Federal Register / Vol. 80, No. 61 / Tuesday, March 31, 2015 / Notices 17081 

to the Decadal Survey of Ocean Sciences 

(DSOS) report. 

STATUS: Closed. 

This meeting will be held by 

teleconference. Please refer to the 

National Science Board Web site 

www.nsf.gov/nsb for additional 

information and schedule updates (time, 

place, subject matter or status of 

meeting) which may be found at 

http://www.nsf.gov/nsb/notices/. Point 

of contact for this meeting is John 

Veysey at jveysey@nsf.gov. 

Ann Bushmiller, 

Senior Counsel to the National Science Board. 

[FR Doc. 2015–07467 Filed 3–27–15; 4:15 pm] 

BILLING CODE 7555–01–P 

NUCLEAR REGULATORY 

COMMISSION 

Advisory Committee on Reactor 

Safeguards (ACRS); Meeting of the 

ACRS Subcommittee on Metallurgy & 

Reactor Fuels; Notice of Meeting 

The ACRS Subcommittee on 

Metallurgy & Reactor Fuels will hold a 

meeting on April 7, 2015, Room T–2B1, 

11545 Rockville Pike, Rockville, 

Maryland. 

The meeting will be open to public 

attendance. 

The agenda for the subject meeting 

shall be as follows: 

Tuesday, April 7, 2015—8:30 a.m. until 

5:00 p.m. 

The Subcommittee will discuss 

Consequential Steam Generator Tube 

Rupture (C–SGTR). The Subcommittee 

will hear presentations by and hold 

discussions with the NRC staff and 

other interested persons regarding this 

matter. The Subcommittee will gather 

information, analyze relevant issues and 

facts, and formulate proposed positions 

and actions, as appropriate, for 

deliberation by the Full Committee. 

Members of the public desiring to 

provide oral statements and/or written 

comments should notify the Designated 

Federal Official (DFO), Christopher 

Brown (Telephone 301–415–7111 or 

Email: Christopher.Brown@nrc.gov) five 

days prior to the meeting, if possible, so 

that appropriate arrangements can be 

made. Thirty-five hard copies of each 

presentation or handout should be 

provided to the DFO thirty minutes 

before the meeting. In addition, one 

electronic copy of each presentation 

should be emailed to the DFO one day 

before the meeting. If an electronic copy 

cannot be provided within this 

timeframe, presenters should provide 

the DFO with a CD containing each 

presentation at least thirty minutes 

before the meeting. Electronic 

recordings will be permitted only 

during those portions of the meeting 

that are open to the public. Detailed 

procedures for the conduct of and 

participation in ACRS meetings were 

published in the Federal Register on 

October 13, 2014 (79 FR 59307–59308). 

Detailed meeting agendas and meeting 

transcripts are available on the NRC 

Web site at http://www.nrc.gov/readingrm/doc-collections/acrs. Information 

regarding topics to be discussed, 

changes to the agenda, whether the 

meeting has been canceled or 

rescheduled, and the time allotted to 

present oral statements can be obtained 

from the Web site cited above or by 

contacting the identified DFO. 

Moreover, in view of the possibility that 

the schedule for ACRS meetings may be 

adjusted by the Chairman as necessary 

to facilitate the conduct of the meeting, 

persons planning to attend should check 

with these references if such 

rescheduling would result in a major 

inconvenience. 

If attending this meeting, please enter 

through the One White Flint North 

building, 11555 Rockville Pike, 

Rockville, MD. After registering with 

security, please contact Mr. Theron 

Brown (Telephone 240–888–9835) to be 

escorted to the meeting room. 

Dated: March 25, 2015. 

Mark L. Banks, 

Chief, Technical Support Branch, Advisory 

Committee on Reactor Safeguards. 

[FR Doc. 2015–07350 Filed 3–30–15; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[Docket Nos. 52–025 and 52–026; NRC– 

2015–0074] 

Vogtle Electric Generating Station, 

Units 3 and 4; Southern Nuclear 

Operating Company; Annex Building 

Structure and Layout Changes 

AGENCY: Nuclear Regulatory 

Commission. 

ACTION: Exemption and combined 

license amendment issuance. 

SUMMARY: The U.S. Nuclear Regulatory 

Commission (NRC) is granting an 

exemption to allow a departure from the 

certification information of Tier 1 of the 

generic design control document (DCD) 

and is issuing License Amendment No. 

27 to Combined Licenses (COL), NPF– 

91 and NPF–92. The COLs were issued 

to Southern Nuclear Operating 

Company, Inc., and Georgia Power 

Company, Oglethorpe Power 

Corporation, Municipal Electric 

Authority of Georgia, and the City of 

Dalton, Georgia (the licensee); for 

construction and operation of the Vogtle 

Electric Generating Plant (VEGP), Units 

3 and 4, located in Burke County, 

Georgia. 

