23892 Federal Register / Vol. 87, No. 77 / Thursday, April 21, 2022 / Notices 

Revision 1 of RG 1.183 of the same 

name. 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 (MHA) 

loss-of-coolant accident (LOCA) to 

define the accident described in 

regulation, (2) adding transient release 

fractions from empirical data from inpile, 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 the 

proposed Revision 1 may provide useful 

information for satisfying the 

radiological dose analysis requirements 

in part 50 of title 10 of the Code of 

Federal Regulations (10 CFR), 

‘‘Domestic Licensing of Production and 

Utilization Facilities’’ and 10 CFR part 

52, ‘‘Licenses, Certifications, and 

Approvals for Nuclear Power Plants,’’ 

for advanced LWR design and siting, (5) 

providing additional guidance for 

modeling boiling-water reactor (BWR) 

main steam isolation valve (MSIV) 

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 holdup 

and retention of MSIV leakage within 

the main steam lines and condenser for 

BWRs, and (9) providing additional 

meteorological assumption guidance. 

On October 14, 2009, the NRC staff 

issued DG–1199, ‘‘Alternative 

Radiological Source Terms for 

Evaluating Design Basis Accidents at 

Nuclear Power Reactors,’’ (ADAMS 

Accession No. ML090960464), for 

public comment (74 FR 52822). DG– 

1199 was a proposed Revision 1 to RG 

1.183. The NRC staff has elected not to 

finalize DG–1199 and is issuing DG– 

1389 as a replacement. The staff notes 

that DG–1389 addresses technical issues 

and considered public comments 

related to the issuance of DG–1199. 

The staff is also issuing for public 

comment a draft regulatory analysis 

(ADAMS Accession No. ML21204A066). 

The staff developed a regulatory 

analysis to assess the value of issuing or 

revising a regulatory guide as well as 

alternative courses of action. 

III. Backfitting, Forward Fitting, and 

Issue Finality 

The NRC staff may use this RG, if 

finalized, as a reference in its regulatory 

processes, such as licensing, inspection, 

or enforcement. However, the NRC staff 

does not intend to use the guidance in 

this RG to support NRC staff actions in 

a manner that would constitute 

backfitting as that term is 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), nor does 

the NRC staff intend to use the guidance 

to affect the issue finality of an approval 

under 10 CFR part 52. The staff also 

does not intend to use the guidance to 

support NRC staff actions in a manner 

that constitutes forward fitting as that 

term is defined and described in MD 

8.4. If a licensee believes that the NRC 

is using this RG in a manner 

inconsistent with the discussion in this 

Implementation section, then the 

licensee may file a backfitting or 

forward fitting appeal with the NRC in 

accordance with the process in MD 8.4. 

IV. Specific Request for Comment 

In addition to the general request for 

comments on DG–1389, the NRC is also 

seeking specific comments on a 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) that is 

referenced in the draft revised guidance. 

The technical assessment provides the 

proposed technical basis for the low risk 

of gross failure of the alternate pathway 

to the condenser at seismic 

accelerations at or below a plant’s 

design basis safe shutdown earthquake, 

as described in DG–1389. The technical 

assessment also supports a proposed 

streamlined approach in DG–1389 for 

demonstrating the seismic capacity of 

structures, systems, and components in 

the alternate pathway, compared to the 

approach in RG 1.183, Revision 0 

(ADAMS Accession No. ML003716792). 

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: April 18, 2022. 

For the Nuclear Regulatory Commission. 

Meraj Rahimi, 

Chief, Regulatory Guide and Programs 

Management Branch, Division of Engineering, 

Office of Nuclear Regulatory Research. 

[FR Doc. 2022–08519 Filed 4–20–22; 8:45 am] 

BILLING CODE 7590–01–P 

RAILROAD RETIREMENT BOARD 

Actuarial Advisory Committee With 

Respect to the Railroad Retirement 

Account; Notice of Public Meeting 

Notice is hereby given in accordance 

with Public Law 92–463 that the 

Actuarial Advisory Committee will hold 

a virtual meeting on May 13, 2022, at 

1:00 p.m. (Central Daylight Time) on the 

conduct of the 2022 Annual Report 

Required by the Railroad Retirement Act 

of 1974 and the Railroad Retirement 

Solvency Act of 1983. The agenda for 

this meeting will include a discussion of 

the assumptions to be used in the 

Annual Report. A report containing 

recommended assumptions and the 

experience on which the 

recommendations are based will have 

been sent by the Chief Actuary to the 

Committee before the meeting. 

The meeting will be open to the 

public. Persons wishing to submit 

written statements, make oral 

presentations, or attend the meeting 

should address their communications or 

notices to Patricia Pruitt 

(Patricia.Pruitt@rrb.gov) so that 

information on how to join the virtual 

meeting can be provided. 

Dated: April 18, 2022. 

Stephanie Hillyard, 

Secretary to the Board. 

[FR Doc. 2022–08542 Filed 4–20–22; 8:45 am] 

BILLING CODE 7905–01–P 


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