Union Electric Company, dba Ameren Missouri; Callaway Plant; Unit No. 1, 71381-71383 [2023-22783]

Download as PDF ddrumheller on DSK120RN23PROD with NOTICES1 Federal Register / Vol. 88, No. 198 / Monday, October 16, 2023 / Notices must require a manual reset before the contactor can be closed. (11) Fail-safe ground check circuits shall cause the contractor to open when either the ground or pilot wire is broken. (12) A monthly examination shall be conducted on each circuit to ensure proper operation of the contactor. (13) The monthly examination shall include activating undervoltage, ground fault, and ground monitor trip devices. The results of the contactor test shall be recorded with the required circuit breaker monthly tests. (b) The petitioner shall use a Variable Frequency Drive (VFD) in series with a circuit breaker instead of a circuit breaker alone. The circuit breaker shall provide short circuit protection. A ground fault relay will provide grounded phase protection which will cause the circuit breaker to open. The VFD shall provide protection from undervoltage and overcurrent. (1) The VFD shall be rated for the maximum voltage of the circuit being protected. (2) The VFD shall be rated for the continuous full load current of the utilization equipment. (3) The nominal voltage of the control circuit(s) shall not exceed 120 volts. (4) The VFD shall provide undervoltage protection. The VFD shall trip at 55 percent of the nominal voltage based on the parameter settings in the VFD that shall de-energize the output of the VFD. (5) The VFD shall provide overcurrent protection to the connected load. The VFD shall use an internal algorithm to protect the equipment based on a rated load. The VFD shall calculate the motor temperature based on current draw over time. If the motor temperature reaches the setpoint for the defined time, the VFD shall fault indicating a motor overload. This shall be a latching fault requires a manual reset. (6) A circuit breaker shall provide short circuit protection for systems using a VFD. A ground fault relay shall provide grounded phase protection by causing the breaker to open. (7) The VFD shall be located in the same main enclosure as the circuit breaker. (8) Each circuit breaker installed in series with a VFD shall be equipped with devices to provide short-circuit protection for each piece of equipment. (9) Ground fault and ground monitor trips shall not automatically reset and shall require a manual reset before the VFD would turn the output on. (10) Fail-safe ground check circuits shall cause the breaker to open when VerDate Sep<11>2014 17:03 Oct 13, 2023 Jkt 262001 either the ground or pilot wire is broken. (11) A monthly examination shall be conducted on each circuit to ensure proper operation of the breaker and VFD. (c) Within 60 days after this proposed decision and order is granted, the petitioner shall submit proposed revisions to its part 48 training plant to the appropriate MSHA District Official(s), specifying task training for all miners who are assigned to work in any pertinent area. (d) The training shall include the purpose of the contractor systems and VFD systems, the potential hazards of working on or near belt conveyors and belt conveyor drives, and the requirements of 30 CFR 75.1725(c) and (d). (e) The requirements of 30 CFR 48.3 for approval of proposed revisions to existing approved training plans shall apply. The petitioner provided documentation to include typical control schemes, contactor specifications, VFD specifications, breaker specifications, ground monitor specifications, ground fault relay specifications, and coupler specifications in support of their petition. The petitioner asserts that the alternate method proposed will at all times guarantee no less than the same measure of protection afforded the miners under the mandatory standard. Song-ae Aromie Noe, Director, Office of Standards, Regulations, and Variances. [FR Doc. 2023–22742 Filed 10–13–23; 8:45 am] BILLING CODE 4520–43–P NATIONAL SCIENCE FOUNDATION Sunshine Act Meetings The National Science Board’s Committee on Oversight hereby gives notice of the scheduling of a teleconference for the transaction of National Science Board business pursuant to the NSF Act and the Government in the Sunshine Act. TIME AND DATE: Wednesday, October 18, 2023, from 10:30–11:30 a.m. EDT. PLACE: This meeting will be via videoconference through the National Science Foundation, 2415 