Federal Register / Vol. 84, No. 127 / Tuesday, July 2, 2019 / Notices 31629

Commission’s rules and regulations. make immediately effective any ADAMS Public Documents collection at The Commission has made appropriate amendment to an operating license or https://www.nrc.gov/reading-rm/ findings as required by the Act and the combined license, as applicable, upon a adams.html. To begin the search, select Commission’s rules and regulations in determination by the Commission that ‘‘Begin Web-based ADAMS Search.’’ For 10 CFR Chapter I, which are set forth in such amendment involves no significant problems with ADAMS, please contact the license amendment. hazards consideration, notwithstanding the NRC’s Public Document Room (PDR) A notice of consideration of issuance the pendency before the Commission of reference staff at 1–800–397–4209, 301– of amendment to facility operating a request for a hearing from any person. 415–4737, or by email to pdr.resource@ license or COL, as applicable, proposed This biweekly notice includes all nrc.gov. The ADAMS accession number no significant hazards consideration notices of amendments issued, or for each document referenced (if it is determination, and opportunity for a proposed to be issued, from June 4, available in ADAMS) is provided the hearing in connection with these 2019, to June 17, 2019. The last first time that it is mentioned in this actions, was published in the Federal biweekly notice was published on June document. Register on February 12, 2019 (84 FR 18, 2019. • NRC’s PDR: You may examine and 3504). No comments were received DATES: Comments must be filed by purchase copies of public documents at during the 30-day comment period. August 1, 2019. A request for a hearing the NRC’s PDR, Room O1–F21, One The Commission has determined that must be filed by September 3, 2019. White Flint North, 11555 Rockville these amendments satisfy the criteria for Pike, Rockville, Maryland 20852. categorical exclusion in accordance ADDRESSES: You may submit comments with 10 CFR 51.22. Therefore, pursuant by any of the following methods: B. Submitting Comments • Federal Rulemaking website: Go to to 10 CFR 51.22(b), no environmental Please include Docket ID NRC–2019– impact statement or environmental https://www.regulations.gov and search for Docket ID NRC–2019–0140. Address 0140, facility name, unit number(s), assessment need be prepared for these plant docket number, application date, amendments. questions about NRC dockets IDs in Regulations.gov to Jennifer Borges; and subject in your comment IV. Conclusion telephone: 301–287–9127; email: submission. Using the reasons set forth in the [email protected]. For technical The NRC cautions you not to include combined safety evaluation, the staff questions, contact the individual listed identifying or contact information that granted the exemption and issued the in the FOR FURTHER INFORMATION you do not want to be publicly amendment that SNC requested on CONTACT section of this document. disclosed in your comment submission. December 13, 2018. The exemption and • Mail comments to: Office of The NRC will post all comment amendment were issued on June 12, Administration, Mail Stop: TWFN–7– submissions at https:// 2019, as part of a combined package to A60M, U.S. Nuclear Regulatory www.regulations.gov as well as enter the SNC (ADAMS Accession No. Commission, Washington, DC 20555– comment submissions into ADAMS. ML19133A167). 0001, ATTN: Program Management, The NRC does not routinely edit Announcements and Editing Staff. comment submissions to remove Dated at Rockville, Maryland, this 26th day identifying or contact information. of June, 2019. For additional direction on obtaining If you are requesting or aggregating For the Nuclear Regulatory Commission. information and submitting comments, see ‘‘Obtaining Information and comments from other persons for Jennifer L. Dixon-Herrity, Submitting Comments’’ in the submission to the NRC, then you should Chief, Licensing Branch 2, Division of SUPPLEMENTARY INFORMATION section of inform those persons not to include Licensing, Siting, and Environmental identifying or contact information that Analysis, Office of New Reactors. this document. FOR FURTHER INFORMATION CONTACT: they do not want to be publicly [FR Doc. 2019–14039 Filed 7–1–19; 8:45 am] disclosed in their comment submission. BILLING CODE 7590–01–P Shirley Rohrer, Office of Nuclear Reactor Regulation, U.S. Nuclear Your request should state that the NRC Regulatory Commission, Washington, does not routinely edit comment submissions to remove such information NUCLEAR REGULATORY D.C. 20555–0001; telephone: 301–415– before making the comment COMMISSION 5411, email: [email protected]. submissions available to the public or SUPPLEMENTARY INFORMATION: [NRC–2019–0140] entering the comment into ADAMS. I. Obtaining Information and II. Background Biweekly Notice; Applications and Submitting Comments Amendments to Facility Operating Pursuant to Section 189a.(2) of the Licenses and Combined Licenses A. Obtaining Information Atomic Energy Act of 1954, as amended Involving No Significant Hazards Please refer to Docket ID NRC–2019– (the Act), the U.S. Nuclear Regulatory Considerations 0140, facility name, unit number(s), Commission (NRC) is publishing this AGENCY: Nuclear Regulatory plant docket number, application date, regular biweekly notice. The Act Commission. and subject when contacting the NRC requires the Commission to publish ACTION: Biweekly notice. about the availability of information for notice of any amendments issued, or this action. You may obtain publicly- proposed to be issued, and grants the SUMMARY: Pursuant to the Atomic available information related to this Commission the authority to issue and Energy Act of 1954, as amended (the action by any of the following methods: make immediately effective any Act), the U.S. Nuclear Regulatory • Federal Rulemaking website: Go to amendment to an operating license or Commission (NRC) is publishing this https://www.regulations.gov and search combined license, as applicable, upon a regular biweekly notice. The Act for Docket ID NRC–2019–0140. determination by the Commission that requires the Commission to publish • NRC’s Agencywide Documents such amendment involves no significant notice of any amendments issued, or Access and Management System hazards consideration, notwithstanding proposed to be issued, and grants the (ADAMS): You may obtain publicly- the pendency before the Commission of Commission the authority to issue and available documents online in the a request for a hearing from any person.

VerDate Sep<11>2014 17:00 Jul 01, 2019 Jkt 247001 PO 00000 Frm 00069 Fmt 4703 Sfmt 4703 E:\FR\FM\02JYN1.SGM 02JYN1 khammond on DSKBBV9HB2PROD with NOTICES 31630 Federal Register / Vol. 84, No. 127 / Tuesday, July 2, 2019 / Notices

III. Notice of Consideration of Issuance action. Petitions shall be filed in to participate fully in the conduct of the of Amendments to Facility Operating accordance with the Commission’s hearing with respect to resolution of Licenses and Combined Licenses and ‘‘Agency Rules of Practice and that party’s admitted contentions, Proposed No Significant Hazards Procedure’’ in 10 CFR part 2. Interested including the opportunity to present Consideration Determination persons should consult a current copy evidence, consistent with the NRC’s The Commission has made a of 10 CFR 2.309. The NRC’s regulations regulations, policies, and procedures. Petitions must be filed no later than proposed determination that the are accessible electronically from the 60 days from the date of publication of following amendment requests involve NRC Library on the NRC’s website at http://www.nrc.gov/reading-rm/doc- this notice. Petitions and motions for no significant hazards consideration. collections/cfr/. Alternatively, a copy of leave to file new or amended Under the Commission’s regulations in the regulations is available at the NRC’s contentions that are filed after the § 50.92 of title 10 of the Code of Federal Public Document Room, located at One deadline will not be entertained absent Regulations (10 CFR), this means that White Flint North, Room O1–F21, 11555 a determination by the presiding officer operation of the facility in accordance Rockville Pike (first floor), Rockville, that the filing demonstrates good cause with the proposed amendment would Maryland 20852. If a petition is filed, by satisfying the three factors in 10 CFR not (1) involve a significant increase in the Commission or a presiding officer 2.309(c)(1)(i) through (iii). The petition the probability or consequences of an will rule on the petition and, if must be filed in accordance with the accident previously evaluated; or (2) appropriate, a notice of a hearing will be filing instructions in the ‘‘Electronic create the possibility of a new or issued. Submissions (E-Filing)’’ section of this different kind of accident from any As required by 10 CFR 2.309(d) the document. accident previously evaluated; or (3) petition should specifically explain the If a hearing is requested, and the involve a significant reduction in a reasons why intervention should be Commission has not made a final margin of safety. The basis for this permitted with particular reference to determination on the issue of no proposed determination for each the following general requirements for significant hazards consideration, the amendment request is shown below. standing: (1) The name, address, and Commission will make a final The Commission is seeking public telephone number of the petitioner; (2) determination on the issue of no comments on this proposed the nature of the petitioner’s right under significant hazards consideration. The determination. Any comments received the Act to be made a party to the final determination will serve to within 30 days after the date of proceeding; (3) the nature and extent of establish when the hearing is held. If the publication of this notice will be the petitioner’s property, financial, or final determination is that the considered in making any final other interest in the proceeding; and (4) amendment request involves no determination. the possible effect of any decision or significant hazards consideration, the Normally, the Commission will not order which may be entered in the Commission may issue the amendment issue the amendment until the proceeding on the petitioner’s interest. and make it immediately effective, expiration of 60 days after the date of In accordance with 10 CFR 2.309(f), notwithstanding the request for a publication of this notice. The the petition must also set forth the hearing. Any hearing would take place Commission may issue the license specific contentions which the after issuance of the amendment. If the amendment before expiration of the 60- petitioner seeks to have litigated in the final determination is that the day period provided that its final proceeding. Each contention must amendment request involves a determination is that the amendment consist of a specific statement of the significant hazards consideration, then involves no significant hazards issue of law or fact to be raised or any hearing held would take place consideration. In addition, the controverted. In addition, the petitioner before the issuance of the amendment Commission may issue the amendment must provide a brief explanation of the unless the Commission finds an prior to the expiration of the 30-day bases for the contention and a concise imminent danger to the health or safety comment period if circumstances statement of the alleged facts or expert of the public, in which case it will issue change during the 30-day comment opinion which support the contention an appropriate order or rule under 10 period such that failure to act in a and on which the petitioner intends to CFR part 2. timely way would result, for example in rely in proving the contention at the A State, local governmental body, derating or shutdown of the facility. If hearing. The petitioner must also Federally-recognized Indian Tribe, or the Commission takes action prior to the provide references to the specific agency thereof, may submit a petition to expiration of either the comment period sources and documents on which the the Commission to participate as a party or the notice period, it will publish in petitioner intends to rely to support its under 10 CFR 2.309(h)(1). The petition the Federal Register a notice of position on the issue. The petition must should state the nature and extent of the issuance. If the Commission makes a include sufficient information to show petitioner’s interest in the proceeding. final no significant hazards that a genuine dispute exists with the The petition should be submitted to the consideration determination, any applicant or licensee on a material issue Commission no later than 60 days from hearing will take place after issuance. of law or fact. Contentions must be the date of publication of this notice. The Commission expects that the need limited to matters within the scope of The petition must be filed in accordance to take this action will occur very the proceeding. The contention must be with the filing instructions in the infrequently. one which, if proven, would entitle the ‘‘Electronic Submissions (E-Filing)’’ petitioner to relief. A petitioner who section of this document, and should A. Opportunity To Request a Hearing fails to satisfy the requirements at 10 meet the requirements for petitions set and Petition for Leave To Intervene CFR 2.309(f) with respect to at least one forth in this section, except that under Within 60 days after the date of contention will not be permitted to 10 CFR 2.309(h)(2) a State, local publication of this notice, any persons participate as a party. governmental body, or Federally- (petitioner) whose interest may be Those permitted to intervene become recognized Indian Tribe, or agency affected by this action may file a request parties to the proceeding, subject to any thereof does not need to address the for a hearing and petition for leave to limitations in the order granting leave to standing requirements in 10 CFR intervene (petition) with respect to the intervene. Parties have the opportunity 2.309(d) if the facility is located within

