Federal Register / Vol. 86, No. 11 / Tuesday, January 19, 2021 / Notices 5267 

Appendix H, ‘‘Disposition of Public 

Comments,’’ of the final ISG. 

This ISG updates NUREG–2191, 

‘‘Generic Aging Lessons Learned for 

Subsequent License Renewal (GALL– 

SLR) Report,’’ and NUREG–2192, 

‘‘Standard Review Plan for Review of 

Subsequent License Renewal 

Applications for Nuclear Power Plants.’’ 

NUREG–2191 and NUREG–2192 were 

published in July 2017, and a full 

review and revision to these documents 

is not scheduled to be performed for 

several years. The staff has reviewed the 

first three subsequent license renewal 

applications (SLRAs) that were based on 

the above guidance documents. During 

these reviews, the staff and applicants 

identified improvements to the 

guidance that would assist in preparing 

and reviewing future SLRAs more 

effectively and efficiently. This ISG 

provides an interim update to NUREG– 

2191 and NUREG–2192 to implement 

these improvements. 

This ISG is not intended for 

standalone use. It provides revisions to 

NUREG–2191 and NUREG–2192 

sections and tables that supersede the 

content in the NUREGs and is intended 

to be used within the context of the 

NUREGs. The revisions captured in this 

ISG include: 

• Updates to GALL–SLR Report aging 

management program XI.M16A, ‘‘PWR 

Vessel Internals’’; 

• changes to aging management 

review items in NUREG–2191 tables and 

corresponding summary tables in 

NUREG–2192; 

• new aging management review 

items in NUREG–2191 tables and 

corresponding summary tables in 

NUREG–2192; 

• changes to NUREG–2192 ‘‘further 

evaluation’’ guidance sections; 

• updates to references listed in 

affected NUREG–2191 sections; and 

• editorial corrections to relevant 

sections. 

II. Availability of Documents 

The documents identified in the 

following table are available to 

interested persons in ADAMS, as 

indicated. 

Document ADAMS accession No. 

NUREG–2191, ‘‘Generic Aging Lessons Learned for Subsequent License Renewal (GALL–SLR) Report’’ ............... ML16274A389 (Vol. 1) 

ML16274A399 (Vol. 2). 

NUREG–2192, ‘‘Standard Review Plan for Review of Subsequent License Renewal Applications for Nuclear Power 

Plants’’.

ML16274A402. 

Draft SLR–ISG–PWRVI–2020–XX, ‘‘Updated Aging Management Criteria for Reactor Vessel Internal Components 

for Pressurized-Water Reactors’’.

ML20156A343. 

Final SLR–ISG–2021–01–PWRVI, ‘‘Updated Aging Management Criteria for Reactor Vessel Internal Components 

for Pressurized-Water Reactors’’.

ML20217L203. 

March 28, 2019, Summary of Category 2 Public Meeting on Lessons Learned from the Review of the First Subsequent License Renewal Applications.ML19112A206. 

Summary of December 12, 2019, Category 2 Public Meeting on Lessons Learned from the Review of the First 

Subsequent License Renewal Applications.

ML20016A347. 

February 20, 2020, Summary of Category 2 Public Meeting on Lessons Learned from the Review of the First Subsequent License Renewal Applications.ML20076E074. 

Summary of March 25, 2020 Meeting with Industry Related to Revisions to Subsequent License Renewal Guidance Documents.ML20107F702. 

Summary of April 3, 2020, Meeting with Industry Regarding Changes to Subsequent License Renewal Guidance 

Documents.

ML20107F733. 

Summary of April 7, 2020, Meeting with Industry Regarding Revisions to the Subsequent License Renewal Guidance Documents.ML20107F699. 

Comment Letter (1) of Christopher Koehler and Brian Burgos, on behalf of the Electric Power Research Institute, 

Subject: ‘‘Industry Comments to Draft Interim Staff Guidance (ISG)–SLR–ISG–PWRVI–2020–XX’’.

ML20245E539. 

Comment Letter (2) of Peter W. Kissinger, on behalf of Nuclear Energy Institute, Subject: ‘‘Comments on the proposed changes to subsequent license renewal document SLR–ISG–PWRVI–2020–XX’’.ML20246G654. 

III. Backfit Discussion 

This ISG intends to revise guidance 

for the NRC staff reviewing SLRAs and 

for prospective applicants in preparing 

SLRAs. Issuance of this ISG does not 

constitute a backfit as defined in section 

50.109(a)(1) of title 10 of the Code of 

Federal Regulations (10 CFR) and is not 

otherwise inconsistent with the issue 

finality provisions in 10 CFR part 52. As 

discussed in the ‘‘Backfitting’’ section of 

the final ISG, the ISG positions do not 

constitute backfitting inasmuch as the 

ISG is guidance directed to the NRC 

staff with respect to its regulatory 

responsibilities and to applicants who 

choose to follow the guidance. 