Eisenhower Avenue, Alexandria, VA 22314. STATUS: Closed. MATTERS TO BE CONSIDERED: The agenda is: Committee Chair’s opening remarks regarding the agenda; Presentation and PO 00000 Frm 00049 Fmt 4703 Sfmt 4703 71381 discussion of the Results of NSF Pilots to Improve Reviewer Training. CONTACT PERSON FOR MORE INFORMATION: Point of contact for this meeting is: Chris Blair, cblair@nsf.gov, 703–292– 7000. Meeting information and updates may be found at www.nsf.gov/nsb. Christopher Blair, Executive Assistant to the National Science Board Office. [FR Doc. 2023–22911 Filed 10–12–23; 4:15 pm] BILLING CODE 7555–01–P NUCLEAR REGULATORY COMMISSION [Docket No. 50–483; NRC–2023–0158] Union Electric Company, dba Ameren Missouri; Callaway Plant; Unit No. 1 Nuclear Regulatory Commission. ACTION: Exemption; issuance. AGENCY: The U.S. Nuclear Regulatory Commission (NRC) has issued an exemption in response to an exemption request from Union Electric Company doing business as Ameren Missouri (the licensee) submitted by letter dated October 12, 2022, as supplemented by letters dated December 1, 2022, May 9, 2023, June 21, 2023, and August 3, 2023. SUMMARY: The exemption was issued on October 5, 2023. ADDRESSES: Please refer to Docket ID NRC–2023–0158 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–2023–0158. 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 https://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 request for DATES: E:\FR\FM\16OCN1.SGM 16OCN1 71382 Federal Register / Vol. 88, No. 198 / Monday, October 16, 2023 / Notices the exemption was submitted by letter dated October 12, 2022 (ADAMS Package Accession No. ML22285A115), as supplemented by letters dated December 1, 2022 (ADAMS Package Accession No. ML22335A497); May 9, 2023 (ADAMS Package Accession No. ML23129A793); June 21, 2023 (ADAMS Accession No. ML23172A145); and August 3, 2023 (ADAMS Package Accession No. ML23215A196). • 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: Mahesh Chawla, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001, telephone: 301–415– 8371; email: Mahesh.Chawla@nrc.gov. SUPPLEMENTARY INFORMATION: The text of the exemption is attached. Dated: October 11, 2023. For the Nuclear Regulatory Commission. Mahesh L. Chawla, Project Manager, Plant Licensing Branch 4, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation. Attachment—Exemption Nuclear Regulatory Commission Docket No. 50–483 Union Electric Company Callaway Plant, Unit No. 1 Exemption ddrumheller on DSK120RN23PROD with NOTICES1 I. Background Union Electric Company, doing business as (dba) as Ameren Missouri (the licensee), is the holder of Renewed Facility Operating License No. NPF–30, which authorizes operation of the Callaway Plant, Unit No. 1 (Callaway). 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 a pressurized-water reactor (PWR) located in Callaway County, Missouri. II. Request/Action By letter dated October 12, 2022 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML22285A115), as supplemented by letters dated December 1, 2022; May 9, 2023; June 21, 2023; and August 3, 2023 VerDate Sep<11>2014 17:03 Oct 13, 2023 Jkt 262001 (ML22335A497, ML23129A793, ML23172A145, and ML23215A196, respectively), Ameren Missouri, submitted a license amendment request (LAR) for Callaway, proposing to load a limited number of Framatome GAIA fuel assemblies starting in operating cycle 27 to obtain incore performance data and acquire operational experience associated with the GAIA fuel design. Pursuant to title 10 of the Code of Federal Regulations (10 CFR) section 50.12, ‘‘Specific exemptions,’’ the licensee also requested an exemption from certain requirements of 10 CFR 50.46, ‘‘Acceptance criteria for emergency core cooling systems,’’ and 10 CFR part 50, appendix K, ‘‘ECCS [Emergency Core Cooling Systems] Evaluation Models,’’ for Callaway in enclosure 2 to the LAR dated October 12, 2022. This exemption request relates solely to the specific types of cladding materials for which 10 CFR 50.46 and 10 CFR part 50, appendix K, are expressly applicable, namely zircaloy and ZIRLOTM. Since these regulations specifically apply only to zircaloy and ZIRLOTM, an exemption would be required to apply them to fuel clad with other materials, in this case Framatome M5®. Therefore, the licensee has requested such an exemption to support the introduction of Framatome GAIA fuel with the M5® cladding. The proposed request would not exempt Callaway from