95-7699. Arizona Public Service Company, et al., Palo Verde Nuclear Generating Station, Unit No. 1; Environmental Assessment and Finding of No Significant Impact  

  • [Federal Register Volume 60, Number 60 (Wednesday, March 29, 1995)]
    [Notices]
    [Pages 16180-16181]
    From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
    [FR Doc No: 95-7699]
    
    
    
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    NUCLEAR REGULATORY COMMISSION
    
    [Docket No. STN 50-528]
    
    
    Arizona Public Service Company, et al., Palo Verde Nuclear 
    Generating Station, Unit No. 1; 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 10 
    CFR Part 50, Appendix J, Paragraph III.D.1.(a), Type A Tests, to the 
    Arizona Public Service Company, et al. (APS or the licensee), for 
    operation of the Palo Verde Nuclear Generating Station, Unit No. 1, 
    located in Maricopa County, Arizona.
    
    Environmental Assessment
    
    Identification of the Proposed Action
    
        The proposed action would exempt the licensee from the requirements 
    of 10 CFR Part 50, Appendix J, Paragraph III.D.1.(a), to the extent 
    that a one-time schedular extension would permit rescheduling the third 
    containment integrated leak rate test (ILRT) in the first 10-year 
    service period from the fifth refueling outage (1R5) currently 
    scheduled for May 1995 to the sixth refueling outage (1R6) planned for 
    September 1996. The requested exemption would also allow the decoupling 
    of this third test from the endpoint of the first 10-year inservice 
    inspection (ISI) period.
        The proposed action is in accordance with the licensee's 
    application for exemption dated December 28, 1994.
    
    The Need for the Proposed Action
    
        The current containment integrated leakage rate test (ILRT) 
    requirements for Palo Verde Nuclear Generating Station, Unit 1, as set 
    forth in Appendix J, are that, after the preoperational leak rate test, 
    a set of three Type A tests must be performed at approximately equal 
    intervals during each 10-year period. Also, the third test of each set 
    must be conducted when the plant is shut down for the 10-year plant 
    inservice inspection. To date, for Palo Verde Nuclear Generating 
    Station, Unit 1, the preoperational and the first two periodic ILRTs 
    have been conducted. The most recent ILRT was conducted in February 
    1990, approximately 59 months ago. Thus, in accordance with Appendix J, 
    an ILRT would have to be conducted during the upcoming refueling outage 
    (1R5, scheduled for May 1995).
        The licensee has requested a schedular exemption from Appendix J. 
    Specifically, the exemption would allow APS to delay the Unit 1 third 
    Type A test until the September 1996 refueling outage (1R6) and allow 
    APS to only perform the three tests required by 10 CFR Part 50, 
    Appendix J. As such, the third Type A test would be performed within 10 
    calendar years from the common start date of the initial ISI interval 
    and 10 years and 8 months from the date of Unit 1 commercial operation. 
    With this exemption, the interval between the second and third Type A 
    test would be approximately 81 months.
        The licensee also requested an exemption that would allow the 
    decoupling of this third test from the endpoint of the first 10-year 
    inservice inspection period. Specifically, subsequent Type A testing 
    would be performed in accordance with the requirements of 10 CFR Part 
    50, Appendix J (three Type A tests every 10 years at approximately 
    equal intervals), commencing from the completion of the Unit 1 sixth 
    refueling outage (1R6). A CILRT would not need to be performed during 
    the 10-year ISI outage planned for the Spring of 1998 (1R7). Therefore, 
    the need for the licensee's proposed action is to allow a longer 
    interval between the Palo Verde Unit 1 second and third periodic Type A 
    ILRTs. This action, along with decoupling the requirement to perform an 
    ILRT at the end of the 10-year inservice inspection period, will 
    eliminate the need for an additional test. The licensee concluded that 
    the extension of the Type A test interval has a negligible impact on 
    overall risk and results in a cost savings.
    
    Environmental Impacts of the Proposed Action
    
        The Commission has completed its evaluation of the proposed action 
    and concludes that the proposed one-time exemption would not increase 
    the probability or consequences of accidents previously analyzed and 
    the proposed one-time exemption would not affect facility radiation 
    levels or facility radiological effluents. The licensee has analyzed 
    the results of previous Type A tests performed at the Palo Verde 
    Nuclear Generating Station, Unit 1. The licensee has provided an 
    acceptable basis for concluding that the proposed one-time extension of 
    the Type A test interval would maintain the containment leakage rates 
    within acceptable limits. Accordingly, the Commission has concluded 
    that the one-time extension does not result in a significant increase 
    in the amounts of any effluents that may be released nor does it result 
    in a significant increase in individual or cumulative occupational 
    radiation exposure. Therefore, there are no significant radiological 
    environmental impacts associated with the proposed exemption.
        With regard to potential nonradiological impacts, the proposed 
    exemption only involves Type A testing on the containment. It does not 
    affect nonradiological plant effluents and has no other environmental 
    impact. Accordingly, the Commission concludes that here are no 
    significant nonradiological environmental impacts associated with the 
    proposed exemption.
    
    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.
        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 not significant increase in the 
    allowable individual or cumulative occupation radiation exposure. 
    Accordingly, the Commission concludes that there are no significant 
    radiological environmental impacts associated with the proposed 
    exemption.
    
    Alternative Use of Resources
    
        This action does not involve the use of resources not previously 
    considered in the ``Final Environmental Statement Related to the 
    Operation of Palo Verde Nuclear Generating Station, Units 1, 2, and 
    3,'' dated February 1982. [[Page 16181]] 
    
    Agencies and Persons Consulted
    
        In accordance with its stated policy, the NRC staff consulted with 
    the Arizona State official 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 exemption.
        For further details with respect to this action, see the licensee's 
    letter dated December 28, 1994, 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 Phoenix Public Library, 12 East McDowell 
    Road, Phoenix, Arizona 85004.
    
    
        Dated at Rockville, Maryland, this 24th day of March 1995.
    
        For the Nuclear Regulatory Commission.
    Theodore R. Quay,
    Director, Project Directorate IV-2, Division of Reactor Projects III/
    IV, Office of Nuclear Reactor Regulation.
    [FR Doc. 95-7699 Filed 3-28-95; 8:45 am]
    BILLING CODE 7590-01-M
    
    

Document Information

Published:
03/29/1995
Department:
Nuclear Regulatory Commission
Entry Type:
Notice
Document Number:
95-7699
Pages:
16180-16181 (2 pages)
Docket Numbers:
Docket No. STN 50-528
PDF File:
95-7699.pdf