VerDate Sep<11>2014 17:00 Jul 01, 2019 Jkt 247001 PO 00000 Frm 00070 Fmt 4703 Sfmt 4703 E:\FR\FM\02JYN1.SGM 02JYN1 khammond on DSKBBV9HB2PROD with NOTICES Federal Register / Vol. 84, No. 127 / Tuesday, July 2, 2019 / Notices 31631

its boundaries. Alternatively, a State, submitting a petition or other filing stating why there is good cause for local governmental body, Federally- adjudicatory document (even in not filing electronically and requesting recognized Indian Tribe, or agency instances in which the participant, or its authorization to continue to submit thereof may participate as a non-party counsel or representative, already holds documents in paper format. Such filings under 10 CFR 2.315(c). an NRC-issued digital ID certificate). must be submitted by: (1) First class If a hearing is granted, any person Based upon this information, the mail addressed to the Office of the who is not a party to the proceeding and Secretary will establish an electronic Secretary of the Commission, U.S. is not affiliated with or represented by docket for the hearing in this proceeding Nuclear Regulatory Commission, a party may, at the discretion of the if the Secretary has not already Washington, DC 20555–0001, Attention: presiding officer, be permitted to make established an electronic docket. Rulemaking and Adjudications Staff; or a limited appearance pursuant to the Information about applying for a (2) courier, express mail, or expedited provisions of 10 CFR 2.315(a). A person digital ID certificate is available on the delivery service to the Office of the making a limited appearance may make NRC’s public website at http:// Secretary, 11555 Rockville Pike, an oral or written statement of his or her www.nrc.gov/site-help/e-submittals/ Rockville, Maryland 20852, Attention: position on the issues but may not getting-started.html. Once a participant Rulemaking and Adjudications Staff. otherwise participate in the proceeding. has obtained a digital ID certificate and Participants filing adjudicatory A limited appearance may be made at a docket has been created, the documents in this manner are any session of the hearing or at any participant can then submit responsible for serving the document on prehearing conference, subject to the adjudicatory documents. Submissions all other participants. Filing is limits and conditions as may be must be in Portable Document Format considered complete by first-class mail imposed by the presiding officer. Details (PDF). Additional guidance on PDF as of the time of deposit in the mail, or regarding the opportunity to make a submissions is available on the NRC’s by courier, express mail, or expedited limited appearance will be provided by public website at http://www.nrc.gov/ delivery service upon depositing the the presiding officer if such sessions are site-help/electronic-sub-ref-mat.html. A document with the provider of the scheduled. filing is considered complete at the time service. A presiding officer, having the document is submitted through the B. Electronic Submissions (E-Filing) granted an exemption request from NRC’s E-Filing system. To be timely, an using E-Filing, may require a participant All documents filed in NRC electronic filing must be submitted to or party to use E-Filing if the presiding adjudicatory proceedings, including a the E-Filing system no later than 11:59 officer subsequently determines that the request for hearing and petition for p.m. Eastern Time on the due date. reason for granting the exemption from leave to intervene (petition), any motion Upon receipt of a transmission, the E- use of E-Filing no longer exists. or other document filed in the Filing system time-stamps the document Documents submitted in adjudicatory proceeding prior to the submission of a and sends the submitter an email notice proceedings will appear in the NRC’s request for hearing or petition to confirming receipt of the document. The electronic hearing docket which is intervene, and documents filed by E-Filing system also distributes an email available to the public at https:// interested governmental entities that notice that provides access to the adams.nrc.gov/ehd, unless excluded request to participate under 10 CFR document to the NRC’s Office of the pursuant to an order of the Commission 2.315(c), must be filed in accordance General Counsel and any others who or the presiding officer. If you do not with the NRC’s E-Filing rule (72 FR have advised the Office of the Secretary have an NRC-issued digital ID certificate 49139; August 28, 2007, as amended at that they wish to participate in the as described above, click cancel when 77 FR 46562; August 3, 2012). The E- proceeding, so that the filer need not the link requests certificates and you Filing process requires participants to serve the document on those will be automatically directed to the submit and serve all adjudicatory participants separately. Therefore, NRC’s electronic hearing dockets where documents over the internet, or in some applicants and other participants (or you will be able to access any publicly cases to mail copies on electronic their counsel or representative) must available documents in a particular storage media. Detailed guidance on apply for and receive a digital ID hearing docket. Participants are making electronic submissions may be certificate before adjudicatory requested not to include personal found in the Guidance for Electronic documents are filed so that they can privacy information, such as social Submissions to the NRC and on the NRC obtain access to the documents via the security numbers, home addresses, or website at http://www.nrc.gov/site-help/ E-Filing system. personal phone numbers in their filings, e-submittals.html. Participants may not A person filing electronically using unless an NRC regulation or other law submit paper copies of their filings the NRC’s adjudicatory E-Filing system requires submission of such unless they seek an exemption in may seek assistance by contacting the information. For example, in some accordance with the procedures NRC’s Electronic Filing Help Desk instances, individuals provide home described below. through the ‘‘Contact Us’’ link located addresses in order to demonstrate To comply with the procedural on the NRC’s public website at http:// proximity to a facility or site. With requirements of E-Filing, at least 10 www.nrc.gov/site-help/e- respect to copyrighted works, except for days prior to the filing deadline, the submittals.html, by email to limited excerpts that serve the purpose participant should contact the Office of [email protected], or by a toll- of the adjudicatory filings and would the Secretary by email at free call at 1–866–672–7640. The NRC constitute a Fair Use application, [email protected], or by telephone Electronic Filing Help Desk is available participants are requested not to include at 301–415–1677, to (1) request a digital between 9 a.m. and 6 p.m., Eastern copyrighted materials in their identification (ID) certificate, which Time, Monday through Friday, submission. allows the participant (or its counsel or excluding government holidays. For further details with respect to representative) to digitally sign Participants who believe that they these license amendment applications, submissions and access the E-Filing have a good cause for not submitting see the application for amendment system for any proceeding in which it documents electronically must file an which is available for public inspection is participating; and (2) advise the exemption request, in accordance with in ADAMS and at the NRC’s PDR. For Secretary that the participant will be 10 CFR 2.302(g), with their initial paper additional direction on accessing

VerDate Sep<11>2014 17:00 Jul 01, 2019 Jkt 247001 PO 00000 Frm 00071 Fmt 4703 Sfmt 4703 E:\FR\FM\02JYN1.SGM 02JYN1 khammond on DSKBBV9HB2PROD with NOTICES 31632 Federal Register / Vol. 84, No. 127 / Tuesday, July 2, 2019 / Notices