The granting of the exemption allows 

the changes to Tier 1 information 

requested in the amendment. Because 

the acceptability of the exemption was 

determined in part by the acceptability 

of the amendment, the exemption and 

amendment are being issued 

concurrently. 

ADDRESSES: Please refer to Docket ID 

NRC–2015–0074 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 Web site: Go to 

http://www.regulations.gov and search 

for Docket ID NRC–2015–0074. Address 

questions about NRC dockets to Carol 

Gallagher; telephone: 301–415–3463; 

email: Carol.Gallagher@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 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 request 

for the amendment and exemption were 

submitted by letter dated August 22, 

2014 (ADAMS Accession No. 

ML14234A423). The licensee revised 

this request by letter dated September 

23, 2014 (ADAMS Accession No. 

ML14266A656), and supplemented the 

request by letters dated October 30 and 

November 6, 2014 (ADAMS Accession 

Nos. ML14303A660 and ML14310A831, 

respectively). 

• 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. 


asabaliauskas on DSK5VPTVN1PROD with NOTICES
17082 Federal Register / Vol. 80, No. 61 / Tuesday, March 31, 2015 / Notices 

FOR FURTHER INFORMATION CONTACT: 

Chandu Patel, Office of New Reactors, 

U.S. Nuclear Regulatory Commission, 

Washington, DC 20555–0001; telephone: 

301–415–3025; email: Chandu.Patel@

nrc.gov. 

SUPPLEMENTARY INFORMATION: 

I. Introduction 

The NRC is granting an exemption 

from Paragraph B of Section III, ‘‘Scope 

and Contents,’’ of appendix D, ‘‘Design 

Certification Rule for the AP1000,’’ to 

part 52 of Title 10 of the Code of Federal 

Regulations (10 CFR) and issuing 

License Amendment No. 27 to COLs, 

NPF–91 and NPF–92, to the licensee. 

The exemption is required by Paragraph 

A.4 of Section VIII, ‘‘Processes for 

Changes and Departures,’’ appendix D 

to 10 CFR part 52 to allow the licensee 

to depart from Tier 1 information. With 

the requested amendment, the licensee 

sought: 

(a) Installation of an additional nonsafety-related battery; 

(b) Revision to the annex building 

internal configuration by converting a 

shift turnover room to a battery room, 

adding an additional battery equipment 

room, and moving a fire area wall; 

(c) Increase in the height of a room in 

the annex building; and 

(d) Increase in thicknesses of certain 

annex building floor slabs. 

In addition, the proposed changes 

also include reconfiguring existing 

rooms and related room, wall, and 

access path changes and making 

changes to the corresponding Tier 1 

information in appendix C to the 

Combined Licenses. 

These changes were necessary as part 

of structural and layout design 

modifications to the annex building. 

Part of the justification for granting 

the exemption was provided by the 

review of the amendment. Because the 

exemption is necessary in order to issue 

the requested license amendment, the 

NRC granted the exemption and issued 

the amendment concurrently, rather 

than in sequence. This included issuing 

a combined safety evaluation containing 

the NRC staff’s review of both the 

exemption request and the license 

amendment. The exemption met all 

applicable regulatory criteria set forth in 

10 CFR 50.12, 10 CFR 52.7, and Section 

VIII.A.4. of appendix D to 10 CFR part 

52. The license amendment was found 

to be acceptable as well. The combined 

safety evaluation is available in ADAMS 

under Accession No. ML14323A649. 

Identical exemption documents 

(except for referenced unit numbers and 

license numbers) were issued to the 

licensee for VEGP Units 3 and 4 (COLs 

NPF–91 and NPF–92). The exemption 

documents for VEGP Units 3 and 4 can 

be found in ADAMS under Accession 

Nos. ML14323A623 and ML14323A629, 

respectively. The exemption is 

reproduced (with the exception of 

abbreviated titles and additional 

citations) in Section II of this document. 

The amendment documents for COLs 

NPF–91 and NPF–92 are available in 

ADAMS under Accession Nos. 

ML14323A635 and ML14323A640, 

respectively. A summary of the 

amendment documents is provided in 

Section III of this document. 

