99-11996. Texas Utilities Electric Company (Comanche Peak Steam Electric Station, Units 1 and 2); Exemption  

  • [Federal Register Volume 64, Number 91 (Wednesday, May 12, 1999)]
    [Notices]
    [Pages 25520-25522]
    From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
    [FR Doc No: 99-11996]
    
    
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    NUCLEAR REGULATORY COMMISSION
    
    [Docket Nos. 50-445 and 50-446]
    
    
    Texas Utilities Electric Company (Comanche Peak Steam Electric 
    Station, Units 1 and 2); Exemption
    
    I.
    
        Texas Utilities Electric Company (the licensee/TU Electric) is the 
    holder of Facility Operating Licenses No. NPF-87 and No. NPF-89, which 
    authorize operation of the Comanche Peak Steam Electric Station 
    (CPSES), Units 1 and 2. The licenses provide, among other things, that 
    the licensee is subject to all rules, regulations, and orders of the 
    Commission now or hereafter in effect.
        These facilities consist of two pressurized-water reactors at the 
    licensee's site located in Somervell County, Texas.
        TU Electric seeks this exemption to the 2 percent above licensed 
    power level assumption to allow for uncertainties specified by Title 10 
    of the Code of Federal Regulations (10 CFR), Part 50, Appendix K, 
    ``ECCS [Emergency Core Cooling System] Evaluation Models,'' Section 
    I.A., to support license amendments for modest increases of up to 1 
    percent in the licensed power levels for both units. This will result 
    in an exemption from the requirements of 10 CFR Part 50, Appendix K to 
    allow ECCS evaluation model assumptions to be conducted at no less than 
    1.01 times licensed power level. The licensee seeks this exemption 
    based on its proposed use of a new feedwater flow measurement system to 
    allow more accurate measurement of thermal power (known as the Leading 
    Edge Flowmeter (LEFM) System), manufactured by Caldon, Inc. The LEFM is 
    described in Caldon, Inc., Topical Report ER-80P, ``Improving Thermal 
    Power Accuracy and Plant Safety While Increasing Operating Power Level 
    Using the LEFM System.'' The subject topical report was approved 
    subject to the limitations stated in a letter and Safety Evaluation 
    (SE) dated March 8, 1999.
    
    [[Page 25521]]
    
    II.
    
        Part 50, Appendix K, Section I. A. states, in part, that ``it shall 
    be assumed that the reactor has been operating continuously at a power 
    level at least 1.02 times the licensed power level (to allow for such 
    uncertainties as instrument error).'' The Appendix K rule was written 
    to ensure that adequate margin for ECCS performance would be available 
    if a design-basis loss-of-coolant accident (LOCA) ever occurred (39 FR 
    1002, January 4, 1974). The margin was provided by incorporating 
    several conservative features into the ECCS performance criteria as 
    well as maintaining conservative requirements and recommendations for 
    evaluation models.
        The basis for the requirement is discussed in background 
    documentation, such as the Statement of Consideration for Appendix K 
    (39 FR 1002, January 4, 1974). The 102 percent assumption is one of 
    several items listed as conservative factors used to model the energy 
    available from reactor operation. The Statement of Consideration also 
    associates the preaccident power level assumption with the modeling of 
    the rate of heat generation after the LOCA occurs. A comparison is made 
    between the estimated uncertainty associated with the decay heat 
    assumption (i.e., 20 percent above the American Nuclear Society (ANS) 
    standard) and the estimated effect on heat generation resulting from 
    the 102 percent power assumption. This is a natural connection since 
    the preaccident power level directly affects the decay heat generation 
    rate after reactor shutdown.
        When it was considering changes to Appendix K to accept the use of 
    best-estimate evaluations, the staff understood that the rule 
    incorporated substantial conservatisms (see SECY 83-472, ``Emergency 
    Core Cooling System Analysis Methods,'' November 17, 1983). These 
    conservatisms were necessary when the rule was written because of 
    limited experimental evidence. The major analysis inputs and 
    assumptions that contribute to the conservatism in Appendix K are 
    grouped together under Sections A through D of the rule: (A) Sources of 
    Heat During the LOCA (the 102 percent power provision is one factor); 
    (B) Swelling and Rupture of the Cladding and Fuel Rod Thermal 
    Parameters; (C) Blowdown Phenomena; and (D) Post-blowdown Phenomena: 
    Heat Removal by ECCS. In each of these areas, several assumptions are 
    typically used to assure conservatism in the analysis results. For 
    instance, under sources of heat during the LOCA, in addition to the 102 
    percent requirement, decay heat is modeled on the basis of an ANS 
    standard with an added 20 percent penalty, and the power distribution 
    shape and peaking factors expected during the operating cycle are 
    chosen to yield the most conservative results. As discussed in SECY-83-
    472, experimental programs provided ample data, which shed light on the 
    considerable margin provided by Appendix K, giving the staff confidence 
    to consider alternative ECCS evaluation models.
    
    III
    
        Section 50.12(a), states that . . .
        The Commission may, upon application by any interested person or 
    upon its own initiative, grant exemptions from the requirements of 
    the regulations of this part, which are--
        (1) Authorized by law, will not present an undue risk to the 
    public health and safety, and are consistent with the common defense 
    and security.
        (2) The Commission will not consider granting an exemption 
    unless special circumstances are present. . . .
        Section 50.12(a)(2), states that special circumstances are 
    present whenever . . .
        (ii) Application of the regulation in the particular 
    circumstances would not serve the underlying purpose of the rule or 
    is not necessary to achieve the underlying purpose of the rule; or
        (iv) The exemption would result in benefit to the public health 
    and safety that compensates for any decrease in safety that may 
    result from the grant of the exemption; or
        (vi) There is present any other material circumstance not 
    considered when the regulation was adopted for which it would be in 
    the public interest to grant an 
    exemption. . . .
    
