Federal Register / Vol. 86, No. 150 / Monday, August 9, 2021 / Notices 43567 

Comments may be submitted either by 

email or by mail: 

To submit 

comments: Send them to: 

By email ......... pubcomment-ees.enrd@

usdoj.gov. 

By mail ........... Assistant Attorney General, 

U.S. DOJ—ENRD, P.O. 

Box 7611, Washington, 

DC 20044–7611. 

During the public comment period, 

the consent decree may be examined 

and downloaded at this Justice 

Department website: https://

www.justice.gov/enrd/consent-decrees. 

We will provide a paper copy of the 

consent decree upon written request 

and payment of reproduction costs. 

Please mail your request and payment 

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Please enclose a check or money order 

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reproduction cost) payable to the United 

States Treasury. 

Susan Akers, 

Assistant Section Chief, Environmental 

Enforcement Section, Environment and 

Natural Resources Division. 

[FR Doc. 2021–16892 Filed 8–6–21; 8:45 am] 

BILLING CODE 4410–15–P 

NUCLEAR REGULATORY 

COMMISSION 

[Docket Nos. 50–424 and 50–425; NRC– 

2021–0086] 

Southern Nuclear Operating Company, 

Inc; Vogtle Electric Generating Plant, 

Units 1 and 2 

AGENCY: Nuclear Regulatory 

Commission. 

ACTION: Exemptions; issuance. 

SUMMARY: The U.S. Nuclear Regulatory 

Commission (NRC) has issued 

exemptions from certain portions of the 

acceptance criteria for emergency core 

cooling systems to allow the use of a 

risk-informed methodology in lieu of a 

deterministic methodology to evaluate 

the effects of debris in containment 

following a loss-of-coolant accident for 

the Vogtle Electric Generating Plant, 

Units 1 and 2 (Vogtle), located in Burke 

County, Georgia. The exemptions are in 

response to a request dated August 17, 

2020, as supplemented by letters dated 

December 17, 2020, and February 15, 

2021, from the Southern Nuclear 

Operating Company, Inc. (SNC, the 

licensee). 

DATES: The exemptions were issued on 

July 30, 2021. 

ADDRESSES: Please refer to Docket ID 

NRC–2021–0086 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–2021–0086. 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, 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. 

• Attention: The PDR, where you may 

examine and order copies of public 

documents, is currently closed. You 

may submit your request to the PDR via 

email at pdr.resource@nrc.gov or call 1– 

800–397–4209 or 301–415–4737, 

between 8:00 a.m. and 4:00 p.m. (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 exemptions is attached. 

Dated: August 3, 2021. 

For the Nuclear Regulatory Commission. 

John G. Lamb, 

Senior Project Manager, Plant Licensing 

Branch 2–1, Division of Operating Reactor 

Licensing, Office of Nuclear Reactor 

Regulation. 

Attachment—Exemption 

NUCLEAR REGULATORY 

COMMISSION 

Docket Nos. 50–424 and 50–425 

Southern Nuclear Operating Company, 

Inc. Vogtle Electric Generating Plant, 

Units 1 and 2 Exemptions 

I. Background 

Southern Nuclear Operating 

Company, Inc. (SNC, the licensee) is the 

holder of Renewed Facility Operating 

License Nos. NPF–68 and NPF–81, 

which authorize operation of Vogtle 

Electric Generating Plant (Vogtle), Units 

1 and 2, respectively. The licenses 

provide, among other things, that the 

facility is subject to all applicable rules, 

regulations, and orders of the U.S. 

Nuclear Regulatory Commission (NRC, 

the Commission) now or hereafter in 

effect. The facility consists of two 

pressurized-water reactors (PWRs) 

located in Burke County, Georgia. 

In 1996, the NRC identified Generic 

Safety Issue (GSl)-191 associated with 

the effects of debris accumulation on 

PWR sump performance during designbasis accidents (Agencywide Documents 

Access and Management System 

(ADAMS) Accession No. 

