Federal Register / Vol. 81, No. 26 / Tuesday, February 9, 2016 / Notices 6897 

Document ADAMS accession 

No. 

Section 11.1, ‘‘Coolant Source Terms,’’ Revision 4 ................................................................................................................... ML15029A022 

Section 11.2, ‘‘Liquid Waste Management System,’’ Revision 5 ............................................................................................... ML15029A032 

Section 11.3, ‘‘Gaseous Waste Management System,’’ Revision 4 ........................................................................................... ML15029A039 

Section 11.4, ‘‘Solid Waste Management System,’’ Revision 4 ................................................................................................. ML15029A174 

Section 11.5, ‘‘Process and Effluent Radiological Monitoring Instrumentation and Sampling Systems,’’ Revision 6 ............... ML15029A182 

BTP 11–3, ‘‘Design Guidance for Solid Radioactive Waste Management Systems Installed in Light-Water-Cooled Nuclear 

Power Reactor Plants,’’ Revision 4*.

ML15027A198 

BTP 11–5, ‘‘Postulated Radioactive Releases Due to a Waste Gas System Leak or Failure,’’ Revision 4 * ........................... ML15027A302 

BTP 11–6, ‘‘Postulated Radioactive Releases due to Liquid Containing Tank Failures,’’ Revision 4 * ..................................... ML15027A401 

* No changes resulting from public comments. See documents in the package at ADAMS Accession Number ML14113A532 to see changes 

made since last revision. 

Dated at Rockville, Maryland, this 8th day 

of January, 2016. 

For the Nuclear Regulatory Commission. 

Kimyata Morgan Butler, 

Chief, New Reactor Rulemaking and 

Guidance Branch, Division of Advanced 

Reactors and Rulemaking, Office of New 

Reactors. 

[FR Doc. 2016–02588 Filed 2–8–16; 8:45 am] 

BILLING CODE 3410–16–P 

NUCLEAR REGULATORY 

COMMISSION 

[NRC–2012–0232] 

Revision Probabilistic Risk 

Assessment and Severe Accident 

Evaluation for New Reactors 

AGENCY: Nuclear Regulatory 

Commission. 

ACTION: Standard review plan—final 

section revision; issuance. 

SUMMARY: The U.S. Nuclear Regulatory 

Commission (NRC) is issuing a final 

revision to the following section in 

Chapter 19 of NUREG–0800, ‘‘Standard 

Review Plan (SRP) for the Review of 

Safety Analysis Reports for Nuclear 

Power Plants: LWR Edition,’’ Section 

19.0, ‘‘Probabilistic Risk Assessment 

and Severe Accident Evaluation for New 

Reactors.’’ 

DATES: The effective date of this 

Standard Review Plan update is March 

10, 2016. 

ADDRESSES: Please refer to Docket ID 

NRC–2012–0232 when contacting the 

NRC about the availability of 

information regarding this document. 

You may access publicly-available 

information related to this document 

using any of the following methods: 

• Federal Rulemaking Web site: Go to 

http://www.regulations.gov and search 

for Docket ID NRC–2012–0232. Address 

questions about NRC dockets to Carol 

Gallagher; telephone: 301–415–3463; 

email: Carol.Gallagher@nrc.gov. For 

technical questions, contact the 

individual(s) listed in the FOR FURTHER

INFORMATION CONTACT section of this 

document. 

• NRC’s Agencywide Documents 

Access and Management System 

(ADAMS): You may obtain publiclyavailable documents online in the 

ADAMS Public Documents collection at 

http://www.nrc.gov/reading-rm/

adams.html. To begin the search, select 

‘‘ADAMS Public Documents’’ and then 

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 available in 

ADAMS) is provided the first time that 

a document is referenced. The final 

revision for the SRP, Section 19.0, 

Revision 3, ‘‘Probabilistic Risk 

Assessment and Severe Accident 

Evaluation for New Reactors,’’ is 

available in ADAMS under Accession 

No. ML15089A068. A redline strikeout 

comparing the proposed revision to the 

final revision can be found in ADAMS 

under Accession No. ML15089A115. 

The responses to public comments can 

be found in ADAMS under Accession 

No. ML15086A472. 

• NRC’s PDR: You may examine and 

purchase copies of public documents at 

the NRC’s PDR, Room O1–F21, One 

White Flint North, 11555 Rockville 

Pike, Rockville, Maryland 20852. 

