85682 Federal Register / Vol. 85, No. 249 / Tuesday, December 29, 2020 / Notices 

LICENSE AMENDMENT ISSUANCE(S)—Continued 

Vistra Operations Company LLC; Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2; Somervell County, TX 

Docket No(s) .................................................................. 50–445, 50–446. 

Amendment Date ........................................................... November 16, 2020. 

ADAMS Accession No ................................................... ML20168A924. 

Amendment No(s) .......................................................... 176 (Unit 1) and 176 (Unit 2). 

Brief Description of Amendment(s) ................................ The amendments revised Technical Specification 3.4.15, ‘‘RCS [Reactor Coolant System] Leakage Detection Instrumentation,’’ to align with the Standard Technical Specifications for Westinghouse Plants and incorporated the changes made by Technical Specifications Task Force (TSTF) Traveler TSTF–513, Revision 3, ‘‘Revise PWR [Pressurized-Water Reactor] Operability Requirements and Actions for RCS Leakage Instrumentation.’’. 

Public Comments Received as to Proposed NSHC 

(Yes/No).

No. 

Wolf Creek Nuclear Operating Corporation; Wolf Creek Generating Station, Unit 1; Coffey County, KS 

Docket No(s) .................................................................. 50–482. 

Amendment Date ........................................................... December 7, 2020. 

ADAMS Accession No. .................................................. ML20276A149. 

Amendment No(s) .......................................................... 226. 

Brief Description of Amendment(s) ................................ The amendment revised Technical Specification 5.5.16, ‘‘Containment Leakage Rate Testing Program,’’ to 

extend the Type A and Type C leak rate test frequencies. Specifically, the change allows the extension of 

the Type A integrated leakage rate test containment test interval to 15 years and the extension of the 

Type C local leakage rate test interval to 75 months. 

Public Comments Received as to Proposed NSHC 

(Yes/No).

No. 

Dated: December 18, 2020. 

For the Nuclear Regulatory Commission. 

Caroline L. Carusone, 

Deputy Director, Division of Operating 

Reactor Licensing, Office of Nuclear Reactor 

Regulation. 

[FR Doc. 2020–28442 Filed 12–28–20; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[NRC–2012–0110] 

Acceptability of Probabilistic Risk 

Assessment Results for Risk-Informed 

Activities 

AGENCY: Nuclear Regulatory 

Commission. 

ACTION: Regulatory guide; issuance. 

SUMMARY: The U.S. Nuclear Regulatory 

Commission (NRC) is issuing Revision 3 

to Regulatory Guide (RG) 1.200, 

‘‘Acceptability of Probabilistic Risk 

Assessment Results for Risk-Informed 

Activities.’’ Revision 3 describes one 

acceptable approach for determining 

whether a base probabilistic risk 

assessment (PRA), in total or the 

portions that are used to support an 

application, is acceptable to provide 

confidence in the results, such that the 

PRA can be used in regulatory 

decisionmaking for light-water reactors 

(LWRs). When used in support of an 

application, the use of this RG will 

obviate the need for an in-depth review 

of the base PRA by NRC reviewers, 

allowing them to focus their review on 

key assumptions and areas identified by 

peer reviewers. 

DATES: Revision 3 to RG 1.200 is 

available on December 29, 2020. 

ADDRESSES: Please refer to Docket ID 

NRC–2012–0110 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–2012–0110. Address 

questions about Docket IDs in 

Regulations.gov to Jennifer Borges; 

telephone: 301–287–9127; email: 

Jennifer.Borges@nrc.gov. For technical 

questions, contact the individuals 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. 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. 

• 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 between 8:00 a.m. and 

4:00 p.m. (EST), Monday through 

Friday, except Federal holidays. 

Regulatory guides are not 

copyrighted, and NRC approval is not 

required to reproduce them. 

FOR FURTHER INFORMATION CONTACT: 

Anders Gilbertson, telephone: 301–415– 

1541, email: Anders.Gilbertson@nrc.gov, 

and Harriet Karagiannis, telephone: 

301–415–2493, email: 

Harriet.Karagiannis@nrc.gov. Both are 

staff of the Office of Nuclear Regulatory 

Research, U.S. Nuclear Regulatory 

Commission, Washington, DC 20555– 

0001. 

SUPPLEMENTARY INFORMATION: 

I. Discussion 

The NRC is issuing a revision to an 

existing guide in the NRC’s ‘‘Regulatory 

Guide’’ series. This series was 

developed to describe and make 

available to the public information 

regarding methods that are acceptable to 

the NRC staff for implementing specific 

parts of the agency’s regulations, 

techniques that the NRC staff uses in 

evaluating specific issues or postulated 

events, and data that the NRC staff 

needs in its review of applications for 

permits and licenses. Regulatory guides 

are not NRC regulations and compliance 

with them is not required. Methods and 

solutions that differ from those set forth 

in RGs are acceptable if supported by a 

basis for the issuance or continuance of 

a permit or license by the Commission. 

Revision 3 to RG 1.200 was issued 

with a temporary identification of Draft 

Regulatory Guide, DG–1362 (ADAMS 

Accession No. ML19308B636). RG 1.200 

(Revision 3) describes one acceptable 

approach for determining whether the 

base PRA, in total or the portions that 

are used to support an application, is 


KHAMMOND on DSKJM1Z7X2PROD with NOTICES
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