98-32107. Steam Generator Tube Integrity for Operating Nuclear Power Plants  

  • [Federal Register Volume 63, Number 231 (Wednesday, December 2, 1998)]
    [Proposed Rules]
    [Pages 66496-66497]
    From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
    [FR Doc No: 98-32107]
    
    
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    NUCLEAR REGULATORY COMMISSION
    
    10 CFR Part 50
    
    RIN 3150-AF04
    
    
    Steam Generator Tube Integrity for Operating Nuclear Power Plants
    
    AGENCY: Nuclear Regulatory Commission.
    
    ACTION: Proposed rule: Withdrawal.
    
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    SUMMARY: The Nuclear Regulatory Commission (NRC) is withdrawing an 
    advance notice of proposed rulemaking (ANPRM) that was published to 
    request public comment on the Commission's regulations pertaining to 
    steam generator (SG) tube integrity. The proposed rule would have 
    implemented a more flexible regulatory framework for steam generator 
    surveillance and maintenance activities that would maintain adequate 
    assurance of tube integrity while allowing a degradation-specific 
    management approach. Because the NRC has concluded that the regulatory 
    objectives set forth for this effort can be achieved by equally 
    effective regulatory alternatives, the ANPR is being withdrawn.
    
    ADDRESSES: The Commission paper, the staff requirement memoranda (SRM), 
    and associated documents are available for public inspection, and 
    copying for a fee, at the NRC Public Document Room located at 2120 L 
    Street NW. (Lower Level), Washington, DC 20012-7082, telephone: (202) 
    512-2249.
    
    FOR FURTHER INFORMATION CONTACT: Tim Reed, Office of Nuclear Reactor 
    Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555-
    0001, telephone (301) 415-1462, e-mail tar@nrc.gov.
    
    SUPPLEMENTARY INFORMATION:
        On September 19, 1994 (59 FR 47817), the Commission published an 
    ANPRM that requested comments, advice, and recommendations from 
    interested parties on the proposed steam generator rule. In response to 
    the ANPRM, two
    
    [[Page 66497]]
    
