83 FR 40342 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations
NUCLEAR REGULATORY COMMISSION Federal Register Volume 83, Issue 157 (August 14, 2018)
Federal Register Volume 83, Issue 157 (August 14, 2018)
| Page Range | 40342-40355 | |
| FR Document | 2018-17132 |
[Federal Register Volume 83, Number 157 (Tuesday, August 14, 2018)] [Notices] [Pages 40342-40355] From the Federal Register Online [www.thefederalregister.org] [FR Doc No: 2018-17132] ----------------------------------------------------------------------- NUCLEAR REGULATORY COMMISSION [NRC-2018-0164] Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations AGENCY: Nuclear Regulatory Commission. ACTION: Biweekly notice. ----------------------------------------------------------------------- SUMMARY: Pursuant to Section 189a.(2) of the Atomic Energy Act of 1954, as amended (the Act), the U.S. Nuclear Regulatory Commission (NRC) is publishing this regular biweekly notice. The Act requires the Commission to publish notice of any amendments issued, or proposed to be issued, and grants the Commission the authority to issue and make immediately effective any amendment to an operating license or combined license, as applicable, upon a determination by the Commission that such amendment involves no significant hazards consideration, notwithstanding the pendency before the Commission of a request for a hearing from any person. This biweekly notice includes all notices of amendments issued, or proposed to be issued, from July 17, 2018, to July 30, 2018. The last biweekly notice was published on July 31, 2018. DATES: Comments must be filed by September 13, 2018. A request for a hearing must be filed by October 15, 2018. ADDRESSES: You may submit comments by any of the following methods:Federal Rulemaking website: Go to http://www.regulations.gov and search for Docket ID NRC-2018-0164. Address questions about NRC dockets to Jennifer Borges; telephone: 301-287- 9127; email: [email protected]. For technical questions, contact the individual listed in the FOR FURTHER INFORMATION CONTACT section of this document. Mail comments to: May Ma, Office of Administration, Mail Stop: TWFN-7-A60M, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001. For additional direction on obtaining information and submitting comments, [[Page 40343]] see ``Obtaining Information and Submitting Comments'' in the SUPPLEMENTARY INFORMATION section of this document. FOR FURTHER INFORMATION CONTACT: Paula Blechman, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington DC 20555-0001; telephone: 301-415-2242; email [email protected]. SUPPLEMENTARY INFORMATION: I. Obtaining Information and Submitting Comments A. Obtaining Information Please refer to Docket ID NRC-2018-0164, facility name, unit number(s), plant docket number, application date, and subject when contacting the NRC about the availability of information for this action. You may obtain publicly-available information related to this action by any of the following methods: Federal Rulemaking website: Go to http://www.regulations.gov and search for Docket ID NRC-2018-0164. NRC's Agencywide Documents Access and Management System (ADAMS): You may obtain publicly-available documents online in the ADAMS Public Documents collection at http://www.nrc.gov/reading-rm/adams.html. To begin the search, select ``Begin Web-based ADAMS Search.'' For problems with ADAMS, please contact the NRC's Public Document Room (PDR) reference staff at 1-800-397-4209, 301-415-4737, or by email to [email protected]. The ADAMS accession number for each document referenced (if it is available in ADAMS) is provided the first time that it is mentioned in this document. NRC's PDR: You may examine and purchase copies of public documents at the NRC's PDR, Room O1-F21, One White Flint North, 11555 Rockville Pike, Rockville, Maryland 20852. B. Submitting Comments Please include Docket ID NRC-2018-0164, facility name, unit number(s), plant docket number, application date, and subject in your comment submission. The NRC cautions you not to include identifying or contact information that you do not want to be publicly disclosed in your comment submission. The NRC will post all comment submissions at http://www.regulations.gov as well as enter the comment submissions into ADAMS. The NRC does not routinely edit comment submissions to remove identifying or contact information. If you are requesting or aggregating comments from other persons for submission to the NRC, then you should inform those persons not to include identifying or contact information that they do not want to be publicly disclosed in their comment submission. Your request should state that the NRC does not routinely edit comment submissions to remove such information before making the comment submissions available to the public or entering the comment into ADAMS. II. Notice of Consideration of Issuance of Amendments to Facility Operating Licenses and Combined Licenses and Proposed No Significant Hazards Consideration Determination The Commission has made a proposed determination that the following amendment requests involve no significant hazards consideration. Under the Commission's regulations in section 50.92 of title 10 of the Code of Federal Regulations (10 CFR), this means that operation of the facility in accordance with the proposed amendment would not (1) involve a significant increase in the probability or consequences of an accident previously evaluated, or (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety. The basis for this proposed determination for each amendment request is shown below. The Commission is seeking public comments on this proposed determination. Any comments received within 30 days after the date of publication of this notice will be considered in making any final determination. Normally, the Commission will not issue the amendment until the expiration of 60 days after the date of publication of this notice. The Commission may issue the license amendment before expiration of the 60- day period provided that its final determination is that the amendment involves no significant hazards consideration. In addition, the Commission may issue the amendment prior to the expiration of the 30- day comment period if circumstances change during the 30-day comment period such that failure to act in a timely way would result, for example in derating or shutdown of the facility. If the Commission takes action prior to the expiration of either the comment period or the notice period, it will publish in the Federal Register a notice of issuance. If the Commission makes a final no significant hazards consideration determination, any hearing will take place after issuance. The Commission expects that the need to take this action will occur very infrequently. A. Opportunity To Request a Hearing and Petition for Leave To Intervene Within 60 days after the date of publication of this notice, any persons (petitioner) whose interest may be affected by this action may file a request for a hearing and petition for leave to intervene (petition) with respect to the action. Petitions shall be filed in accordance with the Commission's ``Agency Rules of Practice and Procedure'' in 10 CFR part 2. Interested persons should consult a current copy of 10 CFR 2.309. The NRC's regulations are accessible electronically from the NRC Library on the NRC's website at http://www.nrc.gov/reading-rm/doc-collections/cfr/. Alternatively, a copy of the regulations is available at the NRC's Public Document Room, located at One White Flint North, Room O1-F21, 11555 Rockville Pike (first floor), Rockville, Maryland 20852. If a petition is filed, the Commission or a presiding officer will rule on the petition and, if appropriate, a notice of a hearing will be issued. As required by 10 CFR 2.309(d) the petition should specifically explain the reasons why intervention should be permitted with particular reference to the following general requirements for standing: (1) The name, address, and telephone number of the petitioner; (2) the nature of the petitioner's right under the Act to be made a party to the proceeding; (3) the nature and extent of the petitioner's property, financial, or other interest in the proceeding; and (4) the possible effect of any decision or order which may be entered in the proceeding on the petitioner's interest. In accordance with 10 CFR 2.309(f), the petition must also set forth the specific contentions which the petitioner seeks to have litigated in the proceeding. Each contention must consist of a specific statement of the issue of law or fact to be raised or controverted. In addition, the petitioner must provide a brief explanation of the bases for the contention and a concise statement of the alleged facts or expert opinion which support the contention and on which the petitioner intends to rely in proving the contention at the hearing. The petitioner must also provide references to the specific sources and documents on which the petitioner intends to rely to support its position on the issue. The petition must include sufficient information to show that a genuine dispute exists with the applicant or licensee on a material issue of law or fact. Contentions must be limited to matters within the scope of [[Page 40344]] the proceeding. The contention must be one which, if proven, would entitle the petitioner to relief. A petitioner who fails to satisfy the requirements at 10 CFR 2.309(f) with respect to at least one contention will not be permitted to participate as a party. Those permitted to intervene become parties to the proceeding, subject to any limitations in the order granting leave to intervene. Parties have the opportunity to participate fully in the conduct of the hearing with respect to resolution of that party's admitted contentions, including the opportunity to present evidence, consistent with the NRC's regulations, policies, and procedures. Petitions must be filed no later than 60 days from the date of publication of this notice. Petitions and motions for leave to file new or amended contentions that are filed after the deadline will not be entertained absent a determination by the presiding officer that the filing demonstrates good cause by satisfying the three factors in 10 CFR 2.309(c)(1)(i) through (iii). The petition must be filed in accordance with the filing instructions in the ``Electronic Submissions (E-Filing)'' section of this document. If a hearing is requested, and the Commission has not made a final determination on the issue of no significant hazards consideration, the Commission will make a final determination on the issue of no significant hazards consideration. The final determination will serve to establish when the hearing is held. If the final determination is that the amendment request involves no significant hazards consideration, the Commission may issue the amendment and make it immediately effective, notwithstanding the request for a hearing. Any hearing would take place after issuance of the amendment. If the final determination is that the amendment request involves a significant hazards consideration, then any hearing held would take place before the issuance of the amendment unless the Commission finds an imminent danger to the health or safety of the public, in which case it will issue an appropriate order or rule under 10 CFR part 2. A State, local governmental body, Federally-recognized Indian Tribe, or agency thereof, may submit a petition to the Commission to participate as a party under 10 CFR 2.309(h)(1). The petition should state the nature and extent of the petitioner's interest in the proceeding. The petition should be submitted to the Commission no later than 60 days from the date of publication of this notice. The petition must be filed in accordance with the filing instructions in the ``Electronic Submissions (E-Filing)'' section of this document, and should meet the requirements for petitions set forth in this section, except that under 10 CFR 2.309(h)(2) a State, local governmental body, or Federally-recognized Indian Tribe, or agency thereof does not need to address the standing requirements in 10 CFR 2.309(d) if the facility is located within its boundaries. Alternatively, a State, local governmental body, Federally-recognized Indian Tribe, or agency thereof may participate as a non-party under 10 CFR 2.315(c). If a hearing is granted, any person who is not a party to the proceeding and is not affiliated with or represented by a party may, at the discretion of the presiding officer, be permitted to make a limited appearance pursuant to the provisions of 10 CFR 2.315(a). A person making a limited appearance may make an oral or written statement of his or her position on the issues but may not otherwise participate in the proceeding. A limited appearance may be made at any session of the hearing or at any prehearing conference, subject to the limits and conditions as may be imposed by the presiding officer. Details regarding the opportunity to make a limited appearance will be provided by the presiding officer if such sessions are scheduled. B. Electronic Submissions (E-Filing) All documents filed in NRC adjudicatory proceedings, including a request for hearing and petition for leave to intervene (petition), any motion or other document filed in the proceeding prior to the submission of a request for hearing or petition to intervene, and documents filed by interested governmental entities that request to participate under 10 CFR 2.315(c), must be filed in accordance with the NRC's E-Filing rule (72 FR 49139; August 28, 2007, as amended at 77 FR 46562; August 3, 2012). The E-Filing process requires participants to submit and serve all adjudicatory documents over the internet, or in some cases to mail copies on electronic storage media. Detailed guidance on making electronic submissions may be found in the Guidance for Electronic Submissions to the NRC and on the NRC website at http://www.nrc.gov/site-help/e-submittals.html. Participants may not submit paper copies of their filings unless they seek an exemption in accordance with the procedures described below. To comply with the procedural requirements of E-Filing, at least 10 days prior to the filing deadline, the participant should contact the Office of the Secretary by email at [email protected], or by telephone at 301-415-1677, to (1) request a digital identification (ID) certificate, which allows the participant (or its counsel or representative) to digitally sign submissions and access the E-Filing system for any proceeding in which it is participating; and (2) advise the Secretary that the participant will be submitting a petition or other adjudicatory document (even in instances in which the participant, or its counsel or representative, already holds an NRC- issued digital ID certificate). Based upon this information, the Secretary will establish an electronic docket for the hearing in this proceeding if the Secretary has not already established an electronic docket. Information about applying for a digital ID certificate is available on the NRC's public website at http://www.nrc.gov/site-help/e-submittals/getting-started.html. Once a participant has obtained a digital ID certificate and a docket has been created, the participant can then submit adjudicatory documents. Submissions must be in Portable Document Format (PDF). Additional guidance on PDF submissions is available on the NRC's public website at http://www.nrc.gov/site-help/electronic-sub-ref-mat.html. A filing is considered complete at the time the document is submitted through the NRC's E-Filing system. To be timely, an electronic filing must be submitted to the E-Filing system no later than 11:59 p.m. Eastern Time on the due date. Upon receipt of a transmission, the E-Filing system time-stamps the document and sends the submitter an email notice confirming receipt of the document. The E-Filing system also distributes an email notice that provides access to the document to the NRC's Office of the General Counsel and any others who have advised the Office of the Secretary that they wish to participate in the proceeding, so that the filer need not serve the document on those participants separately. Therefore, applicants and other participants (or their counsel or representative) must apply for and receive a digital ID certificate before adjudicatory documents are filed so that they can obtain access to the documents via the E-Filing system. A person filing electronically using the NRC's adjudicatory E- Filing system may seek assistance by contacting the NRC's Electronic Filing Help Desk through the ``Contact Us'' link located on the NRC's public website at http://www.nrc.gov/site-help/e-submittals.html, by email to [[Page 40345]] [email protected], or by a toll-free call at 1-866-672-7640. The NRC Electronic Filing Help Desk is available between 9 a.m. and 6 p.m., Eastern Time, Monday through Friday, excluding government holidays. Participants who believe that they have a good cause for not submitting documents electronically must file an exemption request, in accordance with 10 CFR 2.302(g), with their initial paper filing stating why there is good cause for not filing electronically and requesting authorization to continue to submit documents in paper format. Such filings must be submitted by: (1) First class mail addressed to the Office of the Secretary of the Commission, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, Attention: Rulemaking and Adjudications Staff; or (2) courier, express mail, or expedited delivery service to the Office of the Secretary, 11555 Rockville Pike, Rockville, Maryland 20852, Attention: Rulemaking and Adjudications Staff. Participants filing adjudicatory documents in this manner are responsible for serving the document on all other participants. Filing is considered complete by first-class mail as of the time of deposit in the mail, or by courier, express mail, or expedited delivery service upon depositing the document with the provider of the service. A presiding officer, having granted an exemption request from using E-Filing, may require a participant or party to use E-Filing if the presiding officer subsequently determines that the reason for granting the exemption from use of E-Filing no longer exists. Documents submitted in adjudicatory proceedings will appear in the NRC's electronic hearing docket which is available to the public at https://adams.nrc.gov/ehd, unless excluded pursuant to an order of the Commission or the presiding officer. If you do not have an NRC-issued digital ID certificate as described above, click cancel when the link requests certificates and you will be automatically directed to the NRC's electronic hearing dockets where you will be able to access any publicly available documents in a particular hearing docket. Participants are requested not to include personal privacy information, such as social security numbers, home addresses, or personal phone numbers in their filings, unless an NRC regulation or other law requires submission of such information. For example, in some instances, individuals provide home addresses in order to demonstrate proximity to a facility or site. With respect to copyrighted works, except for limited excerpts that serve the purpose of the adjudicatory filings and would constitute a Fair Use application, participants are requested not to include copyrighted materials in their submission. For further details with respect to these license amendment applications, see the application for amendment which is available for public inspection in ADAMS and at the NRC's PDR. For additional direction on accessing information related to this document, see the ``Obtaining Information and Submitting Comments'' section of this document. Arizona Public Service Company, et al., Docket Nos. STN 50-528, STN 50- 529, and STN 50-530, Palo Verde Nuclear Generating Station, Unit Nos. 1, 2, and 3, Maricopa County, Arizona Date of amendment request: July 31, 2015, as supplemented by letters dated April 11, 2016; November 3, 2017; May 18, 2018; and June 1, 2018. Publicly-available versions are in ADAMS under Accession Nos. ML15218A300, ML16102A463, ML17307A188, ML18138A480, and ML18152B874, respectively. Description of amendment request: The amendments would modify the technical specification (TS) requirements related to Completion Times (CTs) for Required Actions to provide the option to calculate longer, risk-informed CTs. The methodology for using the Risk Informed Completion Time (RICT) Program is described in Nuclear Energy Institute (NEI) topical report NEI 06-09, ``Risk-Informed Technical Specifications Initiative 4b, Risk-Managed Technical Specifications (RMTS) Guidelines,'' Revision 0-A (ADAMS Accession No. ML12286A322), which was approved by the NRC on May 17, 2007. The license amendment request (LAR) was originally noticed in the Federal Register on December 8, 2015 (80 FR 76317). The licensee originally proposed to adopt, with plant-specific variations, Technical Specifications Task Force (TSTF) Traveler TSTF-505, Revision 1, ``Provide Risk-Informed Extended Completion Times--RITSTF [Risk Informed TSTF] Initiative 4b'' (ADAMS Accession No. ML111650552). By letter dated November 15, 2016 (ADAMS Accession No. ML16281A021), the NRC staff informed the TSTF of its decision to suspend NRC approval of TSTF-505, Revision 1, because of concerns identified during the review of plant-specific LARs for adoption of the traveler. The NRC staff's letter also stated that it would continue reviewing applications already received and site- specific proposals to address the staff's concerns. Although the scope of the amendment request has not changed, the basis for the amendments will no longer rely on TSTF-505. This notice is being reissued in its entirety to include the revised description of the amendment request. The proposed no significant hazards consideration determination is identical to the one published in the Federal Register on December 8, 2015. Basis for proposed no significant hazards consideration determination: As required by 10 CFR 50.91(a), the licensee has provided its analysis of the issue of no significant hazards consideration, which is presented below: 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated? Response: No. The proposed change permits the use of RICTs provided the associated risk is assessed and managed in accordance with the NRC- accepted RICT Program. The proposed use of RICTs does not involve a significant increase in the probability of an accident previously evaluated because the change only affects TS Conditions, Required Actions and CTs associated with risk informed technical specifications and does not involve changes to the plant, its modes of operation, or TS mode applicability. The proposed license amendment references regulatory commitments to achieve the baseline PRA [probabilistic risk assessment] risk metrics specified in the NRC model evaluation. The changes proposed by regulatory commitments will be implemented under the requirements of 10 CFR 50.59 without the need for prior NRC approval. The proposed change does not increase the consequences of an accident because the accident mitigation functions of the affected systems, structures, or components (SSCs) are not changed. Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated. 2. Does the proposed change create the possibility or different kind of accident from any accident previously evaluated? Response: No. The proposed change permits the use of RICTs provided the associated risk is assessed and managed in accordance with the NRC- accepted RICT Program. The proposed use of RICTs does not create the possibility of a new or different kind of accident from any accident previously evaluated because the change only affects TS Conditions, Required Actions and CTs associated with risk informed technical specifications. The proposed change does not involve a physical alteration of the plant and does not involve installation of new or different kind of equipment. The proposed license amendment references regulatory commitments to achieve the baseline PRA risk metrics specified in the NRC model evaluation. The changes proposed by [[Page 40346]] regulatory commitments will be implemented under the requirements of 10 CFR 50.59 without the need for prior NRC approval. The proposed change does not alter the accident mitigation functions of the affected SSCs and does not introduce new or different SSC failure modes than already evaluated. Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated. 3. Does the proposed change involve a significant reduction in a margin of safety? Response: No. The proposed change permits the use of RICTs provided the risk levels associated with inoperable equipment within the scope of the RICT program are assessed and managed in accordance with the NRC approved RICT Program. The proposed change implements a risk- informed Configuration Risk Management Program (CRMP) to assure that adequate margins of safety are maintained. Application of these new specifications and the CRMP considers cumulative effects of multiple systems or components being out of service and does so more effectively than the current TS. In this regard, the implementation of the CRMP is considered an improvement in safety. Therefore, the proposed change does not involve a significant reduction in a margin of safety. The NRC staff has reviewed the licensee's analysis and, based on that review, it appears that the three standards of 10 CFR 50.92(c) are satisfied. Therefore, the NRC staff proposes to determine that the requested amendments involves no significant hazards consideration. Attorney for licensee: Michael G. Green, Senior Regulatory Counsel, Pinnacle West Capital Corporation, P.O. Box 52034, Mail Station 8695, Phoenix, Arizona 85072-2034. NRC Branch Chief: Robert J. Pascarelli. DTE Electric Company, Docket No. 50-341, Fermi 2, Monroe County, Michigan Date of amendment request: March 14, 2018. A publicly-available version is in ADAMS under Accession No. ML18073A137. Description of amendment request: The proposed amendment modifies the technical specification definition of ``Shutdown Margin'' (SDM) to require calculation of the SDM at a reactor moderator temperature of 68 degrees Fahrenheit ([deg]F) per hour or a higher temperature that represents the most reactive state throughout the operating cycle. This change is needed to address new boiling water reactor (BWR) fuel designs, which may be more reactive at shutdown temperatures above 68[emsp14][deg]F. Basis for proposed no significant hazards consideration determination: As required by 10 CFR 50.91(a), the licensee has provided its analysis of the issue of no significant hazards consideration, which is presented below: 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated? Response: No. The proposed change revises the definition of SDM. SDM is not an initiator to any accident previously evaluated. Accordingly, the proposed change to the definition of SDM has no effect on the probability of any accident previously evaluated. SDM is an assumption in the analysis of some previously evaluated accidents and inadequate SDM could lead to an increase in consequences for those accidents. However, the proposed change revises the SDM definition to ensure that the correct SDM is determined for all fuel types at all times during the fuel cycle. As a result, the proposed change does not adversely affect the consequences of any accident previously evaluated. Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated. 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated? Response: No. The proposed change revises the definition of SDM. The change does not involve a physical alteration of the plant (i.e., no new or different type of equipment will be installed) or a change in the methods governing normal plant operations. The change does not alter assumptions made in the safety analysis regarding SDM. Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated. 3. Does the proposed change involve a significant reduction in a margin of safety? Response: No. The proposed change revises the definition of SDM. The proposed change does not alter the manner in which safety limits, limiting safety system settings or limiting conditions for operation are determined. The proposed change ensures that the SDM assumed in determining safety limits, limiting safety system settings or limiting conditions for operation is correct for all BWR fuel types at all times during the fuel cycle. Therefore, the proposed change does not involve a significant reduction in a margin of safety. The NRC staff has reviewed the licensee's analysis and based on this review, it appears that the three standards of 10 CFR 50.92(c) are satisfied. Therefore, the NRC staff proposes to determine that the amendment request involves no significant hazards consideration. Attorney for licensee: Jon P. Christinidis, DTE Energy, Expert Attorney--Regulatory, 688 WCB, One Energy Plaza, Detroit, MI 48226- 1279. NRC Branch Chief: David J. Wrona. Duke Energy Carolinas, LLC, Docket Nos. 50-413 and 50-414, Catawba Nuclear Station, Unit Nos. 1 and 2 (CNS), York County, South Carolina Duke Energy Carolinas, LLC, Docket Nos. 50-369 and 50-370, McGuire Nuclear Station, Unit Nos. 1 and 2 (MNS), Mecklenburg County, North Carolina Duke Energy Carolinas, LLC, Docket Nos. 50-269, 50-270, and 50-287, Oconee Nuclear Station, Unit Nos. 1, 2, and 3 (ONS), Oconee County, South Carolina Duke Energy Progress, LLC, Docket Nos. 50-325 and 50-324, Brunswick Steam Electric Plant (BNP), Unit Nos. 1 and 2, Brunswick County, North Carolina Duke Energy Progress, LLC, Docket No. 50-261, H. B. Robinson Steam Electric Plant, Unit No. 2 (RNP), Darlington County, South Carolina Duke Energy Progress, LLC, Docket No. 50-400, Shearon Harris Nuclear Power Plant, Unit 1 (HNP), Wake County, North Carolina Date of amendment request: June 20, 2018. A publicly-available version is in ADAMS under Accession No. ML18172A315. Description of amendment request: The amendments would revise the Emergency Action Levels (EALs) for CNS, MNS, ONS, BNP, HNP, and RNP consistent with Emergency Preparedness Frequently Asked Questions (EPFAQs) 2015-013 (EAL HG1.1) and 2016-002 (EALs CA6.1 and SA9.1 (SA8.1 for BNP)). The amendments would revise the EALs for HNP and RNP consistent with EPFAQ 2015-014 (EAL HS6.1). Basis for proposed no significant hazards consideration determination: As required by 10 CFR 50.91(a), the licensee has provided its analysis of the issue of no significant hazards consideration, which is presented below: 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated? Response: No. The proposed changes to EALs HG1.1, CA6.1, SA9.1 (SA8.1 for BNP), and HS6.1 do not reduce the capability to meet the emergency planning requirements established in 10 CFR 50.47 and 10 CFR [Part] 50, Appendix E. The proposed changes do not reduce the functionality, performance, or capability of Duke Energy's Emergency Response Organization (ERO) to respond in mitigating the consequences of any design basis accident. The proposed changes do not involve any physical changes to plant [[Page 40347]] equipment or systems, nor do they alter the assumptions of any accident analyses. The proposed changes do not adversely affect accident initiators or precursors nor do they alter the design assumptions, conditions, and configuration or the manner in which the plants are operated and maintained. The proposed changes do not adversely affect the ability of Structures, Systems, or Components (SSCs) to perform their intended safety functions in mitigating the consequences of an initiating event within the assumed acceptance limits. There is no impact on the source term or pathways assumed in accidents previously assumed. No analysis assumptions are violated and there are no adverse effects on the factors that contribute to offsite or onsite dose as the result of an accident. Therefore, the proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated. 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated? Response: No. The proposed changes to EALs HG1.1, CA6.1, SA9.1 (SA8.1 for BNP), and HS6.1 do not involve any physical changes to plant systems or equipment. The proposed changes do not involve the addition of any new plant equipment. The proposed changes will not alter the design configuration, or method of operation of plant equipment beyond its normal functional capabilities. All Duke Energy ERO functions will continue to be performed as required. The proposed changes do not create any new credible failure mechanisms, malfunctions, or accident initiators. Therefore, the proposed changes do not create the possibility of a new or different kind of accident from any accident previously evaluated. 3. Does the proposed change involve a significant reduction in a margin of safety? Response: No. Margin of safety is related to the confidence in the ability of the fission product barriers to perform their design functions during and following an accident. These barriers include the fuel cladding, the reactor coolant system, and the containment system. The proposed changes to EALs HG1.1, CA6.1, SA9.1 (SA8.1 for BNP), and HS6.1 do not alter or exceed a design basis or safety limit. There is no change being made to safety analysis assumptions, safety limits, or limiting safety system settings that would adversely affect plant safety as a result of the proposed changes. There are no changes to setpoints or environmental conditions of any SSC or the manner in which any SSC is operated. Margins of safety are unaffected by the proposed changes. The applicable requirements of 10 CFR 50.47 and 10 CFR [Part] 50, Appendix E will continue to be met. Therefore, the proposed changes do not involve a significant reduction in a margin of safety. The NRC staff has reviewed the licensee's analysis and, based on this review, it appears that the three standards of 10 CFR 50.92(c) are satisfied. Therefore, the NRC staff proposes to determine that the amendment request involves no significant hazards consideration. Attorney for licensee: Kathryn B. Nolan, Deputy General Counsel, Duke Energy Corporation, 550 South Tryon Street, Mail Code DEC45A, Charlotte NC 28202. NRC Acting Branch Chief: Booma Venkatamaraman. Entergy Nuclear Operations, Inc., Docket No. 50-255, Palisades Nuclear Plant (PNP), Van Buren County, Michigan Date of amendment request: May 30, 2018. A publicly-available version is in ADAMS under Accession No. ML18152A922. Description of amendment request: The proposed amendment would revise the PNP Technical Specification (TS) 3.3.5, ``Diesel Generator (DG)--Undervoltage Start (UV Start),'' Surveillance Requirement (SR) 3.3.5.2a by adding a channel calibration requirement for the combined time delay setpoints for the degraded voltage sensing relay and the degraded voltage time delay relay. Basis for proposed no significant hazards consideration determination: As required by 10 CFR 50.91(a), the licensee has provided its analysis of the issue of no significant hazards consideration, which is presented below: 1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated? Response: No. The proposed amendment would revise a TS SR to include, for each degraded voltage channel, calibration of the time delay setpoint for the degraded voltage sensing relay in combination with the setpoint for the time delay relay. The minimum time delay setpoint in the revised TS SR would be long enough to override any brief voltage disturbances. The maximum time delay setpoint in the revised TS SR would be short enough to not exceed the maximum time delays assumed in the PNP Final Safety Analysis Report accident analyses for the operation of safety related equipment and to not result in failure of safety related equipment due to sustained degraded voltage conditions. Therefore, safety related loads would be available to perform their required safety functions under these conditions. The proposed change does not adversely affect accident initiators or precursors, and does not affect the design assumptions, conditions, or configuration of the plant, or the manner in which the plant is operated or maintained. Therefore, the proposed amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated. 2. Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated? Response: No. The proposed amendment would revise a TS SR to include, for each degraded voltage channel, calibration of the time delay setpoint for the degraded voltage sensing relay in combination with the time delay setpoint for the time delay relay. The conduct of surveillance tests on safety related plant equipment is a means of assuring that the equipment is capable of performing its functions that are credited in the safety analyses for the facility. The proposed amendment would not affect the operation of safety related equipment assumed in accident analyses, and would not create any new failure mechanisms, malfunctions, or accident initiators not considered in the design and licensing bases. Therefore, the possibility of a new or different kind of accident from any previously evaluated has not been created. 3. Does the proposed amendment involve a significant reduction in a margin of safety? Response: No. The proposed amendment would revise a TS SR to include, for each degraded voltage channel, calibration of the time delay setpoint for the degraded voltage sensing relay in combination with the time delay setpoint for the time delay relay. The conduct of surveillance tests on safety related plant equipment is a means of assuring that the equipment is capable of maintaining the margin of safety established in the safety analyses for the facility. The proposed amendment would not introduce changes to limits established in the accident analyses. The minimum time delay setpoint in the revised TS SR would be long enough to override any brief voltage disturbances. The maximum time delay setpoint in the revised TS SR would be short enough to not exceed the maximum time delays assumed in the PNP Final Safety Analysis Report accident analyses for the operation of safety related equipment and to not result in failure of safety related equipment due to sustained degraded voltage conditions. Therefore, the proposed amendment does not involve a significant reduction in a margin of safety. The NRC staff has reviewed the licensee's analysis and, based on this review, it appears that the three standards of 10 CFR 50.92(c) are satisfied. Therefore, the NRC staff proposes to determine that the amendment request involves no significant hazards consideration. Attorney for licensee: Anna Jones, Senior Counsel, Entergy Services, Inc., 101 Constitution Ave., NW, Washington, DC 20001. NRC Branch Chief: David J. Wrona. [[Page 40348]] Exelon Generation Company, LLC, Docket No. 50-461, Clinton Power Station, Unit No. 1, DeWitt County, Illinois Exelon Generation Company, LLC, Docket Nos. 50-237 and 50-249, Dresden Nuclear Power Station, Unit Nos. 2 and 3, Grundy County, Illinois Exelon Generation Company, LLC and Exelon FitzPatrick, LLC, Docket No. 50-333, James A. FitzPatrick Nuclear Power Plant, Oswego County, New York Exelon Generation Company, LLC, Docket Nos. 50-373 and 50-374, LaSalle County Station, Unit Nos. 1 and 2, LaSalle County, Illinois Exelon Generation Company, LLC, Docket Nos. 50-352 and No. 50-353, Limerick Generating Station, Unit Nos. 1 and 2, Montgomery County, Pennsylvania Exelon Generation Company, LLC, Docket Nos. 50-220 and 50-410, Nine Mile Point Nuclear Station, Unit Nos. 1 and 2, Oswego County, New York Exelon Generation Company, LLC, and PSEG Nuclear LLC, Docket Nos. 50- 277 and 50-278, Peach Bottom Atomic Power Station, Unit Nos. 2 and 3, York and Lancaster Counties, Pennsylvania Exelon Generation Company, LLC, Docket Nos. 50-254 and 50-265, Quad Cities Nuclear Power Station, Unit Nos. 1 and 2, Rock Island County, Illinois Date of amendment request: June 15, 2018. A publicly-available version is in ADAMS under Accession No. ML18166A197. Description of amendment request: The amendments would revise the technical specification (TS) requirements associated with the average power range monitors (APRMs). Basis for proposed no significant hazards consideration determination: As required by 10 CFR 50.91(a), the licensee has provided its analysis of the issue of no significant hazards consideration, which is presented below: 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated? Response: No. The APRM system and the RPS [reactor protection system] are not initiators of any accidents previously evaluated. As a result, the proposed change does not affect the probability of any accident previously evaluated. The APRM system and the RPS functions act to mitigate the consequences of accidents previously evaluated. The reliability of the APRM system and the RPS is not significantly affected by removing the gain adjustment requirement on the APRM channels when the APRMs are calibrated conservatively with respect to the calculated heat balance. This is because the actual core thermal power at which the reactor will automatically trip is lower, thereby increasing the margin to the core thermal limits and the limiting safety system settings assumed in the safety analyses. The consequences of an accident during the adjustment of the APRM instrumentation are no different from those during the existing surveillance testing period or the existing time allowed to restore the instruments to operable status. As a result, the ability of the APRM system and the RPS to mitigate any accident previously evaluated is not significantly affected. Therefore, the proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated. 