ML17199A117

NRR E-mail Capture - NRC Notification of Intent to Issue License Amendment for Oconee Nuclear Station - Approval of One Time Change to Technical Specifications to Allow Time to Replace the Stator on Each Keowee Unit

ML17199A117
Person / Time
Site:	Oconee
Issue date:	05/10/2017
From:	Stephen Koenick Plant Licensing Branch II
To:	Jenkins S, Yeager M State of SC, Dept of Health & Environmental Control
References
Download: ML17199A117 (14)

Text

NRR-PMDAPEm Resource From: Koenick, Stephen Sent: Wednesday, May 10, 2017 5:25 PM To: jenkinse@dhec.sc.gov; 'yeagerma@dhec.sc.gov' Cc: Klett, Audrey

Subject:

NRC Notification of Intent to Issue License Amendment for Oconee Nuclear Station -

Approval of one time change to technical specifications to allow time to replace the stator on each Keowee unit Attachments: 2016-15659 BWN Oconee Stator.pdf Follow Up Flag: Follow up Flag Status: Flagged May 10, 2017 Ms. Susan E. Jenkins Manager, Infectious and Radioactive Waste Management Bureau of Land & Waste Management Division of Waste Management/IRWMS South Carolina Department of Health and Environmental Control Mr. Mark A. Yeager Environmental Health Manager Bureau of Land & Waste Management Division of Waste Management/IRWMS South Carolina Department of Health and Environmental Control

Dear Susan and Mark,

The NRC is preparing to issue a license amendment for the Oconee Nuclear Station to revise the Technical Specifications (TS) for a one-time change to allow sufficient time to replace the stator on each Keowee Hydro Unit.

Here is the relevant information for the license amendment request:

Date of submittal: February 26, 2016 (NRC Agencywide Documents Access and Management System (ADAMS) Accession No. ML16064A020).

Federal Register Notice of Consideration: July 5, 2016 (81 FR 43650).

[copy attached, specific BWN starts on page 43650]

Brief description of Amendment: The proposed changes would modify TS 3.8.1, AC Sources - Operating, to allow sufficient time to replace the stator on each Keowee Hydro Unit (KHU).

Specifically, the current TS 3.8.1 RA C.2.2.5 maintenance provision requires the KHU and its required overhead emergency power path to be restored to operable status within 45 days of discovery of an initial inoperability when Condition C is entered due to an inoperable KHU if not used for that KHU in the previous 3 years. This 45-day time period is not sufficient to allow the KHU generator stator replacement work to be performed. Therefore, the licensee proposes to add a temporary Completion Time (CT) to RA C.2.2.5 that would allow 55 days to restore an inoperable KHU due to stator replacement. The temporary CT can be used 1

once for each KHU. The proposed changes are similar to those previously reviewed and approved to support the KHU generator pole rewinds License Amendment Request for Temporary Technical Specification Change to Add a Required Action Completion Time for One Keowee Hydro Unit Inoperable for Generator Field Pole Rewinds, dated February 27, 2012 (ADAMS Accession No. ML12181A312) and Oconee Nuclear Station Units 1, 2 and 3, Issuance of Amendments Temporary Technical Specification Change Request to Extend the Completion Time For An Inoperable Keowee Hydro Unit, dated January 8, 2014 (ADAMS Accession No. ML13357A674.

The licensee also proposes a change to TS 3.8.1 RA C.2.2.3 Note to allow use of the 60-hour dual KHU outage to disassemble and reassemble the KHU and return it to a functional condition.

Please let me know at your earliest convenience if you have any questions or comments regarding this amendment.

On a separate note, Ms. Audrey Klett will become the NRC Project Manager for the Oconee Nuclear Station effective May 14, 2017. Audrey can be reached at (301) 415-0489, or at Audrey.Klett@nrc.gov.

Thanks, Steve Stephen S. Koenick Senior Project Manager Plant Licensing Branch 2-1 (LPL2-1)

Division of Operating Reactor Licensing (DORL)

Office of Nuclear Reactor Regulation (NRR)

US Nuclear Regulatory Commission (301) 415-6631 Stephen.Koenick@nrc.gov 2

Hearing Identifier: NRR_PMDA Email Number: 3608 Mail Envelope Properties (195c80fb0a1343b48b231ecc4fb4b2d8)

Subject:

NRC Notification of Intent to Issue License Amendment for Oconee Nuclear Station - Approval of one time change to technical specifications to allow time to replace the stator on each Keowee unit Sent Date: 5/10/2017 5:24:38 PM Received Date: 5/10/2017 5:24:40 PM From: Koenick, Stephen Created By: Stephen.Koenick@nrc.gov Recipients:

"Klett, Audrey" <Audrey.Klett@nrc.gov>

Tracking Status: None "jenkinse@dhec.sc.gov" <jenkinse@dhec.sc.gov>

Tracking Status: None

"'yeagerma@dhec.sc.gov'" <yeagerma@dhec.sc.gov>

Tracking Status: None Post Office: HQPWMSMRS02.nrc.gov Files Size Date & Time MESSAGE 3281 5/10/2017 5:24:40 PM 2016-15659 BWN Oconee Stator.pdf 266837 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:

Recipients Received: Follow up

43646 Federal Register / Vol. 81, No. 128 / Tuesday, July 5, 2016 / Notices regulations, and orders of the NRC now theft, diversion, or loss. Based on the NUCLEAR REGULATORY or hereafter in effect. The facility information provided, no new accident COMMISSION consists of two pressurized-water precursors are created by the

[NRC-2016-0127]

reactors located in Mecklenburg County, description of actions the licensee has North Carolina. provided concerning the physical Biweekly Notice; Applications and II. Request/Action inventory for the incore nuclear Amendments to Facility Operating detectors. Thus, the probability of Licenses and Combined Licenses The regulation in 10 CFR 74.19, postulated accidents is not increased. Involving No Significant Hazards Recordkeeping, identifies Also, the consequences of postulated Considerations recordkeeping requirements applicable accidents are not increased. Therefore, to special nuclear material (SNM), and AGENCY: Nuclear Regulatory 10 CFR 74.19(c) requires, in part, that, there is no undue risk to public health Commission.

each licensee who is authorized to and safety.

ACTION: Biweekly notice.

possess special nuclear material, at any The Exemption Is Consistent With the one time and site location, in a quantity Common Defense and Security

SUMMARY

Pursuant to Section 189a. (2) greater than 350 grams of contained of the Atomic Energy Act of 1954, as uranium-235, uranium-233, or The proposed exemption would allow amended (the Act), the U.S. Nuclear plutonium, or any combination thereof, the licensee to address the physical Regulatory Commission (NRC) is shall conduct a physical inventory of all inventory of the non-fuel SNM. The publishing this regular biweekly notice.

special nuclear material in its licensee indicated that the overall The Act requires the Commission to possession under license at intervals not alternative approach will continue to publish notice of any amendments to exceed 12 months. meet the intent of the physical issued, or proposed to be issued, and The licensee requested an exemption inventory requirements of 10 CFR grants the Commission the authority to from certain recordkeeping 74.19(c). Therefore, the common issue and make immediately effective requirements in 10 CFR 74.19(c). The defense and security are not impacted any amendment to an operating license exemption would allow the licensee to by this exemption. or combined license, as applicable, seek relief from the physical inventory upon a determination by the requirements only for movable incore IV. Conclusion Commission that such amendment nuclear detectors that have been involves no significant hazards removed from service and stored in a Accordingly, the Commission has consideration, notwithstanding the location that is not readily accessible determined that pursuant to 10 CFR pendency before the Commission of a and is subject to security modifications. 74.7, the exemption is authorized by request for a hearing from any person.

The purpose of this request for law, will not present an undue risk to This biweekly notice includes all exemption is to allow an alternative to the public health and safety, and is notices of amendments issued, or the physical inventory-taking practices consistent with the common defense proposed to be issued from June 7, 2016, for these non-fuel SNM incore detectors. and security. Therefore, the Commission to June 20, 2016. The last biweekly hereby grants Duke Energy Carolinas, notice was published on June 21, 2016.

III. Discussion LLC an exemption from the physical DATES: Comments must be filed by Pursuant to 10 CFR 74.7, Specific inventory requirements of 10 CFR August 4, 2016. A request for a hearing exemptions, the Commission may, 74.19(c) for McGuire. must be filed by September 6, 2016.

upon application of any interested Pursuant to 10 CFR 51.32, Finding of ADDRESSES: You may submit comments person or upon its own initiative, grant no significant impact, the Commission by any of the following methods (unless exemptions from the requirements of 10 has determined that the granting of this this document describes a different CFR part 74 when the exemptions are exemption will not have a significant method for submitting comments on a authorized by law and will not endanger effect on the quality of the human specific subject):

life or property or the common defense environment as published in the

• Federal Rulemaking Web site: Go to and security, and are otherwise in the Federal Register on March 8, 2016 (81 http://www.regulations.gov and search public interest.

FR 12132). for Docket ID NRC-2016-0127. Address The Exemption Is Authorized by Law questions about NRC dockets to Carol The exemption is effective upon Gallagher; telephone: 301-415-3463; This exemption allows the licensee to issuance.

have an alternative to the physical email: Carol.Gallagher@nrc.gov. For inventory requirements of 10 CFR Dated at Rockville, Maryland, this 23rd day technical questions, contact the 74.19(c) only for movable incore nuclear of June, 2016. individual listed in the FOR FURTHER detectors that have been removed from For the Nuclear Regulatory Commission. INFORMATION CONTACT section of this service. The NRC staff has determined document.

