Federal Register / Vol. 88, No. 198 / Monday, October 16, 2023 / Rules and Regulations 71277 

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Illinois (7) 

City Colleges of Chicago—Richard J Daley 

College 

College of Lake County 

Dominican University 

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Goshen College 

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University of Nevada—Las Vegas 

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Atlantic Cape Community College 

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Rutgers University—Newark 

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New Mexico (8) 

Central New Mexico Community College 

Eastern New Mexico University—Main 

Campus 

Eastern New Mexico University—Roswell 

Campus 

Northern New Mexico College 

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University of New Mexico—Los Alamos 

Campus 

University of New Mexico—Main Campus 

Western New Mexico University 

New York (15) 

CUNY Bronx Community College 

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Ponce 

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San German 

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Rico—Ponce 

Universidad Ana G. Mendez—Carolina 

Campus 

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Campus 

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Yakima Valley College 

Done at Washington, DC, this day of 

October 10, 2023. 

Drenda Williams, 

Associate Director for Operations, National 

Institute of Food and Agriculture, U.S. 

Department of Agriculture. 

[FR Doc. 2023–22718 Filed 10–13–23; 8:45 am] 

BILLING CODE 3410–22–P 

NUCLEAR REGULATORY 

COMMISSION 

10 CFR Parts 50 and 52 

[NRC–2021–0179] 

Regulatory Guide: Alternative 

Radiological Source Terms for 

Evaluating Design Basis Accidents at 

Nuclear Power Reactors 

AGENCY: Nuclear Regulatory 

Commission. 

ACTION: Final guide; issuance. 

SUMMARY: The U.S. Nuclear Regulatory 

Commission (NRC) is issuing Revision 1 

to Regulatory Guide (RG), 1.183, 

‘‘Alternative Radiological Source Terms 

for Evaluating Design Basis Accidents at 

Nuclear Power Reactors.’’ This RG 

describes a method that the NRC staff 

considers acceptable in complying with 

regulations for design basis accident 

dose consequence analysis using an 

alternative source term. This guidance 

for light-water reactor (LWR) designs 

includes the scope, nature, and 

documentation of associated analyses 

and evaluations; consideration of 

impacts on analyzed risk; and content of 

submittals. 

DATES: Revision 1 to RG 1.183 is 

available on October 16, 2023. 

ADDRESSES: Please refer to Docket ID 

NRC–2021–0179 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–2021–0179. 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 individuals listed 

in the FOR FURTHER INFORMATION

CONTACT section of this document. 


ddrumheller on DSK120RN23PROD with RULES1
71278 Federal Register / Vol. 88, No. 198 / Monday, October 16, 2023 / Rules and Regulations 

• 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. 

Revision 1 to RG 1.183 and the 

regulatory analysis may be found in 

ADAMS under Accession Nos. 

ML23082A305 and ML21204A066, 

respectively. 

Regulatory guides are not 

copyrighted, and NRC approval is not 

required to reproduce them. 

FOR FURTHER INFORMATION CONTACT: 

Michael Eudy, Office of Nuclear 

Regulatory Research, telephone: 301– 

415–3104, email: Michael.Eudy@

nrc.gov, Mark Blumberg, Office of 

Nuclear Reactor Regulation, telephone: 

301–415–1083, email: Mark.Blumberg@

nrc.gov, and Joseph Messina, Office of 

Nuclear Reactor Regulation, telephone: 

301–415–4226, email: Joseph.Messina@

nrc.gov. All are staff of the U.S. Nuclear 

Regulatory Commission, Washington, 

DC 20555–0001. 

SUPPLEMENTARY INFORMATION: 

I. Discussion 

The NRC is issuing a revision in the 

NRC’s ‘‘Regulatory Guide’’ series. This 

series was developed to describe 

methods that are acceptable to the NRC 

staff for implementing specific parts of 

the agency’s regulations, to explain 

techniques that the staff uses in 

evaluating specific issues or postulated 

events, and to describe information that 

the staff needs in its review of 

applications for permits and licenses. 

The proposed Revision 1 to RG 1.183 

was issued with a temporary 

identification of Draft Regulatory Guide, 

DG–1389. (ADAMS Accession No. 

ML21204A065). 

