Southern Nuclear Operating Company; Vogtle Electric Generating Plant, Units 1 and 2, 52218-52220 [2023-16753]
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Federal Register / Vol. 88, No. 150 / Monday, August 7, 2023 / Notices
NRC staff has determined that SNC’s
evaluation of coated cladding emissivity and
its effect on loss-of-coolant accident peak
clad temperature (PCT) is acceptable, because
data was provided demonstrating no
significant difference in PCT, (3) the NRC
staff has determined that SNC’s evaluation of
ADOPT fuel pellets in the LTAs is
acceptable, because there will be no
reduction in fuel performance and the
applicable limitations and conditions have
been implicitly addressed, and (4) the
number of rods with enrichments exceeding
five weight-percent Uranium 235 is small
compared to the total number of fuel rods.
See the NRC safety evaluation
(ML23093A028) for further details.
C. The Exemption Is Consistent With the
Common Defense and Security
The proposed exemption would allow the
use of four LTAs with a variant cladding
material. This change to the plant core
configuration has no impact on security
issues. Special nuclear material in the LTAs
will continue to be handled and controlled
in accordance with applicable regulations.
Therefore, the common defense and security
is not impacted by this exemption.
ddrumheller on DSK120RN23PROD with NOTICES1
D. Special Circumstances
Special circumstances, in accordance with
10 CFR 50.12(a)(2)(ii), are present whenever
application of the regulation in the particular
circumstances would not serve the
underlying purpose of the rule or is not
necessary to achieve the underlying purpose
of the rule. The underlying purpose of 10
CFR part 50, Appendix K, Section I.A.5 is to
establish acceptance criteria for ECCS
performance. In the safety evaluation (SE)
contained in ML23093A028 for the license
amendment request, the NRC staff evaluated
for Vogtle, Unit 2, four LTAs that
demonstrated the acceptability of the AXIOM
cladding under LOCA conditions. The
unique features of the LTAs were evaluated
for effects on the LOCA analyses. The results
showed that the LTAs would not adversely
affect ECCS performance. Since the BakerJust equation presumes the use of zircaloy or
ZIRLO clad fuel, strict application of this
provision of the rule would not permit use
of the equation for AXIOM cladding for
determining acceptable fuel performance.
Therefore, the NRC staff concludes that
application of the cladding material
applicability requirements of the Baker-Just
equation of 10 CFR part 50, Appendix K in
this particular circumstance is not necessary
for the licensee to achieve the underlying
purpose of the rule.
E. Environmental Considerations
With respect to its impact on the quality
of the human environment, the NRC has
determined that the issuance of the
exemption discussed herein meets the
eligibility criteria for categorical exclusion
set forth in 10 CFR 51.22(c)(9). The NRC
staff’s determination that all of the criteria for
this categorical exclusion are met is as
follows:
The regulation 10 CFR 51.22(c)(9) states:
Issuance of an amendment to a permit or
license for a reactor under part 50 or part 52
of this chapter that changes a requirement or
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issuance of an exemption from a
requirement, with respect to installation or
use of a facility component located within
the restricted area, as defined in part 20 of
this chapter; or the issuance of an
amendment to a permit or license for a
reactor under part 50 or part 52 of this
chapter that changes an inspection or a
surveillance requirement; provided that: (i)
The amendment or exemption involves no
significant hazards consideration; (ii) There
is no significant change in the types or
significant increase in the amounts of any
effluents that may be released offsite; and
(iii). There is no significant increase in
individual or cumulative occupational
radiation exposure.
Staff Analysis: The exemption is from
requirements with respect to the installation
or use of facility components located within
the restricted area as defined in 10 CFR part
20. The criteria for determining whether an
action involves a significant hazards
consideration are found in 10 CFR 50.92. The
proposed action involves installed four
LTAs. As stated in the evaluation in
ML23093A028, the Commission has
previously issued a proposed finding that the
amendments involve no significant hazards
consideration, published in the Federal
Register on November 8, 2022 (87 FR 67508),
and there has been no public comment on
such finding.
