[Federal Register Volume 60, Number 240 (Thursday, December 14, 1995)]
[Notices]
[Pages 64183-64185]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 95-30456]



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NUCLEAR REGULATORY COMMISSION
[Docket Nos. 50-315 and 50-316]


Indiana Michigan Power Company Donald C. Cook Nuclear Plant, Unit 
Nos. 1 and 2; Environmental Assessment and Finding of No Significant 
Impact

    The U.S. Nuclear Regulatory Commission (the Commission) is 
considering issuance of an exemption from certain requirements of 10 
CFR 73.55 for Facility Operating License Nos. DPR-58 and DPR-74, issued 
to Indiana Michigan Power Company, (the licensee), for operation of the 
D.C. Cook Nuclear Plant, Units 1 and 2, located in Berrien County, 
Michigan.

Environmental Assessment

Identification of the Proposed Action

    The proposed action would exempt the licensee from certain 
requirements 

[[Page 64184]]
of 10 CFR 73.55, ``Requirements for physical protection of licensed 
activities in nuclear power reactors against radiological sabotage.'' 
The proposed action would allow implementation of a hand geometry 
biometric system of site access control such that photograph 
identification badges can be taken off site.
    This environmental assessment has been prepared to address 
potential environmental issues related to the licensee's application of 
August 17, 1995.

The Need for the Proposed Action

    Pursuant to 10 CFR 73.55, paragraph (a), the licensee shall 
establish and maintain an onsite physical protection system and 
security organization.
    Paragraph (1) of 10 CFR 73.55(d), ``Access Requirements,'' 
specifies that ``licensee shall control all points of personnel and 
vehicle access into a protected area.'' It is specified in 10 CFR 
73.55(d)(5) that ``A numbered picture badge identification system shall 
be used of all individuals who are authorized access to protected areas 
without escort.'' It also states that an individual not employed by the 
licensee (i.e., contractors) may be authorized access to protected 
areas without escort provided the individual ``receives a picture badge 
upon entrance into the protected area which must be returned upon exit 
from the protected area. * * *''
    Currently, unescorted access into the protected areas of the Cook 
Nuclear Plant is controlled through the use of a photograph on a 
combination badge and keycard. (Hereafter, these are referred to as 
badges). The security officers at the entrance station use the 
photograph on the badge to visually identify the individual requesting 
access. The badges for both licensee employees and contractor personnel 
who have been granted unescorted access are issued upon entrance at the 
entrance/exit location and are returned upon exit. The badges are 
stored and retrievable at the entrance/exit location. In accordance 
with 10 CFR 73.55(d)(5), contractor individuals are not allowed to take 
badges off site. In accordance with the plant's physical security 
plans, neither licensee employees nor contractors are allowed to take 
badges off site.
    The licensee proposes to implement an alternative unescorted access 
control system which would eliminate the need to issue and retrieve 
badges at the entrance/exit location and would allow all individuals 
with unescorted access to keep their badges with them when departing 
the site.
    An exemption from certain requirements of 10 CFR 73.55(d)(5) is 
required to permit contractors to take their badges off site instead of 
returning them when exiting the site.

Environmental Impacts of the Proposed Action

    The Commission has completed its evaluation of the proposed action 
and concludes that the proposed exemption would not increase the 
probability or consequences of accidents previously analyzed and the 
proposed exemption would not affect facility radiation levels or 
facility radiological effluents. Under the proposed system, each 
individual who is authorized for unescorted entry into protected areas 
would have the physical characteristics of their hand (hand geometry) 
registered with their badge number in the access control system. When 
an individual enters the badge into the card reader and places the hand 
on the measuring surface, the system would record the individual's hand 
image. The unique characteristics of the extracted hand image would be 
compared with the previously stored template to verify authorization 
for entry. Individuals, including licensee employees and contractors, 
would be allowed to keep their badges with them when they depart the 
site.
    Based on a Sandia report entitled ``A Performance Evaluation of 
Biometric Identification Devices'' (SAND91--0276, UC--906 Unlimited 
Release, printed June 1991), and on its experience with the current 
photo-identification system, the licensee stated that the false 
acceptance rate of the proposed hand geometry system is comparable to 
that of the current system. The licensee stated that the use of the 
badges with the hand geometry system would increase the overall level 
of access control. Since both the badge and hand geometry would be 
necessary for access into the protected area, the proposed system would 
provide for a positive verification process. Potential loss of a badge 
by an individual, as a result of taking the badge off site, would not 
enable an unauthorized entry into protected areas. The licensee will 
implement a process for testing the proposed system to ensure continued 
overall level of performance equivalent to that specified in the 
regulation. The Physical Security Plan for D.C. Cook will be revised to 
include implementation and testing of the hand geometry access control 
system and to allow licensee employees and contractors to take their 
badges off site.
    All other access processes, including search function capability 
and access revocation, will remain the same. A security officer 
responsible for access control will continue to be positioned within a 
bullet-resistant structure. A numbered picture badge identification 
system will continue to be used for all individuals who are authorized 
access to protected areas without escorts. Badges will continue to be 
displayed by all individuals while inside the protected area. The 
proposed system is only for individuals with authorized unescorted 
access and will not be used for individuals requiring escorts.
    The change will not increase the probability or consequences of 
accidents, no changes are being made in the types or amounts of any 
effluents that may be released off site, and 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 
action involves features located entirely 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 there is no measurable 
environmental impact associated with the proposed action, any 
alternatives with equal or greater environmental impact need not be 
evaluated. As an alternative to the proposed action, the NRC staff 
considered denial of the proposed action. Denial of the application 
would result in no change in current environmental impacts. 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 for D.C. 
Cook, Units 1 and 2, dated August 1973.

Agencies and Persons Consulted

    In accordance with its stated policy, on November 20, 1995, the NRC 
staff consulted with the Michigan State official, Dennis Hahn, of the 
Michigan Department of Public Health, Nuclear Facilities and 
Environmental Monitoring, regarding the environmental impact of the 
proposed 

[[Page 64185]]
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 August 17, 1995, which is 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 the Maud Preston Palenske Memorial Library, 
500 Market Street, St. Joseph, Michigan 49085.

    Dated at Rockville, Maryland, this 1st day of December 1995.

    For the Nuclear Regulatory Commission.
John B. Hickman,
Project Manager, Project Directorate III-1, Division of Reactor 
Projects--III/IV, Office of Nuclear Reactor Regulation.
[FR Doc. 95-30456 Filed 12-13-95; 8:45 am]
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