Anne T. Boland, that granting the licensees proposed

• Mail comments to: Cindy Bladey, Director, Division of Operating Reactor Office of Administration, Mail Stop:

exemption pursuant to 10 CFR 74.7 will Licensing, Office of Nuclear Reactor not result in a violation of the Atomic OWFN-12-H08, U.S. Nuclear Regulation.

Energy Act of 1954, as amended, or the Regulatory Commission, Washington,

[FR Doc. 2016-15868 Filed 7-1-16; 8:45 am]

Commissions regulations. Therefore, DC 20555-0001.

BILLING CODE 7590-01-P For additional direction on obtaining sradovich on DSK3GDR082PROD with NOTICES the exemption is authorized by law.

information and submitting comments, The Exemption Presents No Undue Risk see Obtaining Information and to Public Health and Safety Submitting Comments in the The underlying purpose of 10 CFR SUPPLEMENTARY INFORMATION section of 74.19(c) is to ensure SNM is properly this document.

accounted for, appropriately secured, FOR FURTHER INFORMATION CONTACT:

and that authorities are informed of any Lynn Ronewicz, Office of Nuclear VerDate Sep<11>2014 17:27 Jul 01, 2016 Jkt 238001 PO 00000 Frm 00077 Fmt 4703 Sfmt 4703 E:\FR\FM\05JYN1.SGM 05JYN1

Federal Register / Vol. 81, No. 128 / Tuesday, July 5, 2016 / Notices 43647 Reactor Regulation, U.S. Nuclear before making the comment action may file a request for a hearing Regulatory Commission, Washington DC submissions available to the public or and a petition to intervene with respect 20555-0001; telephone: 301-415-1927, entering the comment into ADAMS. to issuance of the amendment to the email: lynn.ronewicz@nrc.gov. subject facility operating license or II. Notice of Consideration of Issuance combined license. Requests for a I. Obtaining Information and of Amendments to Facility Operating hearing and a petition for leave to Submitting Comments Licenses and Combined Licenses and intervene shall be filed in accordance Proposed No Significant Hazards A. Obtaining Information with the Commissions Agency Rules Consideration Determination of Practice and Procedure in 10 CFR Please refer to Docket ID NRC-2016- The Commission has made a part 2. Interested person(s) should 0127 when contacting the NRC about proposed determination that the consult a current copy of 10 CFR 2.309, the availability of information for this following amendment requests involve which is available at the NRCs PDR, action. You may obtain publicly- no significant hazards consideration. located at One White Flint North, Room available information related to this Under the Commissions regulations in O1-F21, 11555 Rockville Pike (first action by any of the following methods: § 50.92 of Title 10 of the Code of Federal floor), Rockville, Maryland 20852. The

• Federal rulemaking Web site: Go to Regulations (10 CFR), this means that NRCs regulations are accessible http://www.regulations.gov and search operation of the facility in accordance electronically from the NRC Library on for Docket ID NRC-2016-0127. with the proposed amendment would the NRCs Web site at http://

• NRCs Agencywide Documents not (1) involve a significant increase in www.nrc.gov/reading-rm/doc-Access and Management System the probability or consequences of an collections/cfr/. If a request for a hearing (ADAMS): You may obtain publicly- accident previously evaluated, or (2) or petition for leave to intervene is filed available documents online in the create the possibility of a new or within 60 days, the Commission or a ADAMS Public Documents collection at different kind of accident from any presiding officer designated by the http://www.nrc.gov/reading-rm/ accident previously evaluated; or (3) Commission or by the Chief adams.html. To begin the search, select involve a significant reduction in a Administrative Judge of the Atomic ADAMS Public Documents and then margin of safety. The basis for this Safety and Licensing Board Panel, will select Begin Web-based ADAMS proposed determination for each rule on the request and/or petition; and Search. For problems with ADAMS, amendment request is shown below. the Secretary or the Chief please contact the NRCs Public The Commission is seeking public Administrative Judge of the Atomic Document Room (PDR) reference staff at comments on this proposed Safety and Licensing Board will issue a 1-800-397-4209, 301-415-4737, or by determination. Any comments received notice of a hearing or an appropriate email to pdr.resource@nrc.gov. The within 30 days after the date of order.

ADAMS accession number for each publication of this notice will be As required by 10 CFR 2.309, a document referenced (if it is available in considered in making any final petition for leave to intervene shall set ADAMS) is provided the first time that determination. forth with particularity the interest of it is mentioned in the SUPPLEMENTARY Normally, the Commission will not the petitioner in the proceeding, and INFORMATION section. issue the amendment until the how that interest may be affected by the

• NRCs PDR: You may examine and expiration of 60 days after the date of results of the proceeding. The petition purchase copies of public documents at publication of this notice. The should specifically explain the reasons the NRCs PDR, Room O1-F21, One Commission may issue the license why intervention should be permitted White Flint North, 11555 Rockville amendment before expiration of the 60- with particular reference to the Pike, Rockville, Maryland 20852. day period provided that its final following general requirements: (1) The B. Submitting Comments determination is that the amendment name, address, and telephone number of involves no significant hazards the requestor or petitioner; (2) the Please include Docket ID NRC-2016- consideration. In addition, the nature of the requestors/petitioners 0127, facility name, unit number(s), Commission may issue the amendment right under the Act to be made a party application date, and subject in your prior to the expiration of the 30-day to the proceeding; (3) the nature and comment submission. comment period if circumstances extent of the requestors/petitioners The NRC cautions you not to include change during the 30-day comment property, financial, or other interest in identifying or contact information that period such that failure to act in a the proceeding; and (4) the possible you do not want to be publicly timely way would result, for example in effect of any decision or order which disclosed in your comment submission. derating or shutdown of the facility. If may be entered in the proceeding on the The NRC will post all comment the Commission takes action prior to the requestors/petitioners interest. The submissions at http:// expiration of either the comment period petition must also set forth the specific www.regulations.gov as well as enter the or the notice period, it will publish in contentions which the requestor/

comment submissions into ADAMS. the Federal Register a notice of petitioner seeks to have litigated at the The NRC does not routinely edit issuance. If the Commission makes a proceeding.

comment submissions to remove final no significant hazards Each contention must consist of a identifying or contact information. consideration determination, any specific statement of the issue of law or If you are requesting or aggregating hearing will take place after issuance. fact to be raised or controverted. In comments from other persons for The Commission expects that the need addition, the requestor/petitioner shall submission to the NRC, then you should provide a brief explanation of the bases sradovich on DSK3GDR082PROD with NOTICES to take this action will occur very inform those persons not to include infrequently. for the contention and a concise identifying or contact information that statement of the alleged facts or expert they do not want to be publicly A. Opportunity To Request a Hearing opinion which support the contention disclosed in their comment submission. and Petition for Leave To Intervene and on which the requestor/petitioner Your request should state that the NRC Within 60 days after the date of intends to rely in proving the contention does not routinely edit comment publication of this notice, any person(s) at the hearing. The requestor/petitioner submissions to remove such information whose interest may be affected by this must also provide references to those VerDate Sep<11>2014 17:27 Jul 01, 2016 Jkt 238001 PO 00000 Frm 00078 Fmt 4703 Sfmt 4703 E:\FR\FM\05JYN1.SGM 05JYN1

43648 Federal Register / Vol. 81, No. 128 / Tuesday, July 5, 2016 / Notices specific sources and documents of agency thereof, may submit a petition to participant should contact the Office of which the petitioner is aware and on the Commission to participate as a party the Secretary by email at which the requestor/petitioner intends under 10 CFR 2.309(h)(1). The petition hearing.docket@nrc.gov, or by telephone to rely to establish those facts or expert should state the nature and extent of the at 301-415-1677, to request (1) a digital opinion. The petition must include petitioners interest in the proceeding. identification (ID) certificate, which sufficient information to show that a The petition should be submitted to the allows the participant (or its counsel or genuine dispute exists with the Commission by September 6, 2016. The representative) to digitally sign applicant on a material issue of law or petition must be filed in accordance documents and access the E-Submittal fact. Contentions shall be limited to with the filing instructions in the server for any proceeding in which it is matters within the scope of the Electronic Submissions (E-Filing) participating; and (2) advise the amendment under consideration. The section of this document, and should Secretary that the participant will be contention must be one which, if meet the requirements for petitions for submitting a request or petition for proven, would entitle the requestor/ leave to intervene set forth in this hearing (even in instances in which the petitioner to relief. A requestor/ section, except that under § 2.309(h)(2) participant, or its counsel or petitioner who fails to satisfy these a State, local governmental body, or representative, already holds an NRC-requirements with respect to at least one Federally-recognized Indian Tribe, or issued digital ID certificate). Based upon contention will not be permitted to agency thereof does not need to address this information, the Secretary will participate as a party. the standing requirements in 10 CFR establish an electronic docket for the Those permitted to intervene become 2.309(d) if the facility is located within hearing in this proceeding if the parties to the proceeding, subject to any its boundaries. A State, local Secretary has not already established an limitations in the order granting leave to governmental body, Federally- electronic docket.