• The NRC posts its issued staff 

guidance on the NRC’s external Web 

page: http://www.nrc.gov/reading-rm/

doc-collections/nuregs/staff/sr0800/. 

FOR FURTHER INFORMATION CONTACT: 

Mark Notich, telephone: 301–415–3053, 

email: Mark.Notich@nrc.gov or Nishka 

Devaser, telephone: 301–415–5196, 

email: Nishka.Devaser@nrc.gov, both are 

staff of the Office of New Reactors, U.S. 

Nuclear Regulatory Commission, 

Washington, DC 20555–0001. 

SUPPLEMENTARY INFORMATION: 

I. Background 

On December 8, 2014 (79 FR 72709), 

the NRC published for public comment 

a proposed revision to this section of the 

SRP. The staff made changes to the 

proposed revision after consideration of 

comments received. A summary of the 

comments and the staff’s disposition of 

the comments are available in a separate 

document, ‘‘Response to Public 

Comments on Draft SRP Section 19.0’’ 

(ADAMS Accession No. ML15086A472). 

The changes to this SRP section 

reflect current staff review methods and 

practices based on lessons learned from 

NRC reviews of design certification (DC) 

and combined license (COL) 

applications completed since the last 

revision of this chapter. Changes 

include: (1) Incorporation of guidance 

previously published in Interim Staff 

Guidance (ISG) DC/COL–ISG–003 

(ADAMS Accession No. ML081430087) 

concerning the review of probabilistic 

risk assessment (PRA) information and 

severe accident assessments submitted 

to support DC and COL applications, (2) 

incorporation of guidance for DC and 

COL applicants previously published in 

ISG DC/COL–ISG–020 (ADAMS 

Accession No. ML100491233) 

concerning review of information from 

PRA-based seismic margin analyses 

submitted in support of DC and COL 

applications, (3) incorporation of 

guidance previously published in ISG 

Digital Instrumentation and Controls 

(DI&C)/COL–ISG–003 (ADAMS 

Accession No. ML080570048) 

concerning review of DI&C system 

PRAs, including treatment of common 

cause failure (CCFs) in PRAs and 

uncertainty analysis associated with 

new reactor digital systems, (4) 

incorporation of additional procedures 

for review of PRA information and 

severe accident assessments developed 

during NRC reviews of DC and COL 

applications completed after Revision 2 

of SRP Section 19.0 was issued, (5) 

additional proposed acceptance criteria 

and review procedures for the staff’s 

review of an applicant’s assessment of 

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6898 Federal Register / Vol. 81, No. 26 / Tuesday, February 9, 2016 / Notices 

risk from accidents that could affect 

multiple modules in facilities with 

small modular integral pressurized 

water reactors (iPWRs), (6) additional 

review procedures for the staff’s review 

of the results of the PRA for non-power 

modes of operation, and (7) several 

editorial changes to ensure that there is 

no confusion between text in this SRP 

section and text in the ASME/ANS PRA 

Standard currently endorsed by the NRC 

and referenced in this SRP section. The 

ISG DC/COL–ISG–003 and ISG DI&C/

COL–ISG–003 have now been 

superseded by SRP 19.0, Revision 3 and 

should no longer be used. The ISG DC/ 

COL–ISG–020 contains guidance for 

COL holders which has not been 

superseded by SRP 19.0, Revision 3 and 

should still be used by COL holders. 

II. Backfitting and Issue Finality 

Issuance of this final SRP does not 

constitute backfitting as defined in 10 

CFR 50.109 (the Backfit Rule) or 

otherwise be inconsistent with the issue 

finality provisions in 10 CFR part 52. 

The NRC’s position is based upon the 

following considerations: 

1. The SRP positions, does not 

constitute backfitting, inasmuch as the 

SRP is internal guidance to NRC staff. 

The SRP provides internal guidance 

to the NRC staff on how to review an 

application for NRC regulatory approval 

in the form of licensing. Changes in 

internal staff guidance are not matters 

for which either nuclear power plant 

applicants or licensees are protected 

under either the Backfit Rule or the 

issue finality provisions of 10 CFR part 

52. 

2. The NRC staff has no intention to 

impose the SRP positions on existing 

licensees either now or in the future. 

