1198 Federal Register / Vol. 90, No. 4 / Tuesday, January 7, 2025 / Notices 

TOTAL BURDEN HOURS—Continued 

Activity Number of 

respondents Frequency Total annual responses 

Time per 

response 

Total annual 

burden 

(hours) 

Unduplicated Totals ........................................................................ 150 1/annually 150 0.25 hours 37.5 hours 

If additional information is required 

contact: Darwin Arceo, Department 

Clearance Officer, United States 

Department of Justice, Justice 

Management Division, Policy and 

Planning Staff, Two Constitution 

Square, 145 N Street NE, 4W–218, 

Washington, DC. 

Dated: December 31, 2024. 

Darwin Arceo, 

Department Clearance Officer for PRA, U.S. 

Department of Justice. 

[FR Doc. 2024–31784 Filed 1–6–25; 8:45 am] 

BILLING CODE 4410–FY–P 

NATIONAL SCIENCE FOUNDATION 

Sunshine Act Meetings 

The National Science Board’s (NSB) 

Committee on Oversight (CO) hereby 

gives notice of the scheduling of a 

videoconference for the transaction of 

National Science Board business 

pursuant to the National Science 

Foundation Act and the Government in 

the Sunshine Act. 

TIME AND DATE: Friday, January 10, 2025, 

from 1:00 p.m.–2:00 p.m. Eastern. 

PLACE: The meeting will be held by 

videoconference through the National 

Science Foundation, 2415 Eisenhower 

Avenue, Alexandria, VA 22314. 

Members of the public can observe this 

meeting through a YouTube livestream. 

The YouTube link will be available from 

the NSB meetings web page—https://

www.nsf.gov/nsb/meetings/index.jsp. 

STATUS: Open. 

MATTERS TO BE CONSIDERED: Chair’s 

opening remarks and approval of 

previous committee minutes; 

Presentation by NSF regarding the Merit 

Review Digests for FY 2022 and 2023 

and Committee discussion; Update by 

the Chief Financial Officer; Presentation 

by the external auditor for the Office of 

the Inspector General on results of the 

FY 2024 Financial Statement audit; 

Chair’s closing remarks. 

CONTACT PERSON FOR MORE INFORMATION: 

Point of contact for this meeting is Chris 

Blair, cblair@nsf.gov, 703/292–7000. 

Ann E. Bushmiller, 

Senior Counsel to the National Science Board. 

[FR Doc. 2025–00272 Filed 1–3–25; 4:15 pm] 

BILLING CODE 7555–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[Docket Nos. 72–70, 50–373, and 50–374; 

NRC–2024–0205] 

Constellation Energy Generation, LLC; 

LaSalle County Station Units 1 and 2; 

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 Constellation Energy Generation, 

LLC, permitting LaSalle County Station 

(LSCS) to maintain four loaded and to 

load four new 68M multi-purpose 

canister with continuous basket shims 

in HI–STORM 100 Cask System at its 

LSCS Units 1 and 2 independent spent 

fuel storage installation in a storage 

condition where the terms, conditions, 

and specifications in the Certificate of 

Compliance No. 1014, Amendment No. 

8, Revision No. 1, are not met. 

DATES: The exemption was issued on 

December 20, 2024. 

ADDRESSES: Please refer to Docket ID 

NRC–2024–0205 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–2024–0205. 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: 

Martin Ortiz Gonzalez, Office of Nuclear 

Material Safety and Safeguards, U.S. 

Nuclear Regulatory Commission, 

Washington, DC 20555–0001; telephone: 

301–415–3637; email: 

Martin.OrtizGonzalez@nrc.gov. 

SUPPLEMENTARY INFORMATION: The text of 

the exemption is attached. 

Dated: January 2, 2025. 

For the Nuclear Regulatory Commission. 

Yen-Ju Chen, 

Acting Chief, Storage and Transportation 

Licensing Branch, Division of Fuel 

Management, Office of Nuclear Material 

Safety, and Safeguards. 

