Southern Nuclear Operating Company; Vogtle Electric Generating Plant, Unit 2, 52220-52222 [2023-16756]
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52220
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.
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18:58 Aug 04, 2023
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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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Federal Register / Vol. 88, No. 150 / Monday, August 7, 2023 / Notices
Electric Generating Plant (Vogtle), Unit 2.
The license provides, among other things,
that the license is subject to all rules,
regulations, and orders of the Commission
now or hereafter in effect.
The Vogtle, Unit 2, consists of a
pressurized-water reactor 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), January 20, 2023
(ML23020A148), and May 5, 2023
(ML23125A269), SNC requested an
exemption to title 10 of the Code of Federal
Regulations (10 CFR), part 50, section 50.46,
‘‘Acceptance criteria for emergency core
cooling systems for light-water nuclear power
reactors,’’ for Vogtle, Unit 2.
Specifically, SNC requested an exemption
from 10 CFR 50.46 to allow the use of
AXIOM fuel rod cladding material in lead
test assemblies (LTAs) 7ST1, 7ST2, 7ST3,
and 7ST4 for up to two cycles of operation
at Vogtle, Unit 2.
The regulation at 10 CFR 50.46(a)(1)(i)
requires that, ‘‘Each boiling or pressurized
light-water nuclear power reactor fueled with
uranium oxide pellets within cylindrical
zircaloy or ZIRLO cladding must be provided
with an emergency core cooling system
(ECCS) that must be designed so that its
calculated cooling performance following
postulated loss-of-coolant accidents conforms
to the criteria set forth in paragraph (b) of this
section.’’ The regulations make no provisions
for use of fuel rods clad in a material other
than zircaloy or ZIRLO.
ddrumheller on DSK120RN23PROD with NOTICES1
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 50.46, 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 containing AXIOM fuel
rod cladding that is neither Zircaloy nor
ZIRLO, which are the cladding materials
contemplated by 10 CFR 50.46(a)(1)(i).
Selection of a specific cladding material in 10
CFR 50.46 was at the discretion of the
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18:58 Aug 04, 2023
Jkt 259001
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 50.46
related to AXIOM fuel rod cladding, which
is neither Zircaloy nor ZIRLO, 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],
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. Reload
evaluations ensure that acceptance criteria
are met for the insertion of LTAs with fuel
rods clad with AXIOM material. Due to
similarities in the composition of the AXIOM
alloy and the Optimized ZIRLO and standard
ZIRLO alloys, fuel assemblies using AXIOM
fuel rod cladding are evaluated using plantspecific models to address the changes in the
cladding material properties. The LOCA
[loss-of-coolant accident] safety analyses for
VEGP [Vogtle Electric Generating Plant] are
supported by the applicable site-specific
Technical Specifications (TS). Reload cores
are required to be operated in accordance
with the operating limits specified in the TS.
Thus, the granting of this exemption request
will not pose an undue risk to public health
and safety.1
Based upon the limited number of AXIOM
clad fuel rods, the safeguards in place which
would detect anomalous behavior, the use of
NRC-approved models to ensure that all
design criteria remain satisfied, and the
requirement to operate the Vogtle, Unit 2,
core within TS limits, the NRC staff finds the
four LTAs acceptable for Vogtle, Unit 2. In
conclusion, the NRC staff finds that the
requested exemption does not result in any
undue risk to the public health and safety,
because NRC staff concluded that the existing
LOCA evaluation models analysis of records
for Vogtle are representative of the LTAs, and
the presence of the LTAs will have a
negligible impact on the co-resident fuel, and
10 CFR 50.46 acceptance criteria continue to
1 Although this quoted material states that the
LTAs would be placed in limiting core locations,
SNC’s May 5, 2023, supplement, states that the
LTAs will not be placed in core regions that have
been shown to be limiting with respect to the
control rod ejection analysis.
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Fmt 4703
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52221
be met. Further information can be found in
the NRC staff safety evaluation
(ML23093A028).
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.
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 50.46 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.