The proposed action involves installing
four LTAs, and as the NRC staff evaluated
under the SE contained in ML23093A028,
this action does not involve any significant
changes in the types or significant increase
in the amounts of any effluents that may be
released offsite.
The proposed action involves installing
four LTAs, and as the NRC staff evaluated
under the SE contained in ML23093A028,
this action does not involve any significant
increase in individual or cumulative
occupational exposure.
Based on the above, 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
issuance of this exemption.
IV. Conclusions
Accordingly, the NRC 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,
pursuant to 10 CFR 50.12(a)(2)(ii), are
present. Therefore, the NRC hereby grants
SNC an exemption from the requirements of
10 CFR part 50, appendix K to allow the use
of AXIOM fuel rod cladding material in LTAs
7ST1, 7ST2, 7ST3, and 7ST4 for up to two
cycles of operation at Vogtle, Unit 2.
Dated at Rockville, Maryland, this 1st day
of August, 2023.
For the Nuclear Regulatory Commission.
/RA/
Bo M. Pham,
PO 00000
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Director, Division of Operating Reactor
Licensing, Office of Nuclear Reactor
Regulation.
[FR Doc. 2023–16755 Filed 8–4–23; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[Docket Nos. 50–424 and 50–425; NRC–
2023–0093]
Southern Nuclear Operating Company;
Vogtle Electric Generating Plant, Units
1 and 2
Nuclear Regulatory
Commission.
ACTION: Exemption; issuance.
AGENCY:
The U.S. Nuclear Regulatory
Commission (NRC) has issued an
exemption in response to a request
dated June 30, 2022, as supplemented
by letters dated September 13, 2022, and
January 20 and May 5, 2023, from
Southern Nuclear Operating Company
to allow the use of lead test assemblies
(LTAs) 7ST1, 7ST2, 7ST3, and 7ST4,
each with four fuel rods with a
maximum nominal Uranium 235 (U–
235) enrichment of up to six percent by
weight for up to two cycles of operation
at Vogtle Electric Generating Plant, Unit
2, and to receive, inspect, and store the
LTAs at Vogtle, Units 1 and 2.
DATES: The exemption was issued on
August 1, 2023.
ADDRESSES: Please refer to Docket ID
NRC–2023–0093 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–2023–0093. 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 ADAMS
accession number for each document
SUMMARY:
E:\FR\FM\07AUN1.SGM
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Federal Register / Vol. 88, No. 150 / Monday, August 7, 2023 / Notices
referenced (if it 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: John
G. Lamb, Office of Nuclear Reactor
Regulation, U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001; telephone: 301–415–3100, email:
John.Lamb@nrc.gov.
SUPPLEMENTARY INFORMATION: The text of
the exemption is attached.
Dated: August 2, 2023.
For the Nuclear Regulatory Commission.
John G. Lamb,
Senior Project Manager, Licensing Plant
Branch 2–1, Division of Operating Reactor
Licensing, Office of Nuclear Reactor
Regulation.
Attachment—Exemption from 10 CFR
50.68(b)(7) to Allow the Use of Lead Test
Assemblies, 7ST1, 7ST2, 7ST3, and 7ST4,
each with four fuel rods with a maximum
nominal Uranium 235 (U–235) enrichment of
up to six percent by weight for up to two
cycles of operation at Vogtle, Unit 2, and to
receive, inspect, and store the LTAs at
Vogtle, Units 1 and 2.
NUCLEAR REGULATORY COMMISSION
Docket Nos. 50–424, and 50–425
Southern Nuclear Operating Company
Vogtle Electric Generating Plant, Units 1
and 2
Exemption
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I. Background
Southern Nuclear Operating Company
(SNC, the licensee) is the holder of Facility
Operating License Nos. NPF–68, and NPF–
81, for the Vogtle Electric Generating Plant
(Vogtle), Units 1 and 2, respectively. The
licenses provide, among other things, that the
licenses are subject to all rules, regulations,
and orders of the Commission now or
hereafter in effect.
The Vogtle, Units 1 and 2, consist of two
pressurized-water reactors located at the
licensee’s site in Burke County, Georgia.
