[Federal Register Volume 62, Number 166 (Wednesday, August 27, 1997)]
[Notices]
[Page 45452]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 97-22779]



[[Page 45452]]

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NUCLEAR REGULATORY COMMISSION

[Docket Nos. 50-280 and 50-281]


Virginia Electric and Power Company Surry Nuclear Power Station; 
Exemption

I

    The Virginia Electric and Power Company (VEPCO, the licensee) is 
the holder of Facility Operating License No. DPR-32 and Facility 
Operating License No. DPR-37, which authorize operation of the Surry 
Nuclear Power Station, Units 1 and 2. The licenses provide that the 
licensee is subject to all rules, regulations, and orders of the U.S. 
Nuclear Regulatory Commission (NRC or the Commission) now or hereafter 
in effect.
    The facility consists of two pressurized-water reactors at the 
licensee's site located in Surry County, Virginia.

II

    The Code of Federal Regulations at 10 CFR 70.24, ``Criticality 
Accident Requirements,'' requires that each licensee authorized to 
possess special nuclear material shall maintain a criticality accident 
monitoring system in each area in which such material is handled, used, 
or stored. Sections 70.24 (a)(1) and (a)(2) specify detection and 
sensitivity requirements that these monitors must meet. Section 
70.24(a)(1) also specifies that all areas subject to criticality 
accident monitoring must be covered by two detectors. Section 
70.24(a)(3) requires licensees to maintain emergency procedures for 
each area in which this licensed special nuclear material is handled, 
used, or stored, and provides (1) that the procedures ensure that all 
personnel withdraw to an area of safety upon the sounding of a 
criticality accident monitor alarm, (2) that the procedures must 
include drills to familiarize personnel with the evacuation plan, and 
(3) that the procedures designate responsible individuals for 
determining the cause of the alarm and placement of radiation survey 
instruments in accessible locations for use in such an emergency. 
Section 70.24(b)(1) requires licensees to have a means by which to 
quickly identify personnel who have received a dose of 10 rads or more. 
Section 70.24(b)(2) requires licensees to maintain personnel 
decontamination facilities, to maintain arrangements for a physician 
and other medical personnel qualified to handle radiation emergencies, 
and to maintain arrangements for the transportation of contaminated 
individuals to treatment facilities outside the site boundary. Section 
70.24(c) exempts Part 50 licensees from the requirements of 10 CFR 
70.24(c) for special nuclear material used or to be used in the 
reactor. Subsection 70.24(d) states that any licensee who believes that 
there is good cause why he should be granted an exemption from all or 
part of 10 CFR 70.24 may apply to the Commission for such an exemption 
and shall specify the reasons for the relief requested.

III

    By letter dated January 27, 1997, as supplemented March 24, 1997, 
VEPCO requested an exemption from 10 CFR 70.24(a). The Commission has 
reviewed the licensee's submittal and has determined that inadvertent 
criticality is not likely to occur in special nuclear materials 
handling or storage areas at Surry Nuclear Station, Units 1 and 2. The 
quantity of special nuclear material other than fuel that is stored on 
site is small enough to preclude achieving a critical mass.
    The purpose of the criticality monitors required by 10 CFR 70.24 is 
to ensure that if a criticality were to occur during the handling of 
special nuclear material, personnel would be alerted to that fact and 
would take appropriate action. Although the staff has determined that 
such an accident is not likely to occur, the licensee has radiation 
monitors, as required by General Design Criteria 63, in fuel storage 
and handling areas. These monitors will alert personnel to excessive 
radiation levels and allow them to initiate appropriate safety actions. 
The low probability of an inadvertent criticality together with the 
licensee's adherence to General Design Criterion 63 constitute good 
cause for granting an exemption to the requirements of 10 CFR 70.24(a).

IV

    The Commission has determined that, pursuant to 10 CFR 70.14, this 
exemption is authorized by law, will not endanger life or property or 
the common defense and security, and is otherwise in the public 
interest; therefore, the Commission hereby grants the following 
exemption:
    The Virginia Electric and Power Company is exempt from the 
requirements of 10 CFR 70.24(a) for the Surry Nuclear Power Station, 
Unit 1 and Unit 2.
    Pursuant to 10 CFR 51.32, the Commission has determined that the 
granting of this exemption will have no significant impact on the 
quality of the human environment (62 FR 44495).

This exemption is effective upon issuance.

    Dated at Rockville, Maryland, this 21st day of August 1997.

    For the Nuclear Regulatory Commission.
Samuel J. Collins,
Director, Office of Nuclear Reactor Regulation.
[FR Doc. 97-22779 Filed 8-26-97; 8:45 am]
BILLING CODE 7590-01-P