requirements of 10 CFR 50.46 or 10 CFR part 50, appendix K, regarding acceptance criteria, evaluation model features and documentation, reporting of changes or errors, etc. This exemption request is specific to the M5® cladding material exemption request only. The technical analysis necessary to support proposed loading of a limited number of Framatome GAIA fuel assemblies starting in operating cycle 27 is documented in the safety evaluation (SE) for the related LAR (ML23240A369). III. Discussion Pursuant to 10 CFR 50.12, the licensee requested an exemption from the requirements of 10 CFR 50.46, and appendix K to 10 CFR part 50. The proposed exemption request would permit application of the requirements of 10 CFR 50.46 and appendix K to 10 CFR part 50 to fuel rods clad with M5® at Callaway. The technical basis for the use of fuel clad with M5® in PWRs is documented in Topical Report (TR) BAW–10227P–A, Revision 1, ‘‘Evaluation of Advanced Cladding and Structural Material (M5) in PWR Reactor Fuel,’’ dated June 2003 (ADAMS Package No. ML15162B043). PO 00000 Frm 00050 Fmt 4703 Sfmt 4703 This TR describes Framatome’s evaluation for the use of the M5® alloy in PWR fuel assemblies as a replacement for Zircaloy-4. This TR discusses material properties of M5, as well as its behavior under normal operation, anticipated transients, and postulated accident conditions. The regulation in 10 CFR 50.46(a)(1)(i) states, in part: 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 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 clad with materials other than zircaloy or ZIRLOTM requires an exemption from this section of the regulations. Paragraph I.A.5, ‘‘Metal—Water Reaction Rate,’’ of appendix K to 10 CFR part 50 states, in part: The rate of energy release, hydrogen generation, and cladding oxidation from the metal/water reaction shall be calculated using the Baker-Just equation (Baker, L., Just, L.C., ‘‘Studies of Metal Water Reactions at High Temperatures, III. Experimental and Theoretical Studies of the Zirconium-Water Reaction,’’ [Argonne National Laboratory] ANL–6548, page 7, May 1962). The requirement for using the BakerJust equation in appendix K-conformant loss-of-coolant accident (LOCA) evaluation models presume use of zircaloy- or ZIRLOTM-clad fuel rods. Therefore, application of 10 CFR part 50, appendix K to cladding materials other than zircaloy or ZIRLOTM also requires an exemption. Pursuant to 10 CFR 50.12, the Commission may grant exemption from requirements of the regulations in 10 CFR part 50 provided that (1) the exemption is authorized by law, (2) the exemption will not present an undue risk to the public health and safety, (3) the exemption is consistent with the common defense and security, and (4) special circumstances, as defined in 10 CFR 50.12(a)(2), are present. The licensee’s submittal identifies that the special circumstance associated with its exemption request is that restricting application of 10 CFR 50.46 and appendix K to 10 CFR part 50 to fuels E:\FR\FM\16OCN1.SGM 16OCN1 Federal Register / Vol. 88, No. 198 / Monday, October 16, 2023 / Notices clad with only zircaloy or ZIRLOTM is not necessary to achieve the purpose of these regulations. ddrumheller on DSK120RN23PROD with NOTICES1 A. The Exemption Is Authorized by Law The NRC has 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 Callaway is clad with a zirconium-based alloy that is not expressly within the scope of 10 CFR 50.46 and 10 CFR part 50, appendix K. However, the NRC staff considers all other aspects of these regulations (e.g., acceptance criteria, prescribed methods, reporting requirements) applicable to the M5® cladding material, and the licensee states that it will ensure that these regulations are satisfied for operation with fuel clad with M5®. 