II. Request/Action
By letter dated June 30, 2022 (Agencywide
Documents Access and Management System
(ADAMS) Accession No. ML22181B156), as
supplemented by letters dated September 13,
2022 (ML22256A198), and January 20
(ML23020A148) and May 5, 2023
(ML23125A269), SNC requested an
exemption to title 10 of the Code of Federal
Regulations (10 CFR), part 50, section 50.68,
‘‘Criticality accident requirements,’’
paragraph (b)(7) for Vogtle, Units 1 and 2.
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Specifically, SNC requested an exemption
from 10 CFR 50.68(b)(7) to allow the use of
lead test assemblies (LTAs) 7ST1, 7ST2,
7ST3, and 7ST4 each with four fuel rods with
a maximum nominal Uranium 235 (U–235)
enrichment of up to six percent by weight for
up to two cycles of operation at Vogtle, Unit
2, and allow receipt, inspection, and storage
of the LTAs at Vogtle, Units 1 and 2.
The regulation at 10 CFR 50.68(b)(7) states,
‘‘The maximum nominal U–235 enrichment
of the fresh fuel assemblies is limited to five
(5.0) percent by weight.’’
III. Discussion
Pursuant to 10 CFR 50.12, the NRC may,
upon application by any interested person or
upon its own initiative, grant exemptions
from the requirements of 10 CFR part 50,
including 10 CFR 50.68(b)(7) when: (1) the
exemptions are authorized by law, will not
present an undue risk to the public health or
safety, and are consistent with the common
defense and security; and (2) when special
circumstances are present. Under 10 CFR
50.12(a)(2), special circumstances include,
among other things, when application of the
specific regulation in the particular
circumstances would not serve, or is not
necessary to achieve, the underlying purpose
of the rule.
A. The Exemption is Authorized by Law
In accordance with 10 CFR 50.12, the NRC
may grant an exemption from the
requirements of 10 CFR part 50 if the
exemption is authorized by law. The
exemption requested in this instance is
authorized by law, because no other
prohibition of law exists to preclude the
activities which would be authorized by the
exemption.
This exemption would allow the licensee
to insert four LTAs each containing four fuel
rods with a maximum nominal U–235
enrichment of up to six percent by weight.
A specific nominal U–235 enrichment in 10
CFR 50.68(b)(7) is at the discretion of the
Commission consistent with its statutory
authority. No statute required the NRC to
adopt this specification. As stated above, 10
CFR 50.12 allows the Commission to grant
exemptions from the requirements of 10 CFR
part 50. The NRC staff has determined that
granting of an exemption from 10 CFR
50.68(b)(7) related to nominal U–235
enrichment of up to six percent by weight
will 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
SNC stated the following in its letter dated
June 30, 2022:
The Vogtle reactors each contain 193 fuel
assemblies. Each assembly consists of a
matrix of 264 Zircaloy, ZIRLO®[TM], or
Optimized ZIRLO®[TM] clad fuel rods with an
initial composition of natural or slightly
enriched uranium dioxide (UO2) as fuel
material, not to exceed 5 wt% [weightpercent] enrichment. The proposed change is
to load four LTAs with advanced ATF
[accident-tolerant fuel] features, including
ADOPT fuel [2], AXIOM cladding [3],
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52219
chromium coating, and four rods per LTA
with up to 6 wt% enrichment, in limiting
core locations for up to two cycles of
operation.
This exemption will not present an undue
risk to public health and safety. The analysis
performed in support of the enclosed LAR
[license amendment request] addresses the
safe storage of the LTAs. These were
evaluated using AOR [analysis of record]
plant-specific models to determine that
existing storage configurations can be used
for storage of the LTAs, with restrictions (see
Section 3 above and Section 3.12 of
Enclosure 1 [in letter dated June 30, 2022]).
Thus, the granting of this exemption request
will not pose an undue risk to public health
and safety.
