95-27622. Consolidated Edison Company of New York, Inc., Indian Point Nuclear Generating Units No. 1 and 2; Environmental Assessment and Finding of No Significant Impact  

  • [Federal Register Volume 60, Number 216 (Wednesday, November 8, 1995)]
    [Notices]
    [Pages 56357-56359]
    From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
    [FR Doc No: 95-27622]
    
    
    
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    NUCLEAR REGULATORY COMMISSION
    
    [Docket Nos. 50-003 and 50-247]
    
    
    Consolidated Edison Company of New York, Inc., Indian Point 
    Nuclear Generating Units No. 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 its 
    regulations to Provisional Operating License (POL) No. DPR-5 and 
    Facility Operating License DPR-26, issued to Consolidated Edison 
    Company of New York, Inc. (the licensee), for operation of the Indian 
    Point Nuclear Generating Unit Nos. 1 and 2, located in Westchester 
    County, New York. The operating authority of POL DPR-5 for Indian Point 
    Nuclear Generating Unit No. 1 was revoked by Commission Order dated 
    June 19, 1980.
    
    Environmental Assessment
    
    Identification of the Proposed Action
    
        The proposed action is in accordance with the licensee's 
    application dated August 10, 1995, for exemption from 
    
    [[Page 56358]]
    certain requirements of 10 CFR 73.55, ``Requirements for physical 
    protection of licensed activities in nuclear power reactors against 
    radiological sabotage.'' The exemption would allow implementation of a 
    hand geometry biometric system for site access control such that 
    combined picture badges/keycards for certain non-employees can be taken 
    offsite.
    
    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.'' Paragraph (5) of 10 CFR 
    73.55(d) specifies that ``A numbered picture badge identification 
    system shall be used for all individuals who are authorized access to 
    protected areas without escort.'' Paragraph (5) of 10 CFR 73.55(d) 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, employee and contractor combined 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 while the individuals are offsite. This 
    practice has been in effect at the Indian Point site since the 
    operating license was issued. Security personnel retain each 
    identification badge/keycard, 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/keycard 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/keycard, the individual proceeds to the access portal, inserts 
    the badge/keycard into the card reader and passes through the turnstile 
    which unlocks if the badge/keycard is valid.
        This present procedure is labor intensive since security personnel 
    are required to verify badge/keycard issuance, ensure badge/keycard 
    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 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.
    
    Environmental Impacts of the Proposed Action
    
        The Commission has completed its evaluation of the licensee's 
    application. 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 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/keycard, 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/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 combined 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 badge/keycard 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/keycard 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 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.
        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 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 does involve features located entirely within the restricted 
    area as defined in 10 CFR Part 20. It does not effect 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 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 the 
    Indian Point Nuclear Generating Unit No. 2. 
    
    [[Page 56359]]
    
    
    Agencies and Persons Consulted
    
        In accordance with its stated policy, on September 26, 1995, the 
    staff consulted with the New York State official, Heidi Voelk of the 
    Energy Research and Development Authority, regarding the environmental 
    impact of the proposed 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 10, 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 White Plains Public Library, 100 Martine 
    Avenue, White Plains, NY 10610.
    
        Dated at Rockville, Maryland, this 31st day of October 1995.
    
        For the Nuclear Regulatory Commission.
    Ledyard B. Marsh,
    Director, Project Directorate I-1, Division of Reactor Projects--I/II, 
    Office of Nuclear Reactor Regulation.
    [FR Doc. 95-27622 Filed 11-7-95; 8:45 am]
    BILLING CODE 7590-01-P
    
    

Document Information

Published:
11/08/1995
Department:
Nuclear Regulatory Commission
Entry Type:
Notice
Document Number:
95-27622
Pages:
56357-56359 (3 pages)
Docket Numbers:
Docket Nos. 50-003 and 50-247
PDF File:
95-27622.pdf