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated? Response: No. The proposed changes do not alter the protection system designs, create new failure modes, or change any modes of operation. The proposed change does not involve a physical alteration of the plant; no new or different kind of equipment will be installed. Consequently, there are no new initiators that could result in a new or different kind of accident. Therefore, the proposed changes do not create the possibility of a new or different kind of accident from any previously evaluated. 3. Does the proposed change involve a significant reduction in a margin of safety? Response: No. The margin of safety provided by the APRM system and the RPS is to ensure that the reactor is shut down automatically when plant parameters exceed the setpoints for the system. Any reduction in the margin of safety resulting from the adjustment of the APRM channels while continuing operation is considered to be offset by delaying a plant shutdown (i.e., a transient) for a short time with the APRM system, the primary indication of core power and an input to the RPS, not calibrated. Additionally, the short time period required for adjustment is consistent with the time allowed by TS to restore the core power distribution parameters to within limits and is acceptable based on the low probability of a transient or design basis accident occurring simultaneously with inaccurate APRM channels. The proposed changes do not alter setpoints or limits established or assumed by the accident analyses. The TS continue to require operability of the RPS functions, which provide core protection for postulated reactivity insertion events occurring during power operating conditions consistent with the plant safety analyses. Therefore, the proposed changes do not involve a significant reduction in a margin of safety. The NRC staff has reviewed the licensee's analysis and, based on this review, it appears that the three standards of 10 CFR 50.92(c) are satisfied. Therefore, the NRC staff proposes to determine that the requested amendments involve no significant hazards consideration. Attorney for licensee: Tamra Domeyer, Associate General Counsel, Exelon Generation Company, LLC, 4300 Winfield Road, Warrenville, IL 60555. NRC Branch Chief: David J. Wrona. Exelon Generation Company, LLC, Docket Nos. 50-373 and 50-374, LaSalle County Station, Unit Nos. 1 and 2, LaSalle County, Illinois Date of amendment request: April 19, 2018. A publicly-available version is in ADAMS under Accession No. ML18157A123. Description of amendment request: The amendments would revise licenses and the technical specifications (TSs) as follows: Division 3 Battery Surveillance Testing The proposed amendments would revise TS 3.8.4, ``DC Sources- Operating,'' and TS 3.8.6, ``Battery Parameters,'' by removing the Mode restrictions for performance of TS surveillance requirements (SRs) 3.8.4.3 and 3.8.6.6 for the Division 3 direct current (DC) electrical power subsystem battery. The Division 3 DC electrical power subsystem feeds emergency DC loads associated with the high pressure core spray (HPCS) system. Surveillance Requirement 3.8.4.3 verifies that the battery capacity is adequate for the battery to perform its required functions. Surveillance Requirement 3.8.6.6 verifies battery capacity is greater than or equal to (>=) 80 percent of the manufacturer's rating when subjected to a performance discharge test (or a modified performance discharge test). The proposed amendments would remove these Mode restrictions for the Division 3 battery, allowing performance of SRs 3.8.4.3 and 3.8.6.6 for the Division 3 battery during Mode 1 or 2, potentially minimizing impact on HPCS unavailability. Eliminating the requirement to perform SRs 3.8.4.3 and 3.8.6.6 only during Mode 3, 4, or 5 (hot shutdown, cold shutdown, or refueling conditions) will provide greater flexibility in scheduling Division 3 battery testing activities by allowing the testing to be performed during non-outage times. High Pressure Core Spray Diesel Generator Surveillance Testing The proposed amendments would revise TS 3.8.1, ``AC Sources- Operating,'' by revising certain SRs pertaining to the Division 3 diesel generator (DG). The Division 3 DG is an [[Page 40349]] independent source of onsite alternating current (AC) power dedicated to the HPCS system. The TSs currently prohibit performing the testing required by SRs 3.8.1.9, 3.8.1.10, 3.8.1.11, 3.8.1.12, 3.8.1.13, 3.8.1.16, 3.8.1.17, and 3.8.1.19, in Modes 1 or 2. The proposed amendments would remove these Mode restrictions and allow all eight of the identified SRs to be performed in any operating Mode for the Division 3 DG. The Mode restrictions will remain applicable to the other two safety-related (Division 1 and Division 2) DGs. The proposed change will provide greater flexibility in scheduling Division 3 DG testing activities by allowing the testing to be performed during non-outage times. Having a completely tested Division 3 DG available for the duration of a refueling outage will reduce the number of system re-alignments and operator workload during an outage. Basis for proposed no significant hazards consideration determination: As required by 10 CFR 50.91(a), the licensee has provided its analysis of the issue of no significant hazards consideration, which is presented below: 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously analyzed? Response: No. The Division 3 HPCS DG electrical power subsystem and its associated emergency loads are accident mitigating features, not accident initiators. Therefore, the proposed TS changes to allow the performance of certain Division 3 AC Sources surveillance testing in any plant operating Mode will not significantly impact the probability of any previously evaluated accident. The design and function of plant equipment is not being modified by the proposed changes. Neither the battery test frequency nor the time that the TSs allow the HPCS system to be inoperable are being revised. Battery testing in accordance with the proposed TS changes will continue to verify that the Division 3 DC electrical power subsystem is capable of performing its required function of providing DC power to HPCS system equipment, consistent with the plant safety analyses. The battery testing will occur during a planned HPCS outage and therefore will not result in an increase in risk above the current work practices of planned HPCS system maintenance outages. Any risk associated with the testing of the Division 3 battery will be bounded and addressed with the risk associated with the HPCS system outage. In addition, the HPCS system reliability and availability are monitored and evaluated in relationship to Maintenance Rule goals to ensure that total outage times do not degrade operational safety over time. Testing is limited to only one electrical division of equipment at a time to ensure that design basis requirements are met. Should a fault occur while testing the Division 3 battery, there would be no significant impact on any accident consequences since the other two divisional DC electrical power subsystems and their associated emergency loads would be available to provide the minimum safety functions necessary to shut down the unit and maintain it in a safety shutdown condition. The Division 3 HPCS DG and its associated emergency loads are accident mitigating features, not accident initiators. Therefore, the proposed TS changes to allow the performance of Division 3 DG surveillance testing in any plant operating mode will not significantly impact the probability of any previously evaluated accident. The design of plant equipment is not being modified by the proposed changes. As such, the ability of the Division 3 DG to respond to a design basis accident will not be adversely impacted by the proposed changes. The proposed changes to the TS surveillance testing requirements for the Division 3 DG do not affect the operability requirements for the DG, as verification of such operability will continue to be performed as required. Continued verification of operability supports the capability of the Division 3 DG to perform its required function of providing emergency power to HPCS system equipment, consistent with the plant safety analyses. Limiting testing to only one DG at a time ensures that design basis requirements are met. Should a fault occur while testing the Division 3 DG, there would be no significant impact on any accident consequences since the other two divisional DGs and associated emergency loads would be available to provide the minimum safety functions necessary to shut down the unit and maintain it in a safe shutdown condition. Therefore, the proposed change does not result in a significant increase in the probability or consequences of an accident previously evaluated. 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated? Response: No. No changes are being made to the plant that would introduce any new accident causal mechanisms. Equipment will be operated in the same configuration with the exception of the plant operating mode in which the Division 3 battery and DG surveillance testing are conducted. Performance of these surveillance tests while online will continue to verify operability of the Division 3 battery and DG. The battery testing will potentially minimize the out-of-service time for the HPCS system. The proposed amendments do not impact any plant systems that are accident initiators and do not adversely impact any accident mitigating systems. Therefore, the proposed changes do not create the possibility of a new or different kind of accident from any previously evaluated. 3. Does the proposed change involve a significant reduction in a margin of safety? Response: No. The proposed changes do not involve a significant reduction in the margin of safety. Margin of safety is related to confidence in the ability of the fission product barriers (i.e., fuel cladding, reactor coolant system, and primary containment) to perform their design functions during and following postulated accidents. The proposed changes to the TS surveillance testing requirements for the Division 3 AC Sources and DG do not affect the operability requirements, as verification of such operability will continue to be performed as required. Continued verification of operability supports the capability of the Division 3 AC Sources and DG to perform the required functions of providing emergency power to HPCS system equipment, consistent with the plant safety analyses. Consequently, the performance of the fission product barriers will not be adversely impacted by implementation of the proposed amendments. In addition, the proposed changes do not alter setpoints or limits established or assumed by the accident analysis. The additional online unavailability of the HPCS system does not constitute a significant reduction in a margin of safety. The battery testing will be performed when the HPCS system is already out of service for a planned system outage and therefore the testing will not result in an increase in risk above the current work practices of planned system maintenance outages, as currently allowed by the TS. Therefore, the proposed changes do not involve a significant reduction in a margin of safety. The NRC staff has reviewed the licensee's analysis and, based on this review, it appears that the three standards of 10 CFR 50.92(c) are satisfied. Therefore, the NRC staff proposes to determine that the amendment request involves no significant hazards consideration. Attorney for licensee: Tamra Domeyer, Associate General Counsel, Exelon Generation Company, LLC, 4300 Winfield Road, Warrenville, IL 60555. NRC Branch Chief: David J. Wrona. Florida Power and Light Company, et al., Docket Nos. 50-335 and 50-389, St. Lucie Plant, Unit Nos.1 and 2, St. Lucie County, Florida Date of amendment request: December 5, 2014; as supplemented by letters dated July 8 and July 22, 2016; February 25, 2017; and February 1, March 15, and June 7, 2018. Publicly-available versions are in ADAMS under Accession Nos. ML14353A016, ML16193A659, ML16208A061, ML17058A181, ML18032A614, ML18074A116, and ML18158A228, respectively. Description of amendment request: The amendments would modify the Technical Specification (TS) requirements related to Completion Times for Required Actions to provide the option to calculate longer, risk- [[Page 40350]] informed Completion Times. The amendments would also add a new program, the Risk Informed Completion Time (RICT) Program, to TS Section 6.0, ``Administrative Controls.'' The methodology for using the Risk Informed Completion Time Program is described in Nuclear Energy Institute (NEI) topical report NEI 06-09, ``Risk-Informed Technical Specifications Initiative 4b, Risk-Managed Technical Specifications (RMTS) Guidelines,'' Revision 0-A (ADAMS Accession No. ML12286A322), which was approved by the NRC on May 17, 2007. The license amendment request was originally noticed in the Federal Register on March 17, 2015 (80 FR 13908). The licensee originally proposed to adopt, with plant specific variations, Technical Specifications Task Force (TSTF) Traveler TSTF-505, Revision 1, ``Provide Risk-Informed Extended Completion Times--RITSTF [Risk Informed TSTF] Initiative 4b'' (Accession No. ML111650552). By letter dated November 15, 2016 (ADAMS Accession No. ML16281A021), the NRC staff informed the TSTF of its decision to suspend NRC approval of TSTF-505, Revision 1, because of concerns identified during the review of plant-specific license amendment requests for adoption of the traveler. The NRC staff's letter also stated that it would continue reviewing applications already received and site-specific proposals to address the staff's concerns. Although the scope of the amendment request has not changed, the basis for the amendments will no longer rely on TSTF-505. The notice is being reissued in its entirety to include the description of the amendment request and proposed no significant hazards consideration determination. Basis for proposed no significant hazards consideration determination: As required by 10 CFR 50.91(a), the licensee has provided its analysis of the issue of no significant hazards consideration, which is presented below: 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated? Response: No. The proposed change permits the extension of Completion Times provided the associated risk is assessed and managed in accordance with the NRC[-]approved Risk Informed Completion Time Program. The proposed change does not involve a significant increase in the probability of an accident previously evaluated because the change involves no change to the plant or its modes of operation. The proposed change does not increase the consequences of an accident because the design-basis mitigation function of the affected systems is not changed and the consequences of an accident [occurring] during the extended Completion Time are no different from those [occurring] during the existing Completion Time. 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated? Response: No. The proposed change does not change the design, configuration, or method of operation of the plant. The proposed change does not involve a physical alteration of the plant (no new or different kind of equipment will be installed). Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated. 3. Does the proposed change involve a significant reduction in a margin of safety? Response: No. The proposed change permits the extension of Completion Times provided risk is assessed and managed in accordance with the NRC[- ]approved Risk Informed Completion Time Program. The proposed change implements a risk-informed configuration management program to assure that adequate margins of safety are maintained. Application of these new specifications and the configuration management program considers cumulative effects of multiple systems or components being out of service and does so more effectively than the current TS. Therefore, the proposed change does not involve a significant reduction in a margin of safety. The NRC staff has reviewed the licensee's analysis and, based on this review, it appears that the three standards of 10 CFR 50.92(c) are satisfied. Therefore, the NRC staff proposes to determine that the amendment request involves no significant hazards consideration. Attorney for licensee: Debbie Hendell, Managing Attorney--Nuclear, Florida Power & Light Company, 700 Universe Blvd. MS LAW/JB, Juno Beach, Florida 33408-0420. NRC Acting Branch Chief: Booma Venkataraman. Northern States Power Company (NSPM), Docket Nos. 50-282 and 50-306, Prairie Island Nuclear Generating Plant, Unit Nos. 1 and 2, (PINGP) Goodhue County, Minnesota Date of amendment request: May 18, 2018. A publicly-available version is in ADAMS under Accession No. ML18138A402. Brief description of amendment request: The proposed amendments would modify paragraph 2.C(4)(c) of the PINGP Renewed Facility Operating Licenses (RFOLs) which requires the implementation of modification to PINGP as described in Attachment S, Table S-2, of the PINGP license amendment request (LAR) dated December 14, 2016, to adopt the National Fire Protection Association Standard (NFPA) 805. Specifically, NSPM is requesting the deletion of five modifications from Table S-2 of the December 14, 2016, LAR. Basis for proposed no significant hazards consideration determination: As required by 10 CFR 50.91(a), the licensee has provided its analysis of the issue of no significant hazards consideration, which is presented below: 1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated? Response: No. The proposed amendment adds a reference to this letter to the PINGP, Units 1 and 2, RFOLs. The changes encompassed by this proposed amendment are to delete five modifications that are no longer needed from a risk perspective. The revision is based on five changes to Table S-2 proposed in this license amendment request (LAR). The proposed changes have been reviewed in the fire Probabilistic Risk Assessment (PRA) model approved as part of PINGP's transition to NFPA 805 and the results were found to be acceptable. Fire protection defense in depth and adequate safety margins are maintained with the changes proposed in this LAR. The proposed change does not adversely affect accident initiators or precursors, nor alter the design assumptions, conditions, and configuration of the facility or the manner in which the plant is operated and maintained. The proposed changes do not adversely affect the ability of structures, systems and components (SSCs) to perform their intended safety function to mitigate the consequences of an initiating event within the assumed acceptance limits. The proposed change does not increase the probability or consequences of an accident as verified by the risk analysis performed. Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated. 2. Does the proposed amendment create the possibility of a new or different kind of accident from any previously evaluated? Response: No. The proposed amendment adds a reference to this letter to the PINGP, Units 1 and 2, RFOLs. The changes encompassed by this proposed amendment are to delete five modifications that are no longer needed from a risk perspective. The revision is based on five changes to Table S-2 proposed in this LAR. The proposed changes have been reviewed in the fire PRA model approved as part of PINGP's transition to NFPA 805 and the results were found to be acceptable. Fire protection defense in depth and adequate safety margins are maintained with the changes proposed in this LAR. The proposed changes will not result in any new or different kinds of accident from that previously evaluated because it does not [[Page 40351]] change any precursors or equipment that is previously credited for accident mitigation. Therefore, the proposed changes do not create the possibility of a new or different kind of accident from any accident previously evaluated. 