94-29485. Environmental Assessment and Finding of No Significant Impact, Georgia Power Co., et al.; Edwin I. Hatch Nuclear Plant, Units 1 and 2  

  • [Federal Register Volume 59, Number 229 (Wednesday, November 30, 1994)]
    [Unknown Section]
    [Page 0]
    From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
    [FR Doc No: 94-29485]
    
    
    [[Page Unknown]]
    
    [Federal Register: November 30, 1994]
    
    
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    NUCLEAR REGULATORY COMMISSION
    [Docket Nos. 50-321 and 50-366]
    
     
    
    Environmental Assessment and Finding of No Significant Impact, 
    Georgia Power Co., et al.; Edwin I. Hatch Nuclear Plant, Units 1 and 2
    
        This U.S. Nuclear Regulatory Commission (the Commission) is 
    considering issuance of amendments to Facility Operating License Nos. 
    DPR-57 and NPF-5, issued to Georgia Power Company (GPC or the 
    licensee), for operation of the Edwin I. Hatch Nuclear Plant, Units 1 
    and 2, located in Appling County, Georgia.
    
    Environmental Assessment
    
    Identification of the Proposed Action
    
        The proposed amendments will replace the existing Technical 
    Specifications (TS) in their entirety with the Improved Technical 
    Specifications (ITS). The proposed action is in accordance with the 
    licensee's amendment request dated February 25, 1994, and supplemented 
    July 8, August 8 and August 31, September 23, October 19, and November 
    1, 1994.
    
    The Need for the Proposed Action
    
        It has been recognized that nuclear safety in all plants would 
    benefit from improvement and standardization of TS. The ``NRC'' Interim 
    Policy Statement on Technical Specification Improvements for Nuclear 
    Power Reactors,'' (52 FR 3788 dated February 6, 1987) and later the 
    Final Policy Statement, formalized this need. To facilitate the 
    development of individual ITS, each reactor vendor owners group (OG) 
    and the NRC staff developed standard technical specifications. For 
    General Electric (GE) plants, the standard TS (STS) are found in NUREG-
    1433, ``Standard Technical Specifications, General Electric Plants, 
    BWR/4,'' dated September 1992, which formed the basis of the Hatch ITS. 
    The NRC Committee to Review Generic Requirements (CRGR) reviewed the 
    STS, made not of its safety merits, and indicated its support of 
    conversion by operating plants to the STS.
    
    Description of the Proposed Change
    
        The proposed revision to the TS is based on NUREG-1433 and on 
    guidance provided in the Policy Statement. Its objective is to 
    completely rewrite, reformat, and streamline the existing TS. Emphasis 
    is placed on human factors principles to improve clarity and 
    understanding. The Bases section has been significantly expanded to 
    clarify and better explain the purpose and foundation of each 
    specification. In addition to NUREG-1433, portions of the existing TS 
    were also used as the basis for the ITS. Plant-specific issues (unique 
    design features, requirements, and operating practices) were discussed 
    at length with the licensee, and generic matters were discussed with 
    the licensee, GE, and other OGs.
        The proposed changes from the existing TS can be grouped into four 
    general categories, as follows:
        Non-Technical (administrative) changes were intended to make the 
    ITS easier to use for plant operations personnel. They are purely 
    editorial in nature or involve the movement or reformat of requirements 
    without affecting technical content. Every section of the Hatch TS has 
    undergone these types of changes. In order to ensure consistency, the 
    NRC staff and GPC have used NUREG-1433 as guidance to reformat and make 
    other administrative changes.
        Relocation of requirements includes items that were in the existing 
    Hatch TS, but did not meet the criteria set forth in the Policy 
    Statement for inclusion in TS.
        In general, the proposed relocation of items in the Hatch TS to the 
    Final Safety Analysis Report (FSAR), appropriate plant-specific 
    programs, procedures, and ITS Bases follows the guidance of the GE STS, 
    NUREG-1433. Once these items have been relocated by removing them from 
    the TS to other licensee-controlled documents, the licensee may revise 
    them under the provisions of 10 CFR 50.59 or other NRC staff-approved 
    control mechanisms which provide appropriate procedural means to 
    control changes.
        More restrictive requirements are those proposed Hatch ITS items 
    that are either more conservative than corresponding requirements in 
    the existing Hatch TS, or are additional restrictions which are not in 
    the existing Hatch TS, but are contained in NUREG-1433. Examples of 
    more restrictive requirements include: placing a Limiting Condition of 
    Operation (LCO) on plant equipment which is not required by the present 
    TS to be operable; more restrictive requirements to restore inoperable 
    equipment; and more restrictive surveillance requirements.
        Less restrictive requirements are relaxations of corresponding 
    requirements in the existing Hatch TS which provided little or no 
    safety benefit or placed unnecessary burden on the licensee. These 
    relaxations were the result of generic NRC actions or other analyses. 
    They have been justified on a case-by-case basis for Hatch as described 
    in the Safety Evaluation to be issued with the license amendment, which 
    will be noticed in the Federal Register.
    
