2024-21500. Florida Power and Light Company; Turkey Point Nuclear Generating, Unit Nos. 3 and 4; Exemption  

  • AGENCY:

    Nuclear Regulatory Commission.

    ACTION:

    Notice; issuance.

    SUMMARY:

    The U.S. Nuclear Regulatory Commission (NRC) has issued an exemption in response to a November 15, 2023, request from Florida Power and Light Company from certain requirements of NRC regulations to use AXIOM® fuel rod cladding at Turkey Point Nuclear Generating, Unit Nos. 3 and 4. Current NRC regulations limit applicability to the use of fuel rod cladding with zircaloy or ZIRLOTM.

    DATES:

    The exemption was issued on September 13, 2024.

    ADDRESSES:

    Please refer to Docket ID NRC-2024-0142 when contacting the NRC about the availability of information regarding this document. You may obtain publicly available information related to this document using any of the following methods:

    • Federal Rulemaking website: Go to https://www.regulations.gov and search for Docket ID NRC-2024-0142. Address questions about Docket IDs in Regulations.gov to Stacy Schumann; telephone: 301-415-0624; email: Stacy.Schumann@nrc.gov. For technical questions, contact the individual listed in the For Further Information Contact section of this document.
    • NRC's Agencywide Documents Access and Management System (ADAMS): You may obtain publicly available documents online in the ADAMS Public Documents collection at http://www.nrc.gov/​reading-rm/​adams.html. To begin the search, select “Begin Web-based ADAMS Search.” For problems with ADAMS, please contact the NRC's Public Document Room (PDR) reference staff at 1-800-397-4209, at 301-415-4737, or by email to PDR.Resource@nrc.gov. The ADAMS accession number for each document referenced in this document (if that document is available in ADAMS) is provided the first time that it is mentioned in this document.
    • NRC's PDR: The PDR, where you may examine and order copies of publicly available documents, is open by appointment. To make an appointment to visit the PDR, please send an email to PDR.Resource@nrc.gov or call 1-800-397-4209 or 301-415-4737, between 8 a.m. and 4 p.m. eastern time (ET), Monday through Friday, except Federal holidays.

    FOR FURTHER INFORMATION CONTACT:

    Michael Mahoney, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; telephone: 301-415-3867, email: Michael.Mahoney@nrc.gov.

    SUPPLEMENTARY INFORMATION:

    The text of the exemption is attached.

    Dated: September 16, 2024.

    For the Nuclear Regulatory Commission.

    Michael Mahoney,

    Senior Project Manager, Plant Licensing Branch 4, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation.

    Attachment: Exemption

    NUCLEAR REGULATORY COMMISSION

    Docket Nos. 50-250 and 50-251

    Florida Power and Light Company; Turkey Point Nuclear Generating, Unit Nos. 3 and 4 Exemption

    I. Background

    Florida Power and Light Company (FPL, the licensee) is the holder of Renewed Facility Operating License Nos. DPR-31 and DPR-41, which authorize operation of Turkey Point Nuclear Generating, Unit Nos. 3 and 4 (Turkey Point). The license provides, among other things, that the facility is subject to all rules, regulations, and orders of the U.S. Nuclear Regulatory Commission (NRC) now or hereafter in effect. The facility consists of pressurized-water reactors (PWRs) located in Miami-Dade County, Florida.

    II. Request/Action

    By application dated November 15, 2023 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML23320A028), FPL, pursuant to Title 10 of the Code of Federal Regulations (10 CFR), Section 50.12, “Specific exemptions,” requested an exemption from certain requirements of 10 CFR 50.46, “Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors,” to use AXIOM® fuel rod cladding at Turkey Point.

    The regulations in 10 CFR 50.46 are currently limited in applicability to the use of fuel rods with zircaloy or ZIRLOTM cladding. This exemption will allow FPL to use AXIOM® fuel rod cladding at Turkey Point. The special circumstances associated with the exemption request are that application of the regulation in this circumstance is not necessary to achieve the underlying purpose of the rule.

    III. Discussion

    The regulation in 10 CFR 50.46(a)(1)(i) states, in part, that:

    Each boiling or pressurized light-water nuclear power reactor fueled with uranium oxide pellets within cylindrical zircaloy or ZIRLO cladding must be provided with an emergency core cooling system (ECCS) that must be designed so that its calculated cooling performance following postulated loss-of-coolant accidents [LOCA] conforms to the criteria set forth in paragraph (b) of this section. ECCS cooling performance must be calculated in accordance with an acceptable evaluation model and must be calculated for a number of postulated loss-of-coolant accidents of different sizes, locations, and other properties sufficient to provide assurance that the most severe postulated loss-of-coolant, accidents are calculated.

