Federal Register / Vol. 86, No. 33 / Monday, February 22, 2021 / Notices 10601 

NATIONAL SCIENCE FOUNDATION 

Advisory Committee for Environmental 

Research and Education Notice of 

Meeting 

In accordance with the Federal Advisory 

Committee Act (Pub. L. 92–463, as amended), 

the National Science Foundation (NSF) 

announces the following meeting: 

NAME AND COMMITTEE CODE: Advisory 

Committee for Environmental Research 

and Education (9487). 

DATE AND TIME: March 18, 2021; 11:00 

a.m.—5:30 p.m. 

PLACE: National Science Foundation, 

2415 Eisenhower Avenue, Alexandria, 

VA 22314 √ Videoconference. Interested 

parties can register to join via 

teleconference at: https://

nsf.zoomgov.com/meeting/register/ 

vJItcuygrzwoEiu7Xv

04t0Roz4lO1NTmASo. 

Closed Caption will be available at: 

https://www.captionedtext.com/client/ 

event.aspx?EventID=4714537

&CustomerID=321 

TYPE OF MEETING: Open. 

CONTACT PERSON: Gayle Pugh Lev, 

Office of Integrative Activities/Office of 

the Director/National Science 

Foundation, 2415 Eisenhower Avenue, 

Alexandria, VA 22314. (Email: acerepoc@nsf.gov; Telephone: (703) 292– 

8040). 

MINUTES: Will be available on the AC’s 

website at: https://www.nsf.gov/ere/ 

ereweb/minutes.jsp 

PURPOSE OF MEETING: To provide 

advice, recommendations, and oversight 

concerning support for environmental 

research and education. 

AGENDA: To discuss subcommittee work 

and prepare for future advisory 

committee activities. Updated agenda 

will be available at https://www.nsf.gov/ 

ere/ereweb/minutes.jsp. 

Dated: February 17, 2021. 

Crystal Robinson, 

Committee Management Officer. 

[FR Doc. 2021–03475 Filed 2–19–21; 8:45 am] 

BILLING CODE 7555–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[NRC–2020–0171] 

Setpoints for Safety-Related 

Instrumentation 

AGENCY: Nuclear Regulatory 

Commission. 

ACTION: Regulatory guide; issuance. 

SUMMARY: The U.S. Nuclear Regulatory 

Commission (NRC) is issuing Revision 4 

to Regulatory Guide (RG) 1.105, 

‘‘Setpoints for Safety-Related 

Instrumentation.’’ This RG describes an 

approach that is acceptable to the staff 

of the NRC to meet regulatory 

requirements ensuring that setpoints for 

safety-related instrumentation are 

established and maintained within the 

technical specification limits. RG 1.105 

has been revised to incorporate 

additional information regarding 

American National Standards Institute 

(ANSI)/International Society of 

Automation (ISA) Standard 67.04.01– 

2018, ‘‘Setpoints for Nuclear Safety 

Related Instrumentation.’’ 

DATES: Revision 4 to RG 1.105 is 

available on February 22, 2021. 

ADDRESSES: Please refer to Docket ID 

NRC–2020–0171 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–2020–0171. 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. 

• 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. 

• 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. (EST), 

Monday through Friday, except Federal 

holidays. 

Revision 4 to RG 1.105 and the 

Regulatory Analysis may be found in 

ADAMS under Accession Nos. 

ML20330A329 and ML20055G824, 

respectively. 

Regulatory guides are not 

copyrighted, and NRC approval is not 

required to reproduce them. 

FOR FURTHER INFORMATION CONTACT: 

Dawnmathews Kalathiveettil, Office of 

Nuclear Reactor Regulation, telephone: 

301–415–5905, email: 

Dawnmathews.Kalathiveettil@nrc.gov, 

and Michael Eudy, Office of Nuclear 

Regulatory Research, telephone: 301– 

415–3104, email: Michael.Eudy@

nrc.gov. Both are staff of the 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. 

Revision 4 to RG 1.105 endorses 

ANSI/ISA 67.04.01–2018 as a method 

acceptable to the NRC staff for satisfying 

the NRC’s regulations for ensuring that: 

(a) setpoints for safety-related 

instrumentation are established to 

protect plant safety and analytical 

limits, and (b) the maintenance of 

instrument channels implementing 

these setpoints ensures they are 

functioning as required, consistent with 

the plant technical specifications. This 

RG applies to licensees and applicants 

subject to 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.’’ 

II. Additional Information 

Revision 4 of RG 1.105 was issued 

with a temporary identification of Draft 

Regulatory Guide, DG–1363, titled, 

‘‘Setpoints for Safety-Related 

Instrumentation,’’ (ADAMS Accession 

No. ML20055G823). The NRC published 

a notice of the availability of DG–1363 

in the Federal Register on August 14, 

2020 (85 FR 49685) for a 30-day public 

comment period. The public comment 

period closed on September 14, 2020, 

and the NRC received 24 comment 

documents. Public comments on DG– 

1363 and the staff responses to the 

public comments are available in 

ADAMS under Accession No. 