ML030160807). As part of the actions to 

resolve GSl-191, the NRC issued Generic 

Letter (GL) 2004–02, ‘‘Potential Impact 

of Debris Blockage on Emergency 

Recirculation during Design Basis 

Accidents at Pressurized-Water 

Reactors,’’ dated September 13, 2004 

(ADAMS Accession No. ML042360586), 

to holders of operating licenses for 

PWRs. In GL 2004–02, the NRC staff 

requested that these licensees perform 

an evaluation of the emergency core 

cooling system (ECCS) and the 

containment spray system (CSS) 

recirculation functions considering the 

potential for debris-laden coolant to be 

circulated by the ECCS and the CSS 

after a loss-of-coolant accident (LOCA) 

or high-energy line break inside 

containment and, if appropriate, take 

additional actions to ensure system 

function. The GL required that these 

licensees provide a written response to 

the NRC, pursuant to title 10 of the Code 

of Federal Regulations (10 CFR) section 

50.54(f), describing the results of their 

evaluation and any modifications made, 

or planned, to ensure that the ECCS and 

the CSS remain functional. 


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43568 Federal Register / Vol. 86, No. 150 / Monday, August 9, 2021 / Notices 

II. Request/Action 

By letter dated August 17, 2020 

(ADAMS Accession No. ML20230A346), 

as supplemented by letters dated 

December 17, 2020, and February 15, 

2021 (ADAMS Accession Nos. 

ML20352A228 and ML21046A094, 

respectively), SNC requested for the 

NRC to grant exemptions under 10 CFR 

50.12, ‘‘Specific exemptions,’’ from 

certain requirements in 10 CFR 50.46, 

‘‘Acceptance criteria for emergency core 

cooling systems for light-water nuclear 

power reactors,’’ for Vogtle, Units 1 and 

2. The request for exemptions from SNC 

relates to using a specific risk-informed 

methodology to evaluate the effects of 

debris on long-term core cooling in lieu 

of a deterministic methodology. 

III. Discussion 

Pursuant to 10 CFR 50.12, the 

Commission may, upon application by 

any interested person or upon its own 

initiative, grant exemptions from the 

requirements of 10 CFR part 50 when (1) 

the exemptions are authorized by law, 

will not present an undue risk to the 

public health and safety, and are 

consistent with the common defense 

and security and (2) special 

circumstances are present. Under 10 

CFR 50.12(a)(2)(ii), special 

circumstances are present when 

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. Under 

10 CFR 50.12(a)(2)(iii), special 

circumstances are present when 

compliance would result in undue 

hardship or other costs that are 

significantly in excess of those 

contemplated when the regulation was 

adopted, or that are significantly in 

excess of those incurred by others 

similarly situated. 

SNC submitted a request for 

exemptions under 10 CFR 50.12 for 

Vogtle, Units 1 and 2 from certain 

requirements of 10 CFR 50.46(a)(1) as it 

relates to using specific deterministic 

methodology to evaluate the effects of 

debris generated from breaks on longterm core cooling. SNC stated that the 

scope of the requested exemptions 

applies to all debris effects addressed in 

the risk-informed element of the Vogtle 

methodology described in SNC’s July 

2018 submittal responding to GL 2004– 

02 (ADAMS Accession Nos. 

ML18193B163 and ML18193B165). SNC 

stated that the addressed debris effects 

are those associated with breaks that 

potentially generate and transport debris 

amounts that exceed the Vogtle-specific 

analyzed debris limit. 

SNC is requesting exemptions related 

to these breaks to allow evaluation of 

the debris effects using a risk-informed 

methodology in lieu of a deterministic 

methodology. The licensee stated that 

the key elements of the exemption 

request are that (1) the exemptions will 

apply only to the effects of debris as 

described in Enclosures 2 and 3 of the 

submittal dated July 2018 and (2) the 

exemptions will apply to any breaks 

that can generate and transport debris 

that is not bounded by Vogtle-specific 

analyzed debris limits, provided that the 

delta core damage frequency (DCDF) and 

delta large early release frequency 

(DLERF) remain within the acceptance 

guidelines identified as Region III in 

Regulatory Guide (RG) 1.174, ‘‘An 

Approach for Using Probabilistic Risk 

Assessment in Risk-Informed Decisions 

on Plant-Specific Changes to the 

Licensing Basis,’’ Revision 3, dated 

January 2018 (ADAMS Accession No. 