    Since 10 CFR 50.46 specifically refers to fuel with zircaloy or ZIRLOTM cladding, its application to fuel clads with materials other than zircaloy or ZIRLOTM requires an exemption from this section of the regulations.

    The exemption request from the licensee relates solely to the types of fuel cladding materials specified in these regulations. As written, the regulations presume the use of zircaloy or ZIRLOTM cladding. Thus, an exemption is necessary to apply 10 CFR 50.46 to cladding materials ( i.e., AXIOM®), other than zircaloy or ZIRLOTM cladding. The proposed ( print page 77200) request does not exempt Turkey Point from any other requirements of 10 CFR 50.46 regarding acceptance criteria, evaluation model features and documentation, reporting of changes or errors, etc.

    Pursuant to 10 CFR 50.12, the NRC may, upon application by any interested person or upon its own initiative, grant exemptions from requirements of 10 CFR part 50 when: (1) the exemptions are authorized by law, will not present an undue risk to the public health and safety, and are consistent with the common defense and security, and (2) special circumstances, as defined in 10 CFR 50.12(a)(2), are present. The licensee's proposed exemption request which would permit application of the requirements of 10 CFR 50.46 to fuel rods clad with AXIOM® at Turkey Point identifies, in particular, that the special circumstance associated with this exemption request is that the application of the regulation in this circumstance is not necessary to achieve the underlying purpose of the rule.

    The technical basis for the use of fuel cladding with AXIOM® in PWRs is documented in Topical Report (TR) WCAP-18546NP-A, Revision 0, “Westinghouse AXIOM® Cladding for Use in Pressurized Water Reactor Fuel,” dated March 2021 (ML23089A066). This TR describes Westinghouse's evaluation for the use of the AXIOM® alloy in PWR fuel assemblies as a replacement for ZIRLOTM and Optimized ZIRLOTM. This TR discusses material properties of AXIOM®, as well as its behavior under normal operation, anticipated transients, and postulated accident conditions.

    As identified in TR WCAP-18546NP-A, Revision 0, the AXIOM® alloy is a proprietary niobium-bearing variant of zirconium. This material also has tin, vanadium, and copper as alloying elements. Westinghouse stated that the AXIOM® alloy was developed to provide enhanced performance with respect to corrosion, hydrogen pickup, growth, and creep. While demonstrating relevant differences in certain material properties and physical behavior, TR WCAP-18546NP-A, Revision 0 identifies that the basic physical properties of AXIOM® are similar to ZIRLOTM.

    Sections 3.11, 3.12, and 6.2.1.4 of TR WCAP-18546NP-A, Revision 0 provide Westinghouse's rationale for concluding that each of the acceptance criteria in 10 CFR 50.46 is applicable to fuel clad with AXIOM®.

    As documented in the NRC staff's SE on TR WCAP-18546NP-A, Revision 0, the staff concluded that the criteria of 10 CFR 50.46 are acceptable for application to AXIOM® cladding. The technical basis for the NRC staff's conclusions is the testing and analysis Westinghouse performed in support of the AXIOM® alloy is described in the NRC staff's relevant safety evaluation. Despite finding application of 10 CFR 50.46 to AXIOM® acceptable from a technical perspective, current regulations in 10 CFR 50.46 are limited in applicability to the use of fuel rods with zircaloy or ZIRLOTM cladding; therefore, an exemption for use of a new cladding material (such as AXIOM®), is required.

    A. The Exemption Is Authorized by Law

    The NRC has the authority under 10 CFR 50.12 to grant exemptions from the requirements of 10 CFR part 50 upon demonstration of proper justification. The fuel that will be irradiated at Turkey Point is clad with a zirconium-based alloy that is not expressly within the scope of 10 CFR 50.46. However, the NRC staff considers all other aspects of these regulations ( e.g., acceptance criteria, prescribed methods, reporting requirements) applicable to the AXIOM® cladding material, and the licensee states that it will ensure that these regulations are satisfied for operation with fuel clad with AXIOM®. As discussed below, the NRC staff determined that special circumstances exist, which support granting the proposed exemption. Furthermore, granting the exemption would not result in a violation of the Atomic Energy Act of 1954, as amended, or the NRC's regulations. Therefore, the exemption is authorized by law.