Applicants and potential applicants are 

not, with certain exceptions, the subject 

of either the backfit rule or any issue 

finality provisions under 10 CFR part 

52. The NRC staff has no intention to 

impose the ISG positions on existing 

nuclear power plant licensees either 

now or in the future (absent a voluntary 

request for a change from the licensee). 

IV. Congressional Review Act 

This ISG 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. 

Dated: January 13, 2021. 

For the Nuclear Regulatory Commission. 

Robert Caldwell, 

Deputy Director, Division of New and 

Renewed Licenses, Office of Nuclear Reactor 

Regulation. 

[FR Doc. 2021–01041 Filed 1–15–21; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[NRC–2020–0279] 

Application and Testing of SafetyRelated Diesel Generators in Nuclear 

Power Plants 

AGENCY: Nuclear Regulatory 

Commission. 

ACTION: Draft regulatory guide; request 

for comment. 

SUMMARY: The U.S. Nuclear Regulatory 

Commission (NRC) is issuing for public 

comment draft regulatory guide (DG), 

DG–1303, ‘‘Application and Testing of 

Safety-Related Diesel Generators in 

Nuclear Power.’’ This draft guide is 

proposed revision 5 of Regularity Guide 

(RG) 1.9. DG–1303 provides updated 

guidance that the staff of the NRC 

considers acceptable to demonstrate 


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5268 Federal Register / Vol. 86, No. 11 / Tuesday, January 19, 2021 / Notices 

compliance with the NRC regulations 

for safety-related alternating current 

(AC) power supplies intended for use as 

onsite emergency power sources in 

nuclear power plants. This revision of 

RG 1.9 would endorse, with 

supplements and clarifications, Institute 

of Electrical and Electronics Engineers 

(IEEE) Std 387–2017, ‘‘IEEE Standard for 

Criteria for Diesel Generator Units 

Applied as Standby Power Supplies for 

Nuclear Power Generating Stations’’ and 

IEEE Std 2420–2019, ‘‘IEEE Standard for 

Combustion Turbine Generator Units 

Applied as Standby Power Supplies for 

Nuclear Power Generating Stations.’’ 

This guidance would help ensure that 

the standby emergency power supplies 

are qualified, have sufficient capacity, 

and have the necessary reliability and 

availability for design-basis events. 

DATES: Submit comments by February 

18, 2021. Comments received after this 

date will be considered if it is practical 

to do so, but the NRC is able to ensure 

consideration only for comments 

received on or before this date. 

Although a time limit is given, 

comments and suggestions in 

connection with items for inclusion in 

guides currently being developed or 

improvements in all published guides 

are encouraged at any time. 

ADDRESSES: You may submit comments 

by any of the following methods; 

however, the NRC encourages electronic 

comment submission through the 

Federal Rulemaking website: 

• Federal Rulemaking website: Go to 

https://www.regulations.gov and search 

for Docket ID NRC–2020–0279. 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. 

• Mail comments to: Office of 

Administration, Mail Stop: TWFN–7– 

A60M, U.S. Nuclear Regulatory 

Commission, Washington, DC 20555– 

0001, ATTN: Program Management, 

Announcements and Editing Staff. 

For additional direction on accessing 

information and submitting comments, 

see ‘‘Obtaining Information and 

Submitting Comments’’ in the 

SUPPLEMENTARY INFORMATION section of 

this document. 

FOR FURTHER INFORMATION CONTACT: 

Lilianna Ramadan, telephone: 301–415– 

2463, email: Liliana.Ramadan@nrc.gov, 

and Stanley Gardocki, telephone: 301– 

415–1067, email: Stanley.Gardocki@

nrc.gov. Both are staff of the Office of 

Nuclear Regulatory Research, U.S. 

Nuclear Regulatory Commission, 

Washington, DC 20555–0001. 

SUPPLEMENTARY INFORMATION: 

I. Obtaining Information and 

Submitting Comments 

A. Obtaining Information 

Please refer to Docket ID NRC–2020– 

0279 when contacting the NRC about 

the availability of information regarding 

this action. You may obtain publicly 

available information related to this 

action, by any of the following methods: 

• Federal Rulemaking Website: Go to 

https://www.regulations.gov and search 

for Docket ID NRC–2020–0279. 

• 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. 