3. Does the proposed amendment involve a significant reduction in a margin of safety? Response: No. The proposed amendment adds a reference to this letter to the PINGP, Units 1 and 2, RFOLs. The changes encompassed by this proposed amendment are to delete five modifications that are no longer needed from a risk perspective. The revision is based on five changes to Table S-2 proposed in this LAR. The proposed changes have been reviewed in the fire PRA model approved as part of PINGP's transition to NFPA 805 and the results were found to be acceptable. Fire protection defense in depth and adequate safety margins are maintained with the changes proposed in this LAR. The proposed change does not adversely affect any SSCs credited for accident mitigation. The margins of safety previously evaluated are not significantly affected. The change does not affect the design function or capabilities of any plant systems. Therefore, the proposed changes will not impact or reduce any margins of safety previously evaluated. The NRC staff has reviewed the licensee's analysis and, based on this review, it appears that the three standards of 10 CFR 50.92(c) are satisfied. Therefore, the NRC staff proposes to determine that the amendment request involves no significant hazards consideration. Attorney for licensee: Peter M. Glass, Assistant General Counsel, Xcel Energy Services, Inc., 414 Nicollet Mall, Minneapolis, MN 55401. NRC Branch Chief: David J. Wrona. Northern States Power Company, Docket Nos. 50-282 and 50-306, Prairie Island Nuclear Generating Plant, Unit Nos. 1 and 2, (PINGP) Goodhue County, Minnesota Date of amendment request: June 26, 2018. A publicly-available version is in ADAMS under Accession No. ML18177A450. Brief description of amendment request: The proposed amendments would revise PINGP Technical Specifications (TSs) by eliminating second Completion Times limiting time from discovery of failure to meet a limiting condition for operation (LCO). These changes are consistent with NRC-approved Technical Specifications Task Force (TSTF) Traveler TSTF-439, Revision 2, ``Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO.'' Basis for proposed no significant hazards consideration determination: As required by 10 CFR 50.91(a), the licensee has provided its analysis of the issue of no significant hazards consideration, which is presented below: 1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated? Response: No. The proposed change eliminates second Completion Times from the Technical Specifications. Completion Times are not an initiator to any accident previously evaluated. As a result, the probability of an accident previously evaluated is not affected. The consequences of an accident during the revised Completion Time are no different than the consequences of the same accident during the existing Completion Times. As a result, the consequences of an accident previously evaluated are not affected by this change. The proposed change does not alter or prevent the ability of SSCs [structures, systems, and components] from performing their intended function to mitigate the consequences of an initiating event within the assumed acceptance limits. The proposed change does not affect the source term, containment isolation, or radiological release assumptions used in evaluating the radiological consequences of an accident previously evaluated. Further, the proposed change does not increase the types or amounts of radioactive effluent that may be released offsite nor significantly increase individual or cumulative occupational/public radiation exposures. The proposed change is consistent with the safety analysis assumptions and resultant consequences. Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated. 2. Does the proposed amendment create the possibility of a new or different kind of accident from any previously evaluated? Response: No. The proposed change does not involve a physical alteration of the plant (i.e., no new or different type of equipment will be installed) or a change in the methods governing normal plant operation. The proposed change does not alter any assumptions made in the safety analysis. Therefore, the proposed changes do not create the possibility of a new or different kind of accident from any accident previously evaluated. 3. Does the proposed amendment involve a significant reduction in a margin of safety? Response: No. The proposed change to delete the second Completion Time does not alter the manner in which safety limits, limiting safety system settings, or limiting conditions for operation are determined. The safety analysis acceptance criteria are not affected by this change. The proposed change will not result in plant operation in a configuration outside of the design basis. Therefore, the proposed changes do not involve a significant reduction in a margin of safety. The NRC staff has reviewed the licensee's analysis and, based on this review, it appears that the three standards of 10 CFR 50.92(c) are satisfied. Therefore, the NRC staff proposes to determine that the amendment request involves no significant hazards consideration. Attorney for licensee: Peter M. Glass, Assistant General Counsel, Xcel Energy Services, Inc., 414 Nicollet Mall, Minneapolis, MN 55401. NRC Branch Chief: David J. Wrona. PSEG Nuclear LLC, Docket No. 50-354, Hope Creek Generating Station, Salem County, New Jersey PSEG Nuclear LLC and Exelon Generation Company, LLC, Docket Nos. 50-272 and 50-311, Salem Nuclear Generating Station, Unit Nos. 1 and 2, Salem County, New Jersey Date of amendment request: June 29, 2018. A publicly-available version is in ADAMS under Accession No. ML18183A343. Description of amendment request: The amendments would revise technical specification (TS) requirements in Section 3/4.0, ``Applicability,'' regarding Limiting Condition for Operation (LCO) and Surveillance Requirement (SR) usage. These changes are consistent with NRC-approved Technical Specifications Task Force (TSTF) Traveler TSTF- 529, ``Clarify Use and Application Rules.'' Basis for proposed no significant hazards consideration determination: As required by 10 CFR 50.91(a), the licensee has provided its analysis of the issue of no significant hazards consideration, which is presented below: 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated? Response: No. The proposed changes to LCO 3.0.4 have no effect on the requirement for systems to be Operable and have no effect on the application of TS actions. The proposed change to SR 4.0.3 states that the allowance may only be used when there is a reasonable expectation the surveillance will be met when performed. Since the proposed changes do not significantly affect system Operability, the proposed changes will have no significant effect on the initiating events for accidents previously evaluated and will have no significant effect on the ability of the systems to mitigate accidents previously evaluated. Therefore, it is concluded that this change does not involve a significant increase in the probability or consequences of an accident previously evaluated. 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated? Response: No. [[Page 40352]] The proposed change to the TS usage rules does not affect the design or function of any plant systems. The proposed change does not change the Operability requirements for plant systems or the actions taken when plant systems are not operable. Therefore, it is concluded that this change does not create the possibility of a new or different kind of accident from any accident previously evaluated. 3. Does the proposed change involve a significant reduction in a margin of safety? Response: No. The proposed change clarifies the application of LCO 3.0.4 and does not result in changes in plant operation. SR 4.0.3 is revised to allow application of SR 4.0.3 when an SR has not been previously performed and there is reasonable expectation that the SR will be met when performed. This expands the use of SR 4.0.3 while ensuring the affected system is capable of performing its safety function. As a result, plant safety is either improved or unaffected. Therefore, it is concluded that this change does not involve a significant reduction in a margin of safety. The NRC staff has reviewed the licensee's analysis and, based on this review, it appears that the three standards of 10 CFR 50.92(c) are satisfied. Therefore, the NRC staff proposes to determine that the amendment request involves no significant hazards consideration. Attorney for licensee: Ryan K. Lighty, Morgan, Lewis & Bockius LLP, 1111 Pennsylvania Avenue NW, Washington, DC 20004-2541. NRC Branch Chief: James G. Danna. United States Maritime Administration (MARAD), Docket No. 50-238, Nuclear Ship SAVANNAH (NSS), Baltimore, Maryland Date of amendment request: June 19, 2018. A publically-available version is in ADAMS under Accession No. ML18173A128. Description of amendment request: The proposed amendment would revise Technical Specification (TS) Section 2.0, ``Radioactive Releases,'' from its original custom form to industry typical 10 CFR 50.36a TSs for effluents from nuclear power reactors. Basis for proposed no significant hazards consideration determination: As required by 10 CFR 50.91(a), the licensee has provided its analysis of the issue of no significant hazards consideration, which is presented below: 1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated? Response: No. The proposed amendment is administrative and does not involve modification of any plant equipment or affect basic plant operation. The proposed amendment revises all of Technical Specification Section 2.0, Radioactive Releases from its original custom form to typical 10 CFR 50.36a, Technical Specifications on effluents from nuclear power reactors that are consistent with those of plants in advanced stages of decommissioning. The proposed amendment also deletes three Technical Specifications whose requirements are included in STS-005-020, Offsite Dose Calculation Manual and therefore, are no longer necessary as standalone Technical Specifications. These three Technical Specifications include one associated with the annual report, one associated with area monitoring thermoluminescent dosimeters and one associated with environmental monitoring. The NSS's reactor is not operational and the level of radioactivity in the NSS has significantly decreased from the levels that existed when the final shutdown was completed on November 8, 1970. No aspect of any of the proposed changes is an initiator of any accident previously evaluated. Consequently, the probability of an accident previously evaluated is not significantly increased. Therefore, the proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated. 2. Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated? Response: No. All of the proposed changes are administrative and do not involve physical alteration of plant equipment that was not previously allowed by Technical Specifications. The proposed amendment revises all of Technical Specification Section 2.0, Radioactive Releases from its original custom form to typical 10 CFR 50.36a, Technical Specifications on effluents from nuclear power reactors that are consistent with those of plants in advanced stages of decommissioning. The proposed amendment also deletes three Technical Specifications whose requirements are included in STS-005- 020, Offsite Dose Calculation Manual and therefore, are no longer necessary as standalone Technical Specifications. These three Technical Specifications include one associated with the annual report, one associated with area monitoring thermoluminescent dosimeters and one associated with environmental monitoring. These proposed changes do not change the method by which any safety-related system performs its function given that all primary, auxiliary and secondary systems are deactivated, disabled and perform no active function. No new or different types of equipment will be installed, and the basic operation of installed equipment is unchanged. The methods governing plant operation and testing remain consistent with current safety analysis assumptions. Therefore, the proposed changes do not create the possibility of a new or different kind of accident from any previously evaluated. 3. Does the change involve a significant reduction in a margin of safety? Response: No. All of the proposed changes are administrative in nature. The proposed amendment revises all of Technical Specification Section 2.0, Radioactive Releases from its original custom form to typical 10 CFR 50.36a, Technical Specifications on effluents from nuclear power reactors that are consistent with those of plants in advanced stages of decommissioning. The proposed amendment also deletes three Technical Specifications whose requirements are included in STS-005- 020, Offsite Dose Calculation Manual and therefore, are no longer necessary as standalone Technical Specifications. These three Technical Specifications include one associated with the annual report, one associated with area monitoring thermoluminescent dosimeters and one associated with environmental monitoring. No margins of safety exist that are relevant to the ship's defueled and partially dismantled reactor. As such, there are no changes being made to safety analysis assumptions, safety limits or safety system settings that would adversely affect plant safety as a result of the proposed changes. As such, there are no changes being made to safety analysis assumptions, safety limits or safety system settings that would adversely affect plant safety or are relevant to the ship's defueled and partially dismantled reactor as a result of the proposed changes. Therefore, the proposed changes do not involve a significant reduction in a margin of safety. The NRC staff has reviewed the licensee's analysis and, based on this review, it appears that the three standards of 10 CFR 50.92(c) are satisfied. Therefore, the NRC staff proposes to determine that the amendment request involves no significant hazards consideration. Advisor for licensee: Erhard W. Koehler, U.S. Department of Transportation, Maritime Administration, 1200 New Jersey Ave. SE, Washington, DC 20590. NRC Branch Chief: Bruce Watson. III. Previously Published Notices of Consideration of Issuance of Amendments to Facility Operating Licenses and Combined Licenses, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing The following notices were previously published as separate individual notices. The notice content was the same as above. They were published as individual notices either because time did not allow the Commission to wait for this biweekly notice or because the action involved exigent circumstances. They are repeated here because the biweekly notice lists all amendments issued or proposed to be issued involving no significant hazards consideration. [[Page 40353]] For details, see the individual notice in the Federal Register on the day and page cited. This notice does not extend the notice period of the original notice. Exelon Generation Company, LLC and Exelon FitzPatrick, LLC, Docket No. 50-333, James A. FitzPatrick Nuclear Power Plant, Oswego County, New York Date of amendment request: May 17, 2018. A publicly-available version is in ADAMS under Accession No. ML18137A418. Brief description of amendment request: The proposed amendment would revise Technical Specifications 2.1.1, ``Reactor Core SLs [safety limits]'' to change Cycle 24 Safety Limit Minimum Critical Power Ratio (SLMCPR) numeric values resulting from SLMCPR analyses performed. Date of publication of individual notice in Federal Register: July 13, 2018 (83 FR 32691). Expiration date of individual notice: August 13, 2018 (public comments); September 11, 2018 (hearing requests). IV. Notice of Issuance of Amendments to Facility Operating Licenses and Combined Licenses During the period since publication of the last biweekly notice, the Commission has issued the following amendments. The Commission has determined for each of these amendments that the application complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations. The Commission has made appropriate findings as required by the Act and the Commission's rules and regulations in 10 CFR chapter I, which are set forth in the license amendment. A notice of consideration of issuance of amendment to facility operating license or combined license, as applicable, proposed no significant hazards consideration determination, and opportunity for a hearing in connection with these actions, was published in the Federal Register as indicated. Unless otherwise indicated, the Commission has determined that these amendments satisfy the criteria for categorical exclusion in accordance with 10 CFR 51.22. Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared for these amendments. If the Commission has prepared an environmental assessment under the special circumstances provision in 10 CFR 51.22(b) and has made a determination based on that assessment, it is so indicated. For further details with respect to the action see (1) the applications for amendment, (2) the amendment, and (3) the Commission's related letter, Safety Evaluation and/or Environmental Assessment as indicated. All of these items can be accessed as described in the ``Obtaining Information and Submitting Comments'' section of this document. DTE Electric Company, Docket No. 50-341, Fermi 2, Monroe County, Michigan Date of amendment request: July 17, 2017, as supplemented by letter dated January 8, 2018. Brief description of amendment: The amendment revised Fermi 2 Technical Specification (TS) 3.7.2, ``Emergency Equipment Cooling Water (EECW)/Emergency Equipment Service Water (EESW) System and Ultimate Heat Sink (UHS).'' Specifically, the amendment revised TS 3.7.2 conditions and surveillance requirements to reflect a proposed change to the design of the two redundant cross-tie lines that are part of the UHS. Date of issuance: July 17, 2018. Effective date: As of the date of issuance and shall be implemented within 120 days of issuance. Amendment No.: 209. A publicly-available version is in ADAMS under Accession No. ML18144A064; documents related to this amendment are listed in the Safety Evaluation enclosed with the amendment. Renewed Facility Operating License No. NPF-43: Amendment revised the Renewed Facility Operating License and Technical Specifications. Date of initial notice in Federal Register: September 26, 2017 (82 FR 44850). The supplemental letter dated January 8, 2018, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the NRC staff's original proposed no significant hazards consideration determination as published in the Federal Register. The Commission's related evaluation of the amendment is contained in a Safety Evaluation dated July 17, 2018. No significant hazards consideration comments received: No. Entergy Operations, Inc., Docket No. 50-382, Waterford Steam Electric Station, Unit No. 3, St. Charles Parish, Louisiana Date of amendment request: November 28, 2017, as supplemented by letters dated December 7, 2017, and May 8, 2018. Brief description of amendment: The amendment revised Section 4.3.3 of the Updated Final Safety Analysis Report to indicate that the RAPTOR-M3G code is used for reactor vessel fluence calculations. The use of the RAPTOR-M3G code meets the criteria present in Regulatory Guide (RG) 1.190, ``Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence,'' dated March 2001. Date of issuance: July 23, 2018. Effective date: As of the date of issuance and shall be implemented 30 days from the date of issuance. Amendment No.: 252. A publicly-available version is in ADAMS under Accession No. ML18180A298; documents related to this amendment are listed in the Safety Evaluation enclosed with the amendment. Facility Operating License No. NPF-38: The amendment revised the Updated Final Safety Analysis Report. Date of initial notice in Federal Register: January 16, 2018 (83 FR 2228). The supplement dated May 8, 2018, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the NRC staff's original proposed no significant hazards consideration determination as published in the Federal Register. The Commission's related evaluation of the amendment is contained in a Safety Evaluation dated July 23, 2018. No significant hazards consideration comments received: No. Exelon Generation Company, LLC and Exelon FitzPatrick, LLC, Docket No. 50-333, James A. FitzPatrick Nuclear Power Plant, Oswego County, New York Date of amendment request: September 14, 2017, as supplemented by letter dated March 15, 2018. Brief description of amendment: The amendment revised Technical Specification (TS) 3.6.4.1, ``Secondary Containment,'' Surveillance Requirement (SR) 3.6.4.1.3. The SR is revised to address conditions during which the secondary containment pressure may not meet the SR pressure requirements. Date of issuance: July 19, 2018. Effective date: As of the date of issuance, and shall be implemented within 60 days. Amendment No.: 319. A publicly-available version is in ADAMS under Accession No. ML18180A372; documents related to this amendment are listed in the Safety Evaluation enclosed with the amendment. Renewed Facility Operating License No. DPR-59: The amendment revised the Renewed Facility Operating License and TSs. [[Page 40354]] Date of initial notice in Federal Register: November 7, 2017 (82 FR 51650). The supplemental letter dated March 15, 2018, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the NRC staff's original proposed no significant hazards consideration determination as published in the Federal Register. The Commission's related evaluation of the amendment is contained in a Safety Evaluation dated July 19, 2018. No significant hazards consideration comments received: No. FirstEnergy Nuclear Operating Company, et al., Docket Nos. 50-334 and 50-412, Beaver Valley Power Station, Unit Nos. 1 and 2, Beaver County, Pennsylvania FirstEnergy Nuclear Operating Company, et al., Docket No. 50-346, Davis-Besse Nuclear Power Station, Unit No. 1, Ottawa County, Ohio FirstEnergy Nuclear Operating Company, et al., Docket No. 50-440, Perry