Tennessee Valley Authority; Sequoyah Nuclear Plant Independent Spent Fuel Storage Installation; Exemption, 84206-84207 [2024-24191]
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Federal Register / Vol. 89, No. 203 / Monday, October 21, 2024 / Notices
Dated: October 16, 2024.
Crystal Robinson,
Committee Management Officer.
[FR Doc. 2024–24376 Filed 10–18–24; 8:45 am]
BILLING CODE 7555–01–P
NATIONAL SCIENCE FOUNDATION
Advisory Committee for Technology,
Innovation and Partnerships;
Cancellation of Meeting
National Science Foundation.
Notice; Cancellation of meeting
AGENCY:
ACTION:
date.
The National Science Foundation
published a notice in the Federal
Register October 1, 2024, in FR Doc.
2024–22538 at 89 FR 79968, concerning
a meeting of the Advisory Committee for
Technology, Innovation and
Partnerships. The meeting scheduled for
Wednesday, October 30, 2024, at 12
p.m. (ET) is cancelled.
FOR FURTHER INFORMATION CONTACT:
Please contact Crystal Robinson
crrobins@nsf.gov or 703–292–8687.
Dated: October 16, 2024.
Crystal Robinson,
Committee Management Officer, National
Science Foundation.
Dated: October 15, 2024.
Edward R. Hawkens,
Chief Administrative Judge, Atomic Safety
and Licensing Board Panel.
[FR Doc. 2024–24195 Filed 10–18–24; 8:45 am]
BILLING CODE 7590–01–P
[FR Doc. 2024–24253 Filed 10–18–24; 8:45 am]
NUCLEAR REGULATORY
COMMISSION
BILLING CODE 7555–01–P
[Docket Nos. 50–327, 50–328, and 72–34;
NRC–2024–0174]
NUCLEAR REGULATORY
COMMISSION
lotter on DSK11XQN23PROD with NOTICES1
FR 65401 (Aug. 9, 2024), the following
petitioners filed a hearing request on
October 8, 2024: (1) Susan Henderson;
and (2) the Oglala Sioux Tribe, Black
Hills Clean Water Alliance, and NDN
Collective.
The Board is comprised of the
following Administrative Judges:
Jeremy A. Mercer, Chair, Atomic Safety
and Licensing Board Panel, U.S.
Nuclear Regulatory Commission,
Washington, DC 20555–0001
Nicholas G. Trikouros, Atomic Safety
and Licensing Board Panel, U.S.
Nuclear Regulatory Commission,
Washington, DC 20555–0001
Dr. Gary S. Arnold, Atomic Safety and
Licensing Board Panel, U.S. Nuclear
Regulatory Commission, Washington,
DC 20555–0001
All correspondence, documents, and
other materials shall be filed in
accordance with the NRC E-Filing rule.
See 10 CFR 2.302.
Rockville, Maryland
[Docket No. 40–9075–LR; ASLBP No. 25–
987–01–LR–BD01]
Tennessee Valley Authority; Sequoyah
Nuclear Plant Independent Spent Fuel
Storage Installation; Exemption
Establishment of Atomic Safety and
Licensing Board; Powertech (USA) Inc.
AGENCY:
Pursuant to the Commission’s
regulations, see, e.g., 10 CFR §§ 2.104,
2.105, 2.300, 2.309, 2.313, 2.318, 2.321,
notice is hereby given that an Atomic
Safety and Licensing Board (Board) is
being established to preside over the
following proceeding:
POWERTECH (USA) INC.
(Dewey Burdock In-Situ Uranium
Recovery Facility)
Powertech (USA) Inc. requests a
renewed license that, if granted, would
authorize it to operate the DeweyBurdock Uranium In-Situ Recovery
Facility for 20 years beyond the period
specified in the current license. The
facility has not yet been constructed, but
if constructed, it would be located in
Fall River and Custer Counties, South
Dakota.
In response to a notice filed in the
Federal Register announcing the
opportunity to request a hearing, see 89
VerDate Sep<11>2014
16:27 Oct 18, 2024
Jkt 265001
Nuclear Regulatory
Commission.
ACTION: Notice; issuance.