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 Commission’s regulations. Therefore, the exemption is authorized by law. B. The Exemption Presents No Undue Risk to Public Health and Safety As summarized in the staff’s safety evaluation supporting this exemption request (ML23234A152 (Enclosure 2)), the NRC-approved Topical Report BAW–10227P–A, Revision 1, which concerns the properties of the M5® alloy, provides assurance that predicted chemical, thermal, and mechanical characteristics of M5®-alloy cladding are acceptable under normal operation, anticipated transients, and postulated accidents. The NRC staff finds that by utilizing the methods and properties in NRC-approved TR (i.e., BAW–10227P– A), the licensee meets the acceptance criteria and analytical methods in 10 CFR 50.46 and appendix K to 10 CFR part 50, and thus, ensures acceptable safety margins for fuel clad with M5® that are consistent with those the NRC has established for zircaloy and ZIRLOTM. Callaway cores involving M5® cladding will continue to be subject to the operating limits specified in the technical specifications (TSs) and core operating limits report. Thus, granting this exemption request does not pose undue risk to public health and safety. C. The Exemption Is Consistent With the Common Defense and Security The proposed exemption will allow the licensee to use an enhanced fuel rod cladding material relative to the zircaloy VerDate Sep<11>2014 17:03 Oct 13, 2023 Jkt 262001 material for which the requirements of 10 CFR 50.46 and 10 CFR part 50, appendix K were originally established. In addition to its review of the exemption request, the NRC staff has evaluated all licensing-basis changes necessary to support loading fuel clad with M5® in a separate SE for the related license amendment request for fuel transition. Based on these reviews, the NRC staff concludes that the use of M5® fuel rod cladding at Callaway will not significantly affect plant operations and is therefore consistent with the common defense and security. D. Special Circumstances Neither 10 CFR 50.46 nor 10 CFR part 50, appendix K explicitly applies to fuel clad with M5®. However, the underlying purpose of 10 CFR 50.46 and 10 CFR part 50, appendix K is to provide requirements capable of ensuring adequate core cooling following the most limiting postulated loss-of-coolant accident. As discussed above, Framatome has demonstrated in an NRC-approved TR (i.e., BAW– 10227P–A) that application of the acceptance criteria and analytical methods required in 10 CFR 50.46 and 10 CFR part 50, appendix K to fuel clad with M5® is acceptable. 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 Callaway. Therefore, strict application of the material-specific requirements for fuel cladding in 10 CFR 50.46 and 10 CFR part 50, appendix K 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 to fuel clad with M5® at Callaway would be consistent with the underlying regulatory purpose. E. Supplemental Information For more technical details, refer to the SE associated with this exemption under ML23234A152 (Enclosure 2). F. Environmental Considerations As discussed in the SE associated with this exemption, the NRC staff determined that the exemption discussed herein meets the eligibility criteria for the categorical exclusion set forth in 10 CFR 51.22(c)(9) because it is related to a requirement concerning the installation or use of facility components located within the restricted area, as defined in 10 CFR part 20, and the granting of this exemption involves: (i) no significant hazards consideration, (ii) no significant PO 00000 Frm 00051 Fmt 4703 Sfmt 4703 71383 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. 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 Union Electric Company dba Ameren Missouri a one-time exemption from the requirements of 10 CFR 50.46 and 10 CFR part 50, appendix K. The proposed exemption request would permit application of the requirements of 10 CFR 50.46 and appendix K to fuel rods clad with M5® at Callaway. As stated above, this exemption relates solely to the cladding material specified in these regulations. Dated at Rockville, Maryland, this 5th day of October, 2023 For the Nuclear Regulatory Commission. Bo M. Pham, Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation. [FR Doc. 2023–22783 Filed 10–13–23; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [NRC–2023–0001] Sunshine Act Meetings Weeks of October 16, 23, 30, November 6, 13, 20, 2023. The schedule for Commission meetings is subject to change on short notice. The NRC Commission Meeting Schedule can be found on the internet at: https:// www.nrc.gov/public-involve/publicmeetings/schedule.html. PLACE: The NRC provides reasonable accommodation to individuals with disabilities where appropriate. If you need a reasonable accommodation to participate in these public meetings or need this meeting notice or the transcript or other information from the public meetings in another format (e.g., braille, large print), please notify Anne Silk, NRC Disability Program Specialist, TIME AND DATE: E:\FR\FM\16OCN1.SGM 16OCN1