information related to this document, not significantly increase the consequences September 16, 2016, that are currently see the ‘‘Obtaining Information and of accidents previously evaluated. obsolete. Submitting Comments’’ section of this 2. Does the proposed amendment create Therefore, operation of the facility in document. the possibility of a new or different kind of accordance with the proposed changes will accident from any accident previously not involve a significant reduction in the Duke Energy Progress, LLC, Docket No. evaluated? margin of safety. [Response: No.] 50–400, Shearon Harris Nuclear Power The NRC staff has reviewed the Plant, Unit 1, Wake and Chatham The proposed amendment is an extension of the allowed outage time from 72 hours to licensee’s analysis and, based on this Counties, North Carolina 7 days for the ESCWS and its supported TS review, it appears that the three Date of amendment request: February systems that includes Charging Pumps, ECCS standards of 10 CFR 50.92(c) are 18, 2019. A publicly-available version is [emergency core cooling system] subsystems, satisfied. Therefore, the NRC staff in ADAMS under Accession No. Containment Spray System, Containment proposes to determine that the Cooling System, and the Emergency Service amendment request involves no ML19049A027. Water System, ‘B’ Train. The requested Description of amendment request: significant hazards consideration. change does not involve the addition or Attorney for licensee: David The amendment would revise the removal of any plant system, structure, or Technical Specifications (TSs) to permit component. Cummings, Associate General Counsel, one train of the Essential Services The proposed TS changes do not affect the Duke Energy Corporation, Mail Code Chilled Water System (ESCWS) to be basic design, operation, or function of any of DEC45, 550 South Tryon St., Charlotte, inoperable for up to 7 days, from the the systems associated with the TS impacted NC 28202. by the amendment. Implementation of the NRC Branch Chief: Undine Shoop. current 72 hours allowed outage time. In proposed amendment will not create the addition, the amendment would remove possibility of a new or different kind of Entergy Nuclear Operations, Inc., an expired note previously added to TSs accident from that previously evaluated. Docket No. 50–255, Palisades Nuclear by implementation of License The proposed changes to TS 3.1.2.4, TS Plant (PNP), Van Buren County, Amendment 153. 3.5.2, TS 3.6.2.1, TS 3.6.2.2, TS 3.6.2.3, TS Michigan Basis for proposed no significant 3.7.1.2, TS 3.7.3, TS 3.7.4, TS 3.7.6, TS 3.7.7, Date of amendment request: March hazards consideration determination: TS 3.7.13, and TS 3.8.1.1 that remove an expired note are administrative, non- 28, 2019, as supplemented by letter As required by 10 CFR 50.91(a), the dated May 6, 2019. Publicly-available licensee has provided its analysis of the technical changes which remove temporary TS requirements added as part of the HNP versions are in ADAMS under issue of no significant hazards License Amendment 153 issued on Accession Nos. ML19098A966, and consideration, which is presented September 16, 2016, that are currently ML19127A018, respectively. below: obsolete. Description of amendment request: 1. Does the proposed amendment involve In conclusion, this proposed LAR does not The amendment would revise and a significant increase in the probability or impact any plant systems that are accident modify the PNP technical specifications consequences of an accident previously initiators and does not impact any safety (TSs) by relocating specific surveillance evaluated? analysis. Therefore, operation of the facility frequencies to a licensee-controlled [Response: No.] in accordance with the proposed changes The operable train of the ESCWS and will not create the possibility of a new or program with the implementation of supported equipment will remain fully different kind of accident from any Technical Specifications Task Force operable during the 7-day allowed outage previously evaluated. (TSTF) Traveler TSTF–425, ‘‘Relocate time. The unavailable train of the ESCWS 3. Does the proposed amendment involve Surveillance Frequencies to Licensee and supported equipment function as a significant reduction in a margin of safety? Control—RITSTF [Risk-Informed TSTF] accident mitigators. The removal of a train of [Response: No.] Initiative 5b,’’ Revision 3. the ESCWS from service for a limited period The margin of safety is related to the Basis for proposed no significant of time does not affect any accident initiator confidence in the ability of the fission hazards consideration determination: and therefore cannot change the probability product barriers to perform their design As required by 10 CFR 50.91(a), the of an accident. The proposed change has functions during and following an accident licensee has provided its analysis of the been evaluated to assess the impact on condition. These barriers include the fuel systems affected and the upon design basis cladding, the reactor coolant system, and the issue of no significant hazards safety functions. containment system. The performance of the consideration, which is presented The activities covered by this LAR [license fuel cladding, reactor coolant, and below: amendment request] also include defense-in- containment systems will not be impacted by As required by 10 CFR 50.91(a), the depth compensatory measures. There will be the proposed LAR. licensee has provided its analysis of the no effect on the analysis of any accident or Additionally, the proposed amendment issue of no significant hazards the progression of the accident since the does not involve a change in the operation consideration. The NRC staff has operable ESCWS train is capable of serving of the plant. The activity only extends the reviewed the licensee’s analysis against 100 percent of all the required heat loads. As amount of time a train of the ESCWS is the standards of 10 CFR 50.92(c). The such, there is no impact on consequence allowed to be inoperable to complete mitigation for any transient or accident. maintenance for equipment reliability. The NRC staff’s analysis is presented below: The proposed changes to TS 3.1.2.4, TS incremental conditional core damage 1. Does the proposed change involve a 3.5.2, TS 3.6.2.1, TS 3.6.2.2, TS 3.6.2.3, TS probability (ICCDP) and incremental significant increase in the probability or 3.7.1.2, TS 3.7.3, TS 3.7.4, TS 3.7.6, TS 3.7.7, conditional large early release probability consequences of any accident previously TS 3.7.13, and TS 3.8.1.1 that remove an (ICLERP) calculated for the 7-day AOT are evaluated? expired note are administrative, non- within the limits presented in Regulatory Response: No. technical changes which remove temporary Guides 1.174 and 1.177. The proposed change relocates the TS requirements added as part of the HNP The proposed changes to TS 3.1.2.4, TS specified frequencies for periodic License Amendment 153 issued on 3.5.2, TS 3.6.2.1, TS 3.6.2.2, TS 3.6.2.3, TS surveillance requirements to licensee control September 16, 2016 (Agencywide Documents 3.7.1.2, TS 3.7.3, TS 3.7.4, TS 3.7.6, TS 3.7.7, under a new Surveillance Frequency Control Access and Management System Accession TS 3.7.13, and TS 3.8.1.1 that remove an Program [SFCP]. Surveillance frequencies are No. ML16253A059), that are currently expired note are administrative, non- not an initiator to any accident previously obsolete. technical changes which remove temporary evaluated. As a result, the probability of any As a result, operation of the facility in TS requirements added as part of the HNP accident previously evaluated is not accordance with the proposed changes will License Amendment 153 issued on significantly increased. The systems and

VerDate Sep<11>2014 17:00 Jul 01, 2019 Jkt 247001 PO 00000 Frm 00072 Fmt 4703 Sfmt 4703 E:\FR\FM\02JYN1.SGM 02JYN1 khammond on DSKBBV9HB2PROD with NOTICES Federal Register / Vol. 84, No. 127 / Tuesday, July 2, 2019 / Notices 31633

components required by the technical 101 Constitution Avenue NW, Suite 200 Changes to the Licensing Basis.’’ The TMRE specifications for which the surveillance East, Washington, DC 20001. calculations performed by Entergy meet the frequencies are relocated are still required to NRC Acting Branch Chief: Lisa M. acceptance criteria of RG 1.174. be operable, meet the acceptance criteria for Regner. Therefore, this change does not involve a the surveillance requirements, and be significant increase in the probability or capable of performing any mitigation Entergy Operations, Inc. (Entergy), consequences of an accident previously function assumed in the accident analysis. Docket Nos. 50–313 and 50–368, evaluated. As a result, the consequences of any accident Arkansas Nuclear One, Units 1 (ANO– 2. Does the proposed change create the previously evaluated are not significantly 1) and 2 (ANO–2), Pope County, possibility of a new or different kind of accident from any accident previously increased. Arkansas Therefore, the proposed change does not evaluated? involve a significant increase in the Date of amendment request: April 29, Response: No. probability or consequences of an accident 2019. A publicly-available version is in The proposed amendment is to revise the previously evaluated. ADAMS under Accession No. ANO–1 and ANO–2 unit-specific SARs by 2. Does the proposed change create the ML19119A090. reflecting the results of the TMRE analysis, possibility of a new or different kind of Description of amendment request: which demonstrated that tornado-generated accident from any previously evaluated? missile protection is not required for The amendments would revise the identified nonconforming SSCs on each unit. Response: No. license basis documents for ANO–1 and No new or different accidents result from TMRE is an alternative methodology which utilizing the proposed change. The changes ANO–2, to utilize the Tornado Missile can only be applied to discovered conditions do not involve a physical alteration of the Risk Evaluator (TMRE) methodology as where tornado missile protection was not plant (i.e., no new or different type of the licensing basis to qualify several provided, and cannot be used to avoid equipment will be installed) or a change in components that have been identified as providing tornado missile protection in the the methods governing normal plant not conforming to the unit-specific plant modification process. operation. In addition, the changes do not current licensing basis. The proposed amendment involves no impose any new or different requirements. Basis for proposed no significant physical changes to the existing plants; therefore, no new malfunctions could create The changes do not alter assumptions made hazards consideration determination: in the safety analysis. The proposed changes the possibility of a new or different kind of As required by 10 CFR 50.91(a), the accident. The proposed amendment makes are consistent with the safety analysis licensee has provided its analysis of the assumptions and current plant operating no changes to conditions external to the practice. issue of no significant hazards plants that could create the possibility of a Therefore, the proposed changes do not consideration, which is presented new or different kind of accident. The create the possibility of a new or different below: proposed change does not create the possibility of a new or different kind of kind of accident from any accident 1. Does the proposed change involve a previously evaluated. accident due to new accident precursors, significant increase in the probability or failure mechanisms, malfunctions, or 3. Does the proposed change involve a consequences of an accident previously significant reduction in the margin of safety? accident initiators not considered in the evaluated? design and licensing bases. The existing unit- Response: No. Response: No. specific SAR accident analyses will continue The design, operation, testing methods, The proposed amendment is to revise the to meet requirements for the scope and type and acceptance criteria for systems, ANO–1 and ANO–2 unit-specific SARs of accidents that require analysis. structures, and components (SSCs), specified [Safety Analysis Reports] by reflecting the Therefore, this change does not create the in applicable codes and standards (or results of the TMRE analysis, which possibility of a new or different kind of alternatives approved for use by the NRC) demonstrated that tornado-generated missile accident from an accident previously will continue to be met as described in the protection is not required for identified evaluated. plant licensing basis (including the Final nonconforming structures, systems, and 3. Does the proposed change involve a Safety Analysis Report and Bases to TS), components (SSCs) on each unit. TMRE is an significant reduction in a margin of safety? since these are not affected by changes to the alternative methodology which can only be Response: No. surveillance frequencies. Similarly, there is applied to discovered conditions where The proposed amendment is to revise the no impact to safety analysis acceptance tornado missile protection was not provided, ANO–1 and ANO–2 unit-specific SARs by criteria as described in the plant licensing and cannot be used to avoid providing reflecting the results of the TMRE analysis, basis. To evaluate a change in the relocated tornado missile protection in the plant which demonstrated that tornado-generated surveillance frequency, Entergy will perform modification process. missile protection is not required for a probabilistic risk evaluation using the The proposed amendment does not involve identified nonconforming SSCs on each unit. guidance contained in NRC approved an increase in the probability of an accident TMRE is an alternative methodology which [Nuclear Energy Institute] NEI 04–10, previously evaluated. The relevant accident can only be applied to discovered conditions Revision 1 in accordance with the TS SFCP. previously evaluated is a Design Basis where tornado missile protection was not NEI 04–10, Revision 1, methodology provides tornado impacting the ANO site. The provided, and cannot be used to avoid reasonable acceptance guidelines and probability of a Design Basis tornado is providing tornado missile protection in the methods for evaluating the risk increase of driven by external factors and is not affected plant modification process. proposed changes to surveillance frequencies by the proposed amendment. There are no The change does not exceed or alter any consistent with Regulatory Guide 1.177. changes required to any of the previously controlling numerical value for a parameter Therefore, the proposed changes do not evaluated accidents in the SAR. established in the ANO–1 or ANO–2 SAR or involve a significant reduction in a margin of The proposed amendment does not involve elsewhere in the ANO unit-specific licensing safety. a significant increase in the consequences of basis related to design basis or safety limits. a Design Basis tornado. TMRE is a risk- The NRC staff has reviewed the The change does not impact any unit specific informed methodology for determining accident analyses, and those analyses remain licensee’s analysis and, based on this whether certain safety-related features that valid. The change does not reduce diversity review, it appears that the three are currently not protected from tornado- or redundancy as required by regulation or standards of 10 CFR 50.92(c) are generated missiles require such protection. credited in the unit-specific SAR. The change satisfied. Therefore, the NRC staff The criteria for significant increase in does not reduce defense-in-depth as proposes to determine that the consequences was established in the NRC described in the unit-specific SAR. amendment request involves no Policy Statement on probabilistic risk Therefore, this change does not involve a assessment, which were incorporated into significant reduction in a margin of safety. significant hazards consideration. Regulatory Guide (RG) 1.174, ‘‘An Approach Attorney for licensee: Anna V. Jones, for Using Probabilistic Risk Assessment in The NRC staff has reviewed the Senior Counsel, Entergy Services, Inc., Risk-Informed Decisions on Plant-specific licensee’s analysis and, based on this