ML20330A328. 

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 


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10602 Federal Register / Vol. 86, No. 33 / Monday, February 22, 2021 / Notices 

it to be a major rule as defined in the 

Congressional Review Act. 

IV. Backfitting, Forward Fitting, and 

Issue Finality 

Revision 4 of RG 1.105 endorses 

ANSI/ISA 67.04.01–2018 and 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’’; constitute 

forward fitting as that term is defined 

and described in MD 8.4; or affect the 

issue finality of any approval issued 

under 10 CFR part 52. As explained in 

Revision 4 to RG 1.105, applicants and 

licensees are not required to comply 

with the positions set forth in the RG. 

Dated: February 16, 2021. 

For the Nuclear Regulatory Commission. 

Meraj Rahimi, 

Chief, Regulatory Guidance and Generic 

Issues Branch, Division of Engineering, Office 

of Nuclear Regulatory Research. 

[FR Doc. 2021–03466 Filed 2–19–21; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[NRC–2020–0159] 

Design Limits, Loading Combinations, 

Materials, Construction and Testing of 

Concrete Containments 

AGENCY: Nuclear Regulatory 

Commission. 

ACTION: Regulatory guide; issuance. 

SUMMARY: The U.S. Nuclear Regulatory 

Commission (NRC) is issuing Revision 4 

to Regulatory Guide (RG) 1.136, ‘‘Design 

Limits, Loading Combinations, 

Materials, Construction and Testing of 

Concrete Containments.’’ It updates the 

guidance for materials, design, 

construction, fabrication, examination, 

and testing of concrete containments in 

nuclear power plants through 

endorsement, with exceptions, of the 

2019 edition of the American Society of 

Mechanical Engineers (ASME) Boiler & 

Pressure Vessel (B&PV) Code, Section 

III, Division 2 (American Concrete 

Institute (ACI) Standard 359–19), ‘‘Code 

for Concrete Containments.’’ 

DATES: Revision 4 to RG 1.136 is 

available on February 22, 2021. 

ADDRESSES: Please refer to Docket ID 

NRC–2020–0159 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–2020–0159. 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. Revision 4 to RG 1.136 and the 

regulatory analysis may be found in 

ADAMS under Accession Nos. 

ML20301A167 and ML20105A216, 

respectively. 

• 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. (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: 

George Thomas, Office of Nuclear 

Reactor Regulation, telephone: 301– 

415–6181, email: George.Thomas2@

nrc.gov and Edward O’Donnell, Office of 

Nuclear Regulatory Research, telephone: 

301–415–3317, email: 

Edward.ODonnell@nrc.gov. Both are 

staff of the 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, 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. 

Revision 4 of RG 1.136 was issued 

with a temporary identification of Draft 

Regulatory Guide, DG–1372. This 

revision provides guidance to meet 

regulatory requirements for materials, 

design, construction, fabrication, 

examination, and testing of concrete 

containments in nuclear power plants. 

This revision of the guide endorses, 

with exceptions, the 2019 edition of 

Division 2 of the ASME B&PV Code, 

Section III (ACI Standard 359–19), 

‘‘Code for Concrete Containments.’’ This 

revision of the guide also addresses the 

acceptability of the Section III Code 

Cases related to Division 2 of the ASME 

B&PV Code, Section III. 

II. Additional Information 

The NRC published a notice of the 

availability of DG–1372 in the Federal 

Register on July 8, 2020 (85 FR 41071) 

for a 60-day public comment period. 

The public comment period closed on 

September 8, 2020. Public comments on 

DG–1372 and the staff responses to the 

public comments are available in 

ADAMS under Accession No. 

ML20301A168. 

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 regulatory guide provides 

guidance for materials, design, 

construction, fabrication, examination, 

and testing of concrete containments in 

nuclear power plants through 

endorsement, with exceptions, of the 

2019 edition of Division 2 of the ASME 

B&PV Code, Section III (ACI Standard 

359–19), ‘‘Code for Concrete 

Containments.’’ The issuance of this 

regulatory guide does not constitute 

backfitting as defined in section 50.109 

of title 10 of the Code of Federal 

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

described in NRC Management Directive 

8.4, ‘‘Management of Backfitting, 

Forward Fitting, Issue Finality, and 

Information Requests,’’ or affect issue 

finality of any approval issued under 10 

CFR part 52, ‘‘Licenses, Certificates, and 

Approvals for Nuclear Power Plants,’’ 

because, as explained in this regulatory 

guide, licensees are not required to 

comply with the positions set forth in 

this regulatory guide. 

Dated: February 16, 2021. 


tkelley on DSKBCP9HB2PROD with NOTICES