Agencies

[Federal Register Volume 88, Number 198 (Monday, October 16, 2023)]
[Notices]
[Pages 71381-71383]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2023-22783]


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NUCLEAR REGULATORY COMMISSION

[Docket No. 50-483; NRC-2023-0158]


Union Electric Company, dba Ameren Missouri; Callaway Plant; Unit 
No. 1

AGENCY: Nuclear Regulatory Commission.

ACTION: Exemption; issuance.

-----------------------------------------------------------------------

SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) has issued an 
exemption in response to an exemption request from Union Electric 
Company doing business as Ameren Missouri (the licensee) submitted by 
letter dated October 12, 2022, as supplemented by letters dated 
December 1, 2022, May 9, 2023, June 21, 2023, and August 3, 2023.

DATES: The exemption was issued on October 5, 2023.

ADDRESSES: Please refer to Docket ID NRC-2023-0158 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-2023-0158. Address 
questions about Docket IDs in Regulations.gov to Stacy Schumann; 
telephone: 301-415-0624; email: [email protected]. 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 https://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 [email protected]. The request for

[[Page 71382]]

the exemption was submitted by letter dated October 12, 2022 (ADAMS 
Package Accession No. ML22285A115), as supplemented by letters dated 
December 1, 2022 (ADAMS Package Accession No. ML22335A497); May 9, 2023 
(ADAMS Package Accession No. ML23129A793); June 21, 2023 (ADAMS 
Accession No. ML23172A145); and August 3, 2023 (ADAMS Package Accession 
No. ML23215A196).
     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 
[email protected] 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: Mahesh Chawla, Office of Nuclear 
Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 
20555-0001, telephone: 301-415-8371; email: [email protected].

SUPPLEMENTARY INFORMATION: The text of the exemption is attached.

    Dated: October 11, 2023.

    For the Nuclear Regulatory Commission.
Mahesh L. Chawla,
Project Manager, Plant Licensing Branch 4, Division of Operating 
Reactor Licensing, Office of Nuclear Reactor Regulation.

Attachment--Exemption

Nuclear Regulatory Commission

Docket No. 50-483

Union Electric Company Callaway Plant, Unit No. 1

Exemption

I. Background

    Union Electric Company, doing business as (dba) as Ameren Missouri 
(the licensee), is the holder of Renewed Facility Operating License No. 
NPF-30, which authorizes operation of the Callaway Plant, Unit No. 1 
(Callaway). 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 a pressurized-water reactor (PWR) located in Callaway 
County, Missouri.