VerDate Sep<11>2014 17:00 Jul 01, 2019 Jkt 247001 PO 00000 Frm 00073 Fmt 4703 Sfmt 4703 E:\FR\FM\02JYN1.SGM 02JYN1 khammond on DSKBBV9HB2PROD with NOTICES 31634 Federal Register / Vol. 84, No. 127 / Tuesday, July 2, 2019 / Notices

review, it appears that the three Channel Functional Test to allow the Units 1 and 2, Technical Specification standards of 10 CFR 50.92(c) are frequency for testing the components or Limiting Condition for Operation 3.4.15, satisfied. Therefore, the NRC staff devices in each step to be determined in ‘‘RCS [Reactor Coolant System] Specific accordance with the TS SFCP. The design Activity,’’ and associated surveillance proposes to determine that the function or operation of the components amendment request involves no involved are not affected and there is no requirements. The proposed changes significant hazards consideration. physical alteration of the plant (i.e., no new would replace the current technical Attorney for licensee: Anna Vinson or different type of equipment will be specification limit on reactor coolant Jones, Senior Counsel, Entergy Services, installed). No credible new failure system gross specific activity with a Inc., 101 Constitution Avenue NW, mechanisms, malfunctions, or accident new limit on reactor coolant system Suite 200 East, Washington, DC 20001. initiators not considered in the design and noble gas specific activity. The noble NRC Branch Chief: Robert J. licensing bases are introduced. The changes gas specific activity limit would be Pascarelli. do not alter assumptions made in the safety analysis. The proposed changes are based on a new definition of ‘‘DOSE consistent with the safety analysis EQUIVALENT XE–133’’ that would Entergy Operations, Inc., Docket No. 50– ¯ 368, Arkansas Nuclear One (ANO), Unit assumptions. replace the current definition of ‘‘E- 2, Pope County, Arkansas Therefore, the proposed change does not AVERAGE DISINTEGRATION create the possibility of a new or different ENERGY.’’ Also, the current definition Date of amendment request: April 30, kind of accident from any previously of ‘‘DOSE EQUIVALENT I–131’’ would 2019. A publicly-available version is in evaluated. be revised. The proposed changes are ADAMS under Accession No. 3. Does the proposed amendment involve consistent with NRC-approved ML19120A086. a significant reduction in a margin of safety? Response: No. Technical Specifications Task Force Description of amendment request: (TSTF) Traveler, TSTF–490, Revision 0, The amendment would modify the The proposed change revises the TS definitions of Channel Calibration and ‘‘Deletion of E Bar Definition and ANO, Unit 2, Technical Specifications Channel Functional Test to allow the Revision to RCS Specific Activity Tech (TSs) by adopting Technical frequency for testing the components or Spec.’’ Specifications Task Force (TSTF)–563, devices in each step to be determined in Basis for proposed no significant ‘‘Revise Instrument Testing Definitions accordance with the TS SFCP. The SFCP hazards consideration determination: to Incorporate the Surveillance assures sufficient safety margins are As required by 10 CFR 50.91(a), the Frequency Control Program,’’ which maintained, and that the design, operation, surveillance methods, and acceptance criteria licensee has provided its analysis of the would revise the definitions of Channel issue of no significant hazards Calibration and Channel Functional specified in applicable codes and standards (or alternatives approved for use by the NRC) consideration, which is presented Tests in the ANO, Unit 2 TSs. will continue to be met as described in the below: Basis for proposed no significant plants’ licensing basis. The proposed change hazards consideration determination: 1. Does the proposed amendment involve does not adversely affect existing plant safety a significant increase in the probability or As required by 10 CFR 50.91(a), the margins, or the reliability of the equipment consequences of an accident previously licensee has provided its analysis of the assumed to operate in the safety analysis. As evaluated? issue of no significant hazards such, there are no changes being made to Response: No. consideration, which is presented safety analysis assumptions, safety limits, or Reactor coolant specific activity is not an below: limiting safety system settings that would initiator for any accident previously adversely affect plant safety as a result of the evaluated. The Completion Time when 1. Does the proposed amendment involve proposed change. Margins of safety are primary coolant gross activity is not within a significant increase in the probability or unaffected by method of determining limit is not an initiator for any accident consequences of an accident previously surveillance test intervals under an NRC- previously evaluated. The current variable evaluated? approved licensee-controlled program. limit on primary coolant iodine Response: No. Therefore, the proposed change does not concentration is not an initiator to any The proposed change revises the TS involve a significant reduction in a margin of accident previously evaluated. As a result, definitions of Channel Calibration and safety. the proposed change does not significantly Channel Functional Test to allow the increase the probability of an accident. The frequency for testing the components or The NRC staff has reviewed the licensee’s analysis and, based on this proposed change will limit primary coolant devices in each step to be determined in noble gases to concentrations consistent with accordance with the TS SFCP [surveillance review, it appears that the three the accident analyses. The proposed change frequency control program]. All components standards of 10 CFR 50.92(c) are to the Completion Time has no impact on the in the channel continue to be tested. The satisfied. Therefore, the NRC staff consequences of any design basis accident frequency at which a channel test is proposes to determine that the since the consequences of an accident during performed is not an initiator of any accident amendment request involves no the extended Completion Time are the same previously evaluated; therefore, the significant hazards consideration. as the consequences of an accident during probability of an accident is not affected by the Completion Time. As a result, the the proposed change. The channels Attorney for licensee: Anna Vinson Jones, Senior Counsel, Entergy Services, consequences of any accident previously surveilled in accordance with the affected evaluated are not significantly increased. definitions continue to be required to be Inc., 101 Constitution Avenue NW, Therefore, the proposed changes do not operable and the acceptance criteria of the Suite 200 East, Washington, DC 20001. involve a significant increase in the surveillances are unchanged. As a result, any NRC Branch Chief: Robert J. probability or consequences of an accident mitigating functions assumed in the accident Pascarelli. previously evaluated. analysis will continue to be performed. Exelon Generation Company, LLC, 2. Does the proposed amendment create Therefore, the proposed change does not Docket Nos. 50–317 and 50–318, Calvert the possibility of a new or different kind of involve a significant increase in the Cliffs Nuclear Power Plant (CCNPP), accident from any accident previously probability or consequences of an accident Units 1 and 2, Calvert County, Maryland evaluated? previously evaluated. Date of amendment request: May 6, Response: No. 2. Does the proposed amendment create The proposed change in specific activity the possibility of a new or different kind of 2019. A publicly-available version is in limits does not alter any physical part of the accident from any previously evaluated? ADAMS under Accession No. plant nor does it affect any plant operating Response: No. ML19127A076. parameter. The change does not create the The proposed change revises the TS Description of amendment request: potential for a new or different kind of definitions of Channel Calibration and The amendments would revise CCNPP, accident from any previously calculated.

