Federal Register / Vol. 82, No. 175 / Tuesday, September 12, 2017 / Notices 42857 

Position Requirements.’’ Additional 

supporting changes to Beaver Valley, 

Unit Nos. 1 and 2, Technical 

Specifications were also made. 

Date of Issuance: August 16, 2017. 

Effective date: As of the date of 

issuance and shall be implemented 

within 30 days. 

Amendment Nos.: 299 (Unit No. 1) 

and 188 (Unit No. 2). A publiclyavailable version is in ADAMS under 

Accession No. ML17221A280; 

documents related to these amendments 

are listed in the Safety Evaluation 

enclosed with the amendments. 

Renewed Facility Operating License 

Nos. DPR–66 and NPF–73: Amendments 

revised the Renewed Facility Operating 

Licenses and Technical Specifications. 

Date of initial notice in Federal 

Register: July 11, 2017 (82 FR 32017). 

The Commission’s related evaluation 

of the amendments is contained in a 

Safety Evaluation dated August 16, 

2017. 

No significant hazards consideration 

comments received: No. 

Tennessee Valley Authority, Docket 

Nos. 50–259, 50–260, and 50–296, 

Browns Ferry Nuclear Plant, Units 1, 2 

and 3, Limestone County, Alabama 

Date of amendment request: 

September 21, 2015, as supplemented 

by letters dated November 13, December 

15 (two letters), and December 18, 2015; 

February 16, March 8, March 9, March 

24, March 28, April 4, April 5, April 14, 

April 22 (two letters), April 27, May 11, 

May 20 (two letters), May 27, June 9, 

June 17, June 20, June 24, July 13 (two 

letters), July 27, July 29 (two letters), 

August 3 (three letters), September 12, 

September 21, September 23, October 

13, October 28, and October 31, 2016; 

and January 20, February 3, March 3, 

and June 12, 2017. 

Brief description of amendments: The 

amendments revised Renewed Facility 

Operating Licenses (RFOLs) and 

Technical Specifications (TSs) to 

authorize an increase of maximum 

reactor core thermal power level for 

Browns Ferry Nuclear Plant, Units 1, 2, 

and 3 to 3,952 megawatt thermal (MWt). 

These license amendments represent an 

increase of approximately 14.3 percent 

above the current licensed thermal 

power level of 3,458 MWt, which is an 

increase of approximately 20 percent 

above the original licensed thermal 

power level of 3,293 MWt. The NRC 

considers the requested increase in 

power level to be an extended power 

uprate. 

Date of issuance: August 14, 2017. 

Effective date: As of the date of 

issuance and shall be implemented 

prior to startup from the refueling 

outages of fall 2018 (Unit 1), spring 2019 

(Unit 2), and spring 2018 (Unit 3). 

Amendment Nos.: 299 (Unit 1), 323 

(Unit 2), and 283 (Unit 3). A publiclyavailable version is in ADAMS under 

Accession No. ML17032A120; 

documents related to these amendments 

are listed in the Safety Evaluation (SE) 

enclosed with the amendments. 

Renewed Facility Operating License 

Nos. DPR–33, DPR–52, and DPR–68: 

Amendments revised the RFOLs and 

TSs. 

Date of initial notice in Federal 

Register: July 5, 2016 (81 FR 43666). 

The supplemental letters dated April 22 

(two letters), April 27, May 11, May 20 

(two letters), May 27, June 9, June 17, 

June 20, June 24, July 13, (two letters); 

July 27, July 29 (two letters), August 3 

(three letters), September 12, September 

21, September 23, October 13, October 

28, and October 31, 2016; and January 

20, February 3, March 3, and June 12, 

2017, provided additional information 

that clarified the application, did not 

expand the scope of the application as 

originally noticed, and did not change 

the staff’s original proposed no 

significant hazards consideration 

determination as published in the 

Federal Register. 

The Commission’s related evaluation 

of the amendments is contained in the 

SE dated August 14, 2017. 

No significant hazards consideration 

comments received: Yes, refer to Section 

6.0, ‘‘Public Comments,’’ of the SE. 

Wolf Creek Nuclear Operating 

Corporation (WCNOC), Docket No. 50– 

482, Wolf Creek Generating Station 

(WCGS), Coffey County, Kansas 

Date of amendment request: 

September 30, 2016, as supplemented 

by letters dated March 16 and April 26, 

2017. 