The licensee’s requested exemption to
paragraph 50.68(b)(7) is for the fuel rods
enriched above 5.0 wt% U–235. Each LTA is
limited to four rods at 6.0 wt% U–235. Those
four rods add about 0.015% more U–235 to
the LTAs relative to the Vogtle new fuel
storage rack (NFSR) analysis of record (AOR)
and the Vogtle spent fuel pool (SFP) AOR
maximum enrichment of 5.0 wt% U–235.
SNC’s evaluation considered the fissile
material increase due to the higher
enrichment and that due to the higher
fraction of the theoretical density of the
ADOPT fuel. The licensee established
Technical Specifications to control the
storage of the LTAs. The NRC staff has found
that these controls provide reasonable
assurance that the four LTAs as described in
SNC’s amendment and exemption requests
will meet 10 CFR 50.68(b)(2), 10 CFR
50.68(b)(3), and 10 CFR 50.68(b)(4). See the
NRC staff evaluation (ML23093A028) for
further details. Thus, the NRC staff finds that
the requested exemption does not result in
any undue risk to the public health and
safety.
C. The Exemption is Consistent With the
Common Defense and Security
The proposed exemption would allow the
use of four LTAs, each with four fuel rods
with a nominal U–235 enrichment of up to
six percent by weight. This change to the
plant core configuration has no impact on
security issues. Special nuclear material in
the LTAs will continue to be handled and
controlled in accordance with applicable
regulations. Therefore, the common defense
and security is not impacted by this
exemption.
D. Special Circumstances
Special circumstances, in accordance with
10 CFR 50.12(a)(2)(ii), are present whenever
application of the regulation in the particular
circumstances would not serve the
underlying purpose of the rule or is not
necessary to achieve the underlying purpose
of the rule. The underlying purpose of 10
CFR 50.68 is to provide reasonable assurance
that an inadvertent criticality event will not
occur during the storage or handling of
special nuclear material at 10 CFR part 50
licenses. The preamble for the final rule
promulgating 10 CFR 50.68 (Federal
Register/Vol. 63, No. 218/Thursday,
November 12, 1998/Rules and Regulations
[[Page 63127]]) indicated that increases to the
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Federal Register / Vol. 88, No. 150 / Monday, August 7, 2023 / Notices
ddrumheller on DSK120RN23PROD with NOTICES1
enrichment limit of 5.0 wt% U–235 could be
addressed in the future. In the safety
evaluation (SE) contained in ML23093A028
for the license amendment request, the NRC
staff evaluated for Vogtle, Units 1 and 2, four
LTAs that demonstrated the acceptability of
the nominal U–235 enrichment of up to six
percent by weight of four fuel rods per LTA.
The results showed that the LTAs would not
adversely affect subcriticality in the spent
fuel pool or new fuel storage racks.
Therefore, the NRC staff concludes that
application of 10 CFR 50.68(b)(7) in this
particular circumstance is not necessary for
the licensee to achieve the underlying
purpose of the rule.
E. Environmental Considerations
With respect to its impact on the quality
of the human environment, the NRC has
determined that the issuance of the
exemption discussed herein meets the
eligibility criteria for categorical exclusion
set forth in 10 CFR 51.22(c)(9). The NRC
staff’s determination that all of the criteria for
this categorical exclusion are met is as
follows:
The regulation 10 CFR 51.22(c)(9) states:
Issuance of an amendment to a permit or
license for a reactor under part 50 or part 52
of this chapter that changes a requirement or
issuance of an exemption from a
requirement, with respect to installation or
use of a facility component located within
the restricted area, as defined in part 20 of
this chapter; or the issuance of an
amendment to a permit or license for a
reactor under part 50 or part 52 of this
chapter that changes an inspection or a
surveillance requirement; provided that: (i)
The amendment or exemption involves no
significant hazards consideration; (ii) There
is no significant change in the types or
significant increase in the amounts of any
effluents that may be released offsite; and (iii)
There is no significant increase in individual
or cumulative occupational radiation
exposure.