VerDate Sep<11>2014 17:00 Jul 01, 2019 Jkt 247001 PO 00000 Frm 00074 Fmt 4703 Sfmt 4703 E:\FR\FM\02JYN1.SGM 02JYN1 khammond on DSKBBV9HB2PROD with NOTICES Federal Register / Vol. 84, No. 127 / Tuesday, July 2, 2019 / Notices 31635

Therefore, the proposed changes do not need to bypass the protection, do not satisfy satisfied. Therefore, the NRC staff create the possibility of a new or different the four 10 CFR 50.36c(2)(ii) criterion for TS proposes to determine that the kind of accident from any accident inclusion and are thereby appropriate for amendment request involves no previously evaluated. relocation, consistent with the NRC Final significant hazards consideration. 3. Does the proposed amendment involve Policy Statement on TS Improvements. a significant reduction in a margin of safety? Implementing NRC policies developed to Attorney for licensee: Debbie Hendell, Response: No. assure compliance with applicable Managing Attorney—Nuclear, Florida The proposed change revises the limits on regulations cannot adversely affect the Power & Light Company, 700 Universe noble gas radioactivity in the primary likelihood or outcome of any design basis Blvd. MS LAW/JB, Juno Beach, Florida coolant. The proposed change is consistent accident. 33408–0420. with the assumptions in the safety analyses Therefore, the proposed license NRC Branch Chief: Undine Shoop. and will ensure the monitored values protect amendments would not involve a significant the initial assumptions in the safety analyses. increase in the probability or consequences NextEra Energy Duane Arnold, LLC, Based upon the reasoning presented above of an accident previously evaluated. Docket No. 50–331, Duane Arnold and the previous discussion of the 2. Does the proposed amendment create Energy Center (DAEC), Linn County, amendment request, the requested change the possibility of a new or different kind of Iowa does not involve a significant hazards accident from any accident previously consideration. evaluated? Date of amendment request: April 19, Therefore, the proposed changes do not Response: No. 2019. A publicly-available version is in involve a significant reduction in a margin of The proposed change to relocate the MOV ADAMS under Accession No. safety. Thermal Overload Protection Bypass Devices ML19109A031. The NRC staff has reviewed the requirements to licensee control does not Description of amendment request: licensee’s analysis and, based on this install new plant equipment or modify The licensee proposes to change the review, it appears that the three existing plant equipment or modify the technical specifications (TSs) for DAEC manner in which existing plant equipment is standards of 10 CFR 50.92(c) are to permit changes in plant operations operated and controlled. Hence no new when the plant is permanently defueled satisfied. Therefore, the NRC staff failures modes can result from the proposed proposes to determine that the change. MOV Thermal Overload Protection in the fourth quarter of 2020. amendment request involves no and the need to bypass the protection during Specifically, the licensee proposes to significant hazards consideration. accident conditions are not credited in safety revise the TSs to support the Attorney for licensee: Tamra Domeyer, analyses and therefore cannot alter or create implementation of the certified fuel Associate General Counsel, Exelon new inputs, assumptions or limits associated handler and non-certified operator Generation Company, LLC, 4300 with accident analyses. MOV thermal positions. In addition, certain Winfield Road, Warrenville, IL 60555. overload protection, and the need to bypass organization, staffing, and training NRC Branch Chief: James G. Danna. the protection, do not satisfy the four 10 CFR requirements in the TSs will be revised. 50.36c(2)(ii) criterion for TS inclusion and The proposed amendment would also Florida Power & Light Company, et al., are thereby appropriate for relocation consistent with the NRC Final Policy make other administrative changes. Docket No. 50–389, St. Lucie Plant, Unit Basis for proposed no significant No. 2, St. Lucie County, Florida Statement on TS Improvements. Implementing NRC policies developed to hazards consideration determination: Date of amendment request: May 20, assure compliance with applicable As required by 10 CFR 50.91(a), the 2019. A publicly-available version is in regulations cannot create new. or different licensee has provided its analysis of the ADAMS under Accession No. kinds of accidents. issue of no significant hazards ML19140A100. Therefore, the proposed license consideration, which is presented Description of amendment request: amendments would not create the possibility below: The amendment would revise the of a new or different kind of accident from any previously evaluated. 1. Does the proposed change involve a Technical Specifications (TSs) by significant increase in the probability or relocating the requirements for the 3. Does the proposed amendment involve a significant reduction in a margin of safety? consequences of an accident previously Motor Operated Valve (MOV) Thermal Response: No. evaluated? Overload Protection Bypass Devices to The proposed change relocates the MOV Response: No. licensee-controlled documents. Thermal Overload Protection Bypass Devices The proposed changes do not involve any Basis for proposed no significant requirements to licensee control whereby physical changes to plant Structures, hazards consideration determination: future changes will be subject to the Systems, and Components (SSCs) or the As required by 10 CFR 50.91(a), the regulatory controls of 10 CFR 50.59. The manner in which SSCs are operated, licensee has provided its analysis of the proposed change does not involve changes to maintained, modified, tested, or inspected. issue of no significant hazards any safety analyses, safety limits or limiting The proposed changes do not involve a safety system settings. The proposed change change to any safety limits, limiting safety consideration, which is presented system settings, limiting control settings, below: does not adversely impact plant operating margins or the reliability of equipment limiting conditions for operation, 1. Does the proposed amendment involve credited in safety analyses. The proposed surveillance requirements, or design features. a significant increase in the probability or change implements the NRC Final Policy The deletion and modification of consequences of an accident previously Statement on TS Improvements for the MOV provisions of the administrative controls do evaluated? thermal overload protection bypass devices. not directly affect the design of SSCs Response: No. Implementing NRC policies developed to necessary for safe storage of spent irradiated The proposed change relocates the MOV assure compliance with applicable fuel or the methods used for handling and Thermal Overload Protection Bypass Devices regulations cannot result in a reduction in storage of such fuel in the Spent Fuel Pool requirements to licensee control whereby the margin of safety. (SFP). The proposed changes are future changes are subject to the regulatory Therefore, the proposed license administrative in nature and do not affect controls of 10 CFR 50.59. Relocating the amendment would not involve a significant any accidents applicable to the safe MOV Thermal Overload Protection Bypass reduction in the margin of safety. management of spent irradiated fuel or the Devices requirements neither affects the permanently shutdown and defueled physical design of any plant structure, The NRC staff has reviewed the condition of the reactor. system, or component (SSC), nor the manner licensee’s analysis and, based on this DAEC’s accident analyses are contained in in which SSCs are operated and controlled. review, it appears that the three Chapter 15 of the Updated Final Safety MOV thermal overload protection, and the standards of 10 CFR 50.92(c) are Analysis Report (UFSAR). In a permanently

VerDate Sep<11>2014 17:00 Jul 01, 2019 Jkt 247001 PO 00000 Frm 00075 Fmt 4703 Sfmt 4703 E:\FR\FM\02JYN1.SGM 02JYN1 khammond on DSKBBV9HB2PROD with NOTICES 31636 Federal Register / Vol. 84, No. 127 / Tuesday, July 2, 2019 / Notices