The U.S. Nuclear Regulatory
Commission (NRC) issued an exemption
to Tennessee Valley Authority (TVA),
for the Sequoyah Nuclear Plant (SQN)
Independent Spent Fuel Storage
Installation (ISFSI), in accordance with
NRC regulations. Specifically, the
exemption permits SQN’s ISFSI to
deviate from conditions of the NRC
Certificate of Compliance (CoC) No.
1032, which was issued to Holtec
International (Holtec or the CoC holder)
amendment No. 3, appendix B, section
3.3, ‘‘Codes and Standards.’’
DATES: The exemption was issued on
September 18, 2024.
ADDRESSES: Please refer to Docket ID
NRC–2024–0174 when contacting the
NRC about the availability of
information regarding this document.
You may obtain publicly available
SUMMARY:
PO 00000
Frm 00098
Fmt 4703
Sfmt 4703
information related to this document
using any of the following methods:
• Federal Rulemaking website: Go to
https://www.regulations.gov and search
for Docket ID NRC–2024–0174. 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. For the
convenience of the reader, instructions
about obtaining materials referenced in
this document are provided in the
‘‘Availability of Documents’’ section.
• 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 301–4154737, between 8 a.m. and 4 p.m. eastern
time (ET), Monday through Friday,
except Federal holidays.
FOR FURTHER INFORMATION CONTACT:
Tilda Liu, Office of Nuclear Material
Safety and Safeguards, U.S. Nuclear
Regulatory Commission, Washington,
DC 20555–0001; telephone: 404–997–
4730; email: Tilda.Liu@nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Discussion
The NRC issued an exemption to TVA
for the SQN ISFSI. By letter dated
August 4, 2022, as supplemented by
letters dated December 19, 2022, April
27, 2023, and January 3, 2024, TVA
submitted to the NRC an exemption
request for the SQN ISFSI, in
accordance with section 72.7 of title 10
of the Code of Federal Regulations (10
CFR), ‘‘Specific exemptions,’’ from the
requirements of 10 CFR 72.212(a)(2),
72.212(b)(3), 72.212(b)(5)(i),
72.212(b)(11), 72.214, 72.154(b), and
72.174. Specifically, the exemption
request permits SQN ISFSI to deviate
from conditions of the NRC CoC No.
1032, Amendment No. 3, appendix B,
section 3.3, ‘‘Codes and Standards.’’
The requirements contained in 10
CFR 72.212(a)(2), 72.212(b)(3),
E:\FR\FM\21OCN1.SGM
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84207
Federal Register / Vol. 89, No. 203 / Monday, October 21, 2024 / Notices
72.212(b)(5)(i), 72.212(b)(11), 72.214,
72.154(b), and 72.174 are applicable to
CoC No. 1032, which was issued to
Holtec. The condition of CoC No.1032,
appendix B, technical specifications,
section 3.3, ‘‘Codes and Standards,’’
specifies American Society of
Mechanical Engineers (ASME) Boiler
and Pressure Vessel (B&PV) Code, 2007
Edition, as the governing B&PV Code for
Holtec’s HI–STORM Flood/Wind (FW)
Multi-Purpose Canister (MPC) Storage
System, the dry cask spent fuel storage
system in use at SQN ISFSI. The ASME
B&PV Code requires that 100 percent of
the weld seam joining shell-to-shell of
the MPC be inspected by radiography
test (RT) where RT is a form of nondestructive examination.
The licensee loaded spent fuel in the
HI–STORM FW dry cask storage system
MPC Type 37 (MPC–37), Serial No. 234,
for storage in the ISFSI at SQN under
CoC No. 1032, Amendment No. 3, and
its general license. During a review of
manufacturer’s documents, the CoC
holder identified that MPC–37 Serial
No. 234 at SQN ISFSI has a longitudinal
shell-to-shell weld for which no digital
RT is available following a weld repair,
which is inconsistent with the
governing ASME B&PV code for this
CoC system. When TVA was notified of
this issue, MPC–37 Serial No. 234 was
already put in use, and TVA registered
it by letter dated February 24, 2022,
entitled ‘‘Sequoyah Nuclear Plant
Registration of Spent Fuel Storage Cask
Pursuant to 10 CFR 72.212(b)(2).’’ TVA
then submitted this exemption request
to the NRC to allow continued storage
of spent fuel in MPC–37 Serial No. 234
for the service life of the canister at
SQN, despite the non-compliance with
the ASME B&PV code.