    B. The Exemption Presents No Undue Risk to Public Health and Safety

    The NRC staff's previous review of TR WCAP-18546NP-A, Revision 0, which concerns the properties of the AXIOM® alloy, provides assurance that predicted chemical, thermal, and mechanical characteristics of AXIOM®-alloy cladding are acceptable under normal operation, anticipated transients, and postulated accidents. The NRC staff finds that by utilizing the methods and properties listed in the NRC-approved TR ( i.e., TR WCAP-18546NP-A), the licensee meets the acceptance criteria and analytical methods in 10 CFR 50.46 to 10 CFR part 50, and thus, ensures acceptable safety margins for fuel clad with AXIOM® that are consistent with those the Commission has established for zircaloy and ZIRLOTM. Turkey Point cores involving AXIOM® cladding will continue to be subject to the operating limits specified in the technical specifications and core operating limits report. Thus, granting this exemption request will not pose undue risk to public health and safety.

    C. The Exemption Is Consistent with the Common Defense and Security

    The exemption will allow the licensee to use an enhanced fuel rod cladding material relative to the zircaloy material for which the requirements of 10 CFR 50.46 were originally established. The NRC staff concludes that the use of AXIOM® fuel rod cladding at Turkey Point will not significantly affect plant operations and is therefore consistent with the common defense and security. Further, the exemption does not involve security requirements and does not create a security risk. Therefore, the exemption is consistent with the common defense and security.

    D. Special Circumstances

    The regulations in 10 CFR 50.46 do not explicitly apply to fuel clad with AXIOM®. However, the underlying purpose of 10 CFR 50.46 is to provide requirements capable of ensuring adequate core cooling during and after the most limiting postulated LOCA. As discussed above, Westinghouse has demonstrated in an NRC-approved TR ( i.e. TR WCAP-18546NP-A) that application of the acceptance criteria and analytical methods required in 10 CFR 50.46 to fuel cladding with AXIOM® is acceptable. For the maximum local oxidation limit in 50.46(b)(2), Westinghouse meets the 17 percent limit in the rule for cladding without any hydrogen, but further justified the use of an alternative limit that the NRC finds acceptable for maintaining post quench ductility during a postulated LOCA. The licensee stated in the exemption request that the core reload safety analyses will be used to confirm on a cycle-specific basis that there is no adverse impact on ECCS performance for Turkey Point. Therefore, strict application of the material-specific requirements for fuel cladding in 10 CFR 50.46 is not necessary to achieve the underlying purpose of ensuring adequate core cooling in this instance. Furthermore, granting an exemption to allow application of the balance of these regulations for fuel cladding with AXIOM® at Turkey Point would be consistent with the underlying regulatory purpose.

    E. Environmental Considerations

    The exemption requested by the licensee includes changes to requirements with respect to installation or use of a facility component located within the restricted area. The NRC staff determined that the exemption meets ( print page 77201) the eligibility criteria for the categorical exclusion set forth in 10 CFR 51.22(c)(9) because the granting of this exemption involves: (i) no significant hazards consideration, (ii) no significant change in the types or a significant increase in the amounts of any effluents that may be released offsite, and (iii) no significant increase in individual or cumulative occupational radiation exposure. Therefore, in accordance with 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the NRC's consideration of this exemption request. The basis for the NRC staff's determination of each of the requirements in 10 CFR 51.22(c)(9) is discussed below.

    Requirements in 10 CFR 51.22(c)(9)(i)

    The NRC staff evaluated the issue of no significant hazards consideration using the standards described in 10 CFR 50.92(c), as presented below:

    1. Does the proposed exemption involve a significant increase in the probability or consequences of an accident previously evaluated?

    Response: No.

    The proposed exemption to allow the use of AXIOM® fuel rod cladding does not involve a significant increase in the probability or consequences of an accident previously evaluated.

    For the set of previously evaluated accidents, their probability is governed by the failure or malfunction of equipment or components other than the fuel rod cladding. The fuel rod cladding itself is not an accident initiator and does not affect the accident probability. Therefore, the change in fuel rod cladding material does not affect the probability of previously evaluated accidents.

    The proposed exemption does not involve a significant increase in the consequences of previously evaluated accidents. This conclusion is demonstrated by the analysis submitted by the licensee in support of the proposed use of AXIOM® cladding that the NRC staff has reviewed in support of the proposed license amendment. The licensee's analysis shows that fuel clad with AXIOM® material performs comparably to fuel cladding materials that have been used previously. This satisfies the acceptance criteria in 10 CFR 50.46(b) for the LOCA event.