defueled condition, the only credible UFSAR will no longer authorize operation of the emergency preparedness exercise described accident that remains is the Fuel reactor or emplacement or retention of fuel schedule requirements prescribed in 10 Handling Accident (FHA). Other Chapter 15 into the reactor vessel following submittal of CFR part 50, Appendix E, Sections accidents will no longer be applicable to a the certifications required by 10 CFR IV.F.2.a.ii, IV.F.2.a.iii, IV.F.2.b and permanently defueled reactor plant. 50.82(a)(1). As a result, the occurrence of The probability of occurrence of previously certain design basis postulated accidents are IV.F.2.c for multi-unit sites. evaluated accidents is not increased, since no longer considered credible when the Basis for proposed no significant extended operation in a permanently reactor is permanently defueled. hazards consideration determination: defueled condition will be the only operation The only remaining credible UFSAR As required by 10 CFR 50.91(a), the allowed, and therefore, bounded by the described accident is a FHA. The proposed licensee has provided its analysis of the existing analyses. Additionally, the changes do not adversely affect the inputs or issue of no significant hazards occurrence of postulated accidents associated assumptions of any of the design basis consideration, which is presented with reactor operation is no longer credible analyses that impact the FHA. below: in a permanently defueled reactor. This The proposed changes are limited to those significantly reduces the scope of applicable portions of the TS definitions and 1. Does the proposed amendment involve accidents. administrative controls that are related to the a significant increase in the probability or Therefore, the proposed changes do not safe storage and maintenance of spent consequences of an accident previously involve an increase in the probability or irradiated fuel. The requirements that are evaluated? consequences of a previously evaluated proposed to be revised and/or deleted from Response: No. accident. the DAEC TS are not credited in the existing The VEGP Unit 3 and 4 emergency 2. Does the proposed change create the accident analysis for the remaining planning Inspections, Tests, Analyses, and possibility of a new or different kind of postulated accident (i.e., FHA); therefore, Acceptance Criteria (ITAAC) provide accident from any accident previously they do not contribute to the margin of safety assurance that the facility has been evaluated? associated with the accident analysis. Certain constructed and will be operated in Response: No. postulated DBAs [design-basis accidents] conformity with the license, the provisions of The proposed changes have no impact on involving the reactor are no longer possible the Act, and the Commission’s rules and facility SSCs affecting the safe storage of the because the reactor will be permanently shut regulations. The proposed changes do not spent irradiated fuel, or on the methods of down and defueled and DAEC will no longer affect the design of a system, structure, or operation of such SSCs, or on the handling be authorized to operate the reactor. component (SSC) used to meet the design and storage of spent irradiated fuel itself. The Therefore, the proposed changes have no bases of the nuclear plant. The changes do proposed changes do not result in different impact to the margin of safety. not affect the construction or operation of the or more adverse failure modes or accidents nuclear plant itself, so there is no change to than previously evaluated because the reactor The NRC staff has reviewed the the probability or consequences of an will be permanently shut down and defueled licensee’s analysis and, based on this accident previously evaluated. The deletion and DAEC will no longer be authorized to review, it appears that the three of redundant VEGP Unit 3 and 4 emergency operate the reactor. standards of 10 CFR 50.92(c) are planning ITAAC does not affect prevention The proposed changes do not affect satisfied. Therefore, the NRC staff and/or mitigation of abnormal events (e.g., systems credited in the accident analysis for proposes to determine that the accidents, anticipated operational the FHA at DAEC. The proposed changes will amendment request involves no occurrences, earthquakes, floods, or turbine continue to require proper control and missiles) or the applicable safety and design monitoring of safety significant parameters significant hazards consideration. analyses. No safety-related SSC or function is and activities. Attorney for licensee: Steven Hamrick, adversely affected. The changes do not The proposed changes do not result in any Managing Attorney—Nuclear, Florida involve or interface with any SSC accident new mechanisms that could initiate damage Power Light Company, P.O. Box 14000, initiator or initiating sequence of events, so to the remaining relevant safety barriers in Juno Beach, FL 33408–0420. the probabilities of the accidents evaluated in support of maintaining the plant in a NRC Acting Branch Chief: Lisa M. the Updated Final Safety Analysis Report permanently shutdown and defueled Regner. (UFSAR) are not affected. condition (e.g., fuel cladding and SFP The proposed activity will not allow for a cooling). Since extended operation in a Southern Nuclear Operating Company, new fission product release path, nor will it defueled condition will be the only operation Docket Nos. 52–025 and 52–026, Vogtle result in a new fission product barrier failure allowed, and therefore bounded by the Electric Generating Plant (VEGP), Units mode or create a new sequence of events that existing analyses, such a condition does not 3 and 4, Burke County, Georgia would result in fuel cladding failures. The create the possibility of a new of different changes do not involve any safety-related kind of accident. Date of amendment request: May 10, SSC or function used to mitigate an accident. The proposed changes do not alter the 2019. A publicly-available version is in Therefore, the consequences of accidents protection system design, create new failure ADAMS under Accession No. previously evaluated in the UFSAR are not modes, or change any modes of operation. ML19134A059. affected. The proposed changes do not involve a Description of amendment request: Therefore, the proposed amendment does physical alteration of the plant, and no new The amendment request proposes not involve a significant increase in the or different kind of equipment will be changes to the Combined License (COL) probability or consequences of an accident installed. Consequently, there are no new previously evaluated. initiators that could result in a new or Numbers NPF–91 and NPF–92 for VEGP 2. Does the proposed amendment create different kind of accident. Therefore, the Units 3 and 4. The requested the possibility of a new or different kind of proposed changes do not create the amendment proposes to delete accident from any accident previously possibility of a new or different kind of redundant plant-specific emergency evaluated? accident from any accident previously planning Inspections, Tests, Analyses, Response: No. evaluated. and Acceptance Criteria (ITAAC) from The VEGP Unit 3 and 4 emergency 3. Does the proposed change involve a VEGP Units 3 and 4 COL Appendix C planning ITAAC provide assurance that the significant reduction in a margin of safety? that are bounded by other ITAAC or facility has been constructed and will be Response: No. redundant to document submittal operated in conformity with the license, the The proposed changes involve adding TS provisions of the Act, and the Commission’s definitions and deleting and/or modifying regulatory requirements. The proposed rules and regulations. The deletion of certain TS administrative controls once the changes do not involve changes to the redundant VEGP Unit 3 and 4 emergency DAEC facility has been permanently shut approved emergency plan, the plant- planning ITAAC does not affect the design of down and defueled. As specified in 10 CFR specific Tier 2 Design Control a system, structure, or component (SSC) used 50.82(a)(2), the 10 CFR 50 license for DAEC Document, or the VEGP Unit 3 and 4 to meet the design bases of the nuclear plant.

VerDate Sep<11>2014 17:00 Jul 01, 2019 Jkt 247001 PO 00000 Frm 00076 Fmt 4703 Sfmt 4703 E:\FR\FM\02JYN1.SGM 02JYN1 khammond on DSKBBV9HB2PROD with NOTICES Federal Register / Vol. 84, No. 127 / Tuesday, July 2, 2019 / Notices 31637

The changes do not affect the construction or Basis for proposed no significant Therefore, the proposed change does not operation of any systems or equipment such hazards consideration determination: involve a significant reduction in a margin of that a new or different kind of accident, As required by 10 CFR 50.91(a), the safety. failure mode, or malfunction is created, or licensee has provided its analysis of the alter any SSC such that a new accident The NRC staff has reviewed the initiator or initiating sequence of events is issue of no significant hazards licensee’s analysis and, based on this created. consideration, which is presented review, it appears that the three Therefore, the proposed amendment does below: standards of 10 CFR 50.92(c) are not create the possibility of a new or different 1. Does the proposed amendment involve satisfied. Therefore, the NRC staff kind of accident from any accident a significant increase in the probability or proposes to determine that the previously evaluated. consequences of an accident previously amendment request involves no 3. Does the proposed amendment involve evaluated? significant hazards consideration. a significant reduction in a margin of safety? Response: No. Attorney for licensee: Millicent Response: No. The proposed amendment revises the TS The VEGP Unit 3 and 4 emergency Ronnlund, Vice President and General [safety limit MCPR] SLMCPR and the list of Counsel, Southern Nuclear Operating planning ITAAC provide assurance that the core operating limits to be included in the Co., Inc., P.O. Box 1295, Birmingham, facility has been constructed and will be Core Operating Limits Report (COLR). The operated in conformity with the license, the SLMCPR is not an initiator of any accident AL 35201–1295. provisions of the Act, and the Commission’s previously evaluated. The revised safety limit NRC Branch Chief: Michael T. rules and regulations. The deletion of values continue to ensure for all accidents Markley. redundant VEGP Unit 3 and 4 emergency previously evaluated that the fuel cladding IV. Notice of Issuance of Amendments planning ITAAC does not adversely affect will be protected from failure due to safety-related equipment or fission product transition boiling. The proposed change does to Facility Operating Licenses and barriers. No safety analysis or design basis not affect plant operation or any procedural Combined Licenses acceptance limit or criterion is challenged or or administrative controls on plant operation During the period since publication of exceeded by the proposed change. that affect the functions of preventing or Therefore, the proposed amendment does the last biweekly notice, the mitigating any accidents previously Commission has issued the following not involve a significant reduction in a evaluated. margin of safety. Therefore, the proposed change does not amendments. The Commission has The NRC staff has reviewed the involve a significant increase in the determined for each of these licensee’s analysis and, based on this probability or consequences of an accident amendments that the application review, it appears that the three previously evaluated. complies with the standards and standards of 10 CFR 50.92(c) are 2. Does the proposed amendment create requirements of the Atomic Energy Act satisfied. Therefore, the NRC staff the possibility of a new or different kind of of 1954, as amended (the Act), and the accident from any accident previously proposes to determine that the Commission’s rules and regulations. evaluated? The Commission has made appropriate amendment request involves no Response: No. significant hazards consideration. findings as required by the Act and the The proposed amendment revises the TS Commission’s rules and regulations in Attorney for licensee: M. Stanford SLMCPR and the list of core operating limits Blanton, Balch & Bingham LLP, 1710 to be included in the COLR. The proposed 10 CFR chapter I, which are set forth in Sixth Avenue North, Birmingham, AL change will not affect the design function or the license amendment. 35203–2015. operation of any structures, systems or A notice of consideration of issuance NRC Branch Chief: Jennifer L. Dixon- components (SSCs). No new equipment will of amendment to facility operating Herrity. be installed. As a result, the proposed change license or combined license, as will not create any credible new failure applicable, proposed no significant Southern Nuclear Operating Company, mechanisms, malfunctions, or accident hazards consideration determination, Inc., Georgia Power Company, initiators not considered in the design and and opportunity for a hearing in Oglethorpe Power Corporation, licensing bases. connection with these actions, was Municipal Electric Authority of Therefore, the proposed change does not published in the Federal Register as Georgia, City of Dalton, Georgia, Docket create the possibility of a new or different kind of accident from any previously indicated. Nos. 50–321 and 50–366, Edwin I. Unless otherwise indicated, the Hatch Nuclear Plant, Unit Nos. 1 and 2, evaluated. 3. Does the proposed amendment involve Commission has determined that these Appling County, Georgia a significant reduction in a margin of safety? amendments satisfy the criteria for Date of amendment request: April 23, Response: No. categorical exclusion in accordance 2019. A publicly-available version is in The proposed amendment revises the TS with 10 CFR 51.22. Therefore, pursuant ADAMS under Accession No. SLMCPR and the list of core operating limits to 10 CFR 51.22(b), no environmental ML19113A282. to be included in the COLR. This will result impact statement or environmental Description of amendment request: in a change to a safety limit, but will not assessment need be prepared for these result in a significant reduction in the margin The amendments would revise the of safety provided by the safety limit. As amendments. If the Commission has technical specification (TS) safety limit discussed in the application, changing the prepared an environmental assessment (SL) on minimum critical power ratio SLMCPR methodology to one based on a 95% under the special circumstances (MCPR) to reduce the need for cycle- probability with 95% confidence that no fuel provision in 10 CFR 51.22(b) and has specific changes to the value, while still rods experience transition boiling during an made a determination based on that meeting the regulatory requirement for anticipated transient instead of the current assessment, it is so indicated. an SL, by adoption of Technical limit based on ensuring that 99.9% of the For further details with respect to the Specifications Task Force (TSTF) fuel rods are not susceptible to boiling action see (1) the applications for Traveler TSTF–564, Revision 2, ‘‘Safety transition does not have a significant effect amendment, (2) the amendment, and (3) on plant response to any analyzed accident. Limit MCPR,’’ which is an approved The SLMCPR and the TS Limiting Condition the Commission’s related letter, Safety change to the Improved Standard for Operation (LCO) on MCPR continue to Evaluation and/or Environmental Technical Specifications, into the provide the same level of assurance as the Assessment as indicated. All of these Edwin I. Hatch Nuclear Plant, Unit Nos. current limits and do not reduce a margin of items can be accessed as described in 1 and 2, TSs. safety. the ‘‘Obtaining Information and

