95-28608. Consolidated Edison Company of New York (Indian Point Nuclear Generating Unit Nos. 1 and 2); Exemption  

  • [Federal Register Volume 60, Number 226 (Friday, November 24, 1995)]
    [Notices]
    [Pages 58107-58108]
    From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
    [FR Doc No: 95-28608]
    
    
    
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    NUCLEAR REGULATORY COMMISSION
    [Docket Nos. 50-003 and 50-247]
    
    
    Consolidated Edison Company of New York (Indian Point Nuclear 
    Generating Unit Nos. 1 and 2); Exemption
    
    I
    
        Consolidated Edison Company of New York, Inc., (the licensee) is 
    the holder of Facility Operating License No. DPR-26 which authorizes 
    the operation of Indian Point Nuclear Generating Unit No. 2 and 
    Provisional Operating License (POL) No. DPR-5 which authorizes the 
    operation of Indian Point Nuclear Generating Unit No. 1. The operating 
    authority of POL DPR-5 for Indian Point Nuclear Generating Unit No. 1 
    was revoked by Commission Order dated June 19, 1980. The operating 
    licenses provide, among other things, that the licensee is subject to 
    all rules, regulations, and orders of the Commission now and hereafter 
    in effect.
        The facility comprises two pressurized-water reactors at the 
    licensee's site in Westchester County, New York.
    
    II
    
        The Code of Federal Regulations at 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.''
        Paragraph (1), ``Access Requirements,'' of 10 CFR 73.55(d), 
    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 the entrance into the protected area 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 August 
    10, 1995, 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/keycards, 
    are issued and retrieved on the occasion of each entry to and exit from 
    the protected areas of the Indian Point Nuclear Generating Unit Nos. 1 
    and 2 site. Station security personnel are required to maintain control 
    of the badges/keycards while the individuals are offsite. This practice 
    has been in effect at Indian Point Nuclear Generating Unit Nos. 1 and 2 
    since the operating licenses were issued. Security personnel retain 
    each identification badge/keycard when not in use by the authorized 
    individual, within appropriately designed storage receptacles. An 
    individual who meets the access authorization requirements is issued an 
    individual picture badge/keycard which allows entry into preauthorized 
    areas of the station. While entering the plant in the present 
    
    [[Page 58108]]
    configuration, an authorized individual is ``screened'' by the required 
    detection equipment and by the issuing security officer. Having 
    received the picture badge/keycard, the individual proceeds to the 
    access portal, inserts the picture badge/keycard into the card reader, 
    and passes through the turnstile which unlocks if the preset criteria 
    are met.
        This present procedure is labor intensive since security personnel 
    are required to verify badges/keycards issuance, ensure badges/keycards 
    retrieval, and maintain the badges/keycards in orderly storage until 
    the next entry into the protected area. The regulations permit 
    employees to remove their badges/keycards from the site, but an 
    exemption from 10 CFR 73.55(d)(5) is required to permit contractors to 
    take their badges/keycards 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/keycard. Since the hand 
    geometry is unique to each individual and its application in the entry 
    screening function would preclude unauthorized use of a badge/keycard, 
    the requested exemption would allow employees and contractors to keep 
    their badges/keycards at the time of exiting the protected area. The 
    process of verifying badge/keycard issuance, ensuring badge/keycard 
    retrieval, and maintaining badges/keycards 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/keycard, hand 
    geometry is nontransferable. During the initial access authorization or 
    registration process, hand measurements are recorded and the template 
    is stored for subsequent use in the identity verification process 
    required for entry into the protected area.
        Authorized individuals insert their picture badges/keycards 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 badges/keycards 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/keycard 
    by an individual, as a result of taking the badge/keycard offsite, 
    would not enable an unauthorized entry into protected areas.
        The access process will continue to be under the observation of 
    security personnel. The system of identification badges/keycards will 
    continue to be used for all individuals who are authorized access to 
    protected areas without escorts. Badges/keycards will continue to be 
    displayed by all 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 the 
    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 Consolidated Edison 
    Company of New York, Inc. an exemption from those requirements of 10 
    CFR 73.55(d)(5) relating to the returning of picture badges/keycards 
    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/keycards 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 (60 FR 56357). This exemption is 
    effective upon issuance.
    
        Dated at Rockville, Maryland, this 1st day of November 1995.
    
        For the Nuclear Regulatory Commission.
    Steven A. Varga,
    Director, Division of Reactor Projects--I/II, Office of Nuclear Reactor 
    Regulation.
    [FR Doc. 95-28608 Filed 11-22-95; 8:45 am]
    BILLING CODE 7590-01-P
    
    

Document Information

Published:
11/24/1995
Department:
Nuclear Regulatory Commission
Entry Type:
Notice
Document Number:
95-28608
Pages:
58107-58108 (2 pages)
Docket Numbers:
Docket Nos. 50-003 and 50-247
PDF File:
95-28608.pdf