Nuclear Power Plant, Unit No. 1, Lake County, Ohio Date of amendment request: August 11, 2017. Brief description of amendments: The amendments changed the respective technical specifications (TSs) as follows: The changes revised Section 1.3, ``Completion Times,'' and Section 3.0, ``LCO Applicability'' of the TSs to clarify the use and application of the TS usage rules, as described below: Section 1.3 is revised to clarify ``discovery'' and to discuss exceptions to starting the Completion Time at condition entry. Limiting Condition for Operation (LCO) 3.0.4.b is revised to clarify that LCO 3.0.4.a, LCO 3.0.4.b, and LCO 3.0.4.c are independent options. Surveillance Requirement (SR) 3.0.3 is revised to allow application of SR 3.0.3 when an SR has not been previously performed and to clarify the application of SR 3.0.3. The changes to the TSs are consistent with Technical Specifications Task Force (TSTF-529), Revision 4, ``Clarify Use and Application Rules.'' The NRC staff-issued safety evaluation for TSTF-529 was provided to the Technical Specifications Task Force in a letter dated April 21, 2016. This review included a review of the NRC staff's evaluation, as well as the information provided in TSTF-529. Date of issuance: July 30, 2018. Effective date: As of the date of issuance and shall be implemented within 90 days from the date of issuance. Amendment Nos.: 303/192 (Beaver Valley Unit Nos. 1 and 2); 297 (Davis-Besse); and 182 (Perry). A publicly-available version is in ADAMS under Accession No. ML18179A467; documents related to these amendments are listed in the Safety Evaluation enclosed with the amendments. Facility Operating License Nos. DPR-66, NPF-73, NPF-3, and NPF-58: The amendments revised the Licenses and Technical Specifications. Date of initial notice in Federal Register: November 7, 2017 (82 FR 51651). The Commission's related evaluation of the amendments is contained in a Safety Evaluation dated July 30, 2018. No significant hazards consideration comments received: No. Southern Nuclear Operating Company, Docket Nos. 52-025 and 52-026, Vogtle Electric Generating Plant, Unit Nos. 3 and 4, Burke County, Georgia Date of amendment request: January 31, 2018. Description of amendment: The amendments included changes to Combined License Appendix A, Technical Specifications (TSs) related to fuel management. Specifically, the amendments proposed improvements to the TSs for the Rod Position Indication, the Control Rod Drive Mechanism, Power Range Neutron Flux Channels and the Mechanical Shim Augmentation. Date of issuance: July 19, 2018. Effective date: As of the date of issuance and shall be implemented within 30 days of issuance. Amendment Nos.: 134 (Unit 3) and 133 (Unit 4). A publicly-available version is in ADAMS under Accession No. ML18082B374; documents related to this amendment are listed in the Safety Evaluation enclosed with the amendment. Facility Combined Licenses No. NPF-91 and NPF-92: Amendments revised the Facility Combined Licenses. Date of initial notice in Federal Register: February 27, 2018 (83 FR 8509). The Commission's related evaluation of the amendments is contained in the Safety Evaluation dated July 19, 2018. No significant hazards consideration comments received: No. Southern Nuclear Operating Company, Inc., Docket Nos. 50-348 and 50- 364, Joseph M. Farley Nuclear Plant (Farley), Unit Nos. 1 and 2, Houston County, Alabama Southern Nuclear Operating Company, Inc., Docket Nos. 50-321 and 50- 366, Edwin I. Hatch Nuclear Plant (Hatch), Unit Nos. 1 and 2, City of Dalton, Georgia Southern Nuclear Operating Company, Inc., (SNC) Docket Nos. 50-424, 50- 425, 52-025, 52-026, Vogtle Electric Generating Plant (Vogtle), Unit Nos. 1, 2, 3, and 4, Burke County, Georgia Date of amendment request: August 30, 2017. Brief description of amendments: The amendments relocated the emergency operations facility for the eight units of the SNC nuclear fleet from the SNC corporate headquarters in Birmingham, Alabama, to a new location 1.3 miles away. Date of issuance: July 26, 2018. Effective date: As of the date of issuance and shall be implemented 180 days of issuance. Amendment Nos.: 220 (Farley, Unit 1), 217 (Farley, Unit 2), 291 (Hatch, Unit 1), 236 (Hatch, Unit 2), 195 (Vogtle, Unit 1), 178 (Vogtle, Unit 2), 136 (Vogtle, Unit 3), and 135 (Vogtle, Unit 4). A publicly-available version is in ADAMS under Accession No. ML18183A073; documents related to these amendments are listed in the Safety Evaluation enclosed with the amendments. Facility Operating License Nos. NPF-2. NPF-8, DPR-57, NPF-5, NPF- 68, NPF-81, NPF-91, and NPF-92: Amendments revised the Facility Operating Licenses. Date of initial notice in Federal Register: October 10, 2017 (82 FR 47038). The Commission's related evaluation of the amendments is contained in a Safety Evaluation dated July 26, 2018. No significant hazards consideration comments received: No. STP Nuclear Operating Company, Docket Nos. 50-498 and 50-499, South Texas Project, Unit Nos. 1 and 2, Matagorda County, Texas Date of amendment request: July 31, 2017, as supplemented by letter dated February 12, 2018. Brief description of amendment: The amendments revised the South Texas Project Electric Generating Station Emergency Plan to change the emergency response organization (ERO) staffing composition and increase the staff augmentation times for certain ERO positions from the time of declaration of an Alert or higher emergency [[Page 40355]] classification level. The changes also include formatting, clarification, and editorial modifications. Date of issuance: July 19, 2018. Effective date: As of the date of issuance and shall be implemented within 9 months from the date of issuance. Amendment Nos.: 214 (Unit 1) and 200 (Unit 2). A publicly-available version is in ADAMS under Accession No. ML18159A212; documents related to these amendments are listed in the Safety Evaluation enclosed with the amendments. Renewed Facility Operating License Nos. NPF-76 and NPF-80: The amendments revised the Site Emergency Plan. Date of initial notice in Federal Register: September 12, 2017 (82 FR 42855). The supplemental letter dated February 12, 2018, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the NRC staff's original proposed no significant hazards consideration determination as published in the Federal Register. The Commission's related evaluation of the amendments is contained in a Safety Evaluation dated July 19, 2018. No significant hazards consideration comments received: No. Virginia Electric and Power Company, Docket Nos. 50-338 and 50-339, North Anna Power Station, Units Nos. 1 and 2, Louisa County, Virginia Date of amendment request: May 2, 2017, as supplemented by letters dated July 19, 2017, and January 31, 2018. Brief description of amendments: The amendments revised North Anna Power Station (NAPS) Technical Specification (TS) 3.7.18, ``Spent Fuel Pool Storage,'' and TS 4.3.1, ``Criticality,'' to allow the storage of fuel assemblies with a maximum enrichment of up to 5.0 weight percent uranium 235 in the NAPS spent fuel pool storage racks and the New Fuel Storage Area. The amendments further revised the allowable fuel assembly parameters and fuel storage patterns in the spent fuel pool. Date of issuance: July 27, 2018. Effective date: As of the date of issuance and shall be implemented within 180 days of issuance. Amendment Nos.: 279 (Unit 1) and 262 (Unit 2). A publicly-available version is in ADAMS under Accession No. ML18180A197; documents related to these amendments are listed in the Safety Evaluation enclosed with the amendments. Renewed Facility Operating License Nos. NPF-4 and NPF-7: Amendments revised the Renewed Facility Operating Licenses and Technical Specifications. Date of initial notice in Federal Register: March 6, 2018 (83 FR 9553). The supplemental letters dated July 19, 2017, and January 31, 2018, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the NRC staff's original proposed no significant hazards consideration determination as published in the Federal Register. The Commission's related evaluation of the amendment is contained in a Safety Evaluation dated July 27, 2018. No significant hazards consideration comments received: No. Dated at Rockville, Maryland, this 7th day of August, 2018. For the Nuclear Regulatory Commission. Kathryn M. Brock, Deputy Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation. [FR Doc. 2018-17132 Filed 8-13-18; 8:45 am] BILLING CODE 7590-01-P
![40342 Federal Register / Vol. 83, No. 157 / Tuesday, August 14, 2018 / Notices
available documents online in the Chapter 35), the NRC is requesting For the Nuclear Regulatory Commission.
ADAMS Public Documents collection at public comment on its intention to David C. Cullison,
http://www.nrc.gov/reading-rm/ request the OMB’s approval for the NRC Clearance Officer, Office of the Chief
adams.html. To begin the search, select information collection summarized Information Officer.
‘‘ADAMS Public Documents’’ and then below. [FR Doc. 2018–17455 Filed 8–13–18; 8:45 am]
select ‘‘Begin Web-based ADAMS 1. The title of the information BILLING CODE 7590–01–P
Search.’’ For problems with ADAMS, collection: NRC Form 171, ‘‘Duplication
please contact the NRC’s Public Request.’’
Document Room (PDR) reference staff at 2. OMB approval number: 3150–0066. NUCLEAR REGULATORY
1–800–397–4209, 301–415–4737, or by COMMISSION
3. Type of submission: Revision.
email to pdr.resource@nrc.gov. A copy
of the collection of information and 4. The form number, if applicable: [NRC–2018–0164]
related instructions may be obtained NRC Form 171.
5. How often the collection is required Biweekly Notice; Applications and
without charge by accessing ADAMS Amendments to Facility Operating
Accession No. ML18151B019. The or requested: As needed (determined by
the public ordering documents.) Licenses and Combined Licenses
supporting statement is available in Involving No Significant Hazards
ADAMS under Accession No. 6. Who will be required or asked to Considerations
ML18151B018. respond: Individuals, companies, or
• NRC’s PDR: You may examine and organizations requesting document AGENCY: Nuclear Regulatory
purchase copies of public documents at duplication. Commission.
the NRC’s PDR, Room O1–F21, One 7. The estimated number of annual ACTION: Biweekly notice.
White Flint North, 11555 Rockville responses: 74.
Pike, Rockville, Maryland 20852. 8. The estimated number of annual SUMMARY: Pursuant to Section 189a.(2)
• NRC’s Clearance Officer: A copy of respondents: 74. of the Atomic Energy Act of 1954, as
the collection of information and related amended (the Act), the U.S. Nuclear
9. The estimated number of hours
instructions may be obtained without Regulatory Commission (NRC) is
needed annually to comply with the
charge by contacting NRC’s Clearance publishing this regular biweekly notice.
information collection requirement or
Officer, David Cullison, Office of the The Act requires the Commission to
request: 6.
Chief Information Officer, U.S. Nuclear publish notice of any amendments
Regulatory Commission, Washington, 10. Abstract: NRC Form 171 is used issued, or proposed to be issued, and
DC 20555–0001; telephone: 301–415– by the Public Document Room (PDR) grants the Commission the authority to
2084; email: Infocollects.Resource@ staff members who collect information issue and make immediately effective
nrc.gov. from the public requesting reproduction any amendment to an operating license
of publicly available documents in NRC or combined license, as applicable,
B. Submitting Comments Headquarters’ PDR. The information upon a determination by the
Please include Docket ID NRC–2018– collected on the form is necessary for Commission that such amendment
0094 in the subject line of your the reproduction contractor to process involves no significant hazards
comment submission, in order to ensure and fulfill reproduction service orders consideration, notwithstanding the
that the NRC is able to make your from members of the public. Copies of pendency before the Commission of a
comment submission available to the the form are used by the reproduction request for a hearing from any person.
public in this docket. contractor to accompany the orders. One This biweekly notice includes all
The NRC cautions you not to include copy of the form is kept by the notices of amendments issued, or
identifying or contact information in contractor for their records, one copy is proposed to be issued, from July 17,
comment submissions that you do not sent to the public requesting the 2018, to July 30, 2018. The last biweekly
want to be publicly disclosed in your documents, and the third copy (with no notice was published on July 31, 2018.
comment submission. The NRC will credit card data) is kept by the PDR staff
DATES: Comments must be filed by
post all comment submissions at http:// for 90 calendar days, and then securely
September 13, 2018. A request for a
www.regulations.gov as well as enter the discarded.
hearing must be filed by October 15,
comment submissions into ADAMS, III. Specific Requests for Comments 2018.
and the NRC does not routinely edit
comment submissions to remove The NRC is seeking comments that ADDRESSES: You may submit comments
identifying or contact information. address the following questions: by any of the following methods:
If you are requesting or aggregating 1. Is the proposed collection of • Federal Rulemaking website: Go to
comments from other persons for information necessary for the NRC to http://www.regulations.gov and search
submission to the NRC, then you should properly perform its functions? Does the for Docket ID NRC–2018–0164. Address
inform those persons not to include information have practical utility? questions about NRC dockets to Jennifer
identifying or contact information that Borges; telephone: 301–287–9127;
2. Is the estimate of the burden of the
they do not want to be publicly email: Jennifer.Borges@nrc.gov. For
information collection accurate?
disclosed in their comment submission. technical questions, contact the
3. Is there a way to enhance the individual listed in the FOR FURTHER
Your request should state that the NRC
quality, utility, and clarity of the INFORMATION CONTACT section of this
does not routinely edit comment
information to be collected? document.
submissions to remove such information
amozie on DSK3GDR082PROD with NOTICES1
before making the comment 4. How can the burden of the • Mail comments to: May Ma, Office
submissions available to the public or information collection on respondents of Administration, Mail Stop: TWFN–7–
entering the comment into ADAMS. be minimized, including the use of A60M, U.S. Nuclear Regulatory
automated collection techniques or Commission, Washington, DC 20555–
II. Background other forms of information technology? 0001.
In accordance with the Paperwork Dated at Rockville, Maryland, this 9th day For additional direction on obtaining
Reduction Act of 1995 (44 U.S.C. of August, 2018. information and submitting comments,
VerDate Sep<11>2014 19:13 Aug 13, 2018 Jkt 244001 PO 00000 Frm 00131 Fmt 4703 Sfmt 4703 E:\FR\FM\14AUN1.SGM 14AUN1](https://thefederalregister.org/doc/83_FR_40499/page/1.svg)
![Federal Register / Vol. 83, No. 157 / Tuesday, August 14, 2018 / Notices 40345
MSHD.Resource@nrc.gov, or by a toll- of the adjudicatory filings and would concerns. Although the scope of the
free call at 1–866–672–7640. The NRC constitute a Fair Use application, amendment request has not changed,
Electronic Filing Help Desk is available participants are requested not to include the basis for the amendments will no
between 9 a.m. and 6 p.m., Eastern copyrighted materials in their longer rely on TSTF–505. This notice is
Time, Monday through Friday, submission. being reissued in its entirety to include
excluding government holidays. For further details with respect to the revised description of the
Participants who believe that they these license amendment applications, amendment request. The proposed no
have a good cause for not submitting see the application for amendment significant hazards consideration
documents electronically must file an which is available for public inspection determination is identical to the one
exemption request, in accordance with in ADAMS and at the NRC’s PDR. For published in the Federal Register on
10 CFR 2.302(g), with their initial paper additional direction on accessing December 8, 2015.
filing stating why there is good cause for information related to this document, Basis for proposed no significant
not filing electronically and requesting see the ‘‘Obtaining Information and hazards consideration determination:
authorization to continue to submit Submitting Comments’’ section of this As required by 10 CFR 50.91(a), the
documents in paper format. Such filings document. licensee has provided its analysis of the
must be submitted by: (1) First class issue of no significant hazards
Arizona Public Service Company, et al.,
mail addressed to the Office of the consideration, which is presented
Docket Nos. STN 50–528, STN 50–529,
Secretary of the Commission, U.S. below:
and STN 50–530, Palo Verde Nuclear
Nuclear Regulatory Commission,
Generating Station, Unit Nos. 1, 2, and 1. Does the proposed change involve a
Washington, DC 20555–0001, Attention: significant increase in the probability or
3, Maricopa County, Arizona
Rulemaking and Adjudications Staff; or consequences of an accident previously
(2) courier, express mail, or expedited Date of amendment request: July 31, evaluated?
delivery service to the Office of the 2015, as supplemented by letters dated Response: No.
Secretary, 11555 Rockville Pike, April 11, 2016; November 3, 2017; May The proposed change permits the use of
Rockville, Maryland 20852, Attention: 18, 2018; and June 1, 2018. Publicly- RICTs provided the associated risk is
Rulemaking and Adjudications Staff. available versions are in ADAMS under assessed and managed in accordance with
Participants filing adjudicatory Accession Nos. ML15218A300, the NRC-accepted RICT Program. The
ML16102A463, ML17307A188, proposed use of RICTs does not involve a
documents in this manner are significant increase in the probability of an
responsible for serving the document on ML18138A480, and ML18152B874,
accident previously evaluated because the
all other participants. Filing is respectively. change only affects TS Conditions, Required
considered complete by first-class mail Description of amendment request: Actions and CTs associated with risk
as of the time of deposit in the mail, or The amendments would modify the informed technical specifications and does
by courier, express mail, or expedited technical specification (TS) not involve changes to the plant, its modes
delivery service upon depositing the requirements related to Completion of operation, or TS mode applicability. The
document with the provider of the Times (CTs) for Required Actions to proposed license amendment references
service. A presiding officer, having provide the option to calculate longer, regulatory commitments to achieve the
risk-informed CTs. The methodology for baseline PRA [probabilistic risk assessment]
granted an exemption request from risk metrics specified in the NRC model
using E-Filing, may require a participant using the Risk Informed Completion
evaluation. The changes proposed by
or party to use E-Filing if the presiding Time (RICT) Program is described in
regulatory commitments will be
officer subsequently determines that the Nuclear Energy Institute (NEI) topical implemented under the requirements of 10
reason for granting the exemption from report NEI 06–09, ‘‘Risk-Informed CFR 50.59 without the need for prior NRC
use of E-Filing no longer exists. Technical Specifications Initiative 4b, approval. The proposed change does not
Documents submitted in adjudicatory Risk-Managed Technical Specifications increase the consequences of an accident
proceedings will appear in the NRC’s (RMTS) Guidelines,’’ Revision 0–A because the accident mitigation functions of
electronic hearing docket which is (ADAMS Accession No. ML12286A322), the affected systems, structures, or
which was approved by the NRC on components (SSCs) are not changed.
available to the public at https://
May 17, 2007. The license amendment Therefore, the proposed change does not
adams.nrc.gov/ehd, unless excluded involve a significant increase in the
pursuant to an order of the Commission request (LAR) was originally noticed in
probability or consequences of an accident
or the presiding officer. If you do not the Federal Register on December 8, previously evaluated.
have an NRC-issued digital ID certificate 2015 (80 FR 76317). The licensee 2. Does the proposed change create the
as described above, click cancel when originally proposed to adopt, with possibility or different kind of accident from
the link requests certificates and you plant-specific variations, Technical any accident previously evaluated?
will be automatically directed to the Specifications Task Force (TSTF) Response: No.
