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, 42857-42858 [2017-19216]

Download as PDF Federal Register / Vol. 82, No. 175 / Tuesday, September 12, 2017 / Notices pmangrum on DSK3GDR082PROD with NOTICES1 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 VerDate Sep<11>2014 15:19 Sep 11, 2017 Jkt 241001 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. PO 00000 Frm 00077 Fmt 4703 Sfmt 4703 42857 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 Nuclear Regulatory Commission. ACTION: 10 CFR 2.206 request; receipt. AGENCY: 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 SUMMARY: E:\FR\FM\12SEN1.SGM 12SEN1 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 https://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 https://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. VerDate Sep<11>2014 15:19 Sep 11, 2017 Jkt 241001 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 PO 00000 Frm 00078 Fmt 4703 Sfmt 4703 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 Postal Regulatory Commission. Notice. AGENCY: ACTION: 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 https:// 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. SUMMARY: 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 E:\FR\FM\12SEN1.SGM 12SEN1

Agencies

[Federal Register Volume 82, Number 175 (Tuesday, September 12, 2017)]
[Notices]
[Pages 42857-42858]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2017-19216]


-----------------------------------------------------------------------

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

[[Page 42858]]

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 https://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 publicly-available documents online in the 
ADAMS Public Documents collection at https://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
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