    public comments were received. The primary comment was a coordinated 
    industry response submitted by the Nuclear Energy Institute (NEI). The 
    remaining comment, submitted by Virginia Power, endorsed the NEI 
    comment. Subsequently, the NRC staff developed a draft rule and draft 
    regulatory guide intended to implement a performance-based regulatory 
    structure that provides for the development and implementation of 
    appropriate measures to ensure the consistency and quality of 
    inspection methods, repair criteria, and tube condition assessment, 
    while giving appropriate consideration to risk. As part of the 
    rulemaking process, the NRC staff estimated the risk associated with SG 
    tube degradation and used the results to provide the insights required 
    for performing a regulatory analysis of the proposed rulemaking 
    approach.
        In COMSECY-97-013, dated May 23, 1997, the NRC staff provided a 
    risk assessment summary and major conclusions from a regulatory 
    analysis. Based on these results, the NRC staff reassessed whether a 
    rulemaking is the appropriate regulatory vehicle for addressing the 
    problems associated with SG tube integrity. It should be recognized 
    that the NRC staff found that the current regulations governing SG tube 
    integrity provide an adequate basis to ensure public health and safety 
    due to SG operation. However, the NRC staff concluded that further 
    guidance is needed for the industry to continue to effectively meet 
    these regulations. Issues involving a plant's technical specifications 
    (TS) are amenable to a generic letter approach. Given these 
    considerations, the NRC staff informed the Commission that it planned 
    to pursue the following approach in lieu of a new steam generator 
    rulemaking: (1) Complete development of a SG tube integrity regulatory 
    guide which describes an acceptable performance-based program for 
    ensuring adequate tube inspection, monitoring, and assessment; (2) 
    request licensees, through a generic letter, to propose performance-
    based technical specification changes to address the issues regarding 
    inspection, monitoring, and assessment of SG tube condition to ensure 
    that SG tube integrity is maintained consistent with the plant 
    licensing basis; (3) provide licensees with an option to change current 
    SG tube repair criteria and implement a degradation-specific management 
    approach, if it can be demonstrated that risk will be maintained at an 
    acceptable level. An application-specific regulatory guide would 
    provide guidance on acceptable approaches for proposing changes to SG 
    tube integrity criteria and assessing changes in risk associated with 
    relaxation of tube integrity criteria. Licensees would not be able to 
    implement alternate repair criteria until an appropriate risk 
    assessment is submitted and found acceptable by the NRC staff; and (4) 
    as part of the IPE follow-up program, the NRC staff will evaluate 
    pressurized water reactors (PWRs) that appear to have a high potential 
    for core damage sequences that can challenge SG tubes. Any additional 
    requirements would be imposed consistent with the backfit requirements 
    of Sec. 50.109.
        The SRM on COMSECY-97-013, dated June 30, 1997, approved the 
    revised approach. The SRM also directed the NRC staff to seek industry 
    input, as appropriate, in developing the technical basis for the 
    proposed TS changes to ensure that the proposed changes are consistent 
    with current steam generator tube degradation modes. In support of this 
    commitment, the NRC staff developed a proposed generic letter that: (1) 
    informs PWR licensees that plant TSs for maintaining SG tube integrity 
    do not alone provide the needed assurance that SG tube integrity is 
    being adequately monitored and maintained in accordance with NRC 
    regulations and plant licensing bases; (2) advises licensees that they 
    may request license amendments to their plant TSs to implement the 
    model TSs attached to the generic letter for maintaining SG tube 
    integrity, or justify alternate approaches for ensuring that SG tube 
    integrity; and (3) requires that licensees submit to the NRC written 
    responses that describe their ongoing or planned activities to monitor 
    and maintain SG tube integrity. By letter dated December 16, 1997, the 
    NRC staff was informed that the industry, through the NEI Nuclear 
    Strategic Issues Advisory Committee, had voted to adopt NEI 97-06. The 
    chief objective of the industry initiative is for PWR licensees to 
    evaluate their existing SG programs and, where necessary, to revise or 
    strengthen program attributes to meet the intent of the NEI 97-06 
    guidelines. The NEI 97-06 guidelines are intended to improve both the 
    quality and the consistency of SG programs throughout the industry. 
    Consistent with Direction Setting Issue (DSI) 13, the NRC staff's 
    preferred approach is to endorse an industry initiative that addresses 
    all NRC staff and stakeholder concerns, rather than issue a generic 
    letter. As a result, the NRC staff has temporarily deferred issuing the 
    proposed generic letter for public comment while it works with industry 
    to resolve issues associated with NEI 97-06, with the objective of 
    endorsing NEI 97-06 in a regulatory guide.
        Whether the NRC staff ultimately endorses the NEI 97-06 guidance or 
    continues with its efforts to issue a generic letter addressing SG tube 
    integrity, the NRC has concluded that equally effective regulatory 
    alternatives to rulemaking are available to address the issue of SG 
    tube integrity. Therefore, the proposed rule is not required and is 
    being withdrawn.
    
        Dated at Rockville, Maryland, this 24th day of November, 1998.
    
        For the Nuclear Regulatory Commission.
    John C. Hoyle,
    Secretary of the Commission.
    [FR Doc. 98-32107 Filed 12-1-98; 8:45 am]
    BILLING CODE 7590-01-P
    
    
    

Document Information

Published:
12/02/1998
Department:
Nuclear Regulatory Commission
Entry Type:
Proposed Rule
Action:
Proposed rule: Withdrawal.
Document Number:
98-32107
Pages:
66496-66497 (2 pages)
RINs:
3150-AF04: Steam Generator Tube Integrity for Operating Nuclear Power Plants
RIN Links:
https://www.federalregister.gov/regulations/3150-AF04/steam-generator-tube-integrity-for-operating-nuclear-power-plants
PDF File:
98-32107.pdf
CFR: (1)
10 CFR 50