Brief description of amendment: The 

amendment revised the emergency 

action level (EAL) scheme used at 

WCGS. The currently approved EAL 

scheme is based on Nuclear 

Management and Resources Council/ 

National Environmental Studies Project 

(NUMARC/NESP)-007, Revision 2, 

‘‘Methodology for Development of 

Emergency Action Levels,’’ January 

1992. The amendment allows WCNOC 

to adopt an EAL scheme, which is based 

on the guidance established in Nuclear 

Energy Institute (NEI) 99–01, Revision 6, 

‘‘Development of Emergency Action 

Levels for Non-Passive Reactors,’’ 

November 2012. Revision 6 of NEI 99– 

01 has been endorsed by the NRC by 

letter dated March 28, 2013. 

Date of issuance: August 28, 2017. 

Effective date: As of its date of 

issuance and shall be implemented by 

September 30, 2018. 

Amendment No.: 218. A publiclyavailable version is in ADAMS under 

Accession No. ML17166A409; 

documents related to this amendment 

are listed in the Safety Evaluation 

enclosed with the amendment. 

Renewed Facility Operating License 

No. NPF–42. The amendment revised 

the Operating License. 

Date of initial notice in Federal 

Register: December 6, 2016 (81 FR 

87974). The supplemental letters dated 

March 16 and April 26, 2017, provided 

additional information that clarified the 

application, did not expand the scope of 

the application as originally noticed, 

and did not change the staff’s original 

proposed no significant hazards 

consideration determination as 

published in the Federal Register. 

The Commission’s related evaluation 

of the amendment is contained in a 

Safety Evaluation dated August 28, 

2017. 

No significant hazards consideration 

comments received: No. 

Dated at Rockville, Maryland, this 30th day 

of August 2017. 

For the Nuclear Regulatory Commission. 

Eric J. Benner, 

Deputy Director, Division of Operating 

Reactor Licensing, Office of Nuclear Reactor 

Regulation. 

[FR Doc. 2017–19214 Filed 9–11–17; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[Docket Nos. 50–282, 50–306, 50–368, 50– 

334, 50–338, 50–339, 50–280, 50–445, 50– 

395, 50–348, 50–364, 50–498, 50–499, 50– 

327, 50–390, 50–336, 50–335; NRC–2017– 

0188] 

Northern States Power Company— 

Minnesota; Entergy Operations, Inc.; 

FirstEnergy Nuclear Operating 

Company; Virginia Electric and Power 

Company; TEX Operations Company, 

LLC; South Carolina Electric & Gas 

Company, Inc.; STP Nuclear Operating 

Company; Tennessee Valley Authority 

AGENCY: Nuclear Regulatory 

Commission. 

ACTION: 10 CFR 2.206 request; receipt. 

SUMMARY: The U.S. Nuclear Regulatory 

Commission (NRC) is giving notice that 

by petition dated January 24, 2017, Mr. 

Paul Gunter on behalf of Beyond 

Nuclear, and representing numerous 

public interest groups (collectively, 

Beyond Nuclear, et al., or petitioners), 

has requested that the NRC take action 


pmangrum on DSK3GDR082PROD with NOTICES1
42858 Federal Register / Vol. 82, No. 175 / Tuesday, September 12, 2017 / Notices 

with regard to licensees of plants that 

currently rely on potentially defective 

safety-related components and 

potentially falsified quality assurance 

documentation supplied by AREVA-Le 

Creusot Forge and its subcontractor, 

Japan Casting and Forging Corporation. 

The petitioners’ requests are included in 

the SUPPLEMENTARY INFORMATION section 

of this document. 

ADDRESSES: Please refer to Docket ID 

NRC–2017–0188 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–2017–0188. 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 is available in 

ADAMS) is provided the first time that 

it is mentioned in this document. 

• 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: 

Merrilee Banic, Office of Nuclear 

Reactor Regulation, U.S. Nuclear 

Regulatory Commission, Washington, 

DC 20555–0001; telephone: 301–415– 

2771; email: Merrilee.Banic@nrc.gov. 

SUPPLEMENTARY INFORMATION: On 

January 24, 2017, (ADAMS Accession 

No. ML17025A180) the petitioners 

requested that the NRC take action with 

regard to licensees of plants that 

currently rely on potentially defective 

safety-related components and 

potentially falsified quality assurance 

documentation supplied by AREVA-Le 

Creusot Forge and its subcontractor, 

Japan Casting and Forging Corporation. 