II. Exemption 

Reproduced below is the exemption 

document issued to Vogtle Units 3 and 

Unit 4. It makes reference to the 

combined safety evaluation that 

provides the reasoning for the findings 

made by the NRC (and listed under Item 

1) in order to grant the exemption: 

1. In a letter dated August 22, 2014, 

and revised by letter dated September 

23, 2014, and supplemented by letters 

dated October 30 and November 6, 

2014, the licensee requested from the 

Commission an exemption from the 

provisions of 10 CFR part 52, appendix 

D, Section III.B, as part of license 

amendment request 13–038, ‘‘Annex 

Building Structure and Layout Changes’’ 

(LAR–13–038). 

For the reasons set forth in Section 

3.1, ‘‘Evaluation of Exemption,’’ of the 

NRC staff’s Safety Evaluation, which 

can be found in ADAMS under 

Accession No. ML14323A649, the 

Commission finds that: 

A. The exemption is authorized by 

law; 

B. the exemption presents no undue 

risk to public health and safety; 

C. the exemption is consistent with 

the common defense and security; 

D. special circumstances are present 

in that the application of the rule in this 

circumstance is not necessary to serve 

the underlying purpose of the rule; 

E. the special circumstances outweigh 

any decrease in safety that may result 

from the reduction in standardization 

caused by the exemption; and 

F. the exemption will not result in a 

significant decrease in the level of safety 

otherwise provided by the design. 

2. Accordingly, the licensee is granted 

an exemption to the provisions of 10 

CFR part 52, appendix D, Section III.B, 

to allow departures from the certified 

Design Control Document Tier 1, Table 

3.3–1, ‘‘Definition of Wall Thickness for 

Nuclear Island Buildings, Turbine 

Building, and Annex Building,’’ and 

Figure 3.3–11A, ‘‘Annex Building Plan 

View at Elevation 100′-0′′ (sensitive 

unclassified non-safeguards information 

(SUNSI)). The proposed changes 

include non-system based design 

descriptions and other detailed 

information related to these design 

descriptions and associated ITAAC, 

such changes to concrete floor 

thicknesses, annex building wall 

location descriptions, and the interior 

configuration of the annex building as 

described in the licensee’s request dated 

August 22, 2014, and revised by letter 

dated September 23, 2014, and 

supplemented by letters dated October 

30 and November 6, 2014. This 

exemption is related to, and necessary 

for the granting of License Amendment 

No. 27, which is being issued 

concurrently with this exemption. 

3. As explained in Section 3.1, 

‘‘Evaluation of Exemption,’’ of the NRC 

staff’s Safety Evaluation (ADAMS 

Accession No. ML14323A649), this 

exemption meets the eligibility criteria 

for categorical exclusion set forth in 10 

CFR 51.22(c)(9). Therefore, pursuant to 

10 CFR 51.22(b), no environmental 

impact statement or environmental 

assessment needs to be prepared in 

connection with the issuance of the 

exemption. 

4. This exemption is effective as of 

December 23, 2014. 

III. License Amendment Request 

By letter dated August 22, 2014, and 

revised by letter dated September 23, 

2014, and supplemented by letters dated 

October 30 and November 6, 2014, the 

licensee requested that the NRC amend 

the COLs for VEGP, Units 3 and 4, COLs 

NPF–91 and NPF–92. The proposed 

amendment would depart from Tier 2 

material previously incorporated into 

the Updated Final Safety Evaluation 

Report (UFSAR). Additionally, these 

Tier 2 changes involve changes to Tier 

1 Information in the UFSAR, and the 

proposed amendment would also revise 

the associated material that has been 

included in Appendix C of each of the 

VEGP, Units 3 and 4 COLs. The 

requested amendment would revise the 

Tier 2 UFSAR information by revising 

UFSAR to (1) install an additional nonsafety-related battery; (2) revise the 

annex building internal configuration; 

(3) increase the height of Containment 

Filtration Room A (Room 40551) by 4 

feet from elevation (EL.) 146′-3′′ to 

150′-3′′; and (4) increase concrete 

thicknesses from 6 inches to 8 inches in 

a number of floor slabs. 

Additionally, the licensee proposed 

consistency and editorial changes to 

Tier 1 Table 3.3–1, as well as the 

corresponding information in Appendix 

C. These changes were necessary as part 

of a design modification to the structure 

and layout of the annex building. 


asabaliauskas on DSK5VPTVN1PROD with NOTICES
Federal Register / Vol. 80, No. 61 / Tuesday, March 31, 2015 / Notices 17083 

The Commission has determined for 

these amendments that the application 

complies with the standards and 

requirements of the Atomic Energy Act 

of 1954, as amended (the Act), and the 

Commission’s rules and regulations. 

The Commission has made appropriate 

findings as required by the Act and the 

Commission’s rules and regulations in 

10 CFR Chapter I, which are set forth in 

the license amendment. 