intervene, and have the opportunity to recognized Indian Tribe, or agency Information about applying for a participate fully in the conduct of the thereof, may also have the opportunity digital ID certificate is available on the hearing with respect to resolution of to participate under 10 CFR 2.315(c). NRCs public Web site at http://

that persons admitted contentions, If a hearing is granted, any person www.nrc.gov/site-help/e-submittals/

including the opportunity to present who does not wish, or is not qualified, getting-started.html. System evidence and to submit a cross- to become a party to the proceeding requirements for accessing the E-examination plan for cross-examination may, in the discretion of the presiding Submittal server are detailed in the of witnesses, consistent with NRC officer, be permitted to make a limited NRCs Guidance for Electronic regulations, policies and procedures. appearance pursuant to the provisions Submission, which is available on the Petitions for leave to intervene must of 10 CFR 2.315(a). A person making a agencys public Web site at http://

be filed no later than 60 days from the limited appearance may make an oral or www.nrc.gov/site-help/e-date of publication of this notice. written statement of position on the submittals.html. Participants may Requests for hearing, petitions for leave issues, but may not otherwise attempt to use other software not listed to intervene, and motions for leave to participate in the proceeding. A limited on the Web site, but should note that the file new or amended contentions that appearance may be made at any session NRCs E-Filing system does not support are filed after the 60-day deadline will of the hearing or at any prehearing unlisted software, and the NRC Meta not be entertained absent a conference, subject to the limits and System Help Desk will not be able to determination by the presiding officer conditions as may be imposed by the offer assistance in using unlisted that the filing demonstrates good cause presiding officer. Persons desiring to software.

by satisfying the three factors in 10 CFR make a limited appearance are If a participant is electronically 2.309(c)(1)(i)-(iii). If a hearing is requested to inform the Secretary of the submitting a document to the NRC in requested, and the Commission has not Commission by September 6, 2016. accordance with the E-Filing rule, the made a final determination on the issue participant must file the document of no significant hazards consideration, B. Electronic Submissions (E-Filing) using the NRCs online, Web-based the Commission will make a final All documents filed in NRC submission form. In order to serve determination on the issue of no adjudicatory proceedings, including a documents through the Electronic significant hazards consideration. The request for hearing, a petition for leave Information Exchange System, users final determination will serve to decide to intervene, any motion or other will be required to install a Web when the hearing is held. If the final document filed in the proceeding prior browser plug-in from the NRCs Web determination is that the amendment to the submission of a request for site. Further information on the Web-request involves no significant hazards hearing or petition to intervene, and based submission form, including the consideration, the Commission may documents filed by interested installation of the Web browser plug-in, issue the amendment and make it governmental entities participating is available on the NRCs public Web immediately effective, notwithstanding under 10 CFR 2.315(c), must be filed in site at http://www.nrc.gov/site-help/e-the request for a hearing. Any hearing accordance with the NRCs E-Filing rule submittals.html.

held would take place after issuance of (72 FR 49139; August 28, 2007). The E- Once a participant has obtained a the amendment. If the final Filing process requires participants to digital ID certificate and a docket has determination is that the amendment submit and serve all adjudicatory been created, the participant can then request involves a significant hazards documents over the internet, or in some submit a request for hearing or petition consideration, then any hearing held cases to mail copies on electronic for leave to intervene. Submissions would take place before the issuance of storage media. Participants may not should be in Portable Document Format sradovich on DSK3GDR082PROD with NOTICES any amendment unless the Commission submit paper copies of their filings (PDF) in accordance with NRC guidance finds an imminent danger to the health unless they seek an exemption in available on the NRCs public Web site or safety of the public, in which case it accordance with the procedures at http://www.nrc.gov/site-help/e-will issue an appropriate order or rule described below. submittals.html. A filing is considered under 10 CFR part 2. To comply with the procedural complete at the time the documents are A State, local governmental body, requirements of E-Filing, at least ten 10 submitted through the NRCs E-Filing federally-recognized Indian Tribe, or days prior to the filing deadline, the system. To be timely, an electronic VerDate Sep<11>2014 17:27 Jul 01, 2016 Jkt 238001 PO 00000 Frm 00079 Fmt 4703 Sfmt 4703 E:\FR\FM\05JYN1.SGM 05JYN1

Federal Register / Vol. 81, No. 128 / Tuesday, July 5, 2016 / Notices 43649 filing must be submitted to the E-Filing the presiding officer subsequently and the removal of an expired one-time system no later than 11:59 p.m. Eastern determines that the reason for granting Note for Required Action to restore Time on the due date. Upon receipt of the exemption from use of E-Filing no Diesel Generator to OPERABLE status a transmission, the E-Filing system longer exists. for TS 3.8.1, AC SourcesOperating.

time-stamps the document and sends Documents submitted in adjudicatory Basis for proposed no significant the submitter an email notice proceedings will appear in the NRCs hazards consideration determination:

confirming receipt of the document. The electronic hearing docket which is As required by 10 CFR 50.91(a), the E-Filing system also distributes an email available to the public at http:// licensee has provided its analysis of the notice that provides access to the ehd1.nrc.gov/ehd/, unless excluded issue of no significant hazards document to the NRCs Office of the pursuant to an order of the Commission, consideration, which is presented General Counsel and any others who or the presiding officer. Participants are below:

have advised the Office of the Secretary requested not to include personal

1. Does the proposed amendment involve that they wish to participate in the privacy information, such as social a significant increase in the probability or proceeding, so that the filer need not security numbers, home addresses, or consequences of an accident previously serve the documents on those home phone numbers in their filings, evaluated?

participants separately. Therefore, unless an NRC regulation or other law Response: No.

applicants and other participants (or requires submission of such This LAR [license amendment request]

their counsel or representative) must information. However, in some proposes administrative non-technical apply for and receive a digital ID instances, a request to intervene will changes only. These proposed changes do not certificate before a hearing request/ require including information on local adversely affect accident initiators or petition to intervene is filed so that they residence in order to demonstrate a precursors nor alter the design assumptions, can obtain access to the document via proximity assertion of interest in the conditions, or configurations of the facility.

The proposed changes do not alter or prevent the E-Filing system. proceeding. With respect to copyrighted the ability of structures, systems and A person filing electronically using works, except for limited excerpts that components (SSCs) to perform their intended the NRCs adjudicatory E-Filing system serve the purpose of the adjudicatory function to mitigate the consequences of an may seek assistance by contacting the filings and would constitute a Fair Use initiating event within the assumed NRC Meta System Help Desk through application, participants are requested acceptance limits.

the Contact Us link located on the not to include copyrighted materials in Given the above discussion, it is concluded NRCs public Web site at http:// their submission. the proposed amendment does not www.nrc.gov/site-help/e- Petitions for leave to intervene must significantly increase the probability or submittals.html, by email to be filed no later than 60 days from the consequences of an accident previously MSHD.Resource@nrc.gov, or by a toll- date of publication of this notice. evaluated.

Requests for hearing, petitions for leave 2. Does the proposed amendment create free call at 1-866-672-7640. The NRC the possibility of a new or different kind of Meta System Help Desk is available to intervene, and motions for leave to accident from any accident previously between 8 a.m. and 8 p.m., Eastern file new or amended contentions that evaluated?

Time, Monday through Friday, are filed after the 60-day deadline will Response: No.

excluding government holidays. not be entertained absent a This LAR proposes administrative non-Participants who believe that they determination by the presiding officer technical changes only. The proposed have a good cause for not submitting that the filing demonstrates good cause changes will not alter the design documents electronically must file an by satisfying the three factors in 10 CFR requirements of any Structure, System or exemption request, in accordance with 2.309(c)(1)(i)-(iii). Component (SSC) or its function during 10 CFR 2.302(g), with their initial paper For further details with respect to accident conditions. No new or different filing requesting authorization to these license amendment applications, accidents result from the proposed changes.

The changes do not involve a physical continue to submit documents in paper see the application for amendment, alteration of the plant or any changes in format. Such filings must be submitted which is available for public inspection methods governing normal plant operation.

by: (1) First class mail addressed to the in ADAMS and at the NRCs PDR. For The changes do not alter assumptions made Office of the Secretary of the additional direction on accessing in the safety analysis.

Commission, U.S. Nuclear Regulatory information related to this document, Given the above discussion, it is concluded Commission, Washington, DC 20555- see the Obtaining Information and the proposed amendment does not create the 0001, Attention: Rulemaking and Submitting Comments section of this possibility of a new or different kind of Adjudications Staff; or (2) courier, document. accident from any accident previously express mail, or expedited delivery evaluated.

service to the Office of the Secretary, Duke Energy Carolinas, LLC, Docket 3. Does the proposed amendment involve Sixteenth Floor, One White Flint North, Nos. 50-369 and 50-370, McGuire a significant reduction in a margin of safety?

Nuclear Station, Units 1 and 2, Response: No.