VerDate Sep<11>2014 17:00 Jul 01, 2019 Jkt 247001 PO 00000 Frm 00077 Fmt 4703 Sfmt 4703 E:\FR\FM\02JYN1.SGM 02JYN1 khammond on DSKBBV9HB2PROD with NOTICES 31638 Federal Register / Vol. 84, No. 127 / Tuesday, July 2, 2019 / Notices

Submitting Comments’’ section of this Specifications Task Force (TSTF) Renewed Facility Operating License document. Traveler TSTF–425, Revision 3, No. DPR–16: The amendment revised ‘‘Relocate Surveillance Frequencies to the Renewed Facility Operating License. Duke Energy Carolinas, LLC, Docket Licensee Control—RITSTF [Risk- Date of initial notice in Federal Nos. 50–269, 50–270, and 50–287, Informed TSTF] Initiative 5b.’’ Register: December 18, 2018 (83 FR Oconee Nuclear Station, Units 1, 2, and Additionally, the amendment added a 64894). The supplemental letter dated 3, Oconee County, South Carolina new program, the Surveillance February 13, 2019, provided additional Date of amendment request: May 17, Frequency Control Program to TS information that clarified the 2018, as supplemented by letter dated Chapter 5.0, ‘‘Administrative Controls.’’ application, did not expand the scope of February 26, 2019. Date of issuance: June 11, 2019. the application as originally noticed, Brief description of amendments: The Effective date: As of the date of and did not change the staff’s original amendments revise Technical issuance and shall be implemented proposed no significant hazards Specification (TS) 3.8.1, ‘‘AC within 90 days from the date of consideration determination as [Alternating Current] Sources— issuance. published in the Federal Register. Operating,’’ by adding a surveillance Amendment No: 219. A publicly- The Commission’s related evaluation requirement that verifies the ability of available version is in ADAMS under of the amendment is contained in a the Keowee Hydroelectric Unit auxiliary Accession No. ML19094A799; Safety Evaluation dated June 11, 2019. power system to automatically transfer No significant hazards consideration documents related to this amendment from its normal auxiliary power source comments received: No. are listed in the Safety Evaluation to its alternate auxiliary power source. Date of issuance: June 14, 2019. enclosed with the amendment. Exelon Generation Company, LLC, Effective date: As of its date of Renewed Facility Operating License Docket No. 50–461, Clinton Power issuance and shall be implemented No. NPF–29: The amendment revised Station (CPS), Unit No. 1, DeWitt within 60 days of issuance. the Renewed Facility Operating License County, Illinois Amendment Nos.: 411, 413, and 412. and Technical Specifications. Date of amendment request: A publicly-available version is in Date of initial notice in Federal September 17, 2018. A publicly- ADAMS under Accession No. Register: July 31, 2018 (83 FR 36975). available version is in ADAMS under ML19140A026; documents related to The supplemental letters dated Accession No. ML18260A307. these amendments are listed in the November 30, 2018, and March 6, 2019, Brief description of amendment: The Safety Evaluation enclosed with the provided additional information that amendment recaptured low-power amendments. clarified the application, did not expand testing time to extend the full-power Facility Operating License Nos. DPR– the scope of the application as originally operating license (FPOL) to expire on 38, DPR–47 and DPR–55: Amendments noticed, and did not change the NRC April 17, 2027, instead of the current revised the Facility Operating Licenses staff’s original proposed no significant expiration date of September 29, 2026. and TSs. hazards consideration determination as Date of issuance: June 12, 2019. Date of initial notice in Federal published in the Federal Register. Effective date: As of the date of Register: August 28, 2018 (83 FR The Commission’s related evaluation issuance and shall be implemented 43904). The supplemental letter dated of the amendment is contained in a within 30 days from the date of February 26, 2019, provided additional Safety Evaluation dated June 11, 2019. issuance. information that clarified the No significant hazards consideration Amendment No: 224. A publicly- application, did not expand the scope of comments received: No. available version is in ADAMS under the application as originally noticed, Accession No. ML19109A001; and did not change the staff’s original Exelon Generation Company, LLC, documents related to this amendment proposed no significant hazards Docket No. 50–219, Oyster Creek are listed in the Safety Evaluation consideration determination as Nuclear Generating Station (Oyster enclosed with the amendment. published in the Federal Register. Creek), Ocean County, New Jersey Facility Operating License No. NPF– The Commission’s related evaluation Date of amendment request: October 62: The amendment revised the Facility of the amendment is contained in a 22, 2018, as supplemented by letters Operating License. Safety Evaluation dated June 14, 2019. dated November 6, 2018, and February Date of initial notice in Federal No significant hazards consideration 13, 2019. Register: January 31, 2019 (84 FR 813). comments received: No. The Commission’s related evaluation Brief description of amendment: The of the amendment is contained in a Entergy Operations, Inc., System Energy amendment revised the effective and Safety Evaluation dated June 12, 2019. Resources, Inc., Cooperative Energy, A implementation dates of Amendment No significant hazards consideration Mississippi Electric Cooperative, and No. 294 for the Oyster Creek comments received: No. Entergy Mississippi, LLC, Docket No. Permanently Defueled Emergency Plan 50–416, Grand Gulf Nuclear Station (PDEP) and Emergency Action Level Northern States Power Company— (Grand Gulf), Unit 1, Claiborne County, (EAL) scheme for the permanently Minnesota, Docket Nos. 50–282 and 50– Mississippi defueled condition. 306, Prairie Island Nuclear Generating Date of amendment request: April 12, Date of issuance: June 11, 2019. Plant, Units 1 and 2, Goodhue County, 2018, as supplemented by letters dated Effective date: As of June 29, 2019, Minnesota June 7, 2018, November 30, 2018, and and shall be implemented within 30 Date of amendment request: June 26, March 6, 2019. days of the effective date. 2018. Brief description of amendment: The Amendment No.: 296. A publicly Brief description of amendment: The amendment revised the Grand Gulf available version is in ADAMS under amendments revised TS 1.3, Technical Specifications (TSs) by Accession No. ML19098A258; ‘‘Completion Times’’ Example 1.3–3, TS relocating specific surveillance documents related to this amendment 3.6.5, ‘‘Containment Spray and Cooling frequencies to a licensee-controlled are listed in the Safety Evaluation Systems,’’ TS 3.7.5, ‘‘Auxiliary program with the adoption of Technical enclosed with the amendment. Feedwater (AFW) System,’’ TS 3.7.8,

VerDate Sep<11>2014 18:03 Jul 01, 2019 Jkt 247001 PO 00000 Frm 00078 Fmt 4703 Sfmt 4703 E:\FR\FM\02JYN1.SGM 02JYN1 khammond on DSKBBV9HB2PROD with NOTICES Federal Register / Vol. 84, No. 127 / Tuesday, July 2, 2019 / Notices 31639