Staff Analysis: The exemption is from
requirements with respect to the installation
or use of facility components located within
the restricted area as defined in 10 CFR part
20. The criteria for determining whether an
action involves a significant hazards
consideration are found in 10 CFR 50.92. The
proposed action involves installed four
LTAs. As stated in the evaluation in
ML23093A028, the Commission has
previously issued a proposed finding that the
amendments involve no significant hazards
consideration, published in the Federal
Register on November 8, 2022 (87 FR 67508),
and there has been no public comment on
such finding.
The proposed action involves installing
four LTAs, and as the NRC staff evaluated
under the SE contained in ML23093A028,
this action does not involve any significant
change in the types or significant increase in
the amounts of any effluents that may be
released offsite.
The proposed action involves installing
four LTAs, and as the NRC staff evaluated
under the SE contained in ML23093A028,
this action does not involve any significant
increase in individual or cumulative
occupational exposure.
VerDate Sep<11>2014
18:58 Aug 04, 2023
Jkt 259001
Based on the above, 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
issuance of this exemption.
IV. Conclusions
Accordingly, the NRC 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,
pursuant to 10 CFR 50.12(a)(2)(ii), are
present. Therefore, the NRC hereby grants
SNC an exemption from the requirements of
10 CFR 50.68(b)(7) to allow the use of LTAs
7ST1, 7ST2, 7ST3, and 7ST4 each with four
fuel rods with a nominal U–235 enrichment
of up to six percent by weight, for up to two
cycles of operation at Vogtle, Unit 2, and
allow receipt, inspection, and storage of the
LTAs at Vogtle, Units 1 and 2.
Dated at Rockville, Maryland, this 1st day
of August, 2023.
For the Nuclear Regulatory Commission.
/RA/
Bo M. Pham,
Director, Division of Operating Reactor
Licensing, Office of Nuclear Reactor
Regulation.
[FR Doc. 2023–16753 Filed 8–4–23; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[Docket No. 50–425; NRC–2023–0091]
Southern Nuclear Operating Company;
Vogtle Electric Generating Plant, Unit 2
Nuclear Regulatory
Commission.
ACTION: Exemption; issuance.
AGENCY:
The U.S. Nuclear Regulatory
Commission (NRC) has issued an
exemption in response to a request
dated June 30, 2022, as supplemented
by letters dated September 13, 2022, and
January 20, and May 5, 2023, from
Southern Nuclear Operating Company
to allow the use of AXIOM fuel rod
cladding material in lead test assemblies
7ST1, 7ST2, 7ST3, and 7ST4, for up to
two cycles of operation at Vogtle
Electric Generating Plant, Unit 2.
DATES: The exemption was issued on
August 1, 2023.
ADDRESSES: Please refer to Docket ID
NRC–2023–0091 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:
SUMMARY:
PO 00000
Frm 00113
Fmt 4703
Sfmt 4703
• Federal Rulemaking Website: Go to
https://www.regulations.gov and search
for Docket ID NRC–2023–0091. 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 ADAMS
accession number for each document
referenced (if it 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: John
G. Lamb, Office of Nuclear Reactor
Regulation, U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001; telephone: 301–415–3100; email:
John.Lamb@nrc.gov.
SUPPLEMENTARY INFORMATION: The text of
the exemption is attached.
Dated: August 2, 2023.
For the Nuclear Regulatory Commission.
John G. Lamb,
Senior Project Manager, Plant Licensing
Branch 2–1, Division of Operator Reactor
Licensing, Office of Nuclear Reactor
Regulation.
Attachment—Exemption From 10 CFR 50.46
for Vogtle, Unit 2, To Allow the Use of
AXIOM Fuel Rod Cladding Material in Lead
Test Assemblies
Nuclear Regulatory Commission
Docket No. 50–425
Southern Nuclear Operating Company
Vogtle Electric Generating Plant, Unit 2
Exemption
I. Background
Southern Nuclear Operating Company
(SNC, the licensee) is the holder of Facility
Operating License No. NPF–81, for the Vogtle
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]]>Agencies
[Federal Register Volume 88, Number 150 (Monday, August 7, 2023)]
[Rules and Regulations]
[Pages 52218-52220]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2023-16753]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[Docket Nos. 50-424 and 50-425; NRC-2023-0093]
Southern Nuclear Operating Company; Vogtle Electric Generating
Plant, Units 1 and 2
AGENCY: Nuclear Regulatory Commission.