11555 Rockville Pike, Rockville, This LAR proposes administrative non-Maryland, 20852, Attention: Mecklenburg County, North Carolina technical changes only. The proposed Rulemaking and Adjudications Staff. Date of amendment request: May 5, changes do not alter the manner in which Participants filing a document in this 2016. A publicly available version is in safety limits, limiting safety system settings manner are responsible for serving the ADAMS under Accession No. or limiting conditions for operation are document on all other participants. ML16134A068. determined. The safety analysis acceptance Filing is considered complete by first- Description of amendment request: criteria are not affected by these changes. The class mail as of the time of deposit in The amendments would modify proposed changes will not result in plant sradovich on DSK3GDR082PROD with NOTICES the mail, or by courier, express mail, or Technical Specifications (TSs) by the operation in a configuration outside the removal of Note (c), which is no longer design basis. The proposed changes do not expedited delivery service upon adversely affect systems that respond to depositing the document with the applicable from TS Table 3.3.2-1, safely shutdown the plant and to maintain provider of the service. A presiding Engineered Safety Feature Actuation the plant in a safe shutdown condition.

officer, having granted an exemption System Instrumentation, Function 6.f, Given the above discussion, it is concluded request from using E-Filing, may require Auxiliary Feedwater Pump Suction the proposed amendment does not involve a a participant or party to use E-Filing if Transfer on Suction PressureLow, significant reduction in the margin of safety.

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43650 Federal Register / Vol. 81, No. 128 / Tuesday, July 5, 2016 / Notices The NRC staff has reviewed the to use of the 55-day Completion Time of 3.8.1 Required Action C.2.2.5 associated with licensees analysis and, based on this Required Action C.2.2.5). The temporary 55- restoring compliance with TS LCO 3.8.1.

review, it appears that the three day Completion Time will decrease the During the time period that one KHU is likelihood of an unplanned forced shutdown inoperable, the redundancy requirement for standards of 10 CFR 50.92(c) are of all three Oconee Units and the potential the emergency power source will be fulfilled satisfied. Therefore, the NRC staff safety consequences and operational risks by an LCT. Compensatory measures proposes to determine that the associated with that action. Avoiding this previously specified will be in place to amendment request involves no risk offsets the risks associated with having minimize electrical power system significant hazards consideration. a design basis event during the temporary 55- vulnerabilities.

Attorney for licensee: Lara S. Nichols, day completion time for having one KHU The proposed TS change does not involve:

Deputy General Counsel, Duke Energy inoperable. (1) a physical alteration of the Oconee Units; Corporation, 526 South Church Street The temporary addition of the 55-day (2) the installation of new or different Completion Time does not involve: (1) A equipment; (3) operating any installed EC07H, Charlotte, NC 28202. physical alteration to the Oconee Units; (2)

NRC Branch Chief: Michael T. equipment in a new or different manner; (4) the installation of new or different a change to any set points for parameters Markley. equipment; (3) operating any installed which initiate protective or mitigation action; Duke Energy Carolinas, LLC, Docket equipment in a new or different manner; or or (5) any impact on the fission product (4) a change to any set points for parameters barriers or safety limits.

Nos. 50-269, 50-270, and 50-287, which initiate protective or mitigation action.

Oconee Nuclear Station, Units 1, 2, and Therefore, this request does not involve a There is no adverse impact on containment significant reduction in a margin of safety.

3, Oconee County, South Carolina integrity, radiological release pathways, fuel Date of amendment request: February design, filtration systems, main steam relief The NRC staff has reviewed the 26, 2016. A publicly-available version is valve set points, or radwaste systems. No licensees analysis and, based on this new radiological release pathways are review, it appears that the three in ADAMS under Accession No. created.

ML16064A020. standards of 10 CFR 50.92(c) are The consequences of an event occurring Description of amendment request: during the temporary 55-day Completion satisfied. Therefore, the NRC staff The amendments would revise Time are the same as those that would occur proposes to determine that the Technical Specifications (TSs) for the during the existing Completion Time. Duke amendment request involves no Oconee Nuclear Station, Units 1, 2, and Energy reviewed the Probabilistic Risk significant hazards consideration.

3 (Oconee). Specifically, the license Assessment (PRA) to gain additional insights Attorney for licensee: Lara S. Nichols, amendment request (LAR) would revise concerning the configuration of [Oconee] Deputy General Counsel, Duke Energy with one KHU. The results of the risk Corporation, 526 S. Church St.EC07H, TS 3.8.1, AC [Alternating Current] analysis show a risk improvement if no SourcesOperating, Required Action Charlotte, NC 28202.

maintenance is performed on the SSF, EFW C.2.2.5, to allow each Keowee System and AC Power System. The results of NRC Branch Chief: Michael T.

Hydroelectric Unit to be taken out of the risk analysis show a small risk increase Markley.

service for up to 55 days on a one-time using the average nominal maintenance Duke Energy Progress, Inc., Docket Nos.

basis for the purpose of generator stator unavailability values for the SSF, EFW System and AC Power System.

50-325 and 50-324, Brunswick Steam replacement, subject to the Electric Plant, Units 1 and 2 (BSEP),

By limiting maintenance, the risk results implementation of specified Brunswick County, North Carolina are expected to be between these two contingency measures outlined in the extremes (i.e., small risk impact).

LAR. Duke Energy Carolinas, LLC, Docket Therefore, the probability or consequences Basis for proposed no significant Nos. 50-413 and 50-414, Catawba of an accident previously evaluated is not hazards consideration determination: significantly increased. Nuclear Station, Units 1 and 2, York As required by 10 CFR 50.91(a), the 2. Does the proposed amendment create County, South Carolina licensee has provided its analysis of the the possibility of a new or different kind of Duke Energy Progress, Inc., Docket No.

issue of no significant hazards accident from any accident previously 50-400, Shearon Harris Nuclear Power consideration, which is presented evaluated?

Response: No.

Plant, Unit 1 (HNP), Wake County, below, with NRC edits in square North Carolina This change involves the temporary brackets: addition of a 55-day Completion Time for TS Duke Energy Carolinas, LLC, Docket

1. Does the proposed amendment involve 3.8.1 Required Action C.2.2.5 associated with Nos. 50-369 and 50-370, McGuire a significant increase in the probability or restoring compliance with TS LCO 3.8.1.

Nuclear Station, Units 1 and 2, consequences of an accident previously During the time period that one KHU is evaluated? inoperable, the redundancy requirement for Mecklenburg County, North Carolina Response: No. the emergency power source will be fulfilled Duke Energy Carolinas, LLC, Docket This change involves the temporary by an LCT. Compensatory measures Nos. 50-269, 50-270, and 50-287, addition of a 55-day Completion Time for previously specified will be in place to Oconee Nuclear Station, Units 1, 2, and Technical Specification (TS) 3.8.1 Required minimize electrical power system Action C.2.2.5 associated with restoring vulnerabilities. 3, Oconee County, South Carolina compliance with TS Limiting Condition for The temporary 55-day Completion Time Duke Energy Progress, Inc., Docket No.

Operation (LCO) 3.8.1.C. During the time that does not involve a physical effect on the 50-261, H. B. Robinson Steam Electric one Keowee Hydroelectric Unit (KHU) is Oconee Units, nor is there any increased risk Plant, Unit No. 2 (RNP), Darlington inoperable for [greater than] 72 hours3 days <br />0.429 weeks <br />0.0986 months <br />, a Lee of an Oconee Unit trip or reactivity excursion. No new failure modes or credible County, South Carolina Combustion Turbine (LCT) will be energizing both standby buses, two offsite power accident scenarios are postulated from this Date of amendment request: April 29, sources will be maintained available, and activity. 2016. A publicly-available version is in sradovich on DSK3GDR082PROD with NOTICES maintenance on electrical distribution Therefore, the possibility of a new or ADAMS under Accession No.

systems will not be performed unless different kind of accident from any kind of ML16120A076.

necessary. In addition, risk significant accident previously evaluated is not created.

systems (Emergency Feedwater System, 3. Does the proposed amendment involve Description of amendment request:

Protected Service Water System, and Standby a significant reduction in a margin of safety? The amendments would (1) consolidate Shutdown Facility) will be verified operable Response: No. the Emergency Operations Facilities (meeting LCO requirements) within 72 hours3 days <br />0.429 weeks <br />0.0986 months <br /> This change involves the temporary (EOFs) for BSEP, HNP, and RNP with of entering TS 3.8.1 Condition C (i.e., prior addition of a 55-day Completion Time for TS the Duke Energy Progress, Inc. (Duke VerDate Sep<11>2014 17:27 Jul 01, 2016 Jkt 238001 PO 00000 Frm 00081 Fmt 4703 Sfmt 4703 E:\FR\FM\05JYN1.SGM 05JYN1

Federal Register / Vol. 81, No. 128 / Tuesday, July 5, 2016 / Notices 43651 Energy) corporate EOF in Charlotte, changes will not change the design function Duke Energy Progress, Inc., Docket No.

North Carolina; (2) change the BSEP, or operation of SSCs. The changes do not 50-261, H. B. Robinson Steam Electric HNP, and RNP augmentation times to be impact the accident analysis. The changes do Plant, Unit No. 2 (HBRSEP2), Darlington not involve a physical alteration of the plant, consistent with those of the sites a change in the method of plant operation, County, South Carolina currently supported by the Duke Energy or new operator actions. The proposed Date of amendment request: April 24, corporate EOF; and (3) decrease the changes do not introduce failure modes that 2016. A publicly-available version is in frequency of the unannounced could result in a new accident, and the ADAMS under Accession No.

augmentation drill at BSEP from twice changes do not alter assumptions made in the ML16116A033.

per year to once per year. safety analysis.

Description of amendment request:

Basis for proposed no significant Therefore, the proposed change does not create the possibility of a new or different The amendment would adopt Technical hazards consideration determination: Specifications Task Force (TSTF)

As required by 10 CFR 50.91(a), the kind of accident from any accident previously evaluated. Traveler TSTF-339, Revision 2, licensee has provided its analysis of the Relocated TS Parameters to COLR.