NRC’s electronic hearing dockets where Traveler TSTF–505, Revision 1, The proposed change permits the use of
‘‘Provide Risk-Informed Extended RICTs provided the associated risk is
you will be able to access any publicly
assessed and managed in accordance with
available documents in a particular Completion Times—RITSTF [Risk
the NRC-accepted RICT Program. The
hearing docket. Participants are Informed TSTF] Initiative 4b’’ (ADAMS proposed use of RICTs does not create the
requested not to include personal Accession No. ML111650552). By letter possibility of a new or different kind of
privacy information, such as social dated November 15, 2016 (ADAMS accident from any accident previously
security numbers, home addresses, or Accession No. ML16281A021), the NRC evaluated because the change only affects TS
personal phone numbers in their filings, staff informed the TSTF of its decision Conditions, Required Actions and CTs
unless an NRC regulation or other law to suspend NRC approval of TSTF–505, associated with risk informed technical
amozie on DSK3GDR082PROD with NOTICES1
requires submission of such Revision 1, because of concerns specifications. The proposed change does not
identified during the review of plant- involve a physical alteration of the plant and
information. For example, in some
does not involve installation of new or
instances, individuals provide home specific LARs for adoption of the different kind of equipment. The proposed
addresses in order to demonstrate traveler. The NRC staff’s letter also license amendment references regulatory
proximity to a facility or site. With stated that it would continue reviewing commitments to achieve the baseline PRA
respect to copyrighted works, except for applications already received and site- risk metrics specified in the NRC model
limited excerpts that serve the purpose specific proposals to address the staff’s evaluation. The changes proposed by
VerDate Sep<11>2014 19:13 Aug 13, 2018 Jkt 244001 PO 00000 Frm 00134 Fmt 4703 Sfmt 4703 E:\FR\FM\14AUN1.SGM 14AUN1](https://thefederalregister.org/doc/83_FR_40499/page/4.svg)
![40346 Federal Register / Vol. 83, No. 157 / Tuesday, August 14, 2018 / Notices
regulatory commitments will be licensee has provided its analysis of the NRC Branch Chief: David J. Wrona.
implemented under the requirements of 10 issue of no significant hazards
CFR 50.59 without the need for prior NRC Duke Energy Carolinas, LLC, Docket
consideration, which is presented
approval. The proposed change does not alter Nos. 50–413 and 50–414, Catawba
below:
the accident mitigation functions of the Nuclear Station, Unit Nos. 1 and 2
affected SSCs and does not introduce new or 1. Does the proposed change involve a (CNS), York County, South Carolina
different SSC failure modes than already significant increase in the probability or
evaluated. consequences of an accident previously Duke Energy Carolinas, LLC, Docket
Therefore, the proposed change does not evaluated? Nos. 50–369 and 50–370, McGuire
create the possibility of a new or different Response: No. Nuclear Station, Unit Nos. 1 and 2
kind of accident from any accident The proposed change revises the definition (MNS), Mecklenburg County, North
previously evaluated. of SDM. SDM is not an initiator to any Carolina
3. Does the proposed change involve a accident previously evaluated. Accordingly,
significant reduction in a margin of safety? the proposed change to the definition of SDM Duke Energy Carolinas, LLC, Docket
Response: No. has no effect on the probability of any Nos. 50–269, 50–270, and 50–287,
The proposed change permits the use of accident previously evaluated. SDM is an Oconee Nuclear Station, Unit Nos. 1, 2,
RICTs provided the risk levels associated assumption in the analysis of some and 3 (ONS), Oconee County, South
with inoperable equipment within the scope previously evaluated accidents and Carolina
of the RICT program are assessed and inadequate SDM could lead to an increase in
managed in accordance with the NRC consequences for those accidents. However, Duke Energy Progress, LLC, Docket Nos.
approved RICT Program. The proposed the proposed change revises the SDM 50–325 and 50–324, Brunswick Steam
change implements a risk-informed definition to ensure that the correct SDM is Electric Plant (BNP), Unit Nos. 1 and 2,
Configuration Risk Management Program determined for all fuel types at all times Brunswick County, North Carolina
(CRMP) to assure that adequate margins of during the fuel cycle.
safety are maintained. Application of these As a result, the proposed change does not Duke Energy Progress, LLC, Docket No.
new specifications and the CRMP considers adversely affect the consequences of any 50–261, H. B. Robinson Steam Electric
cumulative effects of multiple systems or accident previously evaluated. Plant, Unit No. 2 (RNP), Darlington
components being out of service and does so Therefore, the proposed change does not County, South Carolina
more effectively than the current TS. In this involve a significant increase in the
regard, the implementation of the CRMP is probability or consequences of an accident Duke Energy Progress, LLC, Docket No.
considered an improvement in safety. previously evaluated. 50–400, Shearon Harris Nuclear Power
Therefore, the proposed change does not 2. Does the proposed change create the Plant, Unit 1 (HNP), Wake County,
involve a significant reduction in a margin of possibility of a new or different kind of North Carolina
safety. accident from any accident previously
evaluated? Date of amendment request: June 20,
The NRC staff has reviewed the Response: No. 2018. A publicly-available version is in
licensee’s analysis and, based on that The proposed change revises the definition ADAMS under Accession No.
review, it appears that the three of SDM. The change does not involve a ML18172A315.
standards of 10 CFR 50.92(c) are physical alteration of the plant (i.e., no new Description of amendment request:
satisfied. Therefore, the NRC staff or different type of equipment will be The amendments would revise the
proposes to determine that the installed) or a change in the methods Emergency Action Levels (EALs) for
governing normal plant operations. The
requested amendments involves no CNS, MNS, ONS, BNP, HNP, and RNP
change does not alter assumptions made in
significant hazards consideration. the safety analysis regarding SDM. consistent with Emergency
Attorney for licensee: Michael G. Therefore, the proposed change does not Preparedness Frequently Asked
Green, Senior Regulatory Counsel, create the possibility of a new or different Questions (EPFAQs) 2015–013 (EAL
Pinnacle West Capital Corporation, P.O. kind of accident from any accident HG1.1) and 2016–002 (EALs CA6.1 and
Box 52034, Mail Station 8695, Phoenix, previously evaluated. SA9.1 (SA8.1 for BNP)). The
Arizona 85072–2034. 3. Does the proposed change involve a amendments would revise the EALs for
NRC Branch Chief: Robert J. significant reduction in a margin of safety? HNP and RNP consistent with EPFAQ
Pascarelli. Response: No.
2015–014 (EAL HS6.1).
The proposed change revises the definition
DTE Electric Company, Docket No. 50– of SDM. The proposed change does not alter
Basis for proposed no significant
341, Fermi 2, Monroe County, Michigan the manner in which safety limits, limiting hazards consideration determination:
safety system settings or limiting conditions As required by 10 CFR 50.91(a), the
Date of amendment request: March for operation are determined. The proposed licensee has provided its analysis of the
14, 2018. A publicly-available version is change ensures that the SDM assumed in issue of no significant hazards
in ADAMS under Accession No. determining safety limits, limiting safety consideration, which is presented
ML18073A137. system settings or limiting conditions for below:
Description of amendment request: operation is correct for all BWR fuel types at
The proposed amendment modifies the all times during the fuel cycle. Therefore, the 1. Does the proposed change involve a
proposed change does not involve a significant increase in the probability or
technical specification definition of consequences of an accident previously
‘‘Shutdown Margin’’ (SDM) to require significant reduction in a margin of safety.
evaluated?
calculation of the SDM at a reactor The NRC staff has reviewed the Response: No.
moderator temperature of 68 degrees licensee’s analysis and based on this The proposed changes to EALs HG1.1,
Fahrenheit (°F) per hour or a higher review, it appears that the three CA6.1, SA9.1 (SA8.1 for BNP), and HS6.1 do
temperature that represents the most standards of 10 CFR 50.92(c) are not reduce the capability to meet the
reactive state throughout the operating satisfied. Therefore, the NRC staff emergency planning requirements
amozie on DSK3GDR082PROD with NOTICES1
cycle. This change is needed to address proposes to determine that the established in 10 CFR 50.47 and 10 CFR
[Part] 50, Appendix E. The proposed changes
new boiling water reactor (BWR) fuel amendment request involves no do not reduce the functionality, performance,
designs, which may be more reactive at significant hazards consideration. or capability of Duke Energy’s Emergency
shutdown temperatures above 68 °F. Attorney for licensee: Jon P. Response Organization (ERO) to respond in
Basis for proposed no significant Christinidis, DTE Energy, Expert mitigating the consequences of any design
hazards consideration determination: Attorney—Regulatory, 688 WCB, One basis accident. The proposed changes do not
As required by 10 CFR 50.91(a), the Energy Plaza, Detroit, MI 48226–1279. involve any physical changes to plant
VerDate Sep<11>2014 19:13 Aug 13, 2018 Jkt 244001 PO 00000 Frm 00135 Fmt 4703 Sfmt 4703 E:\FR\FM\14AUN1.SGM 14AUN1](https://thefederalregister.org/doc/83_FR_40499/page/5.svg)
![Federal Register / Vol. 83, No. 157 / Tuesday, August 14, 2018 / Notices 40347
equipment or systems, nor do they alter the review, it appears that the three probability or consequences of an accident
assumptions of any accident analyses. The standards of 10 CFR 50.92(c) are previously evaluated.
proposed changes do not adversely affect satisfied. Therefore, the NRC staff 2. Does the proposed amendment create
accident initiators or precursors nor do they the possibility of a new or different kind of
proposes to determine that the
alter the design assumptions, conditions, and accident from any accident previously
configuration or the manner in which the amendment request involves no
significant hazards consideration. evaluated?
plants are operated and maintained. The Response: No.
proposed changes do not adversely affect the Attorney for licensee: Kathryn B.
Nolan, Deputy General Counsel, Duke The proposed amendment would revise a
ability of Structures, Systems, or Components
TS SR to include, for each degraded voltage
(SSCs) to perform their intended safety Energy Corporation, 550 South Tryon
functions in mitigating the consequences of channel, calibration of the time delay
Street, Mail Code DEC45A, Charlotte NC
an initiating event within the assumed setpoint for the degraded voltage sensing
28202. relay in combination with the time delay
acceptance limits. There is no impact on the NRC Acting Branch Chief: Booma
source term or pathways assumed in setpoint for the time delay relay. The conduct
Venkatamaraman. of surveillance tests on safety related plant
accidents previously assumed. No analysis
assumptions are violated and there are no Entergy Nuclear Operations, Inc., equipment is a means of assuring that the
adverse effects on the factors that contribute Docket No. 50–255, Palisades Nuclear equipment is capable of performing its
to offsite or onsite dose as the result of an Plant (PNP), Van Buren County, functions that are credited in the safety
accident. analyses for the facility. The proposed
Michigan
Therefore, the proposed changes do not amendment would not affect the operation of
involve a significant increase in the Date of amendment request: May 30, safety related equipment assumed in accident
probability or consequences of an accident 2018. A publicly-available version is in analyses, and would not create any new
previously evaluated. ADAMS under Accession No. failure mechanisms, malfunctions, or
2. Does the proposed change create the ML18152A922. accident initiators not considered in the
possibility of a new or different kind of Description of amendment request: design and licensing bases.
accident from any accident previously
The proposed amendment would revise Therefore, the possibility of a new or
evaluated?
Response: No. the PNP Technical Specification (TS) different kind of accident from any
The proposed changes to EALs HG1.1, 3.3.5, ‘‘Diesel Generator (DG)— previously evaluated has not been created.
CA6.1, SA9.1 (SA8.1 for BNP), and HS6.1 do Undervoltage Start (UV Start),’’ 3. Does the proposed amendment involve
not involve any physical changes to plant Surveillance Requirement (SR) 3.3.5.2a a significant reduction in a margin of safety?
systems or equipment. The proposed changes by adding a channel calibration Response: No.
do not involve the addition of any new plant requirement for the combined time The proposed amendment would revise a
equipment. The proposed changes will not delay setpoints for the degraded voltage TS SR to include, for each degraded voltage
alter the design configuration, or method of channel, calibration of the time delay
sensing relay and the degraded voltage
operation of plant equipment beyond its setpoint for the degraded voltage sensing
normal functional capabilities. All Duke time delay relay.
Basis for proposed no significant relay in combination with the time delay
Energy ERO functions will continue to be setpoint for the time delay relay. The conduct
performed as required. The proposed changes hazards consideration determination:
of surveillance tests on safety related plant
do not create any new credible failure As required by 10 CFR 50.91(a), the
equipment is a means of assuring that the
mechanisms, malfunctions, or accident licensee has provided its analysis of the equipment is capable of maintaining the
initiators. issue of no significant hazards margin of safety established in the safety
Therefore, the proposed changes do not consideration, which is presented
create the possibility of a new or different analyses for the facility. The proposed
below: amendment would not introduce changes to
kind of accident from any accident
previously evaluated. 1. Does the proposed amendment involve limits established in the accident analyses.
3. Does the proposed change involve a a significant increase in the probability or The minimum time delay setpoint in the
significant reduction in a margin of safety? consequences of an accident previously revised TS SR would be long enough to
Response: No. evaluated? override any brief voltage disturbances. The
Margin of safety is related to the Response: No. maximum time delay setpoint in the revised
confidence in the ability of the fission The proposed amendment would revise a TS SR would be short enough to not exceed
product barriers to perform their design TS SR to include, for each degraded voltage the maximum time delays assumed in the
functions during and following an accident. channel, calibration of the time delay PNP Final Safety Analysis Report accident
These barriers include the fuel cladding, the setpoint for the degraded voltage sensing analyses for the operation of safety related
reactor coolant system, and the containment relay in combination with the setpoint for the
equipment and to not result in failure of
system. time delay relay. The minimum time delay
setpoint in the revised TS SR would be long safety related equipment due to sustained
The proposed changes to EALs HG1.1, degraded voltage conditions.
CA6.1, SA9.1 (SA8.1 for BNP), and HS6.1 do enough to override any brief voltage
disturbances. The maximum time delay Therefore, the proposed amendment does
not alter or exceed a design basis or safety not involve a significant reduction in a
limit. There is no change being made to setpoint in the revised TS SR would be short
enough to not exceed the maximum time margin of safety.
safety analysis assumptions, safety limits, or
limiting safety system settings that would delays assumed in the PNP Final Safety
Analysis Report accident analyses for the The NRC staff has reviewed the
adversely affect plant safety as a result of the
proposed changes. There are no changes to operation of safety related equipment and to licensee’s analysis and, based on this
setpoints or environmental conditions of any not result in failure of safety related review, it appears that the three
SSC or the manner in which any SSC is equipment due to sustained degraded voltage standards of 10 CFR 50.92(c) are
operated. Margins of safety are unaffected by conditions. Therefore, safety related loads satisfied. Therefore, the NRC staff
the proposed changes. The applicable would be available to perform their required proposes to determine that the
requirements of 10 CFR 50.47 and 10 CFR safety functions under these conditions.
amendment request involves no
amozie on DSK3GDR082PROD with NOTICES1
[Part] 50, Appendix E will continue to be The proposed change does not adversely
affect accident initiators or precursors, and significant hazards consideration.
met.
Therefore, the proposed changes do not does not affect the design assumptions, Attorney for licensee: Anna Jones,
involve a significant reduction in a margin of conditions, or configuration of the plant, or Senior Counsel, Entergy Services, Inc.,
safety. the manner in which the plant is operated or 101 Constitution Ave., NW,
maintained.
The NRC staff has reviewed the Therefore, the proposed amendment does
Washington, DC 20001.
licensee’s analysis and, based on this not involve a significant increase in the NRC Branch Chief: David J. Wrona.
VerDate Sep<11>2014 19:13 Aug 13, 2018 Jkt 244001 PO 00000 Frm 00136 Fmt 4703 Sfmt 4703 E:\FR\FM\14AUN1.SGM 14AUN1](https://thefederalregister.org/doc/83_FR_40499/page/6.svg)
![40348 Federal Register / Vol. 83, No. 157 / Tuesday, August 14, 2018 / Notices
Exelon Generation Company, LLC, conservatively with respect to the calculated standards of 10 CFR 50.92(c) are
Docket No. 50–461, Clinton Power heat balance. This is because the actual core satisfied. Therefore, the NRC staff
Station, Unit No. 1, DeWitt County, thermal power at which the reactor will proposes to determine that the
Illinois automatically trip is lower, thereby requested amendments involve no
increasing the margin to the core thermal
Exelon Generation Company, LLC, limits and the limiting safety system settings
significant hazards consideration.
assumed in the safety analyses. The Attorney for licensee: Tamra Domeyer,
Docket Nos. 50–237 and 50–249,
consequences of an accident during the Associate General Counsel, Exelon
Dresden Nuclear Power Station, Unit
adjustment of the APRM instrumentation are Generation Company, LLC, 4300
Nos. 2 and 3, Grundy County, Illinois
no different from those during the existing Winfield Road, Warrenville, IL 60555.