ACTION: Exemption; issuance.
-----------------------------------------------------------------------
SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) has issued an
exemption in response to a request dated June 30, 2022, as supplemented
by letters dated September 13, 2022, and January 20 and May 5, 2023,
from Southern Nuclear Operating Company to allow the use of lead test
assemblies (LTAs) 7ST1, 7ST2, 7ST3, and 7ST4, each with four fuel rods
with a maximum nominal Uranium 235 (U-235) enrichment of up to six
percent by weight for up to two cycles of operation at Vogtle Electric
Generating Plant, Unit 2, and to receive, inspect, and store the LTAs
at Vogtle, Units 1 and 2.
DATES: The exemption was issued on August 1, 2023.
ADDRESSES: Please refer to Docket ID NRC-2023-0093 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-2023-0093. 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 ADAMS accession number for
each document
[[Page 52219]]
referenced (if it 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
[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: John G. Lamb, Office of Nuclear
Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC
20555-0001; telephone: 301-415-3100, email: [email protected].
SUPPLEMENTARY INFORMATION: The text of the exemption is attached.
Dated: August 2, 2023.
For the Nuclear Regulatory Commission.
John G. Lamb,
Senior Project Manager, Licensing Plant Branch 2-1, Division of
Operating Reactor Licensing, Office of Nuclear Reactor Regulation.
Attachment--Exemption from 10 CFR 50.68(b)(7) to Allow the Use of Lead
Test Assemblies, 7ST1, 7ST2, 7ST3, and 7ST4, each with four fuel rods
with a maximum nominal Uranium 235 (U-235) enrichment of up to six
percent by weight for up to two cycles of operation at Vogtle, Unit 2,
and to receive, inspect, and store the LTAs at Vogtle, Units 1 and 2.
NUCLEAR REGULATORY COMMISSION
Docket Nos. 50-424, and 50-425
Southern Nuclear Operating Company
Vogtle Electric Generating Plant, Units 1 and 2
Exemption
I. Background
Southern Nuclear Operating Company (SNC, the licensee) is the
holder of Facility Operating License Nos. NPF-68, and NPF-81, for
the Vogtle Electric Generating Plant (Vogtle), Units 1 and 2,
respectively. The licenses provide, among other things, that the
licenses are subject to all rules, regulations, and orders of the
Commission now or hereafter in effect.
The Vogtle, Units 1 and 2, consist of two pressurized-water
reactors located at the licensee's site in Burke County, Georgia.
II. Request/Action
By letter dated June 30, 2022 (Agencywide Documents Access and
Management System (ADAMS) Accession No. ML22181B156), as
supplemented by letters dated September 13, 2022 (ML22256A198), and
January 20 (ML23020A148) and May 5, 2023 (ML23125A269), SNC
requested an exemption to title 10 of the Code of Federal
Regulations (10 CFR), part 50, section 50.68, ``Criticality accident
requirements,'' paragraph (b)(7) for Vogtle, Units 1 and 2.
Specifically, SNC requested an exemption from 10 CFR 50.68(b)(7)
to allow the use of lead test assemblies (LTAs) 7ST1, 7ST2, 7ST3,
and 7ST4 each with four fuel rods with a maximum nominal Uranium 235
(U-235) enrichment of up to six percent by weight for up to two
cycles of operation at Vogtle, Unit 2, and allow receipt,
inspection, and storage of the LTAs at Vogtle, Units 1 and 2.
The regulation at 10 CFR 50.68(b)(7) states, ``The maximum
nominal U-235 enrichment of the fresh fuel assemblies is limited to
five (5.0) percent by weight.''