3. Does the proposed change involve a issue of no significant hazards significant reduction in a margin of safety? Based on TSTF-339, the proposed consideration, which is presented Response: No. amendment would relocate reactor below: The proposed changes only impacts the coolant system (RCS)-related cycle-

1. Does the proposed change involve a implementation of the affected stations specific parameters and core safety significant increase in the probability or emergency plans by relocating their onsite or limits from the technical specifications consequences of an accident previously near-site EOFs to the established corporate EOF in Charlotte, North Carolina, changing (TSs) to the Core Operating Limits evaluated?

Response: No. the required response time of responders Report (COLR).

The proposed changes relocate the BSEP, who supplement the onsite staff, and Basis for proposed no significant HNP, and RNP EOFs from their present decreasing the frequency of augmentation hazards consideration determination:

onsite or near-site locations to the established drills at BSEP. The functions and capabilities As required by 10 CFR 50.91(a), the corporate EOF in Charlotte, North Carolina, of the relocated EOFs will continue to meet licensee has provided its analysis of the changes the required response times for the applicable regulatory requirements. It has issue of no significant hazards supplementing onsite personnel in response been evaluated and determined that the consideration, which is presented to a radiological emergency, and decreases change in response time does not below:

the frequency of augmentation drills at BSEP. significantly affect the ability to supplement The functions and capabilities of the the onsite staff. In addition, analysis shows 1. Does the proposed amendment involve relocated EOFs will continue to meet the that the onsite staff can acceptably respond a significant increase in the probability or applicable regulatory requirements. It has to an event for longer than the requested time consequences of an accident previously been evaluated and determined that the for augmented staff to arrive. Margin of safety evaluated?

change in response time does not is associated with confidence in the ability of Response: No.

significantly affect the ability to supplement the fission product barriers (i.e., fuel The relocation of RCS-related cycle-the onsite staff. In addition, analysis shows cladding, reactor coolant system pressure specific parameter limits from the TS to the that the onsite staff can acceptably respond boundary, and containment structure) to COLR proposed by this amendment request to an event for longer than the requested time limit the level of radiation dose to the public. does not result in the alteration of the design, for augmented staff to arrive. The proposed The proposed changes are associated with material, or construction standards that were changes have no effect on normal plant the emergency plans and do not impact applicable prior to the change. The proposed operation or on any accident initiator or operation of the plant or its response to change will not result in the modification of precursors, and do not impact the function of transients or accidents. The changes do not any system interface that would increase the plant structures, systems, or components affect the Technical Specifications. The likelihood of an accident since these events (SSCs). The proposed changes do not alter or changes do not involve a change in the are independent of the proposed change. The prevent the ability of the emergency response method of plant operation, and no accident proposed amendment will not change, organization to perform its intended analyses will be affected by the proposed degrade, or prevent actions, or alter any functions to mitigate the consequences of an changes. Safety analysis acceptance criteria assumptions previously made in evaluating accident or event. Therefore, the proposed are not affected. The emergency plans will the radiological consequences of an accident change does not involve a significant continue to provide the necessary response described in the Updated Final Safety increase in the probability or consequences staff for emergencies as demonstrated by Analysis Report (UFSAR). Therefore, the of an accident previously evaluated. staffing and functional analyses including the proposed amendment does not result in an

2. Does the proposed change create the necessary timeliness of performing major increase in the probability or consequences possibility of a new or different kind of tasks for the functional areas of the of an accident previously evaluated.

accident from any accident previously emergency plans. 2. Does the proposed change create the evaluated? Therefore, the proposed change does not possibility of a new or different kind of Response: No. involve a significant reduction in a margin of accident from any accident previously The proposed changes only impact the safety. evaluated?

implementation of the affected stations Response: No.

emergency plans by relocating their onsite or The NRC staff has reviewed the There are no new accident causal near-site EOFs to the established corporate licensees analysis and, based on this mechanisms created as a result of NRC EOF in Charlotte, North Carolina, changing review, it appears that the three approval of this amendment request. No the required response time of responders standards of 10 CFR 50.92(c) are changes are being made to the facility which who supplement the onsite staff, and satisfied. Therefore, the NRC staff would introduce any new accident causal decreasing the frequency of augmentation proposes to determine that the mechanisms. This amendment request does drills at BSEP. The functions and capabilities amendment request involves no not impact any plant systems that are of the relocated EOFs will continue to meet accident initiators. Therefore, the proposed sradovich on DSK3GDR082PROD with NOTICES significant hazards consideration.

the applicable regulatory requirements. It has Attorney for licensee: Lara S. Nichols, change does not create the possibility of a been evaluated and determined that the new or different kind of accident from any change in response time does not Deputy General Counsel, Duke Energy accident previously evaluated.

significantly affect the ability to supplement Corporation, 550 South Tyron Street, 3. Does the proposed change involve a the onsite staff. In addition, analysis shows Mail Code DEC45A, Charlotte, NC significant reduction in margin of safety?

that the onsite staff can acceptably respond 28202. Response: No.

to an event for longer than the requested time NRC Acting Branch Chief: Tracy J. Implementation of this amendment would for augmented staff to arrive. The proposed Orf. not involve a significant reduction in the VerDate Sep<11>2014 17:27 Jul 01, 2016 Jkt 238001 PO 00000 Frm 00082 Fmt 4703 Sfmt 4703 E:\FR\FM\05JYN1.SGM 05JYN1

43652 Federal Register / Vol. 81, No. 128 / Tuesday, July 5, 2016 / Notices margin of safety. Previously approved examination, testing and service life South Carolina Electric and Gas methodologies will continue to be used in monitoring in compliance with 10 CFR Company and South Carolina Public the determination of cycle-specific core 50.55a or authorized alternatives. The Service Authority, Docket Nos.52-027 operating limits that are present in the COLR. proposed change to the TS 3.7.6 Action for Additionally, previously approved RCS and 52-028, Virgil C. Summer Nuclear inoperable snubbers is administrative in minimum total flow rates for HBRSEP2 are nature and is required for consistency with Station (VCSNS), Units 2 and 3, retained in the TS to assure that lower flow the proposed change to TS SR 4.7.6. The Fairfield County, South Carolina rates will not be used without prior NRC proposed change does not adversely affect Date of amendment request: May 16, approval. Based on the above, it is concluded plant operations, design functions or 2016. A publicly-available version is in that the proposed license amendment request analyses that verify the capability of systems, does not impact any safety margins and will ADAMS under Accession No.

structures, and components to perform their ML16137A171.

not result in a reduction in margin with design functions therefore, the consequences respect to plant safety. Description of amendment request:

of accidents previously evaluated are not The proposed changes, if approved for The NRC staff has reviewed the significantly increased.

Therefore, it is concluded that this change the VCSNS, involve departures from licensees analysis and, based on this does not involve a significant increase in the incorporated plant-specific Tier 2 review, it appears that the three probability or consequences of an accident Updated Final Safety Analysis Report standards of 10 CFR 50.92(c) are previously evaluated. (UFSAR) information and conforming satisfied. Therefore, the NRC staff

2. Does the proposed change create the changes to the combined license proposes to determine that the possibility of a new or different kind of Appendix C, as well as conforming amendment request involves no accident from any accident previously changes to the plant-specific Tier 1 significant hazards consideration. evaluated?

Attorney for licensee: Lara S. Nichols, information, to ensure that the design Response: No. bases Tier 2 information conforms with Deputy General Counsel, Duke Energy The proposed changes do not involve any Corporation, 550 South Tyron Street, the originally certified design. The physical alteration of plant equipment. The Mail Code DEC45A, Charlotte, NC proposed changes do not alter the method by licensee stated in its application that the 28202. which any safety-related system performs its changes are editorial, and with one NRC Acting Branch Chief: Robert G. function. As such, no new or different types exception, bring the plant-specific Tier Schaaf. of equipment will be installed, and the basic 1 and Combined License (COL) operation of installed equipment is Appendix C into alignment with the Florida Power & Light Company, Docket unchanged. The methods governing plant information contained in plant-specific Nos. 50-250 and 50-251, Turkey Point operation and testing remain consistent with Tier 2. In addition, the licensee Nuclear Generating, Unit Nos. 3 and 4, current safety analysis assumptions. requested a change to COL License Miami-Dade County, Florida Therefore, it is concluded that this change Condition 2.D(12)(f)1 to correct a does not create the possibility of a new or Date of amendment request: April 4, reference to a seismic interaction review different kind of accident from any accident 2016. A publicly-available version is in previously evaluated.

discussed in the AP1000 design ADAMS under Accession No. 3. Does the proposed change involve a certification document, Revision 19, ML16110A266. significant reduction in a margin of safety? Section 3.7.5.3.

Description of amendment request: Response: No. Basis for proposed no significant The amendments would revise the The proposed changes ensure snubber hazards consideration determination:

Technical Specifications (TS) examination, testing and service life As required by 10 CFR 50.91(a), the requirements for snubbers. The licensee monitoring will continue to meet the licensee has provided its analysis of the proposed to revise the TSs to conform requirements of 10 CFR 50.55a(g). Snubbers issue of no significant hazards to the licensees Snubber Testing will continue to be demonstrated OPERABLE consideration, which is presented Program. The proposed changes include by performance of a program for below:

additions to, deletions from, and examination, testing and service life monitoring in compliance with 10 CFR 1. Does the proposed amendment involve conforming administrative changes to a significant increase in the probability or 50.55a or authorized alternatives.

the TSs. The proposed change to the TS 3.7.6 consequences of an accident previously Basis for proposed no significant Action for inoperable snubbers is evaluated?

hazards consideration determination: administrative in nature and is required for Response: No.