    Environmental Impacts of the Proposed Action
    
        The Commission has completed its evaluation of the proposed 
    revision to the TS. Changes which are administrative in nature have 
    been found to have no effect on technical content of the TS, and are 
    acceptable. The increased clarity and understanding these changes bring 
    to the TS are expected to improve the operator's control of the plant 
    in normal and accident conditions.
        Relocation of requirements to other licensee-controlled documents 
    does not change the requirements themselves. Future changes to these 
    requirements may be made by the licensee under 10 CFR 50.59 or other 
    NRC-approved control mechanisms, which assure continued maintenance of 
    adequate requirements. All such relocations have been found to be in 
    conformance with the guidelines of NUREG-1433 and the Policy 
    Statements, and, therefore, to be acceptable.
        Changes involving more restrictive requirements have been found to 
    be acceptable.
        Changes involving less restrictive requirements have been reviewed 
    individually. When requirements have been shown to provide little or no 
    safety benefit or to place unnecessary burden on the licensee, their 
    removal from the TS was justified. In most cases, relaxations 
    previously granted to individual plants on a plant-specific basis were 
    the result of a generic NRC action, or of agreements reached during 
    discussions with the OG and found to be acceptable for Hatch. Generic 
    relaxations contained in NUREG-1433 have also been reviewed by the NRC 
    staff and have been found to be acceptable.
        In summary, the proposed revision to the TS was found to provide 
    control of plant operations such that reasonable assurance will be 
    provided that the health and safety of the public will be adequately 
    protected.
        These TS changes will not increase the probability or consequences 
    of accidents, no changes are being made in the types of an effluent 
    that may be released offsite, and there is no significant increase in 
    the allowable individual or cumulative occupational radiation exposure. 
    Therefore, the Commission concludes that there are no significant 
    radiological environmental impacts associated with the proposed TS 
    amendments.
        With regard to potential non-radiological impacts, the proposed 
    amendment involves features located entirely within the restricted 
    areas as defined in 10 CFR Part 20. It does not affect non-radiological 
    plant effluent and has no other environmental impact. Therefore, the 
    Commission concludes that there are no significant non-radiological 
    environmental impacts associated with the proposed amendment.
    
    Alternatives to the Proposed Action
    
        Since the Commission has concluded there is no measurable 
    environmental impact associated with the proposed amendments, any 
    alternatives with equal or greater environmental impact need not be 
    evaluated. The principal alternative to the amendments would be to deny 
    the amendment request. Such action would not enhance the protection of 
    the environment.
    
    Alternative Use of Resources
    
        This action does not involve the use of resources not considered 
    previously in the Final Environmental Statement for the Hatch Nuclear 
    Plant, Units 1 and 2.
    
    Agencies and Persons Consulted
    
        The NRC staff consulted with the State of Georgia regarding the 
    environmental impact of the proposed action.
    
    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 amendment.
        For further details with respect to this proposed action, see the 
    licensee's submittals dated February 25, as supplemented July 8, August 
    8 and 31, September 23, October 19, and November 1, 1994. The 
    submittals are available for public inspection at the Commission's 
    Public Document Room, The Gelman Building, 2120 L Street, NW., 
    Washington, DC 20555, and at the local public document room located at 
    the Appling County Public Library, 301 City Hall Drive, Baxley, Georgia 
    31513.
    
        Dated at Rockville, Maryland, this 21st day of November 1994.
    
        For the Nuclear Regulatory Commission.
    Louis L. Wheeler,
    Acting Director, Project Directorate II-3, Division of Reactor 
    Projects--I/II, Office of Nuclear Reactor Regulation.
    [FR Doc. 94-29485 Filed 11-29-94; 8:45 am]
    BILLING CODE 7590-01-M
    
    
    

Document Information

Published:
11/30/1994
Department:
Nuclear Regulatory Commission
Entry Type:
Uncategorized Document
Document Number:
94-29485
Pages:
0-0 (1 pages)
Docket Numbers:
Federal Register: November 30, 1994, Docket Nos. 50-321 and 50-366