Attachment—Exemption 

NUCLEAR REGULATORY 

COMMISSION 

Docket Nos. 72–70, 50–373, and 50–374 

Constellation Energy Generation, LLC; 

LaSalle County Station Units 1 and 2; 

Independent Spent Fuel Storage 

Installation 

I. Background 

Constellation Energy Generation, LLC 

(CEG), is the holder of Renewed Facility 

Operating Licenses Nos. NPF–11 and 

NPF–18, which authorize operation of 

the LaSalle County Station, (LSCS) 

Units 1 and 2 in Marseilles, Illinois, 

pursuant to Part 50 of Title 10 of the 

Code of Federal Regulations (10 CFR), 

‘‘Domestic Licensing of Production and 

Utilization Facilities.’’ The licenses 

provide, among other things, that the 

facility is subject to all rules, 

regulations, and orders of the U.S. 

Nuclear Regulatory Commission (NRC) 

now or hereafter in effect. 

Consistent with 10 CFR part 72, 

subpart K, ‘‘General License for Storage 

of Spent Fuel at Power Reactor Sites,’’ 


ddrumheller on DSK120RN23PROD with NOTICES1
Federal Register / Vol. 90, No. 4 / Tuesday, January 7, 2025 / Notices 1199 

a general license is issued for the storage 

of spent fuel in an Independent Spent 

Fuel Storage Installation (ISFSI) at 

power reactor sites to persons 

authorized to possess or operate nuclear 

power reactors under 10 CFR part 50. 

CEG is authorized to operate nuclear 

power reactors under 10 CFR part 50 

and holds a 10 CFR part 72 general 

license for storage of spent fuel at the 

LSCS ISFSI. Under the terms of the 

general license, CEG stores spent fuel at 

its LSCS ISFSI using the HI–STORM 

100 Cask System in accordance with 

Certificate of Compliance (CoC) No. 

1014, Amendment No. 8, Revision No. 

1. 

II. Request/Action 

By a letter dated September 19, 2024 

(Agencywide Documents Access and 

Management System [ADAMS] 

Accession No. ML24263A206), CEG 

requested an exemption from the 

requirements of 10 CFR 72.212(a)(2), 

72.212(b)(3), 72.212(b)(5)(i), 

72.212(b)(11), and 72.214 that require 

LSCS to comply with the terms, 

conditions, and specifications of the 

CoC No. 1014, Amendment No. 8, 

Revision No. 1 (ML16041A233). If 

approved, CEG’s exemption request 

would accordingly allow LSCS to 

maintain four loaded and to load, in the 

future loading campaign beginning in 

June 2025, four Multi-Purpose Canisters 

(MPCs) with an unapproved, variant 

basket design with continuous basket 

shims (CBS) (i.e., MPC–68M–CBS) in 

the HI–STORM 100 Cask System, and 

thus, to maintain and load the systems 

in a storage condition where the terms, 

conditions, and specifications in the 

CoC No. 1014, Amendment No. 8, 

Revision No. 1, are not met. 

CEG currently uses the HI–STORM 

100 Cask System under CoC No. 1014, 

Amendment No. 8, Revision No. 1, for 

dry storage of spent nuclear fuel in 

MPC–68M at the LSCS ISFSI. Holtec 

International (Holtec), the designer and 

manufacturer of the HI–STORM 100 

Cask System, developed a variant of the 

design with CBS for the MPC–68M, 

known as MPC–68M–CBS. Holtec 

performed a non-mechanistic tip-over 

analysis with favorable results and 

implemented the CBS variant design 

under the provisions of 10 CFR 72.48, 

‘‘Changes, tests, and experiments,’’ 

which allows licensees to make changes 

to cask designs without a CoC 

amendment under certain conditions 

(listed in 10 CFR 72.48(c)). After 

evaluating the specific changes to the 

cask designs, the NRC determined that 

Holtec erred when it implemented the 

CBS variant design under 10 CFR 72.48, 

as this is not the type of change allowed 

without a CoC amendment. For this 

reason, the NRC issued three Severity 

Level IV violations to Holtec 

(ML24016A190). 

Prior to the issuance of the violation, 

CEG had loaded four MPC–68M–CBS in 

the HI–STORM 100 Cask System, which 

are safely in storage at the LSCS ISFSI. 

CEG’s future loading campaign for the 

LSCS ISFSI includes loading four MPC– 

68M–CBS in the HI–STORM 100 Cask 

System beginning in June 2025. While 

Holtec was required to submit a CoC 

amendment to the NRC to seek approval 

of the CBS variant design, such a 

process will not be completed in time to 

inform decisions for this future loading 

campaign. Therefore, CEG submitted 

this exemption request in order to allow 

for the continued storage of the four 

already loaded MPC–68–CBS, and 

future loading of four MPC–68M–CBS, 

beginning in June 2025, at the LSCS 

ISFSI. This exemption is limited to the 

use of MPC–68M–CBS in the HI– 

STORM 100 Cask System only for the 

four already loaded canisters and the 

specific planned loading of four new 

canisters beginning in June 2025. 