As required by 10 CFR 50.91(a), the consistency with the proposed change to TS The proposed consistency and editorial licensee has provided its analysis of the SR 4.7.6. COL Appendix C (and plant-specific Tier 1) issue of no significant hazards and involved Tier 2 changes, along with one Therefore, it is concluded that the COL paragraph 2.D change, do not involve a consideration, which is presented proposed change does not involve a technical change, (e.g., there is no design below: significant reduction in a margin of safety.

parameter or requirement, calculation,

1. Does the proposed change involve a analysis, function or qualification change).

The NRC staff has reviewed the No structure, system, component design or significant increase in the probability or consequences of an accident previously licensees analysis and, based on this function would be affected. No design or evaluated? review, it appears that the three safety analysis would be affected. The Response: No. standards of 10 CFR 50.92(c) are proposed changes do not affect any accident The proposed changes would revise TS SR satisfied. Therefore, the NRC staff initiating event or component failure, thus

[Surveillance Requirement] 4.7.6 to conform proposes to determine that the the probabilities of the accidents previously the TS to the revised surveillance program amendment request involves no evaluated are not affected. No function used for snubbers. Snubber examination, testing significant hazards consideration. to mitigate a radioactive material release and and service life monitoring will continue to no radioactive material release source term is sradovich on DSK3GDR082PROD with NOTICES meet the requirements of 10 CFR 50.55a(g). Attorney for licensee: William S. involved, thus the radiological releases in the Snubber examination, testing and service Blair, Managing AttorneyNuclear, accident analyses are not affected.

life monitoring is not an initiator of any Florida Power & Light Company, 700 Therefore, the proposed changes do not accident previously evaluated. Therefore, the Universe Blvd., MS LAW/JB, Juno involve a significant increase in the probability of an accident previously Beach, FL 33408-0420. probability or consequences of an accident evaluated is not significantly increased. previously evaluated.

Snubbers will continue to be demonstrated NRC Branch Chief: Benjamin G. 2. Does the proposed amendment create OPERABLE by performance of a program for Beasley. the possibility of a new or different kind of VerDate Sep<11>2014 17:27 Jul 01, 2016 Jkt 238001 PO 00000 Frm 00083 Fmt 4703 Sfmt 4703 E:\FR\FM\05JYN1.SGM 05JYN1

Federal Register / Vol. 81, No. 128 / Tuesday, July 5, 2016 / Notices 43653 accident from any accident previously Basis for proposed no significant Therefore, the proposed amendment does evaluated? hazards consideration determination: not involve a significant reduction in a Response: No. As required by 10 CFR 50.91(a), the margin of safety.

The proposed consistency and editorial licensee has provided its analysis of the The NRC staff has reviewed the COL Appendix C (and plant-specific Tier 1) and involved Tier 2 changes, along with one issue of no significant hazards licensees analysis and, based on this COL paragraph 2.D change, would not affect consideration, which is presented review, it appears that the three the design or function of any structure, below: standards of 10 CFR 50.92(c) are system, component (SSC), but will instead 1. Does the proposed amendment involve satisfied. Therefore, the NRC staff provide consistency between the SSC designs a significant increase in the probability or proposes to determine that the and functions currently presented in the consequences of an accident previously amendment request involves no UFSAR and the Tier 1 information. The evaluated? significant hazards consideration.

proposed changes would not introduce a new Response: No. Attorney for licensee: Ms. Kathryn M.

failure mode, fault or sequence of events that The proposed activity would revise the could result in a radioactive material release.

Sutton, Morgan, Lewis & Bockius LLC, minimum CMT [Core Makeup Tank] volume 1111 Pennsylvania Avenue NW.,

Therefore, the proposed changes do not in the COL [combined operating license]

create the possibility of a new or different Appendix A (Technical Specifications) and Washington, DC 20004-2514.

kind of accident from any accident UFSAR information to be consistent with the NRC Acting Branch Chief: Jennifer previously evaluated. plant-specific Tier 1 and COL Appendix C Dixon-Herrity.

3. Does the proposed amendment involve requirements. Because the new minimum a significant reduction in a margin of safety? Southern Nuclear Operating Company, volume is bounded by the current analyses, Response: No. the proposed activity does not alter the Docket Nos.52-025 and 52-026, Vogtle The proposed consistency and editorial design of an accident initiating component or Electric Generating Plant (VEGP), Units COL Appendix C (and plant-specific Tier 1) system. Thus, the probabilities of an accident 3 and 4, Burke County, Georgia and involved Tier 2 update, along with one previously evaluated are not affected. The Date of amendment request: May 18, COL paragraph 2.D change, is non-technical, proposed activity does not involve other thus would not affect any design parameter, 2016. A publicly-available version is in safety-related equipment or radioactive function or analysis. There would be no material barriers. Thus, the proposed activity ADAMS under Accession No.

change to an existing design basis, design does not affect an accident mitigation ML16139A796.

function, regulatory criterion, or analysis. No function. Description of amendment request:

safety analysis or design basis acceptance Therefore, the proposed changes do not The amendment request proposes limit/criterion is involved. Therefore, the involve a significant increase in the changes to the technical specifications proposed amendment does not involve a probability or consequences of an accident (TS) and Updated Final Safety Analysis significant reduction in a margin of safety. previously evaluated. Report (UFSAR) in the form of

2. Does the proposed amendment create The NRC staff has reviewed the departures from the incorporated plant-the possibility of a new or different kind of licensees analysis and, based on this accident from any accident previously specific Design Control Document Tier review, it appears that the three evaluated? 2 information. Specifically, the standards of 10 CFR 50.92(c) are Response: No. proposed departures consist of changes satisfied. Therefore, the NRC staff The proposed activity would revise the to the TS and UFSAR to revise the proposes to determine that the minimum CMT volume in the COL Appendix minimum volume of the passive core amendment request involves no A (Technical Specifications) and UFSAR cooling system core makeup tanks.

information to be consistent with the plant- Basis for proposed no significant significant hazards consideration.

specific Tier 1 and COL Appendix C Attorney for licensee: Ms. Kathryn M. hazards consideration determination:

requirements. No results or conclusions of Sutton, Morgan, Lewis & Bockius LLC, any design or safety analyses are affected. No As required by 10 CFR 50.91(a), the 1111 Pennsylvania Avenue NW., system or design function or equipment licensee has provided its analysis of the Washington, DC 20004-2514. qualification is affected by the changes. The issue of no significant hazards NRC Acting Branch Chief: Jennifer changes do not result in a new failure mode, consideration, which is presented Dixon-Herrity. malfunction or sequence of events that could below:

affect safety or safety-related equipment. This South Carolina Electric and Gas activity does not allow for a new fission 1. Does the proposed amendment involve Company, Docket Nos.52-027 and 52- product release path, result in a new fission a significant increase in the probability or 028, Virgil C. Summer Nuclear Station product barrier failure mode, or create a new consequences of an accident previously sequence of events that results in significant evaluated?

(VCSNS), Units 2 and 3, Fairfield Response: No.

County, South Carolina fuel cladding failures.

Therefore, the proposed changes do not The proposed activity would revise the Date of amendment request: May 12, create the possibility of a new or different minimum CMT [core makeup tank] volume 2016. A publicly-available version is kind of accident from any accident in the COL [combined operating license]

available in ADAMS under Accession previously evaluated. Appendix A (Technical Specifications) and

3. Does the proposed amendment involve UFSAR information to be consistent with the No. ML16133A382. plant-specific Tier 1 and COL Appendix C Description of amendment request: a significant reduction in a margin of safety?

Response: No. requirements. Because the new minimum The proposed changes, if approved for volume is bounded by the current analyses, The proposed activity would revise the the VCSNS, involve departures from minimum CMT volume in the COL Appendix the proposed activity does not alter the incorporated plant-specific Tier 2 A (Technical Specifications) and UFSAR design of an accident initiating component or Updated Final Safety Analysis Report information to be consistent with the plant- system. Thus, the probabilities of an accident (UFSAR) information and changes to the specific Tier 1 and COL Appendix C previously evaluated are not affected. The combined license Appendix A requirements. No results or conclusions of proposed activity does not involve other sradovich on DSK3GDR082PROD with NOTICES Technical Specifications to ensure that any design or safety analyses are affected. No safety-related equipment or radioactive system design function or equipment is material barriers. Thus, the proposed activity the listed minimum volume of the altered by this activity, and the proposed does not affect an accident mitigation passive core cooling system core changes do not alter any design code, safety function.

makeup tanks are aligned with the classification, or design margin. No safety Therefore, the proposed amendment does current inspections tests analyses and analysis or design basis limit is involved not involve a significant increase in the acceptance criteria and the relevant with the requested change, and consequently, probability or consequences of an accident safety analysis. no margin of safety is reduced. previously evaluated.