Exelon Generation Company, LLC and surveillance testing period or the existing NRC Branch Chief: David J. Wrona.
Exelon FitzPatrick, LLC, Docket No. 50– time allowed to restore the instruments to
333, James A. FitzPatrick Nuclear Power operable status. As a result, the ability of the Exelon Generation Company, LLC,
Plant, Oswego County, New York APRM system and the RPS to mitigate any Docket Nos. 50–373 and 50–374, LaSalle
accident previously evaluated is not County Station, Unit Nos. 1 and 2,
Exelon Generation Company, LLC, significantly affected. LaSalle County, Illinois
Docket Nos. 50–373 and 50–374, LaSalle Therefore, the proposed changes do not Date of amendment request: April 19,
County Station, Unit Nos. 1 and 2, involve a significant increase in the
2018. A publicly-available version is in
LaSalle County, Illinois probability or consequences of an accident
previously evaluated. ADAMS under Accession No.
Exelon Generation Company, LLC, 2. Does the proposed change create the ML18157A123.
Docket Nos. 50–352 and No. 50–353, possibility of a new or different kind of Description of amendment request:
Limerick Generating Station, Unit Nos. accident from any accident previously The amendments would revise licenses
1 and 2, Montgomery County, evaluated? and the technical specifications (TSs) as
Pennsylvania Response: No. follows:
The proposed changes do not alter the • Division 3 Battery Surveillance
Exelon Generation Company, LLC, protection system designs, create new failure
Docket Nos. 50–220 and 50–410, Nine modes, or change any modes of operation.
Testing
Mile Point Nuclear Station, Unit Nos. 1 The proposed change does not involve a The proposed amendments would
and 2, Oswego County, New York physical alteration of the plant; no new or revise TS 3.8.4, ‘‘DC Sources-
different kind of equipment will be installed. Operating,’’ and TS 3.8.6, ‘‘Battery
Exelon Generation Company, LLC, and
Consequently, there are no new initiators that Parameters,’’ by removing the Mode
PSEG Nuclear LLC, Docket Nos. 50–277 could result in a new or different kind of
and 50–278, Peach Bottom Atomic restrictions for performance of TS
accident.
Power Station, Unit Nos. 2 and 3, York Therefore, the proposed changes do not surveillance requirements (SRs) 3.8.4.3
and Lancaster Counties, Pennsylvania create the possibility of a new or different and 3.8.6.6 for the Division 3 direct
kind of accident from any previously current (DC) electrical power subsystem
Exelon Generation Company, LLC, battery. The Division 3 DC electrical
evaluated.
Docket Nos. 50–254 and 50–265, Quad 3. Does the proposed change involve a power subsystem feeds emergency DC
Cities Nuclear Power Station, Unit Nos. significant reduction in a margin of safety? loads associated with the high pressure
1 and 2, Rock Island County, Illinois Response: No. core spray (HPCS) system. Surveillance
Date of amendment request: June 15, The margin of safety provided by the Requirement 3.8.4.3 verifies that the
2018. A publicly-available version is in APRM system and the RPS is to ensure that
battery capacity is adequate for the
the reactor is shut down automatically when
ADAMS under Accession No. plant parameters exceed the setpoints for the battery to perform its required
ML18166A197. system. Any reduction in the margin of safety functions. Surveillance Requirement
Description of amendment request: resulting from the adjustment of the APRM 3.8.6.6 verifies battery capacity is
The amendments would revise the channels while continuing operation is greater than or equal to (≥) 80 percent
technical specification (TS) considered to be offset by delaying a plant of the manufacturer’s rating when
requirements associated with the shutdown (i.e., a transient) for a short time subjected to a performance discharge
average power range monitors (APRMs). with the APRM system, the primary test (or a modified performance
Basis for proposed no significant indication of core power and an input to the discharge test). The proposed
hazards consideration determination: RPS, not calibrated. Additionally, the short
amendments would remove these Mode
As required by 10 CFR 50.91(a), the time period required for adjustment is
consistent with the time allowed by TS to restrictions for the Division 3 battery,
licensee has provided its analysis of the allowing performance of SRs 3.8.4.3 and
restore the core power distribution
issue of no significant hazards parameters to within limits and is acceptable 3.8.6.6 for the Division 3 battery during
consideration, which is presented based on the low probability of a transient or Mode 1 or 2, potentially minimizing
below: design basis accident occurring impact on HPCS unavailability.
1. Does the proposed change involve a simultaneously with inaccurate APRM Eliminating the requirement to perform
significant increase in the probability or channels. SRs 3.8.4.3 and 3.8.6.6 only during
consequences of an accident previously The proposed changes do not alter
evaluated? Mode 3, 4, or 5 (hot shutdown, cold
setpoints or limits established or assumed by
Response: No. shutdown, or refueling conditions) will
the accident analyses. The TS continue to
The APRM system and the RPS [reactor require operability of the RPS functions, provide greater flexibility in scheduling
protection system] are not initiators of any which provide core protection for postulated Division 3 battery testing activities by
accidents previously evaluated. As a result, reactivity insertion events occurring during allowing the testing to be performed
the proposed change does not affect the power operating conditions consistent with during non-outage times.
amozie on DSK3GDR082PROD with NOTICES1
probability of any accident previously the plant safety analyses. • High Pressure Core Spray Diesel
evaluated. The APRM system and the RPS Therefore, the proposed changes do not
functions act to mitigate the consequences of
Generator Surveillance Testing
involve a significant reduction in a margin of The proposed amendments would
accidents previously evaluated. The safety.
reliability of the APRM system and the RPS revise TS 3.8.1, ‘‘AC Sources-
is not significantly affected by removing the The NRC staff has reviewed the Operating,’’ by revising certain SRs
gain adjustment requirement on the APRM licensee’s analysis and, based on this pertaining to the Division 3 diesel
channels when the APRMs are calibrated review, it appears that the three generator (DG). The Division 3 DG is an
VerDate Sep<11>2014 19:13 Aug 13, 2018 Jkt 244001 PO 00000 Frm 00137 Fmt 4703 Sfmt 4703 E:\FR\FM\14AUN1.SGM 14AUN1](https://thefederalregister.org/doc/83_FR_40499/page/7.svg)
![40350 Federal Register / Vol. 83, No. 157 / Tuesday, August 14, 2018 / Notices
informed Completion Times. The function of the affected systems is not Table S–2, of the PINGP license
amendments would also add a new changed and the consequences of an accident amendment request (LAR) dated
program, the Risk Informed Completion [occurring] during the extended Completion December 14, 2016, to adopt the
Time (RICT) Program, to TS Section 6.0, Time are no different from those [occurring] National Fire Protection Association
during the existing Completion Time.
‘‘Administrative Controls.’’ The 2. Does the proposed change create the
Standard (NFPA) 805. Specifically,
methodology for using the Risk possibility of a new or different kind of NSPM is requesting the deletion of five
Informed Completion Time Program is accident from any accident previously modifications from Table S–2 of the
described in Nuclear Energy Institute evaluated? December 14, 2016, LAR.
(NEI) topical report NEI 06–09, ‘‘Risk- Response: No. Basis for proposed no significant
Informed Technical Specifications The proposed change does not change the hazards consideration determination:
Initiative 4b, Risk-Managed Technical design, configuration, or method of operation As required by 10 CFR 50.91(a), the
Specifications (RMTS) Guidelines,’’ of the plant. The proposed change does not licensee has provided its analysis of the
Revision 0–A (ADAMS Accession No. involve a physical alteration of the plant (no issue of no significant hazards
new or different kind of equipment will be
ML12286A322), which was approved by consideration, which is presented
installed).
the NRC on May 17, 2007. The license Therefore, the proposed change does not below:
amendment request was originally 1. Does the proposed amendment involve
create the possibility of a new or different
noticed in the Federal Register on a significant increase in the probability or
kind of accident from any accident
March 17, 2015 (80 FR 13908). The consequences of an accident previously
previously evaluated.
evaluated?
licensee originally proposed to adopt, 3. Does the proposed change involve a
Response: No.
with plant specific variations, Technical significant reduction in a margin of safety? The proposed amendment adds a reference
Specifications Task Force (TSTF) Response: No. to this letter to the PINGP, Units 1 and 2,
Traveler TSTF–505, Revision 1, The proposed change permits the RFOLs. The changes encompassed by this
extension of Completion Times provided risk proposed amendment are to delete five
‘‘Provide Risk-Informed Extended
is assessed and managed in accordance with modifications that are no longer needed from
Completion Times—RITSTF [Risk the NRC[-]approved Risk Informed
Informed TSTF] Initiative 4b’’ a risk perspective. The revision is based on
Completion Time Program. The proposed five changes to Table S–2 proposed in this
(Accession No. ML111650552). By letter change implements a risk-informed license amendment request (LAR). The
dated November 15, 2016 (ADAMS configuration management program to assure proposed changes have been reviewed in the
Accession No. ML16281A021), the NRC that adequate margins of safety are fire Probabilistic Risk Assessment (PRA)
staff informed the TSTF of its decision maintained. Application of these new model approved as part of PINGP’s transition
to suspend NRC approval of TSTF–505, specifications and the configuration to NFPA 805 and the results were found to
Revision 1, because of concerns management program considers cumulative be acceptable. Fire protection defense in
effects of multiple systems or components depth and adequate safety margins are
identified during the review of plant-
being out of service and does so more maintained with the changes proposed in
specific license amendment requests for effectively than the current TS. this LAR.
adoption of the traveler. The NRC staff’s Therefore, the proposed change does not The proposed change does not adversely
letter also stated that it would continue involve a significant reduction in a margin of affect accident initiators or precursors, nor
reviewing applications already received safety. alter the design assumptions, conditions, and
and site-specific proposals to address configuration of the facility or the manner in
The NRC staff has reviewed the
the staff’s concerns. Although the scope which the plant is operated and maintained.
licensee’s analysis and, based on this The proposed changes do not adversely affect
of the amendment request has not
review, it appears that the three the ability of structures, systems and
changed, the basis for the amendments
standards of 10 CFR 50.92(c) are components (SSCs) to perform their intended
will no longer rely on TSTF–505. The
satisfied. Therefore, the NRC staff safety function to mitigate the consequences
notice is being reissued in its entirety to
proposes to determine that the of an initiating event within the assumed
include the description of the acceptance limits. The proposed change does
amendment request involves no
amendment request and proposed no not increase the probability or consequences
significant hazards consideration.
significant hazards consideration Attorney for licensee: Debbie Hendell, of an accident as verified by the risk analysis
determination. Managing Attorney—Nuclear, Florida performed.
Basis for proposed no significant Therefore, the proposed change does not
Power & Light Company, 700 Universe involve a significant increase in the
hazards consideration determination:
Blvd. MS LAW/JB, Juno Beach, Florida probability or consequences of an accident
As required by 10 CFR 50.91(a), the
33408–0420. previously evaluated.
licensee has provided its analysis of the
NRC Acting Branch Chief: Booma 2. Does the proposed amendment create
issue of no significant hazards
Venkataraman. the possibility of a new or different kind of
consideration, which is presented accident from any previously evaluated?
below: Northern States Power Company Response: No.
1. Does the proposed change involve a (NSPM), Docket Nos. 50–282 and 50– The proposed amendment adds a reference
significant increase in the probability or 306, Prairie Island Nuclear Generating to this letter to the PINGP, Units 1 and 2,
consequences of an accident previously Plant, Unit Nos. 1 and 2, (PINGP) RFOLs. The changes encompassed by this
evaluated? Goodhue County, Minnesota proposed amendment are to delete five
Response: No. modifications that are no longer needed from
The proposed change permits the Date of amendment request: May 18, a risk perspective. The revision is based on
extension of Completion Times provided the 2018. A publicly-available version is in five changes to Table S–2 proposed in this
associated risk is assessed and managed in ADAMS under Accession No. LAR. The proposed changes have been
accordance with the NRC[-]approved Risk ML18138A402. reviewed in the fire PRA model approved as
amozie on DSK3GDR082PROD with NOTICES1
Informed Completion Time Program. The Brief description of amendment part of PINGP’s transition to NFPA 805 and
proposed change does not involve a request: The proposed amendments the results were found to be acceptable. Fire
significant increase in the probability of an protection defense in depth and adequate
would modify paragraph 2.C(4)(c) of the safety margins are maintained with the
accident previously evaluated because the
change involves no change to the plant or its PINGP Renewed Facility Operating changes proposed in this LAR.
modes of operation. The proposed change Licenses (RFOLs) which requires the The proposed changes will not result in
does not increase the consequences of an implementation of modification to any new or different kinds of accident from
accident because the design-basis mitigation PINGP as described in Attachment S, that previously evaluated because it does not
VerDate Sep<11>2014 19:13 Aug 13, 2018 Jkt 244001 PO 00000 Frm 00139 Fmt 4703 Sfmt 4703 E:\FR\FM\14AUN1.SGM 14AUN1](https://thefederalregister.org/doc/83_FR_40499/page/9.svg)
![Federal Register / Vol. 83, No. 157 / Tuesday, August 14, 2018 / Notices 40351
change any precursors or equipment that is issue of no significant hazards standards of 10 CFR 50.92(c) are
previously credited for accident mitigation. consideration, which is presented satisfied. Therefore, the NRC staff
Therefore, the proposed changes do not below: proposes to determine that the
create the possibility of a new or different
kind of accident from any accident 1. Does the proposed amendment involve amendment request involves no
previously evaluated. a significant increase in the probability or significant hazards consideration.
3. Does the proposed amendment involve consequences of an accident previously Attorney for licensee: Peter M. Glass,
a significant reduction in a margin of safety? evaluated? Assistant General Counsel, Xcel Energy
Response: No. Response: No. Services, Inc., 414 Nicollet Mall,
The proposed amendment adds a reference The proposed change eliminates second Minneapolis, MN 55401.
to this letter to the PINGP, Units 1 and 2, Completion Times from the Technical
RFOLs. The changes encompassed by this Specifications. Completion Times are not an NRC Branch Chief: David J. Wrona.
proposed amendment are to delete five initiator to any accident previously PSEG Nuclear LLC, Docket No. 50–354,
modifications that are no longer needed from evaluated. As a result, the probability of an Hope Creek Generating Station, Salem
a risk perspective. The revision is based on accident previously evaluated is not affected.
The consequences of an accident during the
County, New Jersey
five changes to Table S–2 proposed in this
LAR. The proposed changes have been revised Completion Time are no different PSEG Nuclear LLC and Exelon
reviewed in the fire PRA model approved as than the consequences of the same accident Generation Company, LLC, Docket Nos.
part of PINGP’s transition to NFPA 805 and during the existing Completion Times. As a 50–272 and 50–311, Salem Nuclear
the results were found to be acceptable. Fire result, the consequences of an accident
Generating Station, Unit Nos. 1 and 2,
protection defense in depth and adequate previously evaluated are not affected by this
safety margins are maintained with the change. The proposed change does not alter Salem County, New Jersey
changes proposed in this LAR. or prevent the ability of SSCs [structures, Date of amendment request: June 29,
The proposed change does not adversely systems, and components] from performing 2018. A publicly-available version is in
affect any SSCs credited for accident their intended function to mitigate the
consequences of an initiating event within
ADAMS under Accession No.
mitigation. The margins of safety previously
evaluated are not significantly affected. The the assumed acceptance limits. The proposed ML18183A343.
change does not affect the design function or change does not affect the source term, Description of amendment request:
capabilities of any plant systems. containment isolation, or radiological release The amendments would revise technical
Therefore, the proposed changes will not assumptions used in evaluating the specification (TS) requirements in
impact or reduce any margins of safety radiological consequences of an accident Section 3/4.0, ‘‘Applicability,’’
previously evaluated. previously evaluated. Further, the proposed regarding Limiting Condition for
change does not increase the types or
The NRC staff has reviewed the Operation (LCO) and Surveillance
amounts of radioactive effluent that may be
licensee’s analysis and, based on this released offsite nor significantly increase Requirement (SR) usage. These changes
review, it appears that the three individual or cumulative occupational/ are consistent with NRC-approved
standards of 10 CFR 50.92(c) are public radiation exposures. The proposed Technical Specifications Task Force
satisfied. Therefore, the NRC staff change is consistent with the safety analysis (TSTF) Traveler TSTF–529, ‘‘Clarify Use
proposes to determine that the assumptions and resultant consequences. and Application Rules.’’
amendment request involves no Therefore, the proposed change does not Basis for proposed no significant
significant hazards consideration. involve a significant increase in the hazards consideration determination:
probability or consequences of an accident
Attorney for licensee: Peter M. Glass, As required by 10 CFR 50.91(a), the
previously evaluated.
