130, and deletes a duplicate 
TS. Specifically, the requested changes; (1) Modify TS 1.2.1, and the 
Bases sections for TS 3.6.E and 4.6.E, to clarify terminology; (2) 
modify TS 3.5.D.2, and the Bases sections for TSs 1.2 and 2.2, to 
correct typographical errors; (3) modify TS 4.2.B, Table 4.2-2, to 
correct an error made in Amendment No. 130 that failed to delete the 
requirement to perform logic functional testing on the ADS bellows 
pressure switch; (4) modify TS 4.5.D.1.b, to move the TS to 4.6.E.4, a 
new section, and clarify the requirements associated with SRV manual 
actuation testing; (5) modify Bases sections for TSs 3.6.E and 4.6.E, 
to move the Bases for the SRV manual actuation testing to the 
applicable sections; and (6) modify TS 4.6.E.4, to delete a duplicate 
specification pertaining to the annual report of SRV failures.
    The application for the amendment complies with the standards and 
requirements of the Atomic Energy Act of 1954, as amended (the Act), 
and the Commission's rules and regulations. The Commission has made 
appropriate findings as required by the Act and the Commission's rules 
and regulations in 10 CFR Chapter I, which are set forth in the license 
amendment.
    Notice of Consideration of Issuance of Amendment and Opportunity 
for Hearing in connection with this action was published in the Federal 
Register on May 15, 1990 (55 FR 20228) and on May 25, 1994 (59 FR 
27064). No request for a hearing or petition for leave to intervene was 
filed following this notice.
    The Commission has prepared an Environmental Assessment (EA) 
related to the action and has determined not to prepare an 
environmental impact statement. Based upon the EA, the Commission has 
concluded that the issuance of this amendment will not have a 
significant effect on the quality of the human environment.
    For further details with respect to the action, see: (1) The 
application for amendment dated December 20, 1989, as supplemented by 
letters dated January 16, 1990, January 3, 1992, January 30, 1992, May 
5, 1993, and May 26, 1993 and superseded March 2, 1994, (2) Amendment 
No. 217 to License No. DPR-59, and (3) the Commission's related Safety 
Evaluation and EA. These letters are available for public inspection at 
the Commission's Public Document Room, 2120 L Street, NW., Washington, 
DC at the Reference and Documents Department, Penfield Library, State 
University of New York, Oswego, New York.

    Dated at Rockville, Maryland, this 28th day of September 1994.

    For the Nuclear Regulatory Commission.
Michael J. Case,
Acting Director, Project Directorate I-1, Division of Reactor 
Projects--I/II, Office of Nuclear Reactor Regulation.
[FR Doc. 94-24598 Filed 10-4-94; 8:45 am]
BILLING CODE 7590-01-M