III. Discussion
Pursuant to 10 CFR 50.12, the NRC may, upon application by any
interested person or upon its own initiative, grant exemptions from
the requirements of 10 CFR part 50, including 10 CFR 50.68(b)(7)
when: (1) the exemptions are authorized by law, will not present an
undue risk to the public health or safety, and are consistent with
the common defense and security; and (2) when special circumstances
are present. Under 10 CFR 50.12(a)(2), special circumstances
include, among other things, when application of the specific
regulation in the particular circumstances would not serve, or is
not necessary to achieve, the underlying purpose of the rule.
A. The Exemption is Authorized by Law
In accordance with 10 CFR 50.12, the NRC may grant an exemption
from the requirements of 10 CFR part 50 if the exemption is
authorized by law. The exemption requested in this instance is
authorized by law, because no other prohibition of law exists to
preclude the activities which would be authorized by the exemption.
This exemption would allow the licensee to insert four LTAs each
containing four fuel rods with a maximum nominal U-235 enrichment of
up to six percent by weight. A specific nominal U-235 enrichment in
10 CFR 50.68(b)(7) is at the discretion of the Commission consistent
with its statutory authority. No statute required the NRC to adopt
this specification. As stated above, 10 CFR 50.12 allows the
Commission to grant exemptions from the requirements of 10 CFR part
50. The NRC staff has determined that granting of an exemption from
10 CFR 50.68(b)(7) related to nominal U-235 enrichment of up to six
percent by weight will 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
SNC stated the following in its letter dated June 30, 2022:
The Vogtle reactors each contain 193 fuel assemblies. Each
assembly consists of a matrix of 264 Zircaloy, ZIRLO[supreg]\[TM]\,
or Optimized ZIRLO[supreg]\[TM]\ clad fuel rods with an initial
composition of natural or slightly enriched uranium dioxide (UO2) as
fuel material, not to exceed 5 wt% [weight-percent] enrichment. The
proposed change is to load four LTAs with advanced ATF [accident-
tolerant fuel] features, including ADOPT fuel [2], AXIOM cladding
[3], chromium coating, and four rods per LTA with up to 6 wt%
enrichment, in limiting core locations for up to two cycles of
operation.
This exemption will not present an undue risk to public health
and safety. The analysis performed in support of the enclosed LAR
[license amendment request] addresses the safe storage of the LTAs.
These were evaluated using AOR [analysis of record] plant-specific
models to determine that existing storage configurations can be used
for storage of the LTAs, with restrictions (see Section 3 above and
Section 3.12 of Enclosure 1 [in letter dated June 30, 2022]). Thus,
the granting of this exemption request will not pose an undue risk
to public health and safety.
The licensee's requested exemption to paragraph 50.68(b)(7) is
for the fuel rods enriched above 5.0 wt% U-235. Each LTA is limited
to four rods at 6.0 wt% U-235. Those four rods add about 0.015% more
U-235 to the LTAs relative to the Vogtle new fuel storage rack
(NFSR) analysis of record (AOR) and the Vogtle spent fuel pool (SFP)
AOR maximum enrichment of 5.0 wt% U-235. SNC's evaluation considered
the fissile material increase due to the higher enrichment and that
due to the higher fraction of the theoretical density of the ADOPT
fuel. The licensee established Technical Specifications to control
the storage of the LTAs. The NRC staff has found that these controls
provide reasonable assurance that the four LTAs as described in
SNC's amendment and exemption requests will meet 10 CFR 50.68(b)(2),
10 CFR 50.68(b)(3), and 10 CFR 50.68(b)(4). See the NRC staff
evaluation (ML23093A028) for further details. Thus, the NRC staff
finds that the requested exemption does not result in any undue risk
to the public health and safety.
C. The Exemption is Consistent With the Common Defense and Security
The proposed exemption would allow the use of four LTAs, each
with four fuel rods with a nominal U-235 enrichment of up to six
percent by weight. This change to the plant core configuration has
no impact on security issues. Special nuclear material in the LTAs
will continue to be handled and controlled in accordance with
applicable regulations. Therefore, the common defense and security
is not impacted by this exemption.