ML17317A256). 

By letter dated September 30, 2019, 

‘‘Final Staff Evaluation for Vogtle 

Electric Generating Plant, Units 1 and 2, 

Systematic Risk-Informed Assessment of 

Debris Technical Report’’ (ADAMS 

Accession No. ML19120A469), the NRC 

staff found that the subject technical 

report enclosed with SNC’s July 2018 

submittal was acceptable for use in 

plant-specific licensing applications for 

Vogtle in accordance with the 

limitations and conditions section and 

applicability provided in the enclosed 

NRC staff evaluation. Except for 

downstream effects—fuel and vessel, 

and licensing basis, the NRC staff 

concluded that the technical report 

contained sufficient information to 

address the information requested in GL 

2004–02. 

The NRC staff performed an 

integrated review of the risk-informed 

approach proposed to be used in lieu of 

a deterministic methodology by the 

requested exemptions, considering the 

five key principles of risk-informed 

decision-making set forth in RG 1.174. 

The five key principles are: (1) The 

proposed change meets the current 

regulations unless it is explicitly relates 

to a requested exemption; (2) the 

proposed change is consistent with the 

defense-in-depth philosophy; (3) the 

proposed change maintains sufficient 

safety margins; (4) when proposed 

changes result in an increase in risk, the 

increases should be small and 

consistent with the intent of the 

Commission’s policy statement on 

safety goals for the operations of nuclear 

power plants (51 FR 30028); and (5) the 

impact of the proposed change should 

be monitored using performance 

measurement strategies. 

The NRC staff finds that the proposed 

risk-informed approach meets the five 

key principles in RG 1.174. The 

proposed risk-informed approach is 

consistent with the defense-in-depth 

philosophy, maintains sufficient safety 

margins, and is monitored using 

performance measurement strategies. 

The proposed risk-informed approach 

also explicitly relates to a requested 

exemption. Finally, the Vogtle risk 

evaluation results show that the risk 

associated with post-accident debris 

effects is within RG 1.174, Region Ill 

acceptance guidelines as a ‘‘Very Small 

Change,’’ and, therefore, is consistent 

with the intent of the Commission’s 

policy statement on safety goals for the 

operations of nuclear power plants. 

A. The Exemptions Are Authorized by 

Law 

The exemptions to use a riskinformed methodology would allow 

SNC to show compliance with 10 CFR 

50.46(a)(1) when considering debris in 

containment generated and transported 

during a postulated LOCA. This 

regulation was promulgated under 

Section 161 of the Atomic Energy Act of 

1954, as amended (AEA), and this 

regulation is consistent with the 

Commission’s authority under Section 

161 of the AEA. Because the application 

of a risk-informed methodology to show 

compliance with 10 CFR 50.46 would 

not violate the AEA or the 

Commission’s regulations, the 

exemptions are authorized by law. 

B. The Exemptions Present No Undue 

Risk to the Public Health and Safety 

The provisions of 10 CFR 50.46 

establish criteria for the ECCS 

performance. SNC submitted a request 

for exemptions under 10 CFR 50.12 for 

Vogtle, Units 1 and 2 from certain 

requirements of 10 CFR 50.46(a)(1) as it 

relates to using specific deterministic 

methodology to evaluate the effects of 

debris generated from breaks on longterm core cooling. The licensee justified 

its requested exemptions by stating that 

they are consistent with the purpose of 

the requirements in that the use of the 

proposed risk-informed approach would 

account for the effects of debris on the 

ECCS cooling performance and would 

support a high probability of successful 

ECCS performance, based on the risk 

results meeting the acceptance 

guidelines of RG 1.174. Additionally, 

the licensee stated that the Vogtle, Units 

1 and 2 risk quantification showed that 

the changes in DCDF and DLERF are 

below the threshold for RG 1.174, 

Region Ill, ‘‘Very Small Changes,’’ 

without significant plant modifications. 

