[Federal Register: July 22, 1998 (Volume 63, Number 140)]
[Notices]               
[Page 39295-39296]
From the Federal Register Online via GPO Access [wais.access.gpo.gov]
[DOCID:fr22jy98-76]

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NUCLEAR REGULATORY COMMISSION

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

 
In the Matter of Virginia Electric and Power Company; Surry Power 
Station, Units 1 and 2; 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 
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

    Title 10 of the Code of Federal Regulations (10 CFR) Section 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

    On August 21, 1997, the NRC granted an exemption from the 
requirements of 10 CFR 70.24 reflecting the licensee's use of fuel 
enriched to 4.1 weight percent U235. By letter dated January 14, 1998, 
VEPCO requested a revised exemption from 10 CFR 70.24(a) based on the 
use of fuel enriched to 4.3 weight percent U235. 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 Power 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

[[Page 39296]]

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 as revised 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 
revised 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 revised exemption will have no significant impact on 
the quality of the human environment (63 FR 38196).
    This revised exemption is effective upon issuance.

    Dated at Rockville, Maryland this 15th day of July 1998.

    For the Nuclear Regulatory Commission.
Samuel J. Collins,
Director, Office of Nuclear Reactor Regulation.
[FR Doc. 98-19539 Filed 7-21-98; 8:45 am]
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