19696 Federal Register / Vol. 80, No. 70 / Monday, April 13, 2015 / Notices 

and Economic Sciences Directorate 

(SBE) programs and activities. 

Agenda 

Wednesday, May 13, 2015 

SBE Directorate Update 

NSF Public Access Plan: Today’s Data, 

Tomorrow’s Discoveries 

Report from SBE AC Subcommittee on 

Replicability in Science 

SBE 2020 Themes/Rebuilding the 

Mosaic 

National Center for Science and 

Engineering Statistics 

Statistical Sciences at NSF (StatsNSF) 

Subcommittee Update 

Science of Broadening Participation 

Thursday, May 14, 2015 

Meeting with NSF Leadership 

Decision-Making under Uncertainty/

Risk and Resilience 

Agenda and Dates for Future Meetings, 

Assignments and Concluding 

Remarks 

Dated: April 7, 2015. 

Suzanne Plimpton, 

Acting Committee Management Officer. 

[FR Doc. 2015–08322 Filed 4–10–15; 8:45 am] 

BILLING CODE 7555–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[Docket Nos. 52–025 and 52–026; NRC– 

2008–0252] 

Vogtle Electric Generating Station, 

Units 3 and 4; Southern Nuclear 

Operating Company; Containment 

Structural Wall Module Design Details 

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. 

29 to Combined Licenses (COLs), 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 asked 

for 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–2008–0252 when contacting the 

NRC about the availability of 

information regarding this document. 

You may access information related to 

this document, which the NRC 

possesses and is publicly available, 

using any of the following methods: 

• Federal Rulemaking Web site: Go to 

http://www.regulations.gov and search 

for Docket ID NRC–2008–0252. 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 access publicly 

available documents online in the NRC 

Library at http://www.nrc.gov/readingrm/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 in this document 

(if that document is available in 

ADAMS) is provided the first time that 

a document is referenced. The request 

for the amendment and exemption was 

submitted by letter dated July 3, 2014 

(ADAMS Accession No. ML14187A533), 

and supplemented by letters dated 

August 28, 2014 (ADAMS Accession 

No. ML14241A287), September 19, 2014 

(ADAMS Accession No. ML14262A475), 

November 6, 2014 (ADAMS Accession 

No. ML14310A846), and December 23, 

2014 (ADAMS Accession No. 

ML14357A650). 

• 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. 

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. 29 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 proposed changes related to the 

design details of the containment 

internal structural wall modules (CA01, 

CA02, and CA05). The proposed 

changes to Tier 2 information in the 

VEGP Units 3 and 4 UFSAR, and the 

involved plant-specific Tier 1 and 

corresponding combined license 

Appendix C information would allow 

the use of thicker than normal faceplates 

to accommodate local demand or 

connection loads in certain areas 

without the use of overlay plates or 

additional backup structures. 

Additional proposed changes to Tier 2 

information and involved Tier 2* 

information would allow: 

(1) a means of connecting the 

structural wall modules to the base 

concrete through use of structural 

shapes, reinforcement bars, and shear 

studs extending horizontally from the 

structural module faceplates and 

embedded during concrete placement as 

an alternative to the use of embedment 

plates and vertically oriented 

reinforcement bars; 

(2) a variance in structural module 

wall thicknesses from the thicknesses 

identified in the VEGP Units 3 and 4 

UFSAR Figure 3.8.3–8, ‘‘Structural 

Modules—Typical Design Details,’’ for 

some walls that separate equipment 

spaces from personnel access areas; 

(3) the use of steel plates, structural 

shapes, reinforcement bars, or tie bars 

between the module faceplates, as 

needed to support localized loads and 

ensure compliance with applicable 

codes; 

(4) revision to containment internal 

structure (CIS) evaluations; and 

(5) clarification to the definition of incontainment ‘‘structural wall modules,’’ 

clarifying that the west wall of the Incontainment Refueling Water Storage 

Tank (IRWST) is not considered a 

‘‘structural wall module,’’ that the CIS 

critical sections identified in VEGP 

Units 3 and 4 UFSAR Subsection 

3.8.3.5.8.1 present design summaries for 

areas of ‘‘large’’ demand in lieu of areas 

of ‘‘largest’’ demand, and revising the 

VEGP Units 3 and 4 UFSAR in several 

places to provide consistency in 

terminology used to identify the 

structural wall modules. 

mstockstill on DSK4VPTVN1PROD with NOTICES

Federal Register / Vol. 80, No. 70 / Monday, April 13, 2015 / Notices 19697 

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. ML15005A265. 

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. ML15005A222 and ML15005A224, 

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. 

ML15005A246 and ML15005A256, 

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 July 3, 2014, and 

supplemented by letters dated August 

28, September 19, November 6, and 

December 23, 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 

14–001, ‘‘Containment Internal 

Structural Module Design Details (LAR– 

14–001).’’ 

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. ML15005A265, 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, Table 3.3–1, 

‘‘Definition of Wall Thicknesses for 

Nuclear Island Buildings, Turbine 

Building, and Annex Building’’ and 

Table 3.3–7, ‘‘Nuclear Island Critical 

Structural Sections’’ as described in the 

licensee’s request dated July 3, 2014 and 

supplemented by the letters dated 

August 28, September 19, November 6, 

and December 23, 2014. This exemption 

is related to, and necessary for the 

granting of License Amendment No. 29, 

which is being issued concurrently with 

this exemption. 

3. As explained in Section 5.0, 

‘‘Environmental Consideration,’’ of the 

NRC staff’s Safety Evaluation (ADAMS 

Accession No. ML15005A265), 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 

January 13, 2015. 

III. License Amendment Request 

By letter dated July 3, 2014, and 

supplemented by letters dated August 

28, September 19, November 6, and 

December 23, 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 

is described in Section I of this Federal 

Register Notice. 

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 

August 5, 2014 (79 FR 45480). The 

August 28, September 19, November 6 

and December 23, 2014 licensee 

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 July 3, 2014, as supplemented by 

letters dated August 28, September 19, 

November 6 and December 23, 2014. 

The exemption and amendment were 

issued on January 13, 2015 as part of a 

combined package to the licensee 

(ADAMS Accession No. ML15005A210). 

Dated at Rockville, Maryland, this 2nd day 

of April 2015. 

For the Nuclear Regulatory Commission. 

Chandu Patel, 

Acting Chief, Licensing Branch 4, Division 

of New Reactor Licensing, Office of New 

Reactors. 

[FR Doc. 2015–08411 Filed 4–10–15; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[Docket No. 50–305; NRC–2015–0089] 

Dominion Energy Kewaunee, Inc.; 

Kewaunee Power Station 

AGENCY: Nuclear Regulatory 

Commission. 

ACTION: Exemption; issuance. 

SUMMARY: The U.S. Nuclear Regulatory 

Commission (NRC) is issuing an 

exemption from the requirement to 

maintain a specified level of onsite 

property damage insurance in response 

to a request from Dominion Energy 

Kewaunee, Inc. (DEK or the licensee) 

dated March 20, 2014. This exemption 

would permit the licensee to reduce its 

onsite property damage insurance from 

$1.06 billion to $50 million. 

DATES: April 13, 2015. 

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