III. Discussion 

Pursuant to 10 CFR 72.7, ‘‘Specific 

exemptions,’’ the Commission may, 

upon application by any interested 

person or upon its own initiative, grant 

such exemptions from the requirements 

of the regulations of 10 CFR part 72 as 

it determines are authorized by law and 

will not endanger life or property or the 

common defense and security and are 

otherwise in the public interest. 

A. The Exemption Is Authorized by Law 

This exemption would allow CEG to 

maintain four loaded and to load four 

MPC–68M–CBS in the future loading 

campaign beginning in June 2025, in the 

HI–STORM 100 Cask System at its LSCS 

ISFSI in a storage condition where the 

terms, conditions, and specifications in 

the CoC No. 1014, Amendment No. 8, 

Revision No. 1, are not met. CEG is 

requesting an exemption from the 

provisions in 10 CFR part 72 that 

require the licensee to comply with the 

terms, conditions, and specifications of 

the CoC for the approved cask model it 

uses. Section 72.7 allows the NRC to 

grant exemptions from the requirements 

of 10 CFR part 72. This authority to 

grant exemptions is consistent with the 

Atomic Energy Act of 1954, as amended, 

and is not otherwise inconsistent with 

NRC’s regulations or other applicable 

laws. Additionally, no other law 

prohibits the activities that would be 

authorized by the exemption. Therefore, 

the NRC concludes that there is no 

statutory prohibition on the issuance of 

the requested exemption, and the NRC 

is authorized to grant the exemption by 

law. 

B. The Exemption Will Not Endanger 

Life or Property or the Common Defense 

and Security 

This exemption would allow CEG to 

maintain four loaded and to load four 

MPC–68M–CBS in the future loading 

campaign beginning in June 2025, in the 

HI–STORM 100 Cask System at the 

LSCS ISFSI in a storage condition where 

the terms, conditions, and specifications 

in the CoC No. 1014, Amendment No. 

8, Revision No. 1, are not met. In 

support of its exemption request, CEG 

asserts that issuance of the exemption 

would not endanger life or property 

because the administrative controls the 

applicant has in place prevent a tip-over 

or handling event, and that the 

containment boundary would be 

maintained in such an event. CEG relies, 

in part, on the approach in the NRC’s 

Safety Determination Memorandum 

(ML24018A085). The NRC issued this 

Safety Determination Memorandum to 

address whether, with respect to the 

enforcement action against Holtec 

regarding this violation, there was any 

need to take an immediate action for the 

cask systems that were already loaded 

with non-compliant basket designs. The 

Safety Determination Memorandum 

documents a risk-informed approach 

concluding that, during the design basis 

event of a non-mechanistic tip-over, the 

fuel in the basket in the MPC–68M–CBS 

remains in a subcritical condition. 

CEG also provided site-specific 

technical information, including 

information explaining why the use of 

the approach in the NRC’s Safety 

Determination Memorandum is 

appropriate for determining the safe use 

of the CBS variant baskets at the LSCS 

ISFSI. Specifically, CEG described that 

the analysis of the tip-over design basis 

event that is relied upon in the NRC’s 

Safety Determination Memorandum, 

which demonstrates that the MPC 

confinement barrier is maintained, is 

documented in the updated final safety 

analysis report (UFSAR) for the HI– 

STORM 100 Cask System CoC No. 1014, 

Amendment 8, Revision No. 1, that is 

used at the LSCS site. CEG also 

described its administrative controls for 

handling of the HI–STORM 100 Cask 

System at the LSCS ISFSI to prevent a 

tip-over or handling event. Those 

controls include operational procedures 

that demonstrate the system is handled 

with a single failure proof device in 

accordance with NUREG–0554 

(ML110450636), ‘‘Single-Failure-Proof 

Cranes for Nuclear Power Plants, 

NUREG–0612, ‘‘Control of Heavy Loads 


ddrumheller on DSK120RN23PROD with NOTICES1
1200 Federal Register / Vol. 90, No. 4 / Tuesday, January 7, 2025 / Notices 

at Nuclear Power Plants’’ 

(ML070250180), and ANSI N14.6, ‘‘for 

Radioactive Materials—Special Lifting 

Devices for Shipping Containers 

Weighing 10 000 Pounds (4500 kg) or 

More,’’ and employing redundant drop 

protection features which comply with 

CoC No. 1014, Amendment 8, Revision 

No. 1, Appendix A. 