This revision of the guide (Revision 1) 

addresses new issues identified since 

the guide was originally issued. These 

include (1) using the term maximum 

hypothetical accident loss-of-coolant 

accident (LOCA) to clarify the accident 

that the staff finds acceptable to use to 

meet the description in the applicable 

regulations, identified in Section A of 

RG 1.183, Revision 1, with a clear 

delineation between source term 

assumptions and plant response; (2) 

adding transient release fractions from 

empirical data from in-pile, prompt 

power pulse test programs and analyses 

from several international publications 

of fuel rod performance under prompt 

power excursion conditions; (3) revising 

steady-state release fractions for 

accidents other than the LOCA based on 

a revision to the American National 

Standards Institute/American Nuclear 

Society Standard 5.4, ‘‘Method for 

Calculating the Fractional Release of 

Volatile Fission Products from Oxide 

Fuel’’; (4) adding information to 

acknowledge that the RG may provide 

useful information for satisfying the 

radiological dose analysis requirements 

in parts 50 and 52 of title 10 of the Code 

of Federal Regulations (10 CFR), for new 

LWR applicants, including advanced 

evolutionary and passive LWR design 

and siting; (5) providing additional 

guidance for modeling boiling-water 

reactor main steam isolation valve 

leakage; (6) adding guidance for 

accident tolerant fuel, high-burnup fuel, 

and increased enrichment source term 

analyses; (7) revising transport and 

decontamination models for the fuel 

handling design basis accident; (8) 

adding guidance for crediting hold-up 

and retention of main steam isolation 

valve leakage within the main 

steamlines and condenser for boilingwater reactors; and (9) providing 

additional guidance on meteorological 

assumptions. 

II. Additional Information 

The NRC published a notice of the 

availability of DG–1389 in the Federal 

Register on April 21, 2022 (87 FR 

23891) for a 60-day public comment 

period. The public comment period 

closed on June 21, 2022. Public 

comments on DG–1389 and the staff 

responses to the public comments are 

available under ADAMS under 

Accession No. ML23082A309. 

In the notice of availability for DG– 

1389, Section IV, ‘‘Specific Request for 

Comment,’’ the NRC sought specific 

comments on the draft staff technical 

assessment titled, ‘‘Technical 

Assessment of Hold-up and Retention of 

Main Steam Isolation Valve Leakage 

within the Main Steam Lines and Main 

Condenser’’ (ADAMS Accession No. 

ML20085J042); the NRC staff did not 

receive any public comments on the 

draft staff technical assessment. At this 

time, the staff has determined to 

incorporate the supporting technical 

basis information from that draft staff 

technical assessment into RG 1.183, 

Revision 1, Appendix A, Section A–5.5, 

rather than finalizing the draft staff 

technical assessment separately for 

inclusion in this RG. Accordingly, the 

reference to the draft staff technical 

assessment was deleted from the final 

RG. 

As noted in the Federal Register on 

December 9, 2022 (87 FR 75671), this 

document is being published in the 

‘‘Rules’’ section of the Federal Register 

to comply with publication 

requirements under 1 CFR chapter I. 

III. Congressional Review Act 

This RG is a rule as defined in the 

Congressional Review Act (5 U.S.C. 

801–808). However, the Office of 

Management and Budget has not found 

it to be a major rule as defined in the 

Congressional Review Act. 

IV. Backfitting, Forward Fitting, and 

Issue Finality 

Issuance of RG 1.183, Revision 1, does 

not constitute backfitting as defined in 

10 CFR 50.109, ‘‘Backfitting,’’ and as 

described in NRC Management Directive 

(MD) 8.4, ‘‘Management of Backfitting, 

Forward Fitting, Issue Finality, and 

Information Requests’’ (ADAMS 

Accession No. ML18093B087); affect the 

issue finality of an approval under 10 

CFR part 52; or constitute forward 

fitting as defined and described in MD 

8.4 because, as explained in RG 1.183, 

Revision 1, applicants and licensees are 

not required to comply with the 

positions set forth in this RG. 

V. Submitting Suggestions for 

Improvement of Regulatory Guides 

A member of the public may, at any 

time, submit suggestions to the NRC for 

improvement of existing RGs or for the 

development of new RGs. Suggestions 

can be submitted on the NRC’s public 

website at https://www.nrc.gov/readingrm/doc-collections/reg-guides/ 

contactus.html. Suggestions will be 

considered in future updates and 

enhancements to the ‘‘Regulatory 

Guide’’ series. 

Dated: October 11, 2023. 

For the Nuclear Regulatory Commission. 

Stephen M. Wyman, 

Acting Chief, Regulatory Guide and Programs 

Management Branch, Division of Engineering, 

Office of Nuclear Regulatory Research. 

[FR Doc. 2023–22789 Filed 10–13–23; 8:45 am] 

BILLING CODE 7590–01–P 


ddrumheller on DSK120RN23PROD with RULES1