84206 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 

AGENCY: National Science Foundation. 

ACTION: Notice; Cancellation of meeting 

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. 

[FR Doc. 2024–24253 Filed 10–18–24; 8:45 am] 

BILLING CODE 7555–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[Docket No. 40–9075–LR; ASLBP No. 25– 

987–01–LR–BD01] 

Establishment of Atomic Safety and 

Licensing Board; Powertech (USA) Inc. 

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 

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 

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 

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: 

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 301–415- 

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: 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), 


lotter on DSK11XQN23PROD with NOTICES1
Federal Register / Vol. 89, No. 203 / Monday, October 21, 2024 / Notices 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 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.

ML17214A040. 

Sequoyah Nuclear Plant—Registration of Spent Fuel Storage Cask Pursuant to 10 CFR 72.212(b)(2), dated February 24, 2022.ML22059B061. 

Sequoyah Nuclear Plant—Request for Exemption from Various 10 CFR part 72 Regulations Resulting from NonDestruction-Examination Compliance, dated August 4, 2022.ML22216A078. 

Sequoyah Nuclear Plant—Response to Request for Supplemental Information (D–RSI) Request for Exemption 

from Non-Destruction-Examination Compliance, dated December 19, 2022.

ML22353A066. 

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.ML23117A116. 

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.

ML24004A040. 

Issuance of Exemption Related to Non-Destructive Examination Compliance Regarding Sequoyah Nuclear Plant 

Independent Spent Fuel Storage Installation, dated September 18, 2024.

ML24185A172 (Package). 

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 

[Docket No. 70–7033; NRC–2024–0138] 

Global Laser Enrichment, LLC; 

Classified Matter Protection; 

Environmental Assessment and 

Finding of No Significant Impact 

AGENCY: Nuclear Regulatory 

Commission. 

ACTION: Notice; issuance. 

SUMMARY: 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. 

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 


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