The licensee stated that the proposed 


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Federal Register / Vol. 86, No. 150 / Monday, August 9, 2021 / Notices 43569 

risk-informed approach would provide 

an equivalent level of assurance for 

sump performance without incurring 

significant cost and occupational dose 

associated with removing, replacing, or 

reinforcing insulation in containment. 

The NRC staff finds that the risk 

associated with the requested 

exemptions is consistent with the 

guidance in RG 1.174 for the use of 

probabilistic risk assessment and with 

the Commission’s policy statement on 

safety goals for the operations of nuclear 

power plants; therefore, the requested 

exemptions present no undue risk to the 

public health and safety. 

C. The Exemptions Are Consistent With 

the Common Defense and Security 

The requested exemptions would 

allow the use of a risk-informed 

methodology to allow SNC to resolve a 

generic safety concern for PWRs 

associated with the potential clogging of 

the ECCS and CSS strainers during 

certain design-basis events. The 

proposed change would be adequately 

controlled by safety acceptance criteria 

and technical specification 

requirements and is not related to 

security issues. Because the common 

defense and security is not impacted by 

the requested exemptions, the requested 

exemptions are consistent with the 

common defense and security. 

D. Special Circumstances Are Present 

The requested exemptions from 10 

CFR 50.46(a)(1) would allow SNC to use 

a risk-informed methodology in lieu of 

a deterministic methodology to show 

conformance with the ECCS and CSS 

performance criteria accounting for 

debris in containment for LOCAs. In its 

request, SNC cited the special 

circumstances criteria of 10 CFR 

50.12(a)(2)(ii) and (iii) and stated that 

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 and that 

compliance would result in undue 

hardship or other costs that are 

significantly in excess of those 

contemplated when the regulation was 

adopted, or that are significantly in 

excess of those incurred by others 

similarly situated. 

The licensee stated that the intent of 

10 CFR 50.46(a)(1) is to ensure that 

ECCS cooling performance design 

requirements imposed by 10 CFR 50.46 

are determined by a rigorous method 

that provides a high level of confidence 

in ECCS performance. SNC stated that 

its proposed risk-informed approach 

accounts for the effects of debris on the 

ECCS cooling performance and supports 

a high probability of successful ECCS 

performance based on the risk results 

meeting the acceptance guidelines of RG 

1.174. 

The licensee also stated that in order 

to meet a deterministic threshold value 

for sump debris loads, the debris 

sources in containment would need to 

be significantly reduced. SNC stated 

that the amount of radiological exposure 

received during the removal and/or 

modification of insulation from the 

Vogtle, Units 1 and 2 containments is 

dependent on the scope of the changes. 

The licensee stated that the expected 

total dose for replacing insulation in 

Vogtle, Units 1 and 2 is estimated 

generically to be about 200 roentgen 

equivalent man (rem) (100 rem per unit) 

based on the South Texas Project pilot 

submittal. 

The licensee concluded that the 

special circumstances described in 10 

CFR 50.12(a)(2)(ii) and (iii) would apply 

to its requested exemptions. 

The NRC staff evaluated the 

exemption request and summarized its 

evaluation of the proposed riskinformed approach in a safety 

evaluation (ADAMS Accession No. 

ML20268A070). Since 10 CFR 

50.46(a)(1) requires a deterministic 

approach, an exemption is an 

appropriate means to grant the licensee 

relief to use an alternative, riskinformed approach. The underlying 

purpose of the regulation is to protect 

the public health and safety in the event 

of a LOCA by establishing criteria for 

the ECCS. In its safety evaluation, the 

NRC staff concluded, in part, that the 

licensee adequately demonstrated that 

the change in risk attributable to debris 

in postulated LOCAs is very small. The 

NRC staff also concluded that the 

licensee’s proposal for demonstrating 

compliance with the ECCS and the CSS 

performance requirements meets the 

risk acceptance guidelines in RG 1.174, 

because the approach is related to a 

permissible exemption request, is 

consistent with defense-in-depth 

philosophy, maintains sufficient safety 

margins, results in a small increase in 

risk, and the impact of the approach is 

monitored by the licensee using 

performance measurement strategies. 

