Federal Register / Vol. 85, No. 249 / Tuesday, December 29, 2020 / Notices 85683 

sufficient to provide confidence in the 

results, such that the PRA can be used 

in regulatory decisionmaking for LWRs. 

Also, it addresses new industry 

guidance and enhancements identified 

since the last revision was issued in 

March 2009. Specifically, this revision 

endorses, with staff clarifications and 

exceptions, the American Society of 

Mechanical Engineers (ASME) and 

American Nuclear Society (ANS) 

Standard ASME/ANS RA–Sa–2009, 

‘‘Standard for Level 1/Large Early 

Release Frequency Probabilistic Risk 

Assessment for Nuclear Power Plant 

Applications’’; the ASME/ANS standard 

ASME/ANS RA–S Case 1 for seismic 

PRA, ‘‘Case for ASME/ANS RA–Sb– 

2013 Standard for Level 1/Large Early 

Release Frequency Probabilistic Risk 

Assessment of Nuclear Power Plant 

Applications’’; Nuclear Energy Institute 

(NEI) 17–07, Revision 2, ‘‘Performance 

of PRA Peer Reviews Using the ASME/ 

ANS PRA Standard’’ (ADAMS 

Accession No. ML19241A615); and 

Pressurized Water Reactor Owners 

Group (PWROG) report PWROG–19027– 

NP, Revision 2, ‘‘Newly Developed 

Method Requirements and Peer Review’’ 

(ADAMS Accession No. ML20213C660). 

This revision of the RG further provides 

for a peer review of newly developed 

methods, clarifies the process for 

determining how to classify changes to 

a PRA, provides definitions related to 

newly developed methods and other 

PRA terms, and enhances guidance 

related to key assumptions and sources 

of uncertainty. 

II. Additional Information 

The NRC published a notice of the 

availability of DG–1362 in the Federal 

Register on July 1, 2020 (85 FR 39599) 

for a 30-day public comment period. 

The public comment period closed on 

July 31, 2020. Public comments on DG– 

1362 and the staff responses to the 

public comments are available in 

ADAMS under Accession No. 

ML20238B873. Revision 3 to RG 1.200 

may be found in ADAMS under 

Accession No. ML20238B871. 

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 

This RG provides one acceptable 

approach for determining whether the 

base PRA, in total or the portions that 

are used to support an application, is 

sufficient to provide confidence in the 

results, such that the PRA can be used 

in regulatory decisionmaking for LWRs. 

Issuance of this RG does not constitute 

backfitting as defined in section 50.109 

of title 10 of the Code of Federal 

Regulations (10 CFR), ‘‘Backfitting,’’ and 

as described in NRC Management 

Directive 8.4, ‘‘Management of 

Backfitting, Forward Fitting, Issue 

Finality, and Information Requests’’ 

(ADAMS Accession No. ML18093B087); 

does not constitute forward fitting as 

that term is defined and described in 

Management Directive 8.4; and does not 

affect the issue finality of any approval 

issued under 10 CFR part 52, ‘‘Licenses, 

Certificates, and Approvals for Nuclear 

Power Plants.’’ As explained in this RG, 

applicants and licensees are not 

required to comply with the positions 

set forth in this RG. 

Dated: December 21, 2020. 

For the Nuclear Regulatory Commission. 

Robert G. Roche-Rivera, 

Acting Chief, Regulatory Guidance and 

Generic Issues Branch, Division of 

Engineering, Office of Nuclear Regulatory 

Research. 

[FR Doc. 2020–28632 Filed 12–28–20; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[Docket Nos. 50–338–SLR and 50–339–SLR; 

ASLBP No. 21–970–01–SLR–01] 

Virginia Electric and Power Company; 

Establishment of Atomic Safety and 

Licensing Board 

Pursuant to delegation by the 

Commission, see 37 FR 28,710 (Dec. 29, 

1972), and 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: 

Virginia Electric and Power Company 

(North Anna Power Station, Units 1 and 

2) 

This proceeding involves an 

application seeking a twenty-year 

subsequent license renewal of Renewed 

Facility Operating License Nos. NPF–4 

and NPF–7, which currently authorize 

Virginia Electric and Power Company to 

operate the North Anna Power 

Company, Units 1 and 2, located in 

Louisa, Virginia, until, respectively, 

April 1, 2038 and August 21, 2040. In 

response to a notice published in the 

Federal Register announcing the 

opportunity to request a hearing, see 85 

FR 65,438 (Oct. 15, 2020), a hearing 

request was filed on December 14, 2020 

on behalf of Beyond Nuclear, Sierra 

Club, and Alliance for Progressive 

Virginia. 

The Board is comprised of the 

following Administrative Judges: 

G. Paul Bollwerk, III, Chairman, 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. December 21, 2020. 

Edward R. Hawkens, 

Chief Administrative Judge, Atomic Safety 

and Licensing Board Panel. 

[FR Doc. 2020–28634 Filed 12–28–20; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[NRC–2020–0237] 

Considerations for Estimating SiteSpecific Probable Maximum 

Precipitation at Nuclear Power Plants 

in the United States of America 

AGENCY: Nuclear Regulatory 

Commission. 

ACTION: Draft NUREG; request for 

comment. 

SUMMARY: The U.S. Nuclear Regulatory 

Commission (NRC) is issuing for public 

comment a draft NUREG, knowledge 

management NUREG, NUREG/KM– 

0015, ‘‘Considerations for Estimating 

Site-Specific Probable Maximum 

Precipitation at Nuclear Power Plants in 

the United States of America.’’ The NRC 

Staff and Oak Ridge National Laboratory 

have prepared a reference document 

summarizing recent lessons-learned in 

connection with a review of the sitespecific probable maximum 

precipitation (SSPMP) estimates used by 

some nuclear power plant owners and 

operators in connection with a recent reevaluation of external flooding at their 

respective project sites. 

DATES: Submit comments by March 1, 

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 before this date. 


KHAMMOND on DSKJM1Z7X2PROD with NOTICES