94-20261. Virginia Electric and Power Company (Surry Power Station Units 1 and 2) (North Anna Power Station Units 1 and 2); Exemption  

  • [Federal Register Volume 59, Number 159 (Thursday, August 18, 1994)]
    [Unknown Section]
    [Page 0]
    From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
    [FR Doc No: 94-20261]
    
    
    [[Page Unknown]]
    
    [Federal Register: August 18, 1994]
    
    
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    NUCLEAR REGULATORY COMMISSION
    [Docket Nos. 50-280, 50-281, 50-338, 50-339]
    
     
    
    Virginia Electric and Power Company (Surry Power Station Units 1 
    and 2) (North Anna Power Station Units 1 and 2); Exemption
    
    I
    
        Virginia Electric and Power Company (the licensee) is the holder of 
    Facility Operating License Nos. DPR-32 and DPR-37, which authorize 
    operation of the Surry Power Station Units 1 and 2, and NPF-4 and NPF-
    7, which authorize operation of the North Anna Power Station Units 1 
    and 2. The licenses provide, among other things, that the licensee is 
    subject to all rules, regulations, and orders of the Commission now or 
    hereafter in effect.
        The facilities consist of two pressurized water reactors at each of 
    the licensee's two sites, Surry Power Station Units 1 and 2, located in 
    Surry County, Virginia, and North Anna Power Station Units 1 and 2, 
    located in Louisa County, Virginia.
    
    II
    
        Title 10 CFR 73.55, ``Requirements for physical protection of 
    licensed activities in nuclear power reactors against radiological 
    sabotage,'' paragraph (a), in part, states that ``The licensee shall 
    establish and maintain an onsite physical protection system and 
    security organization which will have as its objective to provide high 
    assurance that activities involving special nuclear material are not 
    inimical to the common defense and security and do not constitute an 
    unreasonable risk to the public health and safety.''
        10 CFR 73.55(d), ``Access Requirements,'' paragraph (1), specifies 
    that ``The licensee shall control all points of personnel and vehicle 
    access into a protected area.'' 10 CFR 73.55(d)(5) requires that ``A 
    numbered picture badge identification system shall be used for all 
    individuals who are authorized access to protected areas without 
    escort.'' 10 CFR 73.55(d)(5) 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 * * *''
        The licensee proposed 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 badge with them when departing the 
    site.
        An exemption from 10 CFR 73.55(d)(5) is required to allow 
    contractors who have unescorted access to take their badges offsite 
    instead of returning them when exiting the site. By letter dated May 
    27, 1994, the licensee requested an exemption from certain requirements 
    of 10 CFR 73.55(d)(5) for this purpose.
    