    IV
    
        The staff has reviewed the applicable regulations and the 
    regulatory history for Appendix K as well as for Section 50.46, and 
    finds that those regulatory documents do not prohibit the licensee's 
    proposal to use Caldon Inc.'s, Leading Edge Flowmeter System (Caldon 
    LEFM System) instrument. Accordingly, the exemption is authorized by 
    law, as required by 10 CFR 50.12(a)(1).
        The staff used Regulatory Guide 1.174 and Standard Review Plan 
    Chapter 19 to review the application for the exemption. Specifically, 
    the staff reviewed the application considering the defense-in-depth 
    philosophy, the maintenance of sufficient safety margin, and the fact 
    that the increase in risk was small and consistent with the Commission 
    safety goals. A slightly higher power level will result in a small 
    increase in decay heat load that could affect required response time of 
    the ECCS and the available operator response time following transients 
    and accidents. Results of core and containment consequence analyses 
    from higher power levels could also be affected. However, NUREG-1230, 
    ``Compendium of ECCS Research for Realistic LOCA Analysis,'' considered 
    the risk impact of changes associated with the revised ECCS rules, 
    including power increase, and considered a power increase of 5 percent 
    or less to have little risk significance. The staff concludes that this 
    increase of 1 percent is bounded by the NUREG-1230 considerations.
        In the safety evaluation for the Caldon topical report ER-80P dated 
    March 8, 1999, the staff accepted statistical treatment of 
    uncertainties attributed to the LEFM and venturi-based flow measurement 
    instruments and the uncertainty values associated with these two types 
    of flow measurement instruments at CPSES. The use of the Caldon LEFM 
    System and quantification of power measurement uncertainty do not raise 
    inconsistencies with the Commission's safety goals. Further, the 
    Commission has determined that, pursuant to 10 CFR 50.12, the requested 
    exemption is authorized by law, will not result in an undue risk to the 
    public health and safety, and is consistent with the common defense and 
    security and is otherwise in the public interest.
        The Commission also finds that special circumstances exist. By 
    seeking to apply a smaller margin for power measurement uncertainty, 
    the exemption does not violate the underlying purpose of Appendix K. 
    The application of 1.02 times the licensed thermal power is not 
    necessary to achieve the underlying purpose of Appendix K. Indeed, by 
    quantifying a contributor to the uncertainty where the uncertainty was 
    not specifically known, the exemption may better serve the underlying 
    purpose of the requirement. The use of the Caldon LEFM System and the 
    quantification of power measurement uncertainty appear to offer safety 
    benefits.
        By requesting this exemption, the licensee has undertaken to 
    quantify a contributor to the uncertainty in power measurement. 
    Although there is a small safety impact expected from the associated 
    power increase, it is not considered significant. The use of the LEFM 
    system and the quantification of power measurement uncertainty appear 
    to offer safety benefits.
        The Caldon LEFM System and the quantification of power measurement 
    uncertainty associated with use of the Caldon LEFM System constitute
    
    [[Page 25522]]
    
    material circumstances that did not exist when the rule was written. 
    The current Appendix K rule presumes that the 2 percent margin accounts 
    for uncertainties associated with measurement of thermal power. 
    Contributors to the uncertainty were not identified at the time the 
    rule was written and the magnitude of the uncertainty was not 
    demonstrated by experiment or analysis. The rule does not require 
    quantification of actual uncertainties, nor does the regulatory history 
    reflect any detailed technical basis for the choice of a 2 percent 
    margin. Therefore, the Commission has determined that special 
    circumstances as defined in 10 CFR 50.12(a)(2)(ii), (iv), and (vi) are 
    present.
        The Commission hereby grants the licensee an exemption from the 
    requirements of 10 CFR Part 50, Appendix K to allow ECCS evaluation 
    model assumptions to be conducted at no less than 1.01 times licensed 
    power level when the quantification of power measurement uncertainty 
    can be justified by the use of the Caldon LEFM System instrumentation. 
    The granting of this exemption does not, however, provide authority to 
    increase the licensed power of CPSES, Units 1 and 2. A separate license 
    amendment to increase licensed power level, for each licensed unit, 
    will be required to be submitted and approved before such authority may 
    be provided for that unit.
        Pursuant to 10 CFR 51.32, the Commission has determined that 
    granting of this exemption will have no significant effect on the 
    quality of the human environment (64 FR This exemption is effective 
    upon issuance.
    
        Dated at Rockville, Maryland, this 6th day of May 1999.
    
        For the Nuclear Regulatory Commission.
    John A. Zwolinski,
    Director, Division of Licensing Project Management, Office of Nuclear 
    Reactor Regulation.
    [FR Doc. 99-11996 Filed 5-11-99; 8:45 am]
    BILLING CODE 7590-01-P
    
    
    

Document Information

Published:
05/12/1999
Department:
Nuclear Regulatory Commission
Entry Type:
Notice
Document Number:
99-11996
Pages:
25520-25522 (3 pages)
Docket Numbers:
Docket Nos. 50-445 and 50-446
PDF File:
99-11996.pdf