94-31197. Carolina Power & Light Company; Brunswick Steam Electric Plant, Units 1 and 2, et al.; Environmental Assessment and Finding of No Significant Impact  

  • [Federal Register Volume 59, Number 243 (Tuesday, December 20, 1994)]
    [Unknown Section]
    [Page 0]
    From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
    [FR Doc No: 94-31197]
    
    
    [[Page Unknown]]
    
    [Federal Register: December 20, 1994]
    
    
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    NUCLEAR REGULATORY COMMISSION
    [Docket Nos. 50-325, 50-324, 50-400 and 50-261]
    
     
    
    Carolina Power & Light Company; Brunswick Steam Electric Plant, 
    Units 1 and 2, et al.; 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 its 
    regulations to Facility Operating License Nos. DPR-71, DPR-62, DPR-23, 
    NPF-63, issued to the Carolina Power & Light Company (the licensee) for 
    the operation of the Brunswick Steam Electric Plant, Units 1 and 2 
    (Brunswick), H.B. Robinson Steam Electric Plant, Unit No. 2 (Robinson), 
    and Shearon Harris Nuclear Power Plant, Unit 1 (Harris).
        The facilities consist of two boiling water reactors at the 
    Brunswick site in Brunswick County, North Carolina; a pressurized water 
    reactor at the Robinson site in Darlington County, South Carolina; and 
    a pressurized water reactor in Wake County and Chatham County, North 
    Carolina.
    
    Environmental Assessment
    
    Identification of the Proposed Action
    
        The exemption would allow implementation of a hand geometry 
    biometric system of site access control so that photograph 
    identification badges can be taken offsite. The proposed action is in 
    accordance with the licensee's application for exemption dated July 29, 
    1994, as supplemented December 5, 1994.
    
    The Need for the Proposed Action
    
        The proposed action would give an exemption from certain 
    requirements of 10 CFR 73.55, ``Requirements for physical protection of 
    licensed activities in nuclear power reactors against radiological 
    sabotage.''
        Pursuant to 10 CFR 73.55(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 the ``licensee shall control all points of personnel and 
    vehicle access into a protected area.'' Title 10 of the Code of Federal 
    Regulations, paragraph 73.55(d)(5), specifies that ``A numbered picture 
    badge identification system shall be used for all individuals who are 
    authorized access to protected areas without escort.'' Paragraph 
    73.55(d)(5) also states that an individual not employed by the licensee 
    (i.e., a contractor) 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 protected areas of the Brunswick 
    and Robinson units is controlled through the use of a photograph on a 
    combination badge and keycard (hereafter, these are referred to as the 
    badge). At the Harris unit unescorted access into protected areas is 
    controlled through the use of a photograph on a badge and a separate 
    keycard. The security officers at each 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 
    each entrance/exit location and are returned upon exit. The badges are 
    stored and are retrievable at each entrance/exit location. In 
    accordance with 10 CFR 73.55(d)(5), contract individuals are not 
    allowed to take badges offsite. In accordance with the plants' physical 
    security plans, neither licensee employees nor contractors are allowed 
    to take badges offsite.
        The licensee proposes to implement an alternative unescorted access 
    control system which would eliminate the need to issue and retrieve 
    badges at each entrance/exit location and would allow all individuals 
    with unescorted access to keep their badges with them when departing 
    the site. An exemption from 10 CFR 73.55(d)(5) is required to permit 
    contractors to take their badges offsite instead of returning them when 
    exiting the site.
        Under the proposed system, individuals who are 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 badge 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 the licensee's experience with the 
    current photo identification system, the licensee demonstrated that the 
    proposed hand geometry system would provide enhanced site 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 offsite, would not enable 
    an unauthorized entry into the protected area. 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 Plans for the Brunswick, Robinson, 
    and Harris sites 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 offsite.
        The access will continue to be under the observation of security 
    personnel. 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.
        With regard to potential nonradiological impacts, the proposed 
    change does not affect nonradiological plant effluents and has no other 
    environmental impact. Therefore, the Commission concludes that there 
    are no significant nonradiological environmental impacts associated 
    with the proposed action.
    
    Environmental Impacts of the Proposed Action
    
        The Commission has completed its evaluation of the proposed action 
    and concludes that this proposed action would result in no significant 
    radiological environmental impact.
        The change will not increase the probability or consequences of 
    accidents, no changes are being made in the types of any effluents that 
    may be released offsite, and there is no significant increase in the 
    allowable individual or cumulative occupational radiation explosure. 
    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 does involve 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. The principal alternative to the action would be to deny the 
    request. Such action would have no effect on the environmental impact, 
    would not enhance the protection of the environment, and would result 
    in an unjustified loss of cost savings to the licensee.
    
    Alternative Use of Resources
    
        This action does not involve the use of any resources not 
    previously considered in the Final Environmental Statements for the 
    Brunswick, Robinson, and Harris units.
    
    Agencies and Persons Consulted
    
        The NRC staff consulted with the North and South Carolina State 
    officials regarding the environmental impact of the proposed action. 
    The State officials had no commend.
    
    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 letters dated July 29, 1994, as supplemented December 5, 
    1994, which are available for public inspection at the Commission's 
    Public Document Room, The Gelman Building, 2120 L Street, NW., 
    Washington, DC 20555, and at the local public document rooms for 
    Brunswick Steam Electric Plant, Units 1 and 2, at the University of 
    North Carolina at Wilmington, William Madison Randall Library, 601 S. 
    College Road, Wilmington, North Carolina 28403-3297; for the H.B. 
    Robinson Steam Electric Plant, Unit No. 2, at Hartsville Memorial 
    Library, 147 West College, Hartsville, South Carolina 29550; and for 
    the Shearon Harris Nuclear Power Plant, Unit 1, at the Cameron Village 
    Regional Library, 1930 Clark Avenue, Raleigh, North Carolina.
    
        Dated at Rockville, Maryland, this 14th day of December.
    
        For the Nuclear Regulatory Commission.
    Michael L. Boyle,
    Acting Director, Project Directorate II-1, Division of Reactor 
    Projects--I/II, Office of Nuclear Reactor Regulation.
    [FR Doc. 94-31197 Filed 12-19-94; 8:45 am]
    BILLING CODE 7590-01-M
    
    
    

Document Information

Published:
12/20/1994
Department:
Nuclear Regulatory Commission
Entry Type:
Uncategorized Document
Document Number:
94-31197
Pages:
0-0 (1 pages)
Docket Numbers:
Federal Register: December 20, 1994, Docket Nos. 50-325, 50-324, 50-400 and 50-261