    III
    
        Pursuant to 10 CFR 73.5, ``Specific exemptions,'' the Commission 
    may, upon application of any interested person or upon its own 
    initiative, grant such exemptions from the requirements of the 
    regulations in this part as it determines are authorized by law and 
    will not endanger life or property or the common defense and security, 
    and are otherwise in the public interest. Pursuant to 10 CFR 73.55, the 
    Commission may authorize a licensee to provide alternative measures for 
    protection against radiological sabotage provided the licensee 
    demonstrates that the alternative measures have ``the same high 
    assurance objective'' and meet ``the general performance requirements'' 
    of the regulation, and ``the overall level of system performance 
    provides protection against radiological sabotage equivalent'' to that 
    which would be provided by the regulation.
        Currently, employee and contractor identification badges, coupled 
    with their associated access control cards, are issued and retrieved on 
    the occasion of each entry to and exit from the protected areas of the 
    Surry and North Anna sites. Station security personnel are required to 
    maintain control of the badges while the individuals are offsite. This 
    practice has been in effect at the Surry and North Anna Power Stations 
    since each operating license was issued. Security personnel retain each 
    identification badge, as well as the associated access control card, 
    when not in use by the authorized individual, within appropriately 
    designed storage receptacles inside a bullet-resistant enclosure. An 
    individual who meets the access authorization requirements is issued an 
    individual picture identification card and an individual access control 
    card which allows entry into preauthorized areas of the station. While 
    entering the plant in the present configuration, an authorized 
    individual is ``screened'' by the required detection equipment and by 
    the issuing security officer. Having received the badge, the individual 
    proceeds to the access portal, inserts the access control card into the 
    card reader, enters a personal identification number (PIN), and passes 
    through the turnstile which unlocks if the preset criteria are met. 
    Once inside the station, the individual's PIN is not required in order 
    to further utilize the access authorization card.
        This present procedure is labor intensive since security personnel 
    are required to verify badge issuance, ensure badge retrieval, and 
    maintain the badges in orderly storage until the next entry into the 
    protected area. The regulations permit employees to remove their badges 
    from the site, but 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, all individuals authorized to gain 
    unescorted access will have the physical characteristics of their hand 
    (hand geometry) recorded with their badge number. Since the hand 
    geometry is unique to each individual and its application in the entry 
    screening function would preclude unauthorized use of a badge, the 
    requested exemption would allow employees and contractors to keep their 
    badges at the time of exiting the protected area. The process of 
    verifying badge issuance, ensuring badge retrieval, and maintaining 
    badges could be eliminated while the balance of the access procedure 
    would remain intact. Firearm, explosive, and metal detection equipment 
    and provisions for conducting searches will remain as well. The 
    security officer responsible for the last access control function 
    (controlling admission to the protected area) will also remain isolated 
    within a bullet-resistant structure in order to assure his or her 
    ability to respond or to summon assistance.
        Use of a hand geometry biometrics system exceeds the present 
    verification methodology's capability to discern an individual's 
    identity. Unlike the photograph identification badge, hand geometry is 
    nontransferable. During the initial access authorization or 
    registration process, hand measurements are recorded and the tamplate 
    is stored for subsequent use in the identity verification process 
    required for entry into the protected area. Authorized individuals 
    insert their access authorization card into the card reader and the 
    biometrics system records an image of the hand geometry. The unique 
    features of the newly recorded image are then compared to the template 
    previously stored in the database. Access is ultimately granted based 
    on the degree to which the characteristics of the image match those of 
    the ``signature'' template.
        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 protected areas.
        The access process will continue to be under the observation of 
    security personnel. They system of identification badges coupled with 
    their associated access control cards 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 the individuals 
    while inside the protected area. Addition of a hand geometry biometrics 
    system will provide a significant contribution to effective 
    implementation of the security plan at each site.
    
    IV
    
        For the foregoing reasons, pursuant to 10 CFR 73.55, the NRC staff 
    has determined that the proposed alternative measures for protection 
    against radiological sabotage meet ``the same high assurance 
    objective,'' and ``the general performance requirements'' of the 
    regulation and that ``the overall level of system performance provides 
    protection against radiological sabotage equivalent'' to that which 
    would be provided by the regulation.
        Accordingly, the Commission has determined that, pursuant to 10 CFR 
    73.5, an exemption is authorized by law, will not endanger life or 
    property or common defense and security, and is otherwise in the public 
    interest. Therefore, the Commission hereby grants Virginia Electric and 
    Power Company an exemption from those requirements of 10 CFR 
    73.55(d)(5) relating to the returning of picture badges upon exit from 
    the protected area such that individuals not employed by the licensee, 
    i.e., contractors, who are authorized unescorted access into the 
    protected area, can take their badges offsite.
        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 (59 FR 40927).
        This exemption is effective upon issuance.
    
        Dated at Rockville, Maryland, this 11th day of August 1994.
    
        For the Nuclear Regulatory Commission.
    Steven A. Varga,
    Director, Division of Reactor Projects--I/II, Office of Nuclear Reactor 
    Regulation.
    [FR Doc. 94-20261 Filed 8-17-94; 8:45 am]
    BILLING CODE 7590-01-M
    
    
    

Document Information

Published:
08/18/1994
Department:
Nuclear Regulatory Commission
Entry Type:
Uncategorized Document
Document Number:
94-20261
Pages:
0-0 (1 pages)
Docket Numbers:
Federal Register: August 18, 1994, Docket Nos. 50-280, 50-281, 50-338, 50-339