A notice of consideration of issuance 

of amendment to facility operating 

license or combined license, as 

applicable, proposed no significant 

hazards consideration determination, 

and opportunity for a hearing in 

connection with these actions, was 

published in the Federal Register on 

October 14, 2014 (79 FR 61662). The 

September 23, 2014, application 

revision, and the October 30 and 

November 6, 2014, supplements had no 

effect on the no significant hazards 

consideration determination, and no 

comments were received during the 60- 

day comment period. 

The Commission has determined that 

these amendments satisfy the criteria for 

categorical exclusion in accordance 

with 10 CFR 51.22. Therefore, pursuant 

to 10 CFR 51.22(b), no environmental 

impact statement or environmental 

assessment need be prepared for these 

amendments. 

IV. Conclusion 

Using the reasons set forth in the 

combined safety evaluation, the staff 

granted the exemption and issued the 

amendment that the licensee requested 

on August 22, 2014, and revised by 

letter dated September 23, 2014, and 

supplemented by letters dated October 

30 and November 6, 2014. The 

exemption and amendment were issued 

on December 23, 2014 as part of a 

combined package to the licensee 

(ADAMS Accession No. ML14323A609). 

Dated at Rockville, Maryland, this 23rd day 

of March 2015. 

For the Nuclear Regulatory Commission. 

Lawrence Burkhart, 

Chief, Licensing Branch 4, Division of New 

Reactor Licensing, Office of New Reactors. 

[FR Doc. 2015–07277 Filed 3–30–15; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[NRC–2015–0073] 

Biweekly Notice; Applications and 

Amendments to Facility Operating 

Licenses and Combined Licenses 

Involving No Significant Hazards 

Considerations 

AGENCY: Nuclear Regulatory 

Commission. 

ACTION: Biweekly notice. 

SUMMARY: Pursuant to Section 189a. (2) 

of the Atomic Energy Act of 1954, as 

amended (the Act), the U.S. Nuclear 

Regulatory Commission (NRC) is 

publishing this regular biweekly notice. 

The Act requires the Commission to 

publish notice of any amendments 

issued, or proposed to be issued and 

grants the Commission the authority to 

issue and make immediately effective 

any amendment to an operating license 

or combined license, as applicable, 

upon a determination by the 

Commission that such amendment 

involves no significant hazards 

consideration, notwithstanding the 

pendency before the Commission of a 

request for a hearing from any person. 

This biweekly notice includes all 

notices of amendments issued, or 

proposed to be issued from March 5, 

2015 to March 18, 2015. The last 

biweekly notice was published on 

March 17, 2015. 

DATES: Comments must be filed by April 

30, 2015. A request for a hearing must 

be filed by June 1, 2015. 

ADDRESSES: You may submit comments 

by any of the following methods (unless 

this document describes a different 

method for submitting comments on a 

specific subject): 

• Federal Rulemaking Web site: Go to 

http://www.regulations.gov and search 

for Docket ID NRC–2015–0073. Address 

questions about NRC dockets to Carol 

Gallagher; telephone: 301–415–3463; 

email: Carol.Gallagher@nrc.gov. For 

technical questions, contact the 

individual listed in the FOR FURTHER

INFORMATION CONTACT section of this 

document. 

• Mail comments to: Cindy Bladey, 

Office of Administration, Mail Stop: 

OWFN–12–H08, U.S. Nuclear 

Regulatory Commission, Washington, 

DC 20555–0001. 

For additional direction on obtaining 

information and submitting comments, 

see ‘‘Obtaining Information and 

Submitting Comments’’ in the 

SUPPLEMENTARY INFORMATION section of 

this document. 

FOR FURTHER INFORMATION CONTACT: Kay 

Goldstein, Office of Nuclear Reactor 

Regulation, U.S. Nuclear Regulatory 

Commission, Washington DC 20555– 

0001; telephone: 301–415–1506, email: 

Kay.Goldstein@nrc.gov. 

SUPPLEMENTARY INFORMATION: 

I. Obtaining Information and 

Submitting Comments 

A. Obtaining Information 

Please refer to Docket ID NRC–2015– 

0073 when contacting the NRC about 

the availability of information for this 

action. You may obtain publiclyavailable information related to this 

action by any of the following methods: 

• Federal Rulemaking Web site: Go to 

http://www.regulations.gov and search 

for Docket ID NRC–2015–0073. 

• 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 is available in 

ADAMS) is provided the first time that 

it is mentioned in the SUPPLEMENTARY

INFORMATION section. 

• 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. 

B. Submitting Comments 

Please include Docket ID NRC–2015– 

0073, facility name, unit number(s), 

application date, and subject 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 http://

www.regulations.gov as well as entering 

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 


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