    Therefore, the proposed exemption does not involve a significant increase in the probability or consequences of an accident previously evaluated.

    2. Does the proposed exemption create the possibility of a new or different kind of accident from any accident previously evaluated?

    Response: No.

    The use of AXIOM® fuel rod cladding does not create the possibility of a new or different kind of accident from any previously evaluated. The fuel rod cladding is not an accident initiator. The use of AXIOM® cladding has been assessed by the licensee and vendor, and it has been found to exhibit comparable or enhanced behavior relative to Optimized ZIRCLO cladding material specifically identified in 10 CFR 50.46. The NRC staff has previously reviewed this information in its safety evaluation approving TR WCAP-18546NP-A. Use of Westinghouse fuel with AXIOM® cladding in the Turkey Point reactor core is compatible with the plant design and does not introduce any new safety functions for plant structures, systems, or components. Furthermore, the introduction of AXIOM® cladding does not affect any accident mitigation systems and does not introduce any new accident initiation methods.

    Therefore, the proposed exemption does not create the possibility of a new or different kind of accident from any previously evaluated.

    3. Does the proposed exemption involve a significant reduction in a margin of safety?

    Response: No.

    The proposed exemption does not involve a significant reduction in the margin of safety. The licensee's analysis of the spectrum of postulated LOCA events for fuel rods clad with AXIOM® exhibits results comparable to those for the fuel currently in use at Turkey Point for the small-break and the large-break LOCA events. Furthermore, the fuel vendor has generically evaluated the performance of AXIOM® cladding relative to the zircaloy cladding specifically identified in 10 CFR 50.46. The vendor concluded that the performance of the AXIOM® cladding material is quite similar to or enhanced relative to Optimized ZIRCLO cladding material The NRC staff has performed a review of these conclusions and documented in its safety evaluation on TR WCAP-18546NP-A that the AXIOM® material properties and mechanical design methodology are in accordance with applicable regulations and regulatory guidance.

    Therefore, the proposed exemption does not involve a significant reduction in a margin of safety.

    The NRC staff concludes that the proposed exemption presents no significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and, accordingly, a finding of no significant hazards consideration is justified ( i.e., satisfies the provision of 10 CFR 51.22(c)(9)(i)).

    Requirements in 10 CFR 51.22(c)(9)(ii)

    The proposed exemption would allow the use of AXIOM® fuel rod cladding material in the reactors. AXIOM cladding has similar properties and performance characteristics as the currently licensed optimized ZIRLO cladding. Therefore, the use of the AXIOM® fuel rod cladding material will not significantly change the types of effluents that may be released offsite, or significantly increase the amount of effluents that may be released offsite. Therefore, the provision of 10 CFR 51.22(c)(9)(ii) is satisfied.

    Requirements in 10 CFR 51.22(c)(9)(iii)

    The proposed exemption would allow the use of the AXIOM® fuel rod cladding material in the reactors. AXIOM cladding has similar properties and performance characteristics as the currently licensed optimized ZIRLO cladding. Therefore, the use of the AXIOM® fuel rod cladding material will not significantly increase individual occupational radiation exposure, or significantly increase cumulative occupational radiation exposure. Therefore, the provision of 10 CFR 51.22(c)(9)(iii) is satisfied.

    The NRC staff concludes that the proposed exemption meets the eligibility criteria for the categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, in accordance with 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the NRC's proposed granting of this exemption.

    IV. Conclusions

    Accordingly, the Commission has determined that, pursuant to 10 CFR 50.12, the exemption is authorized by law, will not present an undue risk to the public health and safety, and is consistent with the common defense and security. Also, special circumstances are present. Therefore, the Commission hereby grants FPL an exemption from the specific requirements of 10 CFR 50.46 for use of AXIOM® fuel rod cladding.

    Dated: September 13, 2024.

    For the Nuclear Regulatory Commission.

    /RA/

    Bo M. Pham,

    Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulations.

    [FR Doc. 2024-21500 Filed 9-19-24; 8:45 am]

    BILLING CODE 7590-01-P

Document Information

Published:
09/20/2024
Department:
Nuclear Regulatory Commission
Entry Type:
Notice
Action:
Notice; issuance.
Document Number:
2024-21500
Dates:
The exemption was issued on September 13, 2024.
Pages:
77199-77201 (3 pages)
Docket Numbers:
Docket Nos. 50-250 and 50-251, NRC-2024-0142
PDF File:
2024-21500.pdf