Additionally, CEG provided specific 

information from LSCS’s 72.212 

Evaluation Report, Revision 9, 

indicating that during the design basis 

event of a non-mechanistic tip-over, 

LSCS’s ISFSI would meet the 

requirements in 10 CFR 72.104, 

‘‘Criteria for radioactive materials in 

effluents and direct radiation from an 

ISFSI or MRS,’’ and 10 CFR 72.106, 

‘‘Controlled area of an ISFSI or MRS.’’ 

Specifically, CEG described that, in the 

highly unlikely event of a tip-over, any 

potential fuel damage from a nonmechanistic tip-over event would be 

localized, the confinement barrier 

would be maintained, and the shielding 

material would remain intact. Coupled 

with the distance of the LSCS ISFSI to 

the site area boundary, CEG concluded 

that compliance with 72.104 and 72.106 

is not impacted by approving this 

exemption request. 

The NRC staff reviewed the 

information provided by CEG and 

concludes that issuance of the 

exemption would not endanger life or 

property because the administrative 

controls that CEG has in place at the 

LSCS ISFSI sufficiently minimize the 

possibility of a tip-over or handling 

event, and that the containment 

boundary would be maintained in such 

an event. The staff confirmed that these 

administrative controls are documented 

in the technical specifications and 

UFSAR for the HI–STORM 100 Cask 

System CoC No. 1014, Amendment No. 

8, Revision No. 1, that is used at the 

LSCS site. In addition, the staff 

confirmed that the information provided 

by CEG regarding LSCS’s 72.212 

Evaluation Report, Revision 9, 

demonstrates that the consequences of 

normal and accident conditions would 

be within the regulatory limits of the 10 

CFR 72.104 and 10 CFR 72.106. The 

staff also determined that the requested 

exemption is not related to any aspect 

of the physical security or defense of the 

LSCS ISFSI; therefore, granting the 

exemption would not result in any 

potential impacts to common defense 

and security. 

For these reasons, the NRC staff has 

determined that under the requested 

exemption, the storage system will 

continue to meet the safety 

requirements of 10 CFR part 72 and the 

offsite dose limits of 10 CFR part 20 

and, therefore, will not endanger life or 

property or the common defense and 

security. 

C. The Exemption Is Otherwise in the 

Public Interest 

The proposed exemption would allow 

the four already loaded MPC–68M–CBS 

in the HI–STORM 100 Cask System to 

remain in storage at the LSCS ISFSI, and 

allow CEG to load four MPC–68M–CBS 

in the HI–STORM 100 Cask System in 

the future loading campaign beginning 

in June 2025, at the LSCS ISFSI, even 

though the CBS variant basket design is 

not part of the approved CoC No. 1014, 

Amendment No. 8, Revision No. 1. 

According to CEG, the exemption is in 

the public interest because being unable 

to load fuel into dry storage in the future 

loading campaign would impact CEG’s 

ability to offload fuel from the LSCS 

reactor units, consequently impacting 

continued safe reactor operation. 

CEG stated that further delaying the 

future loading campaign would impact 

its ability to effectively manage the 

margin to full core discharge capability 

in the LSCS Units 1 and 2 spent fuel 

pools. The low spent fuel pool capacity 

would make it difficult to refuel and 

present potential risks to fuel handling 

operations. In addition, a crowded spent 

fuel pool would challenge the decay 

heat removal demand of the pool and 

increase the likelihood of a loss of fuel 

pool cooling event and a fuel handling 

accident. Furthermore, CEG loading 

campaigns are scheduled based on 

availability of the specialized work force 

and equipment that is shared 

throughout the CEG fleet. These 

specialty resources support multiple 

competing priorities, including 

refueling outages, loading campaigns, 

fuel pool cleanouts, fuel inspections, 

fuel handling equipment upgrades and 

maintenance, fuel sipping, new fuel 

receipt, and crane maintenance and 

upgrades. Therefore, the available 

windows to complete cask loading 

campaigns are limited, and any delays 

would have a cascading impact on other 

scheduled specialized activities. CEG 

also considered requesting that Holtec 

provide eight (8) fully compliant 

canisters for the June 2025 campaign; 

however, CEG expects that Holtec will 

not be able to meet this request based 

on current manufacturing schedules. 