II. Request/Action

    By letter dated October 12, 2022 (Agencywide Documents Access and 
Management System (ADAMS) Accession No. ML22285A115), as supplemented 
by letters dated December 1, 2022; May 9, 2023; June 21, 2023; and 
August 3, 2023 (ML22335A497, ML23129A793, ML23172A145, and ML23215A196, 
respectively), Ameren Missouri, submitted a license amendment request 
(LAR) for Callaway, proposing to load a limited number of Framatome 
GAIA fuel assemblies starting in operating cycle 27 to obtain incore 
performance data and acquire operational experience associated with the 
GAIA fuel design. Pursuant to title 10 of the Code of Federal 
Regulations (10 CFR) section 50.12, ``Specific exemptions,'' the 
licensee also requested an exemption from certain requirements of 10 
CFR 50.46, ``Acceptance criteria for emergency core cooling systems,'' 
and 10 CFR part 50, appendix K, ``ECCS [Emergency Core Cooling Systems] 
Evaluation Models,'' for Callaway in enclosure 2 to the LAR dated 
October 12, 2022.
    This exemption request relates solely to the specific types of 
cladding materials for which 10 CFR 50.46 and 10 CFR part 50, appendix 
K, are expressly applicable, namely zircaloy and ZIRLOTM. 
Since these regulations specifically apply only to zircaloy and 
ZIRLOTM, an exemption would be required to apply them to 
fuel clad with other materials, in this case Framatome M5[supreg]. 
Therefore, the licensee has requested such an exemption to support the 
introduction of Framatome GAIA fuel with the M5[supreg] cladding. The 
proposed request would not exempt Callaway from requirements of 10 CFR 
50.46 or 10 CFR part 50, appendix K, regarding acceptance criteria, 
evaluation model features and documentation, reporting of changes or 
errors, etc.
    This exemption request is specific to the M5[supreg] cladding 
material exemption request only. The technical analysis necessary to 
support proposed loading of a limited number of Framatome GAIA fuel 
assemblies starting in operating cycle 27 is documented in the safety 
evaluation (SE) for the related LAR (ML23240A369).

III. Discussion

    Pursuant to 10 CFR 50.12, the licensee requested an exemption from 
the requirements of 10 CFR 50.46, and appendix K to 10 CFR part 50. The 
proposed exemption request would permit application of the requirements 
of 10 CFR 50.46 and appendix K to 10 CFR part 50 to fuel rods clad with 
M5[supreg] at Callaway.
    The technical basis for the use of fuel clad with M5[supreg] in 
PWRs is documented in Topical Report (TR) BAW-10227P-A, Revision 1, 
``Evaluation of Advanced Cladding and Structural Material (M5) in PWR 
Reactor Fuel,'' dated June 2003 (ADAMS Package No. ML15162B043). This 
TR describes Framatome's evaluation for the use of the M5[supreg] alloy 
in PWR fuel assemblies as a replacement for Zircaloy-4. This TR 
discusses material properties of M5, as well as its behavior under 
normal operation, anticipated transients, and postulated accident 
conditions.
    The regulation in 10 CFR 50.46(a)(1)(i) states, in part:

    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 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 clad with 
materials other than zircaloy or ZIRLOTM requires an 
exemption from this section of the regulations.
    Paragraph I.A.5, ``Metal--Water Reaction Rate,'' of appendix K to 
10 CFR part 50 states, in part:

    The rate of energy release, hydrogen generation, and cladding 
oxidation from the metal/water reaction shall be calculated using 
the Baker-Just equation (Baker, L., Just, L.C., ``Studies of Metal 
Water Reactions at High Temperatures, III. Experimental and 
Theoretical Studies of the Zirconium-Water Reaction,'' [Argonne 
National Laboratory] ANL-6548, page 7, May 1962).

    The requirement for using the Baker-Just equation in appendix K-
conformant loss-of-coolant accident (LOCA) evaluation models presume 
use of zircaloy- or ZIRLOTM-clad fuel rods. Therefore, 
application of 10 CFR part 50, appendix K to cladding materials other 
than zircaloy or ZIRLOTM also requires an exemption.
    Pursuant to 10 CFR 50.12, the Commission may grant exemption from 
requirements of the regulations in 10 CFR part 50 provided that (1) the 
exemption is authorized by law, (2) the exemption will not present an 
undue risk to the public health and safety, (3) the exemption is 
consistent with the common defense and security, and (4) special 
circumstances, as defined in 10 CFR 50.12(a)(2), are present. The 
licensee's submittal identifies that the special circumstance 
associated with its exemption request is that restricting application 
of 10 CFR 50.46 and appendix K to 10 CFR part 50 to fuels

[[Page 71383]]

clad with only zircaloy or ZIRLOTM is not necessary to 
achieve the purpose of these regulations.