Therefore, the NRC staff finds that the 

licensee’s use of the proposed riskinformed approach to consider the 

impacts of debris meets the underlying 

intent of 10 CFR 50.46 to ensure that a 

licensee demonstrates that the ECCS 

and the CSS will provide adequate 

cooling for the reactor core and 

containment, as well as containment 

atmosphere cleanup, following 

postulated design-basis accidents. 

The NRC staff also finds that the 

licensee demonstrated that using the 

required deterministic approach as 

opposed to the proposed risk-informed 

approach would result in undue 

hardship or other costs that are 

significantly in excess of those 

contemplated when the regulation was 

adopted, or that are significantly in 

excess of those incurred by others 

similarly situated. 

Based on the above, the NRC staff 

concludes that the special 

circumstances described in 10 CFR 

50.12(a)(2)(ii) and (iii) are present for 

the requested exemptions. 

E. Environmental Considerations 

The regulations in 10 CFR 51.21, 

‘‘Criteria for and identification of 

licensing and regulatory actions 

requiring environmental assessments,’’ 

generally provide that NRC licensing 

and regulatory actions require an 

environmental assessment (EA) except 

those identified in 10 CFR 51.20(b) as 

requiring an environmental impact 

statement, those identified in 10 CFR 

51.22(c) as categorical exclusions, and 

those identified in 10 CFR 51.22(d) as 

other actions not requiring 

environmental review. These 

regulations also provide that the NRC 

may, in special circumstances, prepare 

an EA on an action covered by a 

categorical exclusion. Typically, 

exemptions are identified in 10 CFR 

51.22(c) as categorical exclusions; 

however, because the requested 

exemptions propose a novel riskinformed approach to the requirements 

in 10 CFR 50.46(a)(1), the NRC staff 

determined that special circumstances 

were present and prepared an EA. As 

discussed in the EA and the associated 

Finding of No Significant Impact 

published in the Federal Register on 

April 7, 2021, 2021 (86 FR 18076) and 

in accordance with 10 CFR 51.31(a), the 

Commission has determined that 

granting the requested exemptions will 

not have a significant effect on the 

quality of the human environment. 

IV. Conclusion 

Accordingly, the Commission has 

determined, pursuant to 10 CFR 50.12, 

that the requested exemptions are 

authorized by law, will not present an 

undue risk to the public health and 

safety, and are consistent with the 

common defense and security and that 

special circumstances are present. 

Therefore, the Commission hereby 

grants SNC’s request for exemptions 

under 10 CFR 50.12 for Vogtle, Units 1 

and 2, from 10 CFR 50.46(a)(1) to allow 

the use of a risk-informed methodology 

in lieu of a deterministic methodology 


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43570 Federal Register / Vol. 86, No. 150 / Monday, August 9, 2021 / Notices 

to show conformance with the ECCS 

and CSS performance criteria 

accounting for debris in containment for 

LOCAs. 

V. 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 

ADAMS Accession 

No./Federal 

Register citation 

SNC letter, ‘‘Exemption Request and License Amendment Request for a Risk-Informed Resolution to GSI–191,’’ dated August 17, 2020.ML20230A346 

SNC letter, ‘‘Response to Request for Additional Information Regarding Risk-Informed Resolution to GSI–191,’’ dated December 17, 2020.ML20352A228 

SNC letter, ‘‘Supplement to Request for Exemption to Support Risk-Informed Resolution to Generic Letter 2004–02,’’ dated 

February 15, 2021.

ML21046A094 

NRC Generic Letter 2004–02, ‘‘Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors,’’ dated September 13, 2004.ML042360586 

Regulatory Guide 1.174, Revision 3, ‘‘An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on 

Plant-Specific Changes to the Licensing Basis,’’ dated January 2018.

ML17317A256 

NRC Safety Evaluation, Vogtle, Units 1 and 2—Amendments for a Risk-Informed Resolution to GSI–191, dated July 30, 

2021.