Additionally, CEG considered delaying 

the start of the 2025 campaign until 

Amendment 19 of the HISTORM 100 

CoC is approved. This delay would 

result in the LSCS ISFSI campaign 

needing to pull specialty resources 

which would otherwise be required to 

support other CEG refueling and ISFSI 

campaigns. 

For the reasons described by CEG in 

the exemption request, the NRC agrees 

that it is in the public interest to grant 

the exemption. If the exemption is not 

granted, in order to comply with the 

CoC, CEG would have to unload MPC– 

68M–CBS from the HI–STORM 100 

Cask System at the LSCS ISFSI and 

reload into the older design MPC–68M 

to restore compliance with the terms, 

conditions, and specifications of the 

CoC. This would subject onsite 

personnel to additional radiation 

exposures and increase the risk of a 

possible fuel handling accident. 

Furthermore, the removed spent fuel 

would need to be placed in the spent 

fuel pool until it can be loaded into 

another storage cask or remain in the 

spent fuel pool if it is not permitted to 

be loaded into CBS casks for the future 

loadings. As described by CEG, this 

scenario would affect CEG’s ability to 

effectively manage the margin to full 

core discharge capacity and present a 

potential reactivity management risk to 

fuel handling operations during preand post-refueling outages at LSCS. In 

addition, the rescheduling of the 

specialized resources for the future 

loading campaign would impact the 

operations of LSCS. 

Therefore, the staff concludes that 

approving the exemption is in the 

public interest. 

Environmental Consideration 

The NRC staff also considered 

whether there would be any significant 

environmental impacts associated with 

the exemption. For this proposed action, 

the NRC staff performed an 

environmental assessment pursuant to 

10 CFR 51.30. The environmental 

assessment concluded that the proposed 

action would not significantly impact 

the quality of the human environment. 

The NRC staff concluded that the 

proposed action would not result in any 

changes in the types or amounts of any 

radiological or non-radiological 

effluents that may be released offsite, 

and there would be no significant 

increase in occupational or public 

radiation exposure because of the 

proposed action. The environmental 

assessment and the finding of no 

significant impact was published on 

December 20, 2024 (89 FR 104234). 

IV. Conclusion 

Based on these considerations, the 

NRC has 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 

grants CEG an exemption from the 


ddrumheller on DSK120RN23PROD with NOTICES1
Federal Register / Vol. 90, No. 4 / Tuesday, January 7, 2025 / Notices 1201 

requirements of §§ 72.212(a)(2), 

72.212(b)(3), 72.212(b)(5)(i), 

72.212(b)(11), and 72.214 with respect 

to the ongoing storage of four MPC– 

68M–CBS in the HI–STORM 100 Cask 

System and a future loading in the HI– 

STORM 100 Cask System of four new 

MPC–68M–CBS beginning in June 2025. 

This exemption is effective upon 

issuance. 

Dated: December 20, 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. 2025–00116 Filed 1–6–25; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[Docket Nos. 50–277 and 50–278; NRC– 

2024–0214; CEQ ID SEIS–429–00–000– 

1734688863] 

Constellation Energy Generation, LLC; 

Peach Bottom Atomic Power Station, 

Units 2 and 3; Notice of Intent To 

Prepare a Supplement to the 

Supplemental Environmental Impact 

Statement 

AGENCY: Nuclear Regulatory 

Commission. 

ACTION: Notice. 

SUMMARY: The U.S. Nuclear Regulatory 

Commission (NRC, the Commission) 

staff will prepare a supplement to 

NUREG–1437, ‘‘Generic Environmental 

Impact Statement for License Renewal 

of Nuclear Plants,’’ Supplement 10, 

Second Renewal, ‘‘Regarding 

Subsequent License Renewal for Peach 

Bottom Atomic Power Station Units 2 

and 3,’’ dated January 2020 (the final 

supplemental environmental impact 

statement (SEIS)) in order to complete 

its evaluation of the environmental 

impacts of the subsequent license 

renewal (SLR) of Renewed Facility 

Operating License Nos. DPR–44 and 

DPR–56 for Peach Bottom Atomic Power 

Station (Peach Bottom), Units 2 and 3, 

respectively. The supplement will 

address new information since the 

issuance of the final SEIS. A draft of the 

supplement will be issued for public 

comment. 

