95-318. The Cleveland Electric Illuminating Co., et al.; Environmental Assessment and Finding of No Significant Impact  

  • [Federal Register Volume 60, Number 4 (Friday, January 6, 1995)]
    [Notices]
    [Pages 2162-2164]
    From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
    [FR Doc No: 95-318]
    
    
    
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    NUCLEAR REGULATORY COMMISSION
    [Docket No. 50-440]
    
    
    The Cleveland Electric Illuminating Co., et al.; Environmental 
    Assessment and Finding of No Significant Impact
    
        The U.S. Nuclear Regulatory Commission (the Commission) is 
    considering issuance of an amendment to Facility Operating License No. 
    NPF-58, issued to the Cleveland Electric Illuminating Company, 
    Centerior Service Company, Duquesne Light Company, Ohio Edison Company, 
    Pennsylvania Power Company, and Toledo Edison Company (the licensee), 
    for operation of the Perry Nuclear Power Plant, Unit No. 1, located in 
    Lake County, Ohio.
    
    Environmental Assessment
    
    Identification of the Proposed Action
    
        The proposed amendment will replace the existing Technical 
    Specifications (TS), in their entirety, with the Improved Technical 
    Specification (ITS). The proposed action is in accordance with the 
    licensee's amendment request dated December 16, [[Page 2163]] 1993, as 
    supplemented November 7, 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,'' (Federal Register 52 FR 3788, 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 NUREG-1433 
    for BWR/4 reactor facilities and NUREG-1434 for BWR/6 facilities. 
    NUREG-1434 formed the basis of the Perry ITS. The NRC Committee to 
    Review Generic Requirements (CRGR) reviewed the STS and made note of 
    the safety merits of the STS 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-1434, 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-1434, 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 with the GE and other 
    OGs.
        The proposed changes from the existing TS can be grouped into four 
    general categories, as follows:
        1. Non-technical (administrative) changes, which 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 
    Perry TS has undergone these types of changes. In order to ensure 
    consistency, the NRC staff and the licensee have used NUREG-1434 as 
    guidance to reformat and make other administrative changes.
        2. Relocation of requirements, which includes items that were in 
    the existing Perry 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 Perry TS to the Updated Safety Analysis 
    report (USAR), appropriate plant-specific programs, procedures and ITS 
    Bases, follows the guidance of the BWR/6 STS, NUREG-1434. 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.
        3. More restrictive requirements, which consist of proposed Perry 
    ITS items that are either more conservative than corresponding 
    requirements in the existing Perry TS, or are additional restrictions, 
    which are not in the existing Perry TS, but are contained in NUREG-
    1434. Examples of more restrictive requirements include: placing a 
    Limiting Conditions for 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.
        4. Less restrictive requirements, which are relaxations of 
    corresponding requirements in the existing Perry TS, which provided 
    little or no safety benefit, and placed unnecessary burden on the 
    licensee. These relaxations were the result of generic NRC action or 
    other analyses. They have been justified on a case-by-case basis for 
    Perry, 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 assures continued maintenance of 
    adequate requirements. All such relocations have been found to be in 
    conformance with the guidelines of NUREG-1434 and the Policy Statement, 
    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 Perry. 
    Generic relaxations contained in NUREG-1434 have also been reviewed by 
    the NRC staff and have been found to be acceptable.
        In summary, the proposed revision to the TS has been 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 
    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.
        Therefore, the Commission concludes that there are no significant 
    radiological environmental impacts associated with the proposed TS 
    amendment.
        With regard to potential non-radiological impacts, the proposed 
    amendment involves features located entirely within the restricted 
    areas as defined in 10 CFR 20. It does not affect non-radiological 
    plant effluents and has no other environmental impact. Therefore, the 
    Commission concludes that there are no significant non-radiological 
    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 amendment, any 
    alternatives with equal or greater environmental impact need not be 
    evaluated. The principal alternative to the amendment 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 Perry Nuclear 
    Power Plant, Unit 1. [[Page 2164]] 
    
    Agencies and Persons Consulted
    
        The NRC staff consulted with the State of Ohio 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 amendment.
        For futher details with respect to this proposed action, see the 
    licensee's letters dated December 16, 1993 (PY-CEI/NRR-1732 L), and 
    November 7, 1994 (PY-CEI/NRR-1880 L). These letters are 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 Perry Public Library, 3753 Main Street, 
    Perry, Ohio 44081.
    
        Dated at Rockville, Maryland this 30th day of December 1994.
    
        For the Nuclear Regulatory Commission.
    Leif J. Norrholm,
    Director, Project Directorate III-3, Division of Reactor Projects III/
    IV, Office of Nuclear Reactor Regulation.
    [FR Doc. 95-318 Filed 1-5-95; 8:45 am]
    BILLING CODE 7590-01-M
    
    

Document Information

Published:
01/06/1995
Department:
Nuclear Regulatory Commission
Entry Type:
Notice
Document Number:
95-318
Pages:
2162-2164 (3 pages)
Docket Numbers:
Docket No. 50-440
PDF File:
95-318.pdf