Based on the NRC staff’s review of
TVA’s analysis supporting the
exemption request, the NRC staff
determined that, pursuant to 10 CFR
72.7, the exemption is authorized by
law, will not endanger life or property
or the common defense and security,
and is otherwise in the public interest.
Therefore, the NRC granted the licensee
an exemption from the requirements of
10 CFR 72.212(a)(2), 10 CFR
72.212(b)(3), 10 CFR 72.212(b)(5)(i), 10
CFR 72.212(b)(11), 10 CFR 72.214, 10
CFR 72.154(b), and 10 CFR 72.174 with
regard to: (1) meeting the requirement to
repeat volumetric examination as
required for the original weld on an
approximately 7.5-inch portion of the
repaired weld in conformance with
section III, subsection NB, of the ASME
B&PV Code, 2007 Edition, and (2)
maintaining and having available
documentary evidence of the test for the
service life of the canister. The
exemption allowed TVA to continue
using MPC–37 Serial No. 234 to store
spent fuel for the service life of the
canister at SQN. All other relevant
requirements of the CoC shall continue
to be met. This exemption, including
the supporting evaluation for issuance
of it, can be found in the table as
follows.
II. Availability of Documents
The documents identified in the
following table are available to
interested persons through one or more
of the following methods, as indicated.
Document description
ADAMS Accession No.
Issuance of Certificate of Compliance No. 1032, Amendment No. 3 for the HI–STORM Flood/Wind Multipurpose
Canister Storage, dated August 9, 2017.
Sequoyah Nuclear Plant—Registration of Spent Fuel Storage Cask Pursuant to 10 CFR 72.212(b)(2), dated February 24, 2022.
Sequoyah Nuclear Plant—Request for Exemption from Various 10 CFR part 72 Regulations Resulting from NonDestruction-Examination Compliance, dated August 4, 2022.
Sequoyah Nuclear Plant—Response to Request for Supplemental Information (D–RSI) Request for Exemption
from Non-Destruction-Examination Compliance, dated December 19, 2022.
Sequoyah Nuclear Plant—Response to Follow-up Questions to TVA’s Response to NRC’s Request for Supplemental Information (RSI) Related to August 4, 2022, Sequoyah ISFSI Exemption Request, dated April 27, 2023.
Sequoyah Nuclear Plant—Response to NRC’s November 8, 2023, Request for Additional Information—Related to
Sequoyah Nuclear Plant Independent Spent Fuel Storage Installation, dated January 3, 2024.
Issuance of Exemption Related to Non-Destructive Examination Compliance Regarding Sequoyah Nuclear Plant
Independent Spent Fuel Storage Installation, dated September 18, 2024.
Dated: October 15, 2024.
For the Nuclear Regulatory Commission.
Yoira Diaz-Sanabria,
Chief, Storage and Transportation Licensing
Branch, Division of Fuel Management, Office
of Nuclear Material Safety and Safeguards.
[FR Doc. 2024–24191 Filed 10–18–24; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
lotter on DSK11XQN23PROD with NOTICES1
[Docket No. 70–7033; NRC–2024–0138]
Global Laser Enrichment, LLC;
Classified Matter Protection;
Environmental Assessment and
Finding of No Significant Impact
Nuclear Regulatory
Commission.
ACTION: Notice; issuance.
AGENCY:
VerDate Sep<11>2014
16:27 Oct 18, 2024
Jkt 265001
The U.S. Nuclear Regulatory
Commission (NRC) staff is considering
approval of a revision by Global Laser
Enrichment, LLC (GLE) to a Standard
Practice Procedures Plan (SPPP) for the
protection of classified matter. The
revision would remove the Fuels
Growth Engineering (FGE) facility and
confirm the continued use of the
classified matter controls implemented
at the Test Loop facility. The NRC staff
is issuing an environmental assessment
(EA) and finding of no significant
impact (FONSI) associated with the
proposed plans.