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43654 Federal Register / Vol. 81, No. 128 / Tuesday, July 5, 2016 / Notices

2. Does the proposed amendment create The Commission has made appropriate the KHU undergoing maintenance to the possibility of a new or different kind of findings as required by the Act and the OPERABLE status.

accident from any accident previously Commissions rules and regulations in evaluated? Date of issuance: June 6, 2016.

10 CFR Chapter I, which are set forth in Response: No. Effective date: As of the date of The proposed activity would revise the the license amendments.

A notice of consideration of issuance issuance and shall be implemented minimum CMT volume in the COL Appendix of amendment to facility operating within 60 days of issuance.

A (Technical Specifications) and UFSAR information to be consistent with the plant- license or combined license, as Amendment Nos.: 400 (Unit 1), 402 specific Tier 1 and COL Appendix C applicable, proposed no significant (Unit 2), and 401 (Unit 3). A publicly-requirements. No results or conclusions of hazards consideration determination, available version is in ADAMS under any design or safety analyses are affected. No and opportunity for a hearing in Accession No. ML16138A332; system or design function or equipment qualification is affected by the changes. The connection with these actions, was documents related to these amendments changes do not result in a new failure mode, published in the Federal Register as are listed in the Safety Evaluation malfunction or sequence of events that could indicated. enclosed with the amendments.

affect safety or safety-related equipment. This Unless otherwise indicated, the Renewed Facility Operating License activity does not allow for a new fission Commission has determined that these Nos. DPR-38, DPR-47, and DPR-55: The product release path, result in a new fission amendments satisfy the criteria for product barrier failure mode, or create a new amendments revised the Renewed categorical exclusion in accordance Facility Operating Licenses and TSs.

sequence of events that results in significant with 10 CFR 51.22. Therefore, pursuant fuel cladding failures. Date of initial notice in Federal Therefore, the proposed amendment does to 10 CFR 51.22(b), no environmental impact statement or environmental Register: November 10, 2015 (80 FR not create the possibility of a new or different 69710).

kind of accident from any accident assessment need be prepared for these previously evaluated. amendments. If the Commission has The Commissions related evaluation

3. Does the proposed amendment involve prepared an environmental assessment of the amendments is contained in a a significant reduction in a margin of safety? under the special circumstances Safety Evaluation dated June 6, 2016.

Response: No. provision in 10 CFR 51.22(b) and has The proposed activity would revise the No significant hazards consideration made a determination based on that comments received: No.

minimum CMT volume in the COL Appendix A (Technical Specifications) and UFSAR assessment, it is so indicated.

For further details with respect to the Entergy Nuclear Operations, Inc.,

information to be consistent with the plant-specific Tier 1 and COL Appendix C action, see (1) the applications for Docket No. 50-293, Pilgrim Nuclear requirements. No results or conclusions of amendment, (2) the amendment, and (3) Power Station (PNPS), Plymouth any design or safety analyses are affected. No the Commissions related letter, safety County, Massachusetts system design function or equipment is evaluation, and/or environmental altered by this activity, and the proposed Date of amendment request: July 15, assessment, as indicated. All of these changes do not alter any design code, safety 2015.

items can be accessed as described in classification, or design margin. No safety Brief description of amendment: The analysis or design basis limit is involved the Obtaining Information and Submitting Comments section of this amendment approved the revised with the requested change, and consequently, document. schedule for full implementation of the no margin of safety is reduced. Therefore, the proposed amendment does not involve a Cyber Security Plan (CSP) for Milestone Duke Energy Carolinas, LLC, Docket 8 by extending the date from June 30, significant reduction in a margin of safety.

Nos. 50-269, 50-270, and 50-287, 2016, to December 15, 2017, and revised The NRC staff has reviewed the Oconee Nuclear Station, Units 1, 2, and paragraphs 3.B and 3.G of Facility licensees analysis and, based on this 3, Oconee County, South Carolina Operating License No. DPR-35 for PNPS review, it appears that the three to incorporate the revised CSP standards of 10 CFR 50.92(c) are Date of amendment request: July 17, 2015. implementation schedule.

satisfied. Therefore, the NRC staff proposes to determine that the Brief description of amendments: The Date of issuance: June 6, 2016.

amendment request involves no amendments correct a usage problem Effective date: As of the date of significant hazards consideration. with recently issued Amendment Nos. issuance and shall be implemented Attorney for licensee: M. Stanford 382, 384, and 383 (ADAMS Accession within 30 days.

Blanton, Balch & Bingham LLP, 1710 No. ML13231A013), which precludes Oconee Nuclear Station Technical Amendment No.: 244. A publicly-Sixth Avenue North, Birmingham, AL Specification (TS) 3.8.1, AC available version is in ADAMS under 35203-2015.

[Alternating Current] Sources Accession No. ML16082A460; NRC Acting Branch Chief: Jennifer Operating, Condition H, from being documents related to this amendment Dixon-Herrity.

used as planned. The change revises the are listed in the Safety Evaluation III. Notice of Issuance of Amendments note to TS 3.8.1, Required Actions L.1, enclosed with the amendment.

to Facility Operating Licenses and L.2, and L.3 to delete the 12-hour time Facility Operating License No. DPR-Combined Licenses limitation when the second Keowee 35: The amendment revised the During the period since publication of Hydroelectric Unit (KHU) is made Renewed Facility Operating License.

the last biweekly notice, the inoperable for the purpose of restoring Date of initial notice in Federal Commission has issued the following the KHU undergoing maintenance to sradovich on DSK3GDR082PROD with NOTICES Register: October 27, 2015 (80 FR amendments. The Commission has OPERABLE status. Deletion of the 12- 65812).

determined for each of these hour time limitation allows the use of amendments that the application the full 60-hour Completion Time of The Commissions related evaluation complies with the standards and Required Action H.2 when the unit(s) of the amendment is contained in a requirements of the Atomic Energy Act have been in Condition C for greater Safety Evaluation dated June 6, 2016.

of 1954, as amended (the Act), and the than 72 hours3 days <br />0.429 weeks <br />0.0986 months <br />, and both units are made No significant hazards consideration Commissions rules and regulations. inoperable for the purpose of restoring comments received: No.

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Federal Register / Vol. 81, No. 128 / Tuesday, July 5, 2016 / Notices 43655 FirstEnergy Nuclear Operating Levels for Non-Passive Reactors, Safety Evaluation enclosed with the Company, Docket Nos. 50-334 and 50- November 2012. amendments.

412, Beaver Valley Power Station Date of issuance: June 14, 2016. Renewed Facility Operating License (BVPS), Unit Nos. 1 and 2, Beaver Effective date: As of the date of Nos. DPR-42 and DPR-60: The County, Pennsylvania Docket No. 50- issuance and shall be implemented amendments revised the Renewed 346, Davis-Besse Nuclear Power Station within 270 days from the date of Facility Operating Licenses and (DBNPS), Unit No. 1, Ottawa County, issuance. Technical Specifications.

Ohio Amendment Nos.: 166 (Unit 1) and Date of initial notice in Federal 166 (Unit 2). A publicly-available Register: October 13, 2015 (80 FR Date of application for amendments: version is in ADAMS under Accession November 19, 2015, as supplemented by 61484). The supplemental letters dated No. ML16137A056; documents related December 30, 2015; January 25, 2016; letter dated March 22, 2016. to these amendments are listed in the Brief description of amendments: The March 31, 2016; and April 14, 2016, Safety Evaluation enclosed with the provided additional information that amendments changed the BVPS and amendments.

DBNPS Technical Specifications (TSs). clarified the application, did not expand Facility Operating License Nos. NPF- the scope of the application as originally Specifically, the license amendments 87 and NPF-89: The amendments revised TS 5.3.1, Unit Staff noticed, and did not change the staffs revised the Facility Operating Licenses original proposed no significant hazards Qualifications, by incorporating an to authorize revision to the CPNPP exception to American National consideration determination as Emergency Plan. published in the Federal Register.

Standards Institute (ANSI) Standard Date of initial notice in Federal N18.1-1971, Selection and Training of The Commissions related evaluation Register: August 14, 2015 (80 FR of the amendments is contained in a Nuclear Power Plant Personnel, such 48923), and corrected on August 20, that licensed operators are only required Safety Evaluation dated June 16, 2016.

2015 (80 FR 50663). The supplemental No significant hazards consideration to comply with the requirements of 10 letters dated January 27, 2016, and CFR part 55, Operators Licenses. comments received: No.

March 3, 2016, provided additional Date of issuance: June 7, 2016. information that clarified the Omaha Public Power District, Docket Effective date: As of the date of application, did not expand the scope of No. 50-285, Fort Calhoun Station, Unit issuance and shall be implemented the application as originally noticed, No. 1, Washington County, Nebraska within 90 days from the date of and did not change the staffs original issuance. Date of amendment request:

proposed no significant hazards September 11, 2015.