B. Submitting Comments 

The NRC encourages electronic 

comment submission through the 

Federal Rulemaking website (https://

www.regulations.gov). Please include 

Docket ID NRC–2020–0279 in your 

comment submission. 

The NRC cautions you not to include 

identifying or contact information that 

you do not want to be publicly 

disclosed in your comment submission. 

The NRC posts all comment 

submissions at https://

www.regulations.gov/ as well as enters 

the comment submissions into ADAMS. 

The NRC does not routinely edit 

comment submissions to remove 

identifying or contact information. 

If you are requesting or aggregating 

comments from other persons for 

submission to the NRC, then you should 

inform those persons not to include 

identifying or contact information that 

they do not want to be publicly 

disclosed in their comment submission. 

Your request should state that the NRC 

does not routinely edit comment 

submissions to remove such information 

before making the comment 

submissions available to the public or 

entering the comment submissions into 

ADAMS. 

II. Additional Information 

The NRC is issuing for public 

comment a draft regulatory guide 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 NRC’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. 

This DG titled, ‘‘Application and 

Testing of Safety-Related Diesel 

Generators in Nuclear Power Plants,’’ is 

identified by its temporary task number, 

DG–1303. The draft guide is proposed 

revision 5 of RG 1.9 of the same name 

(ADAMS Accession No. ML14281A071). 

This DG provides updated guidance for 

actions and information that is needed 

for licensees, applicants, and combined 

operating license (COL) holders to meet 

the NRC regulations for safety-related 

standby AC power supplies intended for 

use as onsite emergency power sources 

in nuclear power plants. Information 

provided in this DG may be used by 

NRC staff, applicants, COLs holders, 

and licensees. This guidance helps 

ensure that the emergency standby AC 

power supplies are qualified, have 

sufficient capacity, and have the 

necessary reliability and availability for 

design-basis events. 

The staff is also issuing for public 

comment a draft regulatory analysis 

(ADAMS Accession No. ML14297A097). 

The staff develops 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 

DG–1303, if finalized, would revise 

RG 1.9, revision 4, which describes 

methods acceptable to the NRC staff for 

complying with the NRC’s regulations 

for safety-related standby AC power 

supplies intended for use as onsite 

emergency power sources in nuclear 

power plants. 

Issuance of DG–1303, if finalized, 

would not constitute backfitting as 

defined in section 50.109 of title 10 of 

the Code of Federal Regulations (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 


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Federal Register / Vol. 86, No. 11 / Tuesday, January 19, 2021 / Notices 5269 

issue finality of any approval issued 

under 10 CFR part 52. As explained in 

DG–1303, applicants and licensees 

would not be required to comply with 

the positions set forth in DG–1303. 

Dated: January 12, 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. 2021–00940 Filed 1–15–21; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[Docket Nos. 50–334, 50–412, 50–456, 50– 

457, 50–259, 50–260, 50–296, 50–325, 50– 

324, 50–454, 50–455, 50–317, 50–318, 50– 

413, 50–414, 50–461, 50–397, 50–445, 50– 

446, 50–298, 50–346, 50–275, 50–323, 50– 

315, 50–316, 50–237, 50–249, 50–321, 50– 

366, 50–341, 50–354, 50–272, 50–311, 50– 

003, 50–247, 50–286, 50–333, 50–348, 50– 

364, 50–261, 50–373, 50–374, 50–352, 50– 

353, 50–369, 50–370, 50–245, 50–336, 50– 

423, 50–263, 50–220, 50–410, 50–338, 50– 

339, 50–269, 50–270, 50–287, 50–243, 50– 

255, 50–528, 50–529, 50–530, 50–277, 50– 

278, 50–440, 50–266, 50–301, 50–282, 50– 

306, 50–254, 50–265, 50–244, 50–458, 50– 

335, 50–389, 50–443, 50–400, 50–498, 50– 

499, 50–280, 50–281, 50–387, 50–388, 50– 

395, 50–424, 50–425, 50–382, 50–390, 50– 

391; NRC–2020–0110] 

Issuance of Multiple Exemptions in 

Response to COVID–19 Public Health 

Emergency 

AGENCY: Nuclear Regulatory 

Commission. 

ACTION: Exemptions; issuance. 

SUMMARY: The U.S. Nuclear Regulatory 

Commission (NRC) issued 68 

exemptions in response to requests from 

26 licensees. The exemptions afford 

these licensees temporary or permanent 

relief from certain requirements under 

NRC regulations. The exemptions are in 

response to the licensees’ requests for 

relief due to the coronavirus disease 

2019 (COVID–19) public health 

emergency (PHE). The NRC is issuing a 

single notice to announce the issuance 

of the exemptions. 