DATES: The EA and FONSI referenced in
this document are available on October
21, 2024.
ADDRESSES: Please refer to Docket ID
NRC–2024–0138 when contacting the
NRC about the availability of
information regarding this document.
SUMMARY:
PO 00000
Frm 00099
Fmt 4703
Sfmt 4703
ML17214A040.
ML22059B061.
ML22216A078.
ML22353A066.
ML23117A116.
ML24004A040.
ML24185A172 (Package).
You may obtain publicly available
information related to this document
using any of the following methods:
• Federal Rulemaking Website: Go to
https://www.regulations.gov and search
for Docket ID NRC–2024–0138. 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
E:\FR\FM\21OCN1.SGM
21OCN1
]]>Agencies
[Federal Register Volume 89, Number 203 (Monday, October 21, 2024)]
[Notices]
[Pages 84206-84207]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2024-24191]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[Docket Nos. 50-327, 50-328, and 72-34; NRC-2024-0174]
Tennessee Valley Authority; Sequoyah Nuclear Plant Independent
Spent Fuel Storage Installation; Exemption
AGENCY: Nuclear Regulatory Commission.
ACTION: Notice; issuance.
-----------------------------------------------------------------------
SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) issued an
exemption to Tennessee Valley Authority (TVA), for the Sequoyah Nuclear
Plant (SQN) Independent Spent Fuel Storage Installation (ISFSI), in
accordance with NRC regulations. Specifically, the exemption permits
SQN's ISFSI to deviate from conditions of the NRC Certificate of
Compliance (CoC) No. 1032, which was issued to Holtec International
(Holtec or the CoC holder) amendment No. 3, appendix B, section 3.3,
``Codes and Standards.''
DATES: The exemption was issued on September 18, 2024.
ADDRESSES: Please refer to Docket ID NRC-2024-0174 when contacting the
NRC about the availability of information regarding this document. You
may obtain publicly available information related to this document
using any of the following methods:
Federal Rulemaking website: Go to https://www.regulations.gov and search for Docket ID NRC-2024-0174. 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]. For the convenience of the reader,
instructions about obtaining materials referenced in this document are
provided in the ``Availability of Documents'' section.
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: Tilda Liu, Office of Nuclear Material
Safety and Safeguards, U.S. Nuclear Regulatory Commission, Washington,
DC 20555-0001; telephone: 404-997-4730; email: [email protected].
SUPPLEMENTARY INFORMATION:
I. Discussion
The NRC issued an exemption to TVA for the SQN ISFSI. By letter
dated August 4, 2022, as supplemented by letters dated December 19,
2022, April 27, 2023, and January 3, 2024, TVA submitted to the NRC an
exemption request for the SQN ISFSI, in accordance with section 72.7 of
title 10 of the Code of Federal Regulations (10 CFR), ``Specific
exemptions,'' from the requirements of 10 CFR 72.212(a)(2),
72.212(b)(3), 72.212(b)(5)(i), 72.212(b)(11), 72.214, 72.154(b), and
72.174. Specifically, the exemption request permits SQN ISFSI to
deviate from conditions of the NRC CoC No. 1032, Amendment No. 3,
appendix B, section 3.3, ``Codes and Standards.''
The requirements contained in 10 CFR 72.212(a)(2), 72.212(b)(3),
[[Page 84207]]
72.212(b)(5)(i), 72.212(b)(11), 72.214, 72.154(b), and 72.174 are
applicable to CoC No. 1032, which was issued to Holtec. The condition
of CoC No.1032, appendix B, technical specifications, section 3.3,
``Codes and Standards,'' specifies American Society of Mechanical
Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code, 2007 Edition,
as the governing B&PV Code for Holtec's HI-STORM Flood/Wind (FW) Multi-
Purpose Canister (MPC) Storage System, the dry cask spent fuel storage
system in use at SQN ISFSI. The ASME B&PV Code requires that 100
percent of the weld seam joining shell-to-shell of the MPC be inspected
by radiography test (RT) where RT is a form of non-destructive
examination.