Therefore, the NRC staff concludes that
application of the limitation to zircaloy and
ZIRLO in 10 CFR 50.46 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
E:\FR\FM\07AUN1.SGM
07AUN1
52222
Federal Register / Vol. 88, No. 150 / Monday, August 7, 2023 / Notices
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 50.46 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,
Director, Division of Operating Reactor
Licensing, Office of Nuclear Reactor
Regulation.
[FR Doc. 2023–16756 Filed 8–4–23; 8:45 am]
BILLING CODE 7590–01–P
ddrumheller on DSK120RN23PROD with NOTICES1
OFFICE OF PERSONNEL
MANAGEMENT
Submission for Review: 3206–0226, It’s
Time To Sign Up for Direct Deposit or
Direct Express, RI 38–128
Office of Personnel
Management.
ACTION: 30-Day notice and request for
comments.
AGENCY:
The Office of Personnel
Management (OPM), Retirement
SUMMARY:
VerDate Sep<11>2014
18:58 Aug 04, 2023
Jkt 259001
Services, offers the general public and
other Federal agencies the opportunity
to comment on an expiring information
collection request (ICR), RI 38–128—It’s
Time to Sign Up for Direct Deposit or
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DATES: Comments are encouraged and
will be accepted until September 6,
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Written comments and
recommendations for the proposed
information collection should be sent
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notice to https://www.reginfo.gov/public/
do/PRAMain. Find this particular
information collection by selecting
‘‘Currently under Review—Open for
Public Comments’’ or by using the
search function or fax to (202) 395–
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ADDRESSES:
A
copy of this ICR with applicable
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NW, Room 3316–L, Washington, DC
20415, Attention: Cyrus S. Benson, or
sent via electronic mail to
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previously published in the Federal
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comment period. No comments were
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of this notice is to allow an additional
30 days for public comments. The Office
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particularly interested in comments
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1. Evaluate whether the proposed
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2. Evaluate the accuracy of the
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including the validity of the
methodology and assumptions used;
3. Enhance the quality, utility, and
clarity of the information to be
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4. Minimize the burden of the
collection of information on those who
are to respond, including through the
use of appropriate automated,
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technological collection techniques or
other forms of information technology,
FOR FURTHER INFORMATION CONTACT:
PO 00000
Frm 00115
Fmt 4703
Sfmt 4703
e.g., permitting electronic submissions
of responses.
RI 38–128, It’s Time to Sign Up for
Direct Deposit or Direct Express,
provides the opportunity for the
annuitant to elect Direct Deposit or
Direct Express. This election is required
only once: when a person is first put on
our annuity roll. If there is no evidence
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person this election, OPM must provide
RI 38–128.
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Agency: Retirement Operations,
Retirement Services, Office of Personnel
Management.
Title: It’s Time to Sign Up for Direct
Deposit or Direct Express.
OMB Number: 3206–0226.
Frequency: On occasion.
Affected Public: Individuals or
Households.
Number of Respondents: 20,000.
Estimated Time per Respondent: 30
minutes.
Total Burden Hours: 10,000.
Office of Personnel Management.
Kayyonne Marston,
Federal Register Liaison.
[FR Doc. 2023–16801 Filed 8–4–23; 8:45 am]
BILLING CODE 6325–38–P
OFFICE OF PERSONNEL
MANAGEMENT
Agency Information Collection
Activities; Proposals, Submissions,
and Approvals: Questionnaire for
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Office of Personnel
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comments.
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In accordance with the
Paperwork Reduction Act of 1995, the
Office of Personnel Management (OPM)
requests clearance from the Office of
Management and Budget (OMB) on the
renewal of a previously approved
information collection request (ICR),
Questionnaire for National Security
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Written comments and
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E:\FR\FM\07AUN1.SGM
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Agencies
[Federal Register Volume 88, Number 150 (Monday, August 7, 2023)]
[Rules and Regulations]
[Pages 52220-52222]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2023-16756]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[Docket No. 50-425; NRC-2023-0091]
Southern Nuclear Operating Company; Vogtle Electric Generating
Plant, Unit 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 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:
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: [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 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, 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
[[Page 52221]]
Electric Generating Plant (Vogtle), Unit 2. The license provides,
among other things, that the license is subject to all rules,
regulations, and orders of the Commission now or hereafter in
effect.