ML20268A070 

SNC Letter ‘‘Vogtle Electric Generating Plant—Units 1 & 2, Supplemental Response to NRC Generic Letter 2004–02,’’ 

dated July 10, 2018.

ML18193B163 and 

ML18193B165 

NRC letter, ‘‘Final Staff Evaluation for Gotle Electric Generating Plant, Units 1 and 2, Systematic Risk-Informed Assessment 

of Debris Tenical Report,’’ dated September 30, 2019.

ML19120A469 

NRC, ‘‘Safety Goals for the Operations of Nuclear Power Plants; Policy Statement; Republication,’’ dated August 21, 1986 51 FR 30028 

Dated: July 30, 2021. 

For the Nuclear Regulatory Commission. 

/RA/ 

Caroline L. Carusone, 

Deputy Director, Division of Operating 

Reactor Licensing, Office of Nuclear Reactor 

Regulation. 

[FR Doc. 2021–16899 Filed 8–6–21; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[Docket No. 50–331; NRC–2020–0148] 

NextEra Energy Duane Arnold, LLC; 

Duane Arnold Energy Center; PostShutdown Decommissioning Activities 

Report 

AGENCY: Nuclear Regulatory 

Commission. 

ACTION: Extension of comment period. 

SUMMARY: On June 19, 2020, the U.S. 

Nuclear Regulatory Commission (NRC) 

solicited comments on the postshutdown decommissioning activities 

report (PSDAR) for the Duane Arnold 

Energy Center (DAEC). The PSDAR, 

which includes the site-specific 

decommissioning cost estimate (DCE), 

provides an overview of NextEra Energy 

Duane Arnold, LLC’s (NEDA or the 

licensee’s) planned decommissioning 

activities, schedule, projected costs, and 

environmental impacts for DAEC. The 

public comment period closed on 

October 19, 2020, was reopened on 

October 26, 2020, closed again on 

February 19, 2021, was reopened on 

March 5, 2021, and will currently close 

on August 19, 2021. The NRC has 

decided to extend the public comment 

period for a third time to provide 

additional time for members of the 

public to develop and submit their 

comments, as well as to allow time for 

an in-person public meeting on the 

PSDAR. The NRC will hold a public 

meeting to discuss the PSDAR’s content 

and receive comments once restrictions 

associated with the Coronavirus Disease 

2019 public health emergency are lifted, 

and will notice this meeting in a 

separate Federal Register notice. 

DATES: The comment period for the 

document published on June 19, 2020 

(85 FR 37116) has been extended. 

Comments should be filed no later than 

December 20, 2021. Comments received 

after this date will be considered, if it 

is practical to do so, but the 

Commission is able to ensure 

consideration only for comments 

received on or before this date. 

ADDRESSES: You may submit comments 

by any of the following methods; 

however, the NRC encourages electronic 

comment submission through the 

Federal Rulemaking website: 

• Federal Rulemaking Website: Go to 

https://www.regulations.gov and search 

for Docket ID NRC–2020–0148. 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. 

• Mail comments to: Office of 

Administration, Mail Stop: TWFN–7– 

A60M, U.S. Nuclear Regulatory 

Commission, Washington, DC 20555– 

0001, ATTN: Program Management, 

Announcements and Editing Staff. 

For additional direction on obtaining 

information and submitting comments, 

see ‘‘Obtaining Information and 

Submitting Comments’’ in the 

SUPPLEMENTARY INFORMATION section of 

this document. 

FOR FURTHER INFORMATION CONTACT: 

Marlayna V. Doell, Office of Nuclear 

Materials Safety and Safeguards, U.S. 

Nuclear Regulatory Commission, 

Washington, DC 20555–0001, telephone: 

301–415–3178; email: Marlayna.Doell@

nrc.gov. 

SUPPLEMENTARY INFORMATION: 

I. Obtaining Information and 

Submitting Comments 

A. Obtaining Information 

Please refer to Docket ID NRC–2020– 

0148 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–2020–0148. 

• 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, 301– 

415–4737, or by email to pdr.resource@

nrc.gov. The ADAMS accession number 


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