‘‘Cooling Water (CL) System,’’ TS 3.8.1, Safety Evaluation enclosed with the dated November 9, 2018, and March 21, ‘‘AC Sources—Operating,’’ and TS 3.8.9, amendments. 2019. ‘‘Distribution Systems—Operating’’ by Renewed Facility Operating License Brief description of amendment: The eliminating the second completion time Nos. NPF–76 and NPF–80: The amendments revised Technical in accordance with Technical amendments revised the Renewed Specification 3.8.9 to add a new Specifications Task Force (TSTF)–439, Facility Operating Licenses and Condition C with an 8-hour completion Revision 2, ‘‘Eliminate Second Technical Specifications. time for performing maintenance on the Completion Times Limiting Time from Date of initial notice in Federal opposite unit’s vital bus when the Discovery of Failure to Meet an LCO Register: January 2, 2019 (84 FR 25) opposite unit is in Mode 5, Mode 6, or [limiting condition for operation].’’ The Commission’s related evaluation defueled. Date of issuance: June 6, 2019. of the amendments is contained in a Date of issuance: June 7, 2019. Effective date: As of the date of Safety Evaluation dated June 6, 2019. Effective date: As of the date of issuance and shall be implemented No significant hazards consideration issuance and shall be implemented within 90 days of issuance. comments received: No. within 60 days of issuance. Amendment Nos.: 126 and 29. A Amendment Nos.: 227–Unit 1; 215– Tennessee Valley Authority, Docket No. publicly-available version is in ADAMS Unit 2. A publicly-available version is 50–391, Watts Bar Nuclear Plant, Unit 2, under Accession No. ML19098A774; in ADAMS under Accession No. Rhea County, Tennessee ML19128A133; documents related to documents related to these amendments these amendments are listed in the Date of amendment request: May 14, are listed in the Safety Evaluation Safety Evaluation enclosed with the 2018, as supplemented by letter dated enclosed with the amendments. amendments. November 8, 2018. Facility Operating License Nos. NPF– Brief description of amendment: The Renewed Facility Operating License 90 and NPF–96: Amendments revised amendment revised the Technical Nos. DPR–42 and DPR–60: The the Facility Operating Licenses and Specifications to implement a voltage- amendments revised the Renewed Technical Specifications. based alternate repair criteria (ARC) for Federal Facility Operating Licenses and Date of initial notice in degraded steam generator (SG) tubes in Register Technical Specifications. : November 20, 2018 (83 FR the Unit 2 Westinghouse Model D3 SGs. Date of initial notice in Federal 58619). The supplemental letters dated The ARC follow the guidelines set forth Register: August 14, 2018 (83 FR November 9, 2018, and March 21, 2019, in NRC Generic Letter 95–05, ‘‘Voltage- 40351) provided additional information that Based Criteria for Westinghouse Steam clarified the application, did not expand The Commission’s related evaluation Generator Tubes Affected by Outside the scope of the application as originally of the amendment is contained in a Diameter Stress Corrosion Cracking.’’ noticed, and did not change the NRC Safety Evaluation dated June 6, 2019. Date of issuance: June 3, 2019. staff’s original proposed no significant No significant hazards consideration Effective date: As of the date of hazards consideration determination as comments received: No. issuance and shall be implemented published in the Federal Register. STP Nuclear Operating Company, within 60 days of issuance. The Commission’s related evaluation Docket Nos. 50–498 and 50–499, South Amendment No.: 28. A publicly- of the amendments is contained in a Texas Project, Units 1 and 2, Matagorda available version is in ADAMS under Safety Evaluation dated June 7, 2019. County, Texas Accession No. ML19063B721; No significant hazards consideration documents related to this amendment comments received: No. Date of amendment request: are listed in the Safety Evaluation September 27, 2018. enclosed with the amendment. United States Maritime Administration Brief description of amendment: The Facility Operating License No. NPF– (MARAD), Docket No. 50–238, Nuclear amendments revised Surveillance 96: Amendment revised the Facility Ship SAVANNAH (NSS), Baltimore, Requirement 4.7.7.b of TS Section Operating License and Technical Maryland 3 ⁄4.7.7, ‘‘Control Room Makeup and Specifications. Date of application for amendment: Cleanup Filtration System,’’ to operate Date of initial notice in Federal June 19, 2018. for at least 15 continuous minutes at a Register: November 20, 2018 (83 FR Brief description of amendment: The frequency controlled in accordance with 58618). The supplemental letter dated amendment revised the Technical the Surveillance Frequency Control November 8, 2018, provided additional Specifications to establish and Program by adoption of Technical information that clarified the incorporate reporting requirements for a Specifications Task Force (TSTF) application, did not expand the scope of Process Control Program, an Offsite Traveler TSTF–522, Revision 0, ‘‘Revise the application as originally noticed, Dose Calculation Manual, a Radioactive Ventilation System Surveillance and did not change the NRC staff’s Effluent Controls Program, and a Requirements to Operate for 10 Hours original proposed no significant hazards Radiological Environmental Monitoring per Month.’’ The NRC approved TSTF– consideration determination as Program. 522, Revision 0, as a part of the published in the Federal Register. Date of issuance: June 18, 2019. consolidated line item improvement The Commission’s related evaluation Effective date: As of the date of process on September 20, 2012 (77 FR of the amendment is contained in a issuance and shall be implemented 58421). Safety Evaluation dated June 23, 2019. within 60 days. Date of issuance: June 6, 2019. No significant hazards consideration Amendment No.: 17. A publicly- Effective date: As of the date of comments received: No. available version is in ADAMS under issuance and shall be implemented Accession No. ML19085A482. The within 90 days of issuance. Tennessee Valley Authority, Docket Commission’s related evaluation of the Amendment Nos.: Unit 1—215; Unit Nos. 50–390 and 50–391, Watts Bar amendment is contained in a Safety 2—201. A publicly-available version is Nuclear Plant, Units 1 and 2, Rhea Evaluation dated November 26, 2018. in ADAMS under Accession No. County, Tennessee Facility Operating License No. NS–1: ML19067A222; documents related to Date of amendment request: February This amendment revises the Technical these amendments are listed in the 28, 2018, as supplemented by letters Specifications of the License.

VerDate Sep<11>2014 18:03 Jul 01, 2019 Jkt 247001 PO 00000 Frm 00079 Fmt 4703 Sfmt 4703 E:\FR\FM\02JYN1.SGM 02JYN1 khammond on DSKBBV9HB2PROD with NOTICES 31640 Federal Register / Vol. 84, No. 127 / Tuesday, July 2, 2019 / Notices

Date of initial notice in Federal For the Nuclear Regulatory Commission. The NRC provides reasonable Register: August 14, 2018 (83 FR Blake D. Welling, accommodation to individuals with 40352). Acting Deputy Director, Division of Operating disabilities where appropriate. If you No significant hazards consideration Reactor Licensing, Office of Nuclear Reactor need a reasonable accommodation to comments received: No. Regulation. participate in these public meetings or Virginia Electric and Power Company, [FR Doc. 2019–14001 Filed 7–1–19; 8:45 am] need this meeting notice or the Docket Nos. 50–280 and 50–281, Surry BILLING CODE 7590–01–P transcript or other information from the Power Station, Unit Nos. 1 and 2, Surry public meetings in another format (e.g., County, Virginia. braille, large print), please notify NUCLEAR REGULATORY Kimberly Meyer-Chambers, NRC Date of amendment request: March 2, COMMISSION Disability Program Manager, at 301– 2018, as supplemented by letter dated [NRC–2019–0001] 287–0739, by videophone at 240–428– October 25, 2018. 3217, or by email at Kimberly.Meyer- Brief description of amendments: The Sunshine Act Meetings [email protected]. Determinations on amendments revised the Surry Power requests for reasonable accommodation Station (SPS), Unit Nos. 1 and 2 TIME AND DATE: Weeks of July 1, 8, 15, will be made on a case-by-case basis. Technical Specifications consistent with 22, 29, August 5, 12, 2019. Members of the public may request to Revision 0 to the Technical PLACE: Commissioners’ Conference receive this information electronically. Specification Task Force (TSTF) Room, 11555 Rockville Pike, Rockville, If you would like to be added to the Traveler, TSTF–490, ‘‘Deletion of E Bar Maryland. distribution, please contact the Nuclear Definition and Revision to RCS [reactor Regulatory Commission, Office of the coolant system] Specific Activity Tech STATUS: Public and Closed. MATTERS TO BE CONSIDERED: Secretary, Washington, DC 20555 (301– Spec.’’ The amendments adopted TSTF– 415–1969), or by email at 490, Revision 0, and made associated Week of July 1, 2019 [email protected] or Tyesha.Bush@ changes, which included replacing the nrc.gov. current limits on primary coolant gross There are no meetings scheduled for the week of July 1, 2019. The NRC is holding the meetings specific activity with limits on primary under the authority of the Government coolant noble gas specific activity. The Week of July 8, 2019—Tentative in the Sunshine Act, 5 U.S.C. 552b. amendments also updated the There are no meetings scheduled for Alternative Source Term (AST) analyses Dated at Rockville, Maryland, this 27th day the week of July 8, 2019. bases for new codes, revised of June, 2019. atmospheric dispersion factors, new fuel Week of July 15, 2019—Tentative For the Nuclear Regulatory Commission. handling accident fuel rod gap fractions There are no meetings scheduled for Denise L. McGovern, and control room isolation operator the week of July 15, 2019. Policy Coordinator, Office of the Secretary. action time, and elimination of the [FR Doc. 2019–14181 Filed 6–28–19; 11:15 am] Week of July 22, 2019—Tentative locked rotor accident dose BILLING CODE 7590–01–P consequences. There are no meetings scheduled for Date of issuance: June 12, 2019. the week of July 22, 2019. Effective date: As of the date of issuance and shall be implemented Week of July 29, 2019—Tentative POSTAL SERVICE within 60 days of issuance. There are no meetings scheduled for Product Change—Priority Mail Amendment Nos.: 295 and 295. A the week of July 29, 2019. Express, Priority Mail, & First-Class publicly-available version is in ADAMS Package Service Negotiated Service under Accession No. ML19028A384; Week of August 5, 2019—Tentative Agreement documents related to these amendments There are no meetings scheduled for are listed in the Safety Evaluation the week of August 5, 2019. AGENCY: Postal ServiceTM. enclosed with the amendments. ACTION: Notice. Renewed Facility Operating License Week of August 12, 2019—Tentative Nos. DPR–32 and DPR–37: Amendments Wednesday, August 14, 2019 SUMMARY: The Postal Service gives revised the Renewed Facility Operating notice of filing a request with the Postal 9:00 a.m. Hearing on Early Site Permit Licenses and Technical Specifications. Regulatory Commission to add a for the Clinch River Nuclear Site: Date of initial notice in Federal domestic shipping services contract to Section 189a. of the Atomic Energy Register: June 19, 2018, 83 FR 28465. the list of Negotiated Service Act Proceeding (Public Meeting) The supplemental letter dated October Agreements in the Mail Classification (Contact: Mallecia Sutton: 301–415– 25, 2018 provided additional Schedule’s Competitive Products List. 0673) information that clarified the DATES: Date of required notice: July 2, This hearing will be webcast live at application, did not expand the scope of 2019. the application as originally noticed, the web address—http://www.nrc.gov/. and did not change the staff’s original CONTACT PERSON FOR MORE INFORMATION: FOR FURTHER INFORMATION CONTACT: proposed no significant hazards For more information or to verify the Elizabeth Reed, 202–268–3179. consideration determination as status of meetings, contact Denise SUPPLEMENTARY INFORMATION: The published in the Federal Register. McGovern at 301–415–0681 or via email United States Postal Service® hereby The Commission’s related evaluation at [email protected]. The gives notice that, pursuant to 39 U.S.C. of the amendment is contained in a schedule for Commission meetings is 3642 and 3632(b)(3), on June 25, 2019, Safety Evaluation dated June 12, 2019. subject to change on short notice. it filed with the Postal Regulatory No significant hazards consideration The NRC Commission Meeting Commission a USPS Request to Add comments received: No. Schedule can be found on the internet Priority Mail Express, Priority Mail, & Dated at Rockville, Maryland, this 26th day at: http://www.nrc.gov/public-involve/ First-Class Package Service Contract 63 of June 2019. public-meetings/schedule.html. to Competitive Product List. Documents

VerDate Sep<11>2014 18:03 Jul 01, 2019 Jkt 247001 PO 00000 Frm 00080 Fmt 4703 Sfmt 4703 E:\FR\FM\02JYN1.SGM 02JYN1 khammond on DSKBBV9HB2PROD with NOTICES