97-19932. Public Service Electric & Gas Co., et al; Environmental Assessment and Finding of No Significant Impact  

  • [Federal Register Volume 62, Number 145 (Tuesday, July 29, 1997)]
    [Notices]
    [Pages 40551-40553]
    From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
    [FR Doc No: 97-19932]
    
    
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    NUCLEAR REGULATORY COMMISSION
    
    [Docket Nos. 50-272 and 50-311, etc.]
    
    
    Public Service Electric & Gas Co., et al; Environmental 
    Assessment and Finding of No Significant Impact
    
        In the matter of: Public Service Electric & Gas Company, 
    Philadelphia Electric Company, Delmarva Power and Light Company, 
    Atlantic City Electric Company, Salem Nuclear Generating Station, 
    Unit Nos. 1 and 2, Docket Nos. 50-272 and 50-311; and Public Service 
    Electric & Gas Company, Atlantic City Electric Company, Hope Creek 
    Generating Station; Docket No. 50-354; 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 for Facility Operating License Nos. DPR-70, DPR-75, and 
    NPF-57, issued to Public Service Electric & Gas Company (PSE&G, the 
    licensee), for operation of the Salem Nuclear Generating Station, Units 
    1 and 2, and Hope Creek Generating Station (Salem/Hope Creek), 
    respectively.
        The facilities consist of two pressurized water reactors, Salem 
    Units 1 and 2, and a boiling water reactor, Hope Creek, at the 
    licensee's site located in Salem County, New Jersey.
    
    [[Page 40552]]
    
    Environmental Assessment
    
    Identification of Proposed Action
    
        The proposed action would allow implementation of a hand geometry 
    biometric system of site access control such that photograph 
    identification badges can be taken offsite.
        The proposed action is in accordance with the licensee's 
    application dated January 17, 1997, for exemption from certain 
    requirements of 10 CFR 73.55, ``Requirements for physical protection of 
    licensed activities in nuclear power reactors against radiological 
    sabotage.''
    
    The Need for the Proposed Action
    
        Pursuant to 10 CFR 73.55, paragraph (a), ``General performance 
    objective and requirements,'' 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 for 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 protected areas of the Salem/Hope 
    Creek site is controlled through the use of a photograph on a 
    combination badge and keycard. (Hereafter, these are referred to as a 
    ``badge''). 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 are retrievable at the entrance/exit location. In accordance 
    with 10 CFR 73.55(d)(5), contractor 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 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 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
    
        Under the proposed alternative unescorted access control 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 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 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 offsite, 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 the Salem/Hope Creek site 
    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 process 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.
        The change will not increase the probability or consequences of 
    accidents, no changes are being made in the types of any effluent 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 involves features located entirely within the restricted area as 
    defined in 10 CFR Part 20. It does not affect nonradiological plant 
    effluent 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 not change any 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 related to 
    the operation of Hope Creek Generating Station,'' NUREG-1074, dated 
    December 1984 or ``Final Environmental Statement related to the 
    operation of Salem Nuclear Generating Station Units 1 and 2,'' dated 
    April 1973.
    
    Agencies and Persons Consulted
    
        In accordance with its stated policy, on February 19, 1997, the 
    staff consulted with the New Jersey State Official, Mr. Dennis Zannoni, 
    of the New Jersey Department of Environmental Protection and Energy, 
    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
    
    [[Page 40553]]
    
    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 January 17, 1997, 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 rooms located at the Salem Free Public Library, 112 West 
    Broadway, Salem, New Jersey, for Salem and at the Pennsville Public 
    Library, 190 S. Broadway, Pennsville, New Jersey, for Hope Creek.
    
        Dated at Rockville, Maryland, this 23rd day of July 1997.
    
        For the Nuclear Regulatory Commission.
    John F. Stolz,
    Director Project Directorate, I-2, Division of Reactor Projects--I/II, 
    Office of Nuclear Reactor Regulation.
    [FR Doc. 97-19932 Filed 7-28-97; 8:45 am]
    BILLING CODE 7590-01-P
    
    
    

Document Information

Published:
07/29/1997
Department:
Nuclear Regulatory Commission
Entry Type:
Notice
Document Number:
97-19932
Pages:
40551-40553 (3 pages)
Docket Numbers:
Docket Nos. 50-272 and 50-311, etc.
PDF File:
97-19932.pdf