The Vogtle, Unit 2, consists of a pressurized-water reactor
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),
January 20, 2023 (ML23020A148), and May 5, 2023 (ML23125A269), SNC
requested an exemption to title 10 of the Code of Federal
Regulations (10 CFR), part 50, section 50.46, ``Acceptance criteria
for emergency core cooling systems for light-water nuclear power
reactors,'' for Vogtle, Unit 2.
Specifically, SNC requested an exemption from 10 CFR 50.46 to
allow the use of AXIOM fuel rod cladding material in lead test
assemblies (LTAs) 7ST1, 7ST2, 7ST3, and 7ST4 for up to two cycles of
operation at Vogtle, Unit 2.
The regulation at 10 CFR 50.46(a)(1)(i) requires that, ``Each
boiling or pressurized light-water nuclear power reactor fueled with
uranium oxide pellets within cylindrical zircaloy or ZIRLO cladding
must be provided with an emergency core cooling system (ECCS) that
must be designed so that its calculated cooling performance
following postulated loss-of-coolant accidents conforms to the
criteria set forth in paragraph (b) of this section.'' The
regulations make no provisions for use of fuel rods clad in a
material other than zircaloy or ZIRLO.
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 50.46, 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
containing AXIOM fuel rod cladding that is neither Zircaloy nor
ZIRLO, which are the cladding materials contemplated by 10 CFR
50.46(a)(1)(i). Selection of a specific cladding material in 10 CFR
50.46 was 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 50.46
related to AXIOM fuel rod cladding, which is neither Zircaloy nor
ZIRLO, 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. Reload evaluations ensure that acceptance criteria are
met for the insertion of LTAs with fuel rods clad with AXIOM
material. Due to similarities in the composition of the AXIOM alloy
and the Optimized ZIRLO and standard ZIRLO alloys, fuel assemblies
using AXIOM fuel rod cladding are evaluated using plant-specific
models to address the changes in the cladding material properties.
The LOCA [loss-of-coolant accident] safety analyses for VEGP [Vogtle
Electric Generating Plant] are supported by the applicable site-
specific Technical Specifications (TS). Reload cores are required to
be operated in accordance with the operating limits specified in the
TS. Thus, the granting of this exemption request will not pose an
undue risk to public health and safety.\1\
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\1\ Although this quoted material states that the LTAs would be
placed in limiting core locations, SNC's May 5, 2023, supplement,
states that the LTAs will not be placed in core regions that have
been shown to be limiting with respect to the control rod ejection
analysis.
Based upon the limited number of AXIOM clad fuel rods, the
safeguards in place which would detect anomalous behavior, the use
of NRC-approved models to ensure that all design criteria remain
satisfied, and the requirement to operate the Vogtle, Unit 2, core
within TS limits, the NRC staff finds the four LTAs acceptable for
Vogtle, Unit 2. In conclusion, the NRC staff finds that the
requested exemption does not result in any undue risk to the public
health and safety, because NRC staff concluded that the existing
LOCA evaluation models analysis of records for Vogtle are
representative of the LTAs, and the presence of the LTAs will have a
negligible impact on the co-resident fuel, and 10 CFR 50.46
acceptance criteria continue to be met. Further information can be
found in the NRC staff safety evaluation (ML23093A028).
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.
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 50.46 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. Therefore, the NRC staff
concludes that application of the limitation to zircaloy and ZIRLO
in 10 CFR 50.46 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
[[Page 52222]]
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 50.46 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,
Director, Division of Operating Reactor Licensing, Office of Nuclear
Reactor Regulation.
[FR Doc. 2023-16756 Filed 8-4-23; 8:45 am]
BILLING CODE 7590-01-P