As a basis for this request, the 

petitioners provided the expert review 

of John Large & Associates identifying 

significant ‘‘irregularities’’ and 

‘‘anomalies’’ in both the manufacturing 

process and quality assurance 

documentation of large reactor 

components manufactured by the 

AREVA-Le Creusot Forge for French 

reactors and reactors in other countries. 

The request is being treated pursuant 

to section 2.206 of title 10 of the Code 

of Federal Regulations (10 CFR) of the 

Commission’s regulations. The request 

has been referred to the Director of the 

Office of Nuclear Reactor Regulation. 

The petitioners supplemented the 

petition on February 16, March 6, June 

16, June 22, June 27, June 30, and July 

5, 2017 (ADAMS Accession Nos. 

ML17052A032, ML17068A061, 

ML17067A562, ML17174A087, 

ML17174A788, ML17179A288, 

ML17184A058, and ML17187A026, 

respectively). The supplements are 

being considered in evaluating the 

petitioners’ request for enforcement 

action. 

The petitioners addressed the Petition 

Review Board in a public meeting on 

March 8, 2017; the transcript of that 

meeting (ADAMS Accession No. 

ML17081A418) is an additional 

supplement to the petition. The results 

of that meeting were considered in the 

Board’s determination regarding the 

petitioners’ request for enforcement 

action. The Director determined that the 

petitioners’ request for enforcement 

action concerning potentially defective 

safety-related components met the 

criteria for review under the 10 CFR 

2.206 process, but that the request about 

potentially falsified quality assurance 

documentation would be referred to 

another NRC process for appropriate 

action. Because the allegation process 

provides an opportunity for the 

petitioners to address these concerns, 

the issue of potentially falsified quality 

assurance documentation will not be 

reviewed as part of this 2.206 petition. 

The NRC will take appropriate action on 

this petition within a reasonable time. 

Dated at Rockville, Maryland, this 30th day 

of August 2017. 

For the Nuclear Regulatory Commission. 

Michele G. Evans, 

Deputy Director, Office of Nuclear Reactor 

Regulation. 

[FR Doc. 2017–19216 Filed 9–11–17; 8:45 am] 

BILLING CODE 7590–01–P 

POSTAL REGULATORY COMMISSION 

[Docket Nos. MC2017–184 and CP2017–285; 

MC2017–185 and CP2017–286; MC2017–186 

and CP2017–287; MC2017–187 and CP2017– 

288; MC2017–188 and CP2017–289; 

MC2017–189 and CP2017–290; MC2017–190 

and CP2017–291; MC2017–191 and CP2017– 

292; MC2017–192 and CP2017–293; 

MC2017–193 and CP2017–294] 

New Postal Products 

AGENCY: Postal Regulatory Commission. 

ACTION: Notice. 

SUMMARY: The Commission is noticing a 

recent Postal Service filing for the 

Commission’s consideration concerning 

negotiated service agreements. This 

notice informs the public of the filing, 

invites public comment, and takes other 

administrative steps. 

DATES: Comments are due: September 

18, 2017 and September 19, 2017. 

ADDRESSES: Submit comments 

electronically via the Commission’s 

Filing Online system at http://

www.prc.gov. Those who cannot submit 

comments electronically should contact 

the person identified in the FOR FURTHER

INFORMATION CONTACT section by 

telephone for advice on filing 

alternatives. 

FOR FURTHER INFORMATION CONTACT: 

David A. Trissell, General Counsel, at 

202–789–6820. 

SUPPLEMENTARY INFORMATION: The 

September 18, 2017 comment due date 

applies to Docket Nos. MC2017–184 and 

CP2017–285; MC2017–185 and CP2017– 

286; MC2017–186 and CP2017–287; 

MC2017–187 and CP2017–288; 

MC2017–188 and CP2017–289. 

The September 19, 2017 comment due 

date applies to Docket Nos. MC2017– 

189 and CP2017–290; MC2017–190 and 

CP2017–291; MC2017–191 and CP2017– 

292; MC2017–192 and CP2017–293; 

MC2017–193 and CP2017–294. 

Table of Contents 

I. Introduction 

II. Docketed Proceeding(s) 

I. Introduction 

The Commission gives notice that the 

Postal Service filed request(s) for the 

Commission to consider matters related 

to negotiated service agreement(s). The 

request(s) may propose the addition or 

removal of a negotiated service 

agreement from the market dominant or 

the competitive product list, or the 

modification of an existing product 

currently appearing on the market 

dominant or the competitive product 

list. 

Section II identifies the docket 

number(s) associated with each Postal 


pmangrum on DSK3GDR082PROD with NOTICES1