[Federal Register Volume 62, Number 59 (Thursday, March 27, 1997)]
[Notices]
[Pages 14705-14706]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 97-7913]


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NUCLEAR REGULATORY COMMISSION

[Docket No. 50-286]


Power Authority of the State of New York; Indian Point Nuclear 
Generating Unit No. 3; Environmental Assessment and Finding of No 
Significant Impact

    The U.S. Nuclear Regulatory Commission (the Commission) is 
considering issuance of an amendment to Facility Operating License No. 
DPR-64 issued to the Power Authority of the State of New York (the 
licensee) for the Indian Point Nuclear Generating Unit No. 3, located 
in Westchester County, New York.

Environmental Assessment

Identification of Proposed Action

    The proposed action would exempt the licensee from the requirements 
of 10 CFR 70.24(a), which requires a monitoring system that will 
energize clearly audible alarms if accidental criticality occurs in 
each area in which special nuclear material is handled, used, or 
stored. The proposed amendment would also exempt the licensee from the 
requirements of 10 CFR 70.24(a)(1), which specifies the detection and 
sensitivity capabilities of the monitors required by 10 CFR 70.24(a). 
Finally, the proposed action would exempt the licensee from the 
requirements of 10 CFR 70.24(a)(3), which states that the licensee 
shall maintain emergency procedures for each area in which this 
licensed special nuclear material is handled, used, or stored.
    The proposed action is in accordance with the licensee's 
application for exemption dated December 20, 1996, as supplemented 
March 5, 1997, and March 19, 1997.

The Need for the Proposed Action

    Power reactor license applicants are evaluated for the safe 
handling, use, and storage of special nuclear materials. The proposed 
exemption from criticality accident requirements is based on the 
original design for radiation monitoring at Indian Point Unit 3. An 
exemption from the requirements of 10 CFR 70.24(a), ``Criticality 
Accident Requirements,'' was granted in the Special Nuclear Material 
(SNM) licenses for IP3 as part of the 10 CFR Part 70 license; however, 
with the issuance of the Part 50 license this exemption expired because 
it was not specifically addressed in the Part 50 license. The proposed 
exemption is needed for IP3 to continue to operate in accordance with 
its license and Commission regulations.

Environmental Impacts of the Proposed Action

    The Commission has completed its evaluation of the proposed action 
and concludes that there will be no significant environmental impact if 
the exemption is granted. The potential environmental impact evaluated 
was the increase in radiation dose as a result of an inadvertent 
criticality.
    Inadvertent or accidental criticality during fuel handling will be 
prevented by Technical Specifications (i.e., requirements on minimum 
soluble boron concentration in the spent fuel pit), by procedure (i.e., 
compliance with the procedures for fuel handling), and by design (i.e., 
the geometric spacing of fuel assemblies in the new fuel storage 
facility and spent fuel storage pit).
    Inadvertent or accidental criticality in the reactor vessel is 
prevented through compliance with the facility Technical 
Specifications, including reactivity requirements (e.g., shutdown 
margin limits and control rod movement limits), instrumentation 
requirements (e.g., power and radiation monitors), and control on 
refueling operations (e.g., refueling boron concentration and source 
range monitor requirements).
    Adherence to procedures precludes inadvertent criticality; however, 
the licensee is pursuing a defense in-depth approach. During fuel 
handling, the licensee has committed to have in operation in the IP3 
Fuel Storage Building at least one detector meeting the requirements of 
Sections 5.6 and 5.7 of ANSI/ANS 8.3 (1986), ``American National 
Standard Criticality Alarm System.'' The detection and sensitivity 
requirements of ANSI/ANS 8.3 are as rigorous as those of 10 CFR 
70.24(a)(1). Upon detection, this detector shall automatically cause an 
immediate alarm audible in all areas from which evacuation is necessary 
to minimize exposure. The licensee maintains emergency procedures and 
trains radiation workers on the proper actions should such an alarm 
occur.
    Because inadvertent criticality is precluded by both design and 
procedure, because adequate radiation monitoring is present, and 
because the licensee maintains emergency procedures for the areas in 
which fuel is handled, the staff has concluded that there is adequate 
assurance that an inadvertent criticality and the attendant

[[Page 14706]]

increase radiation doses will not result from granting this exemption. 
No changes are being made in the types or amounts of any radiological 
effluents that may be released offsite. There is no significant 
increase in the allowable individual or cumulative occupational 
radiation exposure. Accordingly, the Commission concludes that there 
are no significant radiological environmental impacts associated with 
the proposed action.
    With regard to potential nonradiological impacts, the proposed 
exemption involves systems located within the restricted area as 
defined in 10 CFR Part 20. It does not affect nonradiological plant 
effluents and has no other environmental impact. Accordingly, the 
Commission concludes that there are no significant nonradiological 
environmental impacts associated with the proposed action.

Alternatives to the Proposed Action

    Since the Commission has concluded that there is no measurable 
environmental impact associated with the proposed action, any 
alternatives with equal or greater environmental impact need not be 
evaluated. The principal alternative would be to deny the requested 
exemption. The environmental impacts of the proposed action and the 
alternative action are similar.

Alternative Use of Resources

    This action does not involve the use of any resources not 
previously considered in the Final Environmental Statement related to 
the operation of Indian Point Unit 3 dated December 1975.

Agencies and Persons Consulted

    In accordance with its stated policy, on March 12, 1997, the staff 
consulted with the New York State Official, Mr. Jack Spath of the New 
York State Energy Research and Development Authority, regarding the 
environmental impact of the proposed action. The State official had no 
comments.

Finding of No Significant Impact

    Based upon the environmental assessment, the Commission concludes 
that the proposed action will not have a significant effect on the 
quality of the human environment. Accordingly, the Commission has 
determined not to prepare an environmental impact statement for the 
proposed action.
    For further details with respect to the proposed action, see the 
licensee's letter dated December 20, 1996, as supplemented March 5, 
1997, and March 19, 1997, which are available for public inspection at 
the Commission's Public Document Room, The Gelman Building, 2120 L 
Street, NW., Washington, DC and at the local public document room 
located at White Plains Public Library, 100 Martine Avenue, White 
Plains, New York.

    Dated at Rockville, Maryland, this 25th day of March 1997.

    For the Nuclear Regulatory Commission.
George F. Wunder,
Project Manager, Project Directorate I-1, Division of Reactor 
Projects--I/II, Office of Nuclear Reactor Regulation.
[FR Doc. 97-7913 Filed 3-26-97; 9:49 am]
BILLING CODE 7590-01-P