The licensee loaded spent fuel in the HI-STORM FW dry cask storage
system MPC Type 37 (MPC-37), Serial No. 234, for storage in the ISFSI
at SQN under CoC No. 1032, Amendment No. 3, and its general license.
During a review of manufacturer's documents, the CoC holder identified
that MPC-37 Serial No. 234 at SQN ISFSI has a longitudinal shell-to-
shell weld for which no digital RT is available following a weld
repair, which is inconsistent with the governing ASME B&PV code for
this CoC system. When TVA was notified of this issue, MPC-37 Serial No.
234 was already put in use, and TVA registered it by letter dated
February 24, 2022, entitled ``Sequoyah Nuclear Plant Registration of
Spent Fuel Storage Cask Pursuant to 10 CFR 72.212(b)(2).'' TVA then
submitted this exemption request to the NRC to allow continued storage
of spent fuel in MPC-37 Serial No. 234 for the service life of the
canister at SQN, despite the non-compliance with the ASME B&PV code.
Based on the NRC staff's review of TVA's analysis supporting the
exemption request, the NRC staff determined that, pursuant to 10 CFR
72.7, the exemption is authorized by law, will not endanger life or
property or the common defense and security, and is otherwise in the
public interest. Therefore, the NRC granted the licensee an exemption
from the requirements of 10 CFR 72.212(a)(2), 10 CFR 72.212(b)(3), 10
CFR 72.212(b)(5)(i), 10 CFR 72.212(b)(11), 10 CFR 72.214, 10 CFR
72.154(b), and 10 CFR 72.174 with regard to: (1) meeting the
requirement to repeat volumetric examination as required for the
original weld on an approximately 7.5-inch portion of the repaired weld
in conformance with section III, subsection NB, of the ASME B&PV Code,
2007 Edition, and (2) maintaining and having available documentary
evidence of the test for the service life of the canister. The
exemption allowed TVA to continue using MPC-37 Serial No. 234 to store
spent fuel for the service life of the canister at SQN. All other
relevant requirements of the CoC shall continue to be met. This
exemption, including the supporting evaluation for issuance of it, can
be found in the table as follows.
II. Availability of Documents
The documents identified in the following table are available to
interested persons through one or more of the following methods, as
indicated.
------------------------------------------------------------------------
Document description ADAMS Accession No.
------------------------------------------------------------------------
Issuance of Certificate of Compliance No. 1032, ML17214A040.
Amendment No. 3 for the HI-STORM Flood/Wind
Multipurpose Canister Storage, dated August 9,
2017.
Sequoyah Nuclear Plant--Registration of Spent ML22059B061.
Fuel Storage Cask Pursuant to 10 CFR
72.212(b)(2), dated February 24, 2022.
Sequoyah Nuclear Plant--Request for Exemption ML22216A078.
from Various 10 CFR part 72 Regulations
Resulting from Non-Destruction-Examination
Compliance, dated August 4, 2022.
Sequoyah Nuclear Plant--Response to Request for ML22353A066.
Supplemental Information (D-RSI) Request for
Exemption from Non-Destruction-Examination
Compliance, dated December 19, 2022.
Sequoyah Nuclear Plant--Response to Follow-up ML23117A116.
Questions to TVA's Response to NRC's Request
for Supplemental Information (RSI) Related to
August 4, 2022, Sequoyah ISFSI Exemption
Request, dated April 27, 2023.
Sequoyah Nuclear Plant--Response to NRC's ML24004A040.
November 8, 2023, Request for Additional
Information--Related to Sequoyah Nuclear Plant
Independent Spent Fuel Storage Installation,
dated January 3, 2024.
Issuance of Exemption Related to Non-Destructive ML24185A172 (Package).
Examination Compliance Regarding Sequoyah
Nuclear Plant Independent Spent Fuel Storage
Installation, dated September 18, 2024.
------------------------------------------------------------------------
Dated: October 15, 2024.
For the Nuclear Regulatory Commission.
Yoira Diaz-Sanabria,
Chief, Storage and Transportation Licensing Branch, Division of Fuel
Management, Office of Nuclear Material Safety and Safeguards.
[FR Doc. 2024-24191 Filed 10-18-24; 8:45 am]
BILLING CODE 7590-01-P