DATES: January 7, 2025. 

ADDRESSES: Please refer to Docket ID 

NRC–2024–0214 when contacting the 

NRC about the availability of 

information for this action. You may 

obtain publicly available information 

related to this action by any of the 

following methods: 

• Federal Rulemaking website: Go to 

https://www.regulations.gov and search 

for Docket ID NRC–2024–0214. Go to 

https://www.regulations.gov and search 

for Docket ID NRC–2024–0214. 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 in this document (if it is 

available in ADAMS) is provided the 

first time that it is referenced. 

• 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: 

Kevin Folk, telephone: 301–415–6944; 

email: Kevin.Folk@nrc.gov or Karen 

Loomis, telephone: 301–415–5142; 

email: Karen.Loomis@nrc.gov. Both are 

staff in the Office of Nuclear Material 

Safety and Safeguards, U.S. Nuclear 

Regulatory Commission, Washington, 

DC 20555–0001. 

SUPPLEMENTARY INFORMATION: 

I. Background 

By letter dated July 10, 2018 (ADAMS 

Package Accession No. ML18193A689), 

Exelon Generation Company, LLC (now 

operating as Constellation Energy 

Generation, LLC (CEG)) submitted to the 

NRC an application, filed pursuant to 

section 103 of the Atomic Energy Act of 

1954, as amended, and part 54 of title 

10 of the Code of Federal Regulations 

(10 CFR), ‘‘Requirements for Renewal of 

Operating Licenses for Nuclear Power 

Plants,’’ for subsequent renewed facility 

operating licenses with expiration dates 

of August 8, 2053, for Peach Bottom, 

Unit 2 and July 2, 2054, for Peach 

Bottom, Unit 3, which are 20 years 

beyond when the current renewed 

facility operating licenses expire. The 

SLR application included an 

environmental report (ADAMS Package 

Accession No. ML18271A185). Peach 

Bottom is located primarily in Peach 

Bottom Township, York County, 

Pennsylvania, near Delta, Pennsylvania. 

A notice of receipt of the Peach 

Bottom SLR application was published 

in the Federal Register on August 1, 

2018 (83 FR 37529). A notice of 

acceptance for docketing of the 

application and opportunity to request a 

hearing was published in the Federal 

Register on September 6, 2018 (83 FR 

45285). A notice of intent to conduct a 

scoping process and prepare a SEIS was 

published in the Federal Register on 

September 10, 2018 (83 FR 45692). A 

notice of issuance of the draft SEIS and 

request for comment was published in 

the Federal Register on August 7, 2019 

(84 FR 38676). A notice of issuance of 

the final SEIS was published in the 

Federal Register on January 31, 2020 

(85 FR 5725). A notice of issuance of the 

subsequent renewed facility operating 

licenses was published in the Federal 

Register on March 11, 2020 (85 FR 

14247). The issuance of the licenses was 

also supported by an NRC Record of 

Decision (ROD) (ADAMS Accession No. 

ML20024G429). 

The final SEIS (ADAMS Accession 

No. ML20023A937) and the ROD 

document the NRC staff’s environmental 

review, including its recommendation 

that the adverse environmental impacts 

of SLR for Peach Bottom are not so great 

that preserving the option of license 

renewal for energy-planning 

decisionmakers would be unreasonable. 

As discussed in the final SEIS and the 

ROD, the NRC staff considered the 

reasonably foreseeable environmental 

impacts of SLR for Peach Bottom, as 

well as a range of reasonable 

alternatives to SLR. As part of its 

environmental review, the NRC staff 

relied upon NUREG–1437, Revision 1, 

‘‘Generic Environmental Impact 

Statement for License Renewal of 

Nuclear Plants,’’ dated June 2013 

(ADAMS Package Accession No. 

ML13107A023) (the 2013 LR GEIS), to 

meet its obligations under the NRC’s 

environmental protection regulations in 

10 CFR part 51, ‘‘Environmental 

Protection Regulations for Domestic 

Licensing and Related Regulatory 

Functions,’’ and the National 

Environmental Policy Act of 1969, as 

amended. Specifically, for issues 

classified as Category 1 (generic to all or 

a distinct subset of nuclear power 

plants) in the 2013 LR GEIS, the NRC 

staff did not identify new and 

significant information and, therefore, 

relied upon the conclusions of the 2013 


ddrumheller on DSK120RN23PROD with NOTICES1