Assistant General Counsel, Xcel Energy 2. Does the proposed amendment create licensee has provided its analysis of the
Services, Inc., 414 Nicollet Mall, the possibility of a new or different kind of issue of no significant hazards
Minneapolis, MN 55401. accident from any previously evaluated? consideration, which is presented
NRC Branch Chief: David J. Wrona. Response: No. below:
The proposed change does not involve a
Northern States Power Company, physical alteration of the plant (i.e., no new
1. Does the proposed change involve a
Docket Nos. 50–282 and 50–306, Prairie significant increase in the probability or
or different type of equipment will be
Island Nuclear Generating Plant, Unit consequences of an accident previously
installed) or a change in the methods
Nos. 1 and 2, (PINGP) Goodhue County, evaluated?
governing normal plant operation. The
Response: No.
Minnesota proposed change does not alter any
assumptions made in the safety analysis. The proposed changes to LCO 3.0.4 have
Date of amendment request: June 26, Therefore, the proposed changes do not no effect on the requirement for systems to
2018. A publicly-available version is in create the possibility of a new or different be Operable and have no effect on the
ADAMS under Accession No. kind of accident from any accident application of TS actions. The proposed
ML18177A450. previously evaluated. change to SR 4.0.3 states that the allowance
Brief description of amendment 3. Does the proposed amendment involve may only be used when there is a reasonable
request: The proposed amendments a significant reduction in a margin of safety? expectation the surveillance will be met
Response: No. when performed. Since the proposed changes
would revise PINGP Technical do not significantly affect system Operability,
Specifications (TSs) by eliminating The proposed change to delete the second
Completion Time does not alter the manner the proposed changes will have no
second Completion Times limiting time significant effect on the initiating events for
in which safety limits, limiting safety system
from discovery of failure to meet a settings, or limiting conditions for operation accidents previously evaluated and will have
limiting condition for operation (LCO). are determined. The safety analysis no significant effect on the ability of the
These changes are consistent with NRC- acceptance criteria are not affected by this systems to mitigate accidents previously
approved Technical Specifications Task change. The proposed change will not result evaluated.
Force (TSTF) Traveler TSTF–439, in plant operation in a configuration outside Therefore, it is concluded that this change
amozie on DSK3GDR082PROD with NOTICES1
Revision 2, ‘‘Eliminate Second of the design basis. does not involve a significant increase in the
Therefore, the proposed changes do not probability or consequences of an accident
Completion Times Limiting Time from previously evaluated.
Discovery of Failure to Meet an LCO.’’ involve a significant reduction in a margin of
safety. 2. Does the proposed change create the
Basis for proposed no significant possibility of a new or different kind of
hazards consideration determination: The NRC staff has reviewed the accident from any accident previously
As required by 10 CFR 50.91(a), the licensee’s analysis and, based on this evaluated?
licensee has provided its analysis of the review, it appears that the three Response: No.
VerDate Sep<11>2014 19:13 Aug 13, 2018 Jkt 244001 PO 00000 Frm 00140 Fmt 4703 Sfmt 4703 E:\FR\FM\14AUN1.SGM 14AUN1](https://thefederalregister.org/doc/83_FR_40499/page/10.svg)
![Federal Register / Vol. 83, No. 157 / Tuesday, August 14, 2018 / Notices 40353
For details, see the individual notice For further details with respect to the indicate that the RAPTOR–M3G code is
in the Federal Register on the day and action see (1) the applications for used for reactor vessel fluence
page cited. This notice does not extend amendment, (2) the amendment, and (3) calculations. The use of the RAPTOR–
the notice period of the original notice. the Commission’s related letter, Safety M3G code meets the criteria present in
Evaluation and/or Environmental Regulatory Guide (RG) 1.190,
Exelon Generation Company, LLC and
Assessment as indicated. All of these ‘‘Calculational and Dosimetry Methods
Exelon FitzPatrick, LLC, Docket No. 50–
items can be accessed as described in for Determining Pressure Vessel
333, James A. FitzPatrick Nuclear Power
the ‘‘Obtaining Information and Neutron Fluence,’’ dated March 2001.
Plant, Oswego County, New York
Submitting Comments’’ section of this Date of issuance: July 23, 2018.
Date of amendment request: May 17, document. Effective date: As of the date of
2018. A publicly-available version is in issuance and shall be implemented 30
ADAMS under Accession No. DTE Electric Company, Docket No. 50–
341, Fermi 2, Monroe County, Michigan days from the date of issuance.
ML18137A418. Amendment No.: 252. A publicly-
Brief description of amendment Date of amendment request: July 17, available version is in ADAMS under
request: The proposed amendment 2017, as supplemented by letter dated Accession No. ML18180A298;
would revise Technical Specifications January 8, 2018. documents related to this amendment
2.1.1, ‘‘Reactor Core SLs [safety limits]’’ Brief description of amendment: The are listed in the Safety Evaluation
to change Cycle 24 Safety Limit amendment revised Fermi 2 Technical enclosed with the amendment.
Minimum Critical Power Ratio Specification (TS) 3.7.2, ‘‘Emergency Facility Operating License No. NPF–
(SLMCPR) numeric values resulting Equipment Cooling Water (EECW)/ 38: The amendment revised the
from SLMCPR analyses performed. Emergency Equipment Service Water Updated Final Safety Analysis Report.
Date of publication of individual (EESW) System and Ultimate Heat Sink Date of initial notice in Federal
notice in Federal Register: July 13, (UHS).’’ Specifically, the amendment Register: January 16, 2018 (83 FR
2018 (83 FR 32691). revised TS 3.7.2 conditions and
Expiration date of individual notice: 2228). The supplement dated May 8,
surveillance requirements to reflect a 2018, provided additional information
August 13, 2018 (public comments); proposed change to the design of the
September 11, 2018 (hearing requests). that clarified the application, did not
two redundant cross-tie lines that are expand the scope of the application as
IV. Notice of Issuance of Amendments part of the UHS. originally noticed, and did not change
to Facility Operating Licenses and Date of issuance: July 17, 2018. the NRC staff’s original proposed no
Combined Licenses Effective date: As of the date of
significant hazards consideration
issuance and shall be implemented
During the period since publication of determination as published in the
within 120 days of issuance.
the last biweekly notice, the Federal Register.
Amendment No.: 209. A publicly-
Commission has issued the following available version is in ADAMS under The Commission’s related evaluation
amendments. The Commission has Accession No. ML18144A064; of the amendment is contained in a
determined for each of these documents related to this amendment Safety Evaluation dated July 23, 2018.
amendments that the application are listed in the Safety Evaluation No significant hazards consideration
complies with the standards and enclosed with the amendment. comments received: No.
requirements of the Atomic Energy Act Renewed Facility Operating License Exelon Generation Company, LLC and
of 1954, as amended (the Act), and the No. NPF–43: Amendment revised the Exelon FitzPatrick, LLC, Docket No. 50–
Commission’s rules and regulations. Renewed Facility Operating License and 333, James A. FitzPatrick Nuclear Power
The Commission has made appropriate Technical Specifications. Plant, Oswego County, New York
findings as required by the Act and the Date of initial notice in Federal
Commission’s rules and regulations in Register: September 26, 2017 (82 FR Date of amendment request:
10 CFR chapter I, which are set forth in 44850). The supplemental letter dated September 14, 2017, as supplemented
the license amendment. January 8, 2018, provided additional by letter dated March 15, 2018.
A notice of consideration of issuance information that clarified the Brief description of amendment: The
of amendment to facility operating application, did not expand the scope of amendment revised Technical
license or combined license, as the application as originally noticed, Specification (TS) 3.6.4.1, ‘‘Secondary
applicable, proposed no significant and did not change the NRC staff’s Containment,’’ Surveillance
hazards consideration determination, original proposed no significant hazards Requirement (SR) 3.6.4.1.3. The SR is
and opportunity for a hearing in consideration determination as revised to address conditions during
connection with these actions, was published in the Federal Register. which the secondary containment
published in the Federal Register as The Commission’s related evaluation pressure may not meet the SR pressure
indicated. of the amendment is contained in a requirements.
Unless otherwise indicated, the Safety Evaluation dated July 17, 2018. Date of issuance: July 19, 2018.
Commission has determined that these No significant hazards consideration Effective date: As of the date of
amendments satisfy the criteria for comments received: No. issuance, and shall be implemented
categorical exclusion in accordance within 60 days.
with 10 CFR 51.22. Therefore, pursuant Entergy Operations, Inc., Docket No. 50– Amendment No.: 319. A publicly-
to 10 CFR 51.22(b), no environmental 382, Waterford Steam Electric Station, available version is in ADAMS under
impact statement or environmental Unit No. 3, St. Charles Parish, Louisiana Accession No. ML18180A372;
amozie on DSK3GDR082PROD with NOTICES1
assessment need be prepared for these Date of amendment request: documents related to this amendment
amendments. If the Commission has November 28, 2017, as supplemented by are listed in the Safety Evaluation
prepared an environmental assessment letters dated December 7, 2017, and May enclosed with the amendment.
under the special circumstances 8, 2018. Renewed Facility Operating License
provision in 10 CFR 51.22(b) and has Brief description of amendment: The No. DPR–59: The amendment revised
made a determination based on that amendment revised Section 4.3.3 of the the Renewed Facility Operating License
assessment, it is so indicated. Updated Final Safety Analysis Report to and TSs.
VerDate Sep<11>2014 19:13 Aug 13, 2018 Jkt 244001 PO 00000 Frm 00142 Fmt 4703 Sfmt 4703 E:\FR\FM\14AUN1.SGM 14AUN1](https://thefederalregister.org/doc/83_FR_40499/page/12.svg)
![Federal Register / Vol. 83, No. 157 / Tuesday, August 14, 2018 / Notices 40355
classification level. The changes also Renewed Facility Operating License Borges; telephone: 301–287–9127;
include formatting, clarification, and Nos. NPF–4 and NPF–7: Amendments email: Jennifer.Borges@nrc.gov. For
editorial modifications. revised the Renewed Facility Operating technical questions, contact the
Date of issuance: July 19, 2018. Licenses and Technical Specifications. individual listed in the FOR FURTHER
Effective date: As of the date of Date of initial notice in Federal INFORMATION CONTACT section of this
issuance and shall be implemented Register: March 6, 2018 (83 FR 9553). document.
within 9 months from the date of The supplemental letters dated July 19, • NRC’s Agencywide Documents
issuance. 2017, and January 31, 2018, provided Access and Management System
Amendment Nos.: 214 (Unit 1) and additional information that clarified the (ADAMS): You may obtain publicly-
200 (Unit 2). A publicly-available application, did not expand the scope of available documents online in the
version is in ADAMS under Accession the application as originally noticed, ADAMS Public Documents collection at
No. ML18159A212; documents related and did not change the NRC staff’s https://www.nrc.gov/reading-rm/
to these amendments are listed in the original proposed no significant hazards adams.html. To begin the search, select
Safety Evaluation enclosed with the consideration determination as ‘‘Begin Web-based ADAMS Search.’’ For
amendments. published in the Federal Register. problems with ADAMS, please contact
Renewed Facility Operating License The Commission’s related evaluation the NRC’s Public Document Room (PDR)
Nos. NPF–76 and NPF–80: The of the amendment is contained in a reference staff at 1–800–397–4209, 301–
amendments revised the Site Emergency Safety Evaluation dated July 27, 2018. 415–4737, or by email to pdr.resource@
Plan. No significant hazards consideration nrc.gov. The ADAMS accession number
Date of initial notice in Federal comments received: No. for each document referenced in this
Register: September 12, 2017 (82 FR Dated at Rockville, Maryland, this 7th day document (if that document is available
42855). The supplemental letter dated of August, 2018. in ADAMS) is provided the first time
February 12, 2018, provided additional For the Nuclear Regulatory Commission. that a document is referenced.
information that clarified the Kathryn M. Brock, • NRC’s PDR: You may examine and
application, did not expand the scope of Deputy Director, Division of Operating
purchase copies of public documents at
the application as originally noticed, Reactor Licensing, Office of Nuclear Reactor the NRC’s PDR, Room O1–F21, One
and did not change the NRC staff’s Regulation. White Flint North, 11555 Rockville
original proposed no significant hazards [FR Doc. 2018–17132 Filed 8–13–18; 8:45 am] Pike, Rockville, Maryland 20852.
consideration determination as BILLING CODE 7590–01–P FOR FURTHER INFORMATION CONTACT: Kim
published in the Federal Register. Conway, Office of Nuclear Material
The Commission’s related evaluation Safety and Safeguards, U.S. Nuclear
of the amendments is contained in a NUCLEAR REGULATORY Regulatory Commission, Washington
Safety Evaluation dated July 19, 2018. COMMISSION D.C. 20555–0001; telephone: 301–415–
No significant hazards consideration 1335; email: Kimberly.Conway@nrc.gov.
[Docket No. 50–57; NRC–2018–0166]
comments received: No. SUPPLEMENTARY INFORMATION:
Virginia Electric and Power Company, Termination of Operating License for The BMRC reactor in Buffalo, New
Docket Nos. 50–338 and 50–339, North the Buffalo Materials Research Center York, was located on the south campus
Anna Power Station, Units Nos. 1 and Reactor of UB. The BMRC reactor began
2, Louisa County, Virginia operation in 1961 and was shut down
AGENCY: Nuclear Regulatory on June 23, 1994. On June 6, 1997, the
Date of amendment request: May 2, Commission. license was amended to possession
2017, as supplemented by letters dated ACTION: License termination; issuance. only.
July 19, 2017, and January 31, 2018. By letter dated February 17, 2012
Brief description of amendments: The SUMMARY: The U.S. Nuclear Regulatory (ADAMS Package No. ML120540187), as
amendments revised North Anna Power Commission (NRC) is providing notice supplemented by letters dated June 20,
Station (NAPS) Technical Specification of the termination of Facility Operating 2012 (ADAMS Accession No.
(TS) 3.7.18, ‘‘Spent Fuel Pool Storage,’’ License No. R–77 for the Buffalo ML121870132), September 21, 2012
and TS 4.3.1, ‘‘Criticality,’’ to allow the Materials Research Center (BMRC). The (ADAMS Accession No. ML122780454),
storage of fuel assemblies with a NRC has terminated the license of the and October 15, 2012 (ADAMS
maximum enrichment of up to 5.0 decommissioned BMRC at the State Accession No. ML12297A237), the
weight percent uranium 235 in the University of New York at Buffalo (UB licensee submitted a request to the NRC
NAPS spent fuel pool storage racks and or the licensee) facility in Buffalo, New to approve a license amendment and a
the New Fuel Storage Area. The York, and has released the site for revised decommissioning plan (DP) for
amendments further revised the unrestricted use. the BMRC reactor. The NRC approved
allowable fuel assembly parameters and DATES: Notice of termination of Facility the UB revised DP by Amendment No.
fuel storage patterns in the spent fuel Operating License No. R–77 given on 27, dated November 5, 2012 (ADAMS
pool. August 14, 2018. Accession No. ML12290A694).
Date of issuance: July 27, 2018. ADDRESSES: Please refer to Docket ID In the Safety Evaluation Report
Effective date: As of the date of NRC–2018–0166 when contacting the related to the DP approval (ADAMS
issuance and shall be implemented NRC about the availability of Accession No. ML12286A352), the NRC
within 180 days of issuance. information regarding this document. staff determined that the revised Final
amozie on DSK3GDR082PROD with NOTICES1
Amendment Nos.: 279 (Unit 1) and You may obtain publicly-available Status Survey (FSS) Plan for the BMRC
262 (Unit 2). A publicly-available information related to this document (ADAMS Accession No. ML12278A373)
version is in ADAMS under Accession using any of the following methods: was consistent with the guidance and
No. ML18180A197; documents related • Federal Rulemaking website: Go to methodology in NUREG–1575, ‘‘Multi-
to these amendments are listed in the https://www.regulations.gov and search Agency Radiation Survey and Site
Safety Evaluation enclosed with the for Docket ID NRC–2018–0166. Address Investigation Manual (MARSSIM),’’ and
amendments. questions about NRC dockets to Jennifer NUREG–1757, ‘‘Consolidated
VerDate Sep<11>2014 19:13 Aug 13, 2018 Jkt 244001 PO 00000 Frm 00144 Fmt 4703 Sfmt 4703 E:\FR\FM\14AUN1.SGM 14AUN1](https://thefederalregister.org/doc/83_FR_40499/page/14.svg)
Document Created: 2018-08-14 02:19:38
Document Modified: 2018-08-14 02:19:38
| Category | Regulatory Information | |
| Collection | Federal Register | |
| sudoc Class | AE 2.7: GS 4.107: AE 2.106: | |
| Publisher | Office of the Federal Register, National Archives and Records Administration | |
| Section | Notices | |
| Action | Biweekly notice. | |
| Dates | Comments must be filed by September 13, 2018. A request for a hearing must be filed by October 15, 2018. | |
| Contact | Paula Blechman, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington DC 20555-0001; telephone: 301-415-2242; email [email protected] | |
| FR Citation | 83 FR 40342 |
2025 Federal Register | Disclaimer | Privacy Policy
USC | CFR | eCFR