DATES: During the period from 

December 1, 2020, to December 28, 

2020, the NRC granted 68 exemptions in 

response to requests submitted by 

licensees from September 30, 2020, to 

December 23, 2020. 

ADDRESSES: Please refer to Docket ID 

NRC–2020–0110 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–2020–0110. Address 

questions about NRC Docket IDs in 

Regulations.gov to Jennifer Borges; 

telephone: 301–287–9127; email: 

Jennifer.Borges@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. 

• 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. 

For the convenience of the reader, 

instructions about obtaining materials 

referenced in this document are 

provided in the ‘‘Availability of 

Documents’’ section. 

FOR FURTHER INFORMATION CONTACT: 

James Danna, Office of Nuclear Reactor 

Regulation, U.S. Nuclear Regulatory 

Commission, Washington DC 20555– 

0001; telephone: 301–415–7422, email: 

James.Danna@nrc.gov. 

SUPPLEMENTARY INFORMATION: 

I. Introduction 

During the period from December 1, 

2020, to December 28, 2020, the NRC 

granted 68 exemptions in response to 

requests submitted by licensees from 

September 30, 2020, to December 23, 

2020. These exemptions allow the 

licensees to deviate from certain 

requirements (as cited in this notice) of 

various parts of chapter I of title 10 of 

the Code of Federal Regulations (10 

CFR). 

The exemptions from certain 

requirements of 10 CFR part 26, 

‘‘Fitness for Duty Programs,’’ for Exelon 

Generation Company, LLC (for 

Braidwood Station, Units 1 and 2; Byron 

Station, Unit Nos. 1 and 2; Clinton 

Power Station, Unit No. 1; LaSalle 

County Station, Units 1 and 2; and Quad 

Cities Nuclear Power Station, Units 1 

and 2); for Vistra Operations Company 

LLC (for Comanche Peak Nuclear Power 

Plant, Unit Nos. 1 and 2); for Arizona 

Public Service Company (for Palo Verde 

Nuclear Generating Station, Units 1, 2, 

and 3); for PSEG Nuclear LLC (for Hope 

Creek Generating Station and Salem 

Nuclear Generating Station, Unit Nos. 1 

and 2); and for Indiana Michigan Power 

Company (for Donald C. Cook Nuclear 

Plant, Unit Nos. 1 and 2), afford these 

licensees temporary relief from the 

work-hour controls under 10 CFR 

26.205(d)(1) through (d)(7). The 

exemptions from 10 CFR 26.205(d)(1) 

through (d)(7) ensure that the control of 

work hours and management of worker 

fatigue do not unduly limit licensee 

flexibility in using personnel resources 

to most effectively manage the impacts 

of the COVID–19 PHE on maintaining 

the safe operation of these facilities. 

Specifically, these licensees have stated 

that their staffing levels are affected or 

are expected to be affected by the 

COVID–19 PHE, and they can no longer 

meet or likely will not meet the workhour controls of 10 CFR 26.205(d)(1) 

through (d)(7). These licensees have 

committed to effecting site-specific 

administrative controls for COVID–19 

PHE fatigue management for personnel 

specified in 10 CFR 26.4(a). 

The exemptions from certain 

requirements of 10 CFR part 50, 

appendix E, ‘‘Emergency Planning and 

Preparedness for Production and 

Utilization Facilities,’’ section IV.F., 

‘‘Training,’’ for Energy Northwest (for 

Columbia Generating Station); for DTE 

Electric Company (for Fermi-2); for 

PSEG Nuclear LLC (for Hope Creek 

Generating Station and Salem Nuclear 

Generating Station, Unit Nos. 1 and 2); 

for Entergy Nuclear Operations, Inc. (for 

Indian Point Nuclear Generating 

Station, Unit Nos. 1, 2, and 3; and 

Palisades Nuclear Plant); for Virginia 

Electric and Power Company (for North 

Anna Power Station, Unit Nos. 1 and 2); 

for Exelon Generation Company, LLC 

(for LaSalle County Station, Units 1 and 

2); for Oregon State University (for the 

Oregon State TRIGA Reactor); for 

Entergy Operations, Inc. (for River Bend 

Station, Unit 1); for NextEra Energy 

Seabrook, LLC (for Seabrook Station, 

Unit No. 1), grant temporary exemptions 

from the biennial emergency 

preparedness exercise requirement. The 

exemptions allow a temporary 

exemption from the requirements of 10 

CFR part 50, appendix E, regarding the 

conduct of the biennial emergency 

preparedness exercise. These 

exemptions will not adversely affect the 

emergency response capability of the 

facilities because affected licensee 


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