Amendment Nos.: 297 and 185 for consideration determination as BVPS, Units 1 and 2, and 292 for Brief description of amendment: The published in the Federal Register. amendment revised the Technical DBNPS, Unit 1. A publicly-available The Commissions related evaluation version is in ADAMS under Accession Specifications (TSs) to provide a short of the amendments is contained in a Completion Time to restore an No. ML16040A084. Documents related Safety Evaluation dated June 14, 2016.

to these amendments are listed in the inoperable system for conditions under No significant hazards consideration Safety Evaluation (SE) enclosed with the which the existing TSs require a plant comments received: No.

amendments. shutdown. The amendment is consistent Renewed Facility Operating License Northern States Power Company with NRC-approved Technical Nos. DPR-66, NPF-73, and NPF-3: The Minnesota, Docket Nos. 50-282 and 50- Specifications Task Force (TSTF) amendments revised the TSs and 306, Prairie Island Nuclear Generating Traveler TSTF-426, Revision 5, Revise Renewed Facility Operating Licenses. Plant, Units 1 and 2, Goodhue County, or Add Actions to Preclude Entry into Date of initial notice in Federal Minnesota LCO [Limiting Condition for Operation]

Register: January 19, 2016 (81 FR Date of amendment request: June 29, 3.0.3RITSTF [Risk-Informed TSTF]

2918). The supplemental letter dated 2015, as supplemented by letters dated Initiatives 6b & 6c, with certain plant-March 22, 2016, contained clarifying December 30, 2015; January 25, 2016; specific administrative variations.

information and did not change the NRC March 31, 2016; and April 14, 2016. Date of issuance: June 8, 2016.

staffs initial proposed finding of no Brief description of amendments: The Effective date: As of the date of significant hazards consideration. amendments revised surveillance issuance and shall be implemented The Commissions related evaluation requirements (SRs) related to gas within 90 days from the date of of the amendments is contained in an accumulation for the emergency core issuance.

SE dated June 7, 2016. cooling system and added new SRs Amendment No.: 288. A publicly-No significant hazards consideration related to gas accumulation for the available version is in ADAMS under comments received: No. residual heat removal and containment Accession No. ML16139A804; spray systems, consistent with NRC- documents related to this amendment Luminant Generation Company LLC, are listed in the Safety Evaluation approved Technical Specifications Task Docket Nos. 50-445 and 50-446, enclosed with the amendment.

Force (TSTF) Standard Technical Comanche Peak Nuclear Power Plant, Renewed Facility Operating License Specifications Change Traveler TSTF-Unit Nos. 1 and 2 (CPNPP), Somervell No. DPR-40: The amendment revised 523, Revision 2, Generic Letter 2008-County, Texas the Renewed Facility Operating License 01, Managing Gas Accumulation.

Date of amendment request: June 30, Date of issuance: June 16, 2016. and TSs.

2015, as supplemented by letters dated Effective date: As of the date of Date of initial notice in Federal sradovich on DSK3GDR082PROD with NOTICES January 27, 2016, and March 3, 2016. issuance and shall be implemented Register: November 24, 2015 (80 FR Brief description of amendments: The within 90 days of issuance. 73239).

amendments revised the current Amendment Nos.: 217 (Unit 1) and The Commissions related evaluation emergency action level scheme for 205 (Unit 2). A publicly-available of the amendment is contained in a CPNPP to a scheme based on Nuclear version is in ADAMS under Accession Safety Evaluation dated June 8, 2016.

Energy Institute (NEI) 99-01, Revision 6, No. ML16133A406; documents related No significant hazards consideration Development of Emergency Action to these amendments are listed in the comments received: No.

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43656 Federal Register / Vol. 81, No. 128 / Tuesday, July 5, 2016 / Notices Southern Nuclear Operating Company, Standard Technical Specifications proposed amendment would revise Inc., Docket Nos. 50-424 and 50-425, Change Traveler-432, Revision 1, Technical Specification (TS) 4.2.1, Vogtle Electric Generating Plant, Units 1 Change in Technical Specifications Fuel Assemblies; TS 3.5.1 and 2, Burke County, Georgia End States (WCAP-16294), dated Accumulators; Surveillance Date of amendment request: July 18, November 29, 2010. Requirement (SR) 3.5.1.4; TS 3.5.4, 2014, as supplemented by letters dated Date of issuance: June 10, 2016. Refueling Water Storage Tank; and SR February 27, 2015, and May 2, 2016. Effective date: As of its date of 3.5.4.3, to increase the maximum Brief description of amendments: The issuance and shall be implemented number of tritium producing burnable amendments revised 22 Technical within 90 days of issuance. absorber rods (TPBARs) and to delete Specifications (TSs) by adopting Amendment Nos.: 202 (Unit 1) and outdated information related to the multiple previously NRC-approved 198 (Unit 2). A publicly-available tritium production program. The NRC Technical Specifications Task Force version is in ADAMS under Accession staff is issuing an environmental (TSTF) Travelers. One proposed change No. ML15289A227; documents related assessment (EA) and finding of no is not included in this license to these amendments are listed in the significant impact (FONSI) associated amendment and will be addressed by Safety Evaluation enclosed with the with the proposed license amendment.

further correspondence. Southern amendments.

Facility Operating License Nos. NPF- DATES: The Environmental assessment Nuclear Operating Company, Inc. (SNC) referenced in this document is available stated that these TSTF Travelers are 2 and NPF-8: The amendments revised the Renewed Facility Operating on July 5, 2016.

generic changes chosen to increase the consistency between the Vogtle Electric Licenses and Technical Specifications. ADDRESSES: Please refer to Docket ID Generating Plant TSs, the Improved Date of initial notice in Federal NRC-2016-0131 when contacting the Standard Technical Specifications for Register: May 26, 2015 (80 FR 30102). NRC about the availability of Westinghouse plants (NUREG-1431), The supplemental letters dated information regarding this document.

and the TSs of the other plants in the September 17, 2015, and April 13, 2016, You may obtain publicly-available SNC fleet. provided additional information that information related to this document Date of issuance: June 9, 2016. clarified the application, did not expand using any of the following methods:

the scope of the application as originally Effective date: As of the date of

• Federal Rulemaking Web site: Go to issuance and shall be implemented noticed, and did not change the staffs http://www.regulations.gov and search within 120 days of issuance. original proposed no significant hazards for Docket ID NRC-2016-0131. Address Amendment Nos.: 180 (Unit 1) and consideration determination as questions about NRC dockets to Carol 161 (Unit 2). A publicly-available published in the Federal Register.

Gallagher; telephone: 301-415-3463; version is in ADAMS under Accession The Commissions related evaluation email: Carol.Gallagher@nrc.gov. For No. ML15132A569; documents related of the amendments is contained in a technical questions, contact the to these amendments are listed in the Safety Evaluation dated June 10, 2016.

individual listed in the FOR FURTHER Safety Evaluation enclosed with the No significant hazards consideration INFORMATION CONTACT section of this amendments. comments received: No.

document.

Facility Operating License Nos. NPF- Dated at Rockville, Maryland, this 22nd day of June 2016.

• NRCs Agencywide Documents 68 and NPF-81: Amendments revised Access and Management System the Facility Operating Licenses and TSs. For the Nuclear Regulatory Commission.

(ADAMS): You may obtain publicly-Date of initial notice in Federal Anne T. Boland, available documents online in the Register: March 3, 2015 (80 FR 11480). Director, Division of Operating Reactor ADAMS Public Documents collection at The supplemental letters dated February Licensing, Office of Nuclear Reactor http://www.nrc.gov/reading-rm/

27, 2015, and May 2, 2016, provided Regulation.

adams.html. To begin the search, select additional information that clarified the [FR Doc. 2016-15659 Filed 7-1-16; 8:45 am]

ADAMS Public Documents and then application, did not expand the scope of BILLING CODE 7590-01-P select Begin Web-based ADAMS the application as originally noticed, Search. For problems with ADAMS, and did not change the staffs original please contact the NRCs Public proposal no significant hazards NUCLEAR REGULATORY Document Room (PDR) reference staff at consideration determination as COMMISSION 1-800-397-4209, 301-415-4737, or by published in the Federal Register.

[Docket No. 50-390; NRC-2016-0131] email to pdr.resource@nrc.gov. For the The Commissions related evaluation convenience of the reader, the ADAMS of the amendments is contained in a Tennessee Valley Authority Watts Bar accession numbers are provided in a Safety Evaluation dated June 9, 2016. Nuclear Plant, Unit 1 table in the AVAILABILITY OF No significant hazards consideration AGENCY: Nuclear Regulatory DOCUMENTS section of this document.

comments received: No.

Commission.

• NRCs PDR: You may examine and Southern Nuclear Operating Company, purchase copies of public documents at Docket Nos. 50-348 and 50-364, Joseph ACTION: Environmental assessment and finding of no significant impact; the NRCs PDR, Room O1-F21, One M. Farley Nuclear Plant, Units 1 and 2, White Flint North, 11555 Rockville Houston County, Alabama issuance.

Pike, Rockville, Maryland 20852.

Date of amendment request: April 13,

SUMMARY

The U.S. Nuclear Regulatory sradovich on DSK3GDR082PROD with NOTICES FOR FURTHER INFORMATION CONTACT:

2015, as supplemented by letters dated Commission (NRC) is considering the Robert Schaaf, Office of Nuclear Reactor September 17, 2015, and April 13, 2016. issuance of an amendment to Facility Regulation, Nuclear Regulatory Brief description of amendments: The Operating License No. NFP-90, issued Commission, Washington, DC 20555-amendments consist of changes to the February 7, 1996, and held by the 0001; telephone: 301-415-6020, email:

Technical Specifications consistent with Tennessee Valley Authority (TVA, the Robert.Schaaf@nrc.gov.

the NRC-approved Technical licensee) for the operation of Watts Bar Specification Task Force Improved Nuclear Plant (WBN), Unit 1. The SUPPLEMENTARY INFORMATION:

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