The NRC staff does not intend to 

impose or apply the positions described 

in the draft SRP to existing licenses and 

regulatory approvals. Hence, the 

issuance of a final SRP—even if 

considered guidance within the purview 

of the issue finality provisions in 10 

CFR part 52—need not be evaluated as 

if it were a backfit or inconsistent with 

issue finality provisions. If, in the 

future, the NRC staff seeks to impose a 

position in the SRP on holders of 

already issued licenses in a manner that 

does not provide issue finality as 

described in the applicable issue finality 

provision, then the staff must make the 

showing as set forth in the Backfit Rule 

or address the criteria for avoiding issue 

finality as described in the applicable 

issue finality provision. 

3. Backfitting and issue finality do 

not—with limited exceptions not 

applicable here—protect current or 

future applicants. 

Applicants and potential applicants 

are not, with certain exceptions, 

protected by either the Backfit Rule or 

any issue finality provisions under 10 

CFR part 52. Neither the Backfit Rule 

nor the issue finality provisions under 

10 CFR part 52, with certain exclusions, 

were intended to apply to every NRC 

action that substantially changes the 

expectations of current and future 

applicants. The exceptions to the 

general principle are applicable 

whenever an applicant references a 10 

CFR part 52 license (e.g., an early site 

permit) and/or NRC regulatory approval 

(e.g., a design certification rule) with 

specified issue finality provisions. 

The exceptions to the general 

principle are applicable whenever an 

applicant references a 10 CFR part 52 

license (e.g., an early site permit) and/ 

or NRC regulatory approval (e.g., a 

design certification rule) with specified 

issue finality provisions. The NRC staff 

does not, at this time, intend to impose 

the positions represented in the draft 

SRP in a manner that is inconsistent 

with any issue finality provisions. If, in 

the future, the staff seeks to impose a 

position in the draft SRP in a manner 

that does not provide issue finality as 

described in the applicable issue finality 

provision, then the staff must address 

the criteria for avoiding issue finality as 

described in the applicable issue finality 

provision. 

III. Congressional Review Act 

In accordance with the Congressional 

Review Act, the NRC has determined 

that this action is not a major rule and 

has verified this determination with the 

Office of Information and Regulatory 

Affairs of the Office of Management and 

Budget. 

Dated at Rockville, Maryland, this 21st day 

of January, 2016. 

For the Nuclear Regulatory Commission. 

Tanya Smith, 

Chief, New Reactor Rulemaking and 

Guidance Branch, Division of Advanced 

Reactors and Rulemaking, Office of New 

Reactors. 

[FR Doc. 2016–02564 Filed 2–8–16; 8:45 am] 

BILLING CODE 7590–01–P 

OFFICE OF PERSONNEL 

MANAGEMENT 

Excepted Service 

AGENCY: U.S. Office of Personnel 

Management (OPM). 

ACTION: Notice. 

SUMMARY: This notice identifies 

Schedule A, B, and C appointing 

authorities applicable to a single agency 

that were established or revoked from 

November 1, 2015, to November 30, 

2015. 

FOR FURTHER INFORMATION CONTACT: 

Senior Executive Resources Services, 

Senior Executive Services and 

Performance Management, Employee 

Services, 202–606–2246. 

SUPPLEMENTARY INFORMATION: In 

accordance with 5 CFR 213.103, 

Schedule A, B, and C appointing 

authorities available for use by all 

agencies are codified in the Code of 

Federal Regulations (CFR). Schedule A, 

B, and C appointing authorities 

applicable to a single agency are not 

codified in the CFR, but the Office of 

Personnel Management (OPM) 

publishes a notice of agency-specific 

authorities established or revoked each 

month in the Federal Register at 

www.gpo.gov/fdsys/. OPM also 

publishes an annual notice of the 

consolidated listing of all Schedule A, 

B, and C appointing authorities, current 

as of June 30, in the Federal Register. 

Schedule A 

11. Department of Homeland Security 

(Sch. A, 213.3111) 

(d) General— 

(1) Not to exceed 1,000 positions to 

perform cyber risk and strategic 

analysis, incident handling and 

malware/vulnerability analysis, program 

management, distributed control 

systems security, cyber incident 

response, cyber exercise facilitation and 

management, cyber vulnerability 

detection and assessment, network and 

systems engineering, enterprise 

architecture, intelligence analysis, 

investigation, investigative analysis and 

cyber-related infrastructure 

interdependency analysis requiring 

unique qualifications currently not 

established by OPM. Positions will be at 

the General Schedule (GS) grade levels 

09–15. Appointments may be made 

under this authority until March 31, 

2017. 

Schedule B 

No Schedule B Authorities to report 

during November 2015. 

Schedule C 

The following Schedule C appointing 

authorities were approved during 

November 2015. 

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