D. Special Circumstances
Special circumstances, in accordance with 10 CFR
50.12(a)(2)(ii), are present whenever application of the regulation
in the particular circumstances would not serve the underlying
purpose of the rule or is not necessary to achieve the underlying
purpose of the rule. The underlying purpose of 10 CFR 50.68 is to
provide reasonable assurance that an inadvertent criticality event
will not occur during the storage or handling of special nuclear
material at 10 CFR part 50 licenses. The preamble for the final rule
promulgating 10 CFR 50.68 (Federal Register/Vol. 63, No. 218/
Thursday, November 12, 1998/Rules and Regulations [[Page 63127]])
indicated that increases to the
[[Page 52220]]
enrichment limit of 5.0 wt% U-235 could be addressed in the future.
In the safety evaluation (SE) contained in ML23093A028 for the
license amendment request, the NRC staff evaluated for Vogtle, Units
1 and 2, four LTAs that demonstrated the acceptability of the
nominal U-235 enrichment of up to six percent by weight of four fuel
rods per LTA. The results showed that the LTAs would not adversely
affect subcriticality in the spent fuel pool or new fuel storage
racks. Therefore, the NRC staff concludes that application of 10 CFR
50.68(b)(7) in this particular circumstance is not necessary for the
licensee to achieve the underlying purpose of the rule.
E. Environmental Considerations
With respect to its impact on the quality of the human
environment, the NRC has determined that the issuance of the
exemption discussed herein meets the eligibility criteria for
categorical exclusion set forth in 10 CFR 51.22(c)(9). The NRC
staff's determination that all of the criteria for this categorical
exclusion are met is as follows:
The regulation 10 CFR 51.22(c)(9) states:
Issuance of an amendment to a permit or license for a reactor
under part 50 or part 52 of this chapter that changes a requirement
or issuance of an exemption from a requirement, with respect to
installation or use of a facility component located within the
restricted area, as defined in part 20 of this chapter; or the
issuance of an amendment to a permit or license for a reactor under
part 50 or part 52 of this chapter that changes an inspection or a
surveillance requirement; provided that: (i) The amendment or
exemption involves no significant hazards consideration; (ii) There
is no significant change in the types or significant increase in the
amounts of any effluents that may be released offsite; and (iii)
There is no significant increase in individual or cumulative
occupational radiation exposure.
Staff Analysis: The exemption is from requirements with respect
to the installation or use of facility components located within the
restricted area as defined in 10 CFR part 20. The criteria for
determining whether an action involves a significant hazards
consideration are found in 10 CFR 50.92. The proposed action
involves installed four LTAs. As stated in the evaluation in
ML23093A028, the Commission has previously issued a proposed finding
that the amendments involve no significant hazards consideration,
published in the Federal Register on November 8, 2022 (87 FR 67508),
and there has been no public comment on such finding.
The proposed action involves installing four LTAs, and as the
NRC staff evaluated under the SE contained in ML23093A028, this
action does not involve any significant change in the types or
significant increase in the amounts of any effluents that may be
released offsite.
The proposed action involves installing four LTAs, and as the
NRC staff evaluated under the SE contained in ML23093A028, this
action does not involve any significant increase in individual or
cumulative occupational exposure.
Based on the above, 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 issuance of this exemption.
IV. Conclusions
Accordingly, the NRC 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, pursuant
to 10 CFR 50.12(a)(2)(ii), are present. Therefore, the NRC hereby
grants SNC an exemption from the requirements of 10 CFR 50.68(b)(7)
to allow the use of LTAs 7ST1, 7ST2, 7ST3, and 7ST4 each with four
fuel rods with a nominal U-235 enrichment of up to six percent by
weight, for up to two cycles of operation at Vogtle, Unit 2, and
allow receipt, inspection, and storage of the LTAs at Vogtle, Units
1 and 2.
Dated at Rockville, Maryland, this 1st day of August, 2023.
For the Nuclear Regulatory Commission.
/RA/
Bo M. Pham,
Director, Division of Operating Reactor Licensing, Office of Nuclear
Reactor Regulation.
[FR Doc. 2023-16753 Filed 8-4-23; 8:45 am]
BILLING CODE 7590-01-P