A. The Exemption Is Authorized by Law

    The NRC has 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 Callaway is clad 
with a zirconium-based alloy that is not expressly within the scope of 
10 CFR 50.46 and 10 CFR part 50, appendix K. However, the NRC staff 
considers all other aspects of these regulations (e.g., acceptance 
criteria, prescribed methods, reporting requirements) applicable to the 
M5[supreg] cladding material, and the licensee states that it will 
ensure that these regulations are satisfied for operation with fuel 
clad with M5[supreg]. 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 
Commission's regulations. Therefore, the exemption is authorized by 
law.

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

    As summarized in the staff's safety evaluation supporting this 
exemption request (ML23234A152 (Enclosure 2)), the NRC-approved Topical 
Report BAW-10227P-A, Revision 1, which concerns the properties of the 
M5[supreg] alloy, provides assurance that predicted chemical, thermal, 
and mechanical characteristics of M5[supreg]-alloy cladding are 
acceptable under normal operation, anticipated transients, and 
postulated accidents. The NRC staff finds that by utilizing the methods 
and properties in NRC-approved TR (i.e., BAW-10227P-A), the licensee 
meets the acceptance criteria and analytical methods in 10 CFR 50.46 
and appendix K to 10 CFR part 50, and thus, ensures acceptable safety 
margins for fuel clad with M5[supreg] that are consistent with those 
the NRC has established for zircaloy and ZIRLOTM. Callaway 
cores involving M5[supreg] cladding will continue to be subject to the 
operating limits specified in the technical specifications (TSs) and 
core operating limits report. Thus, granting this exemption request 
does not pose undue risk to public health and safety.

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

    The proposed 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 and 10 CFR part 50, appendix K were 
originally established. In addition to its review of the exemption 
request, the NRC staff has evaluated all licensing-basis changes 
necessary to support loading fuel clad with M5[supreg] in a separate SE 
for the related license amendment request for fuel transition. Based on 
these reviews, the NRC staff concludes that the use of M5[supreg] fuel 
rod cladding at Callaway will not significantly affect plant operations 
and is therefore consistent with the common defense and security.

D. Special Circumstances

    Neither 10 CFR 50.46 nor 10 CFR part 50, appendix K explicitly 
applies to fuel clad with M5[supreg]. However, the underlying purpose 
of 10 CFR 50.46 and 10 CFR part 50, appendix K is to provide 
requirements capable of ensuring adequate core cooling following the 
most limiting postulated loss-of-coolant accident. As discussed above, 
Framatome has demonstrated in an NRC-approved TR (i.e., BAW-10227P-A) 
that application of the acceptance criteria and analytical methods 
required in 10 CFR 50.46 and 10 CFR part 50, appendix K to fuel clad 
with M5[supreg] is acceptable. 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 Callaway. Therefore, strict application of the 
material-specific requirements for fuel cladding in 10 CFR 50.46 and 10 
CFR part 50, appendix K 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 to fuel clad with M5[supreg] at Callaway would be 
consistent with the underlying regulatory purpose.

E. Supplemental Information

    For more technical details, refer to the SE associated with this 
exemption under ML23234A152 (Enclosure 2).

F. Environmental Considerations

    As discussed in the SE associated with this exemption, the NRC 
staff determined that the exemption discussed herein meets the 
eligibility criteria for the categorical exclusion set forth in 10 CFR 
51.22(c)(9) because it is related to a requirement concerning the 
installation or use of facility components located within the 
restricted area, as defined in 10 CFR part 20, and 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.

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 Union Electric Company dba 
Ameren Missouri a one-time exemption from the requirements of 10 CFR 
50.46 and 10 CFR part 50, appendix K. The proposed exemption request 
would permit application of the requirements of 10 CFR 50.46 and 
appendix K to fuel rods clad with M5[supreg] at Callaway. As stated 
above, this exemption relates solely to the cladding material specified 
in these regulations.

    Dated at Rockville, Maryland, this 5th day of October, 2023

    For the Nuclear Regulatory Commission.

Bo M. Pham,

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

[FR Doc. 2023-22783 Filed 10-13-23; 8:45 am]
BILLING CODE 7590-01-P


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