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
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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
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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
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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
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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).
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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
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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
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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
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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:
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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]
=======================================================================
-----------------------------------------------------------------------
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