82 FR 38714 - Biweekly Notice: Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations
NUCLEAR REGULATORY COMMISSION Federal Register Volume 82, Issue 156 (August 15, 2017)
Federal Register Volume 82, Issue 156 (August 15, 2017)
| Page Range | 38714-38722 | |
| FR Document | 2017-16998 |
[Federal Register Volume 82, Number 156 (Tuesday, August 15, 2017)] [Notices] [Pages 38714-38722] From the Federal Register Online [www.thefederalregister.org] [FR Doc No: 2017-16998] ======================================================================= ----------------------------------------------------------------------- NUCLEAR REGULATORY COMMISSION [NRC-2017-0175] 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 18 to July 31, 2017. The last biweekly notice was published on August 1, 2017. DATES: Comments must be filed by September 14, 2017. A request for a hearing must be filed by October 16, 2017. ADDRESSES: You may submit comments by any of the following methods:Federal Rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2017-0175. Address questions about NRC dockets to Carol Gallagher; telephone: 301-415- 3463; email: [email protected]. For technical questions, contact the individual listed in the FOR FURTHER INFORMATION CONTACT section of this document. Mail comments to: Cindy Bladey, Office of Administration, Mail Stop: TWFN-8-D36M, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001. For additional direction on obtaining information and submitting comments, see ``Obtaining Information and Submitting Comments'' in the SUPPLEMENTARY INFORMATION section of this document. FOR FURTHER INFORMATION CONTACT: Beverly Clayton, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; telephone: 301-415-3475, email: [email protected]. SUPPLEMENTARY INFORMATION: I. Obtaining Information and Submitting Comments A. Obtaining Information Please refer to Docket ID NRC-2017-0175, 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 Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2017-0175. 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 ``ADAMS Public Documents'' and then select ``Begin Web-based ADAMS Search.'' For problems with ADAMS, please contact the NRC's Public Document Room (PDR) reference staff at 1-800-397-4209, 301-415-4737, or by email to [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-2017-0175, 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 posts all comment submissions at http://www.regulations.gov as well as entering 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 submissions 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 Sec. 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. [[Page 38715]] 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 Web site 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 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's Web site 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 [[Page 38716]] 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 Web site 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 Web site 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 Web site at http://www.nrc.gov/site-help/e-submittals.html, by email to [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, Units 1, 2, and 3 (PVNGS), Maricopa County, Arizona Date of amendment request: June 22, 2017. A publicly-available version is in ADAMS under Accession No. ML17173A877. Description of amendment request: The amendment would revise the PVNGS Technical Specifications (TSs) to eliminate TS Section 5.5.8, ``Inservice Testing Program.'' A new defined term, ``Inservice Testing Program,'' will be added to the TS definitions section. This request is consistent with Technical Specification Task Force (TSTF) Traveler TSTF-545, Revision 3, ``TS Inservice Testing Program Removal & Clarify SR [Surveillance Requirement] Usage Rule Application to Section 5.5 Testing.'' The proposed change eliminates the PVNGS TS, Section 5.5.8, to remove requirements duplicated in the American Society of Mechanical Engineers Code for Operations and Maintenance of Nuclear Power Plants (ASME OM Code) Code Case OMN-20, ``Inservice Test Frequency.'' 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 revises Chapter 5, Administrative Controls, Section 5.5, Programs and Manuals, by eliminating the Inservice Testing Program specification. Requirements in the IST [Inservice Testing] Program are removed, as they are duplicative of requirements in the ASME OM Code, as clarified by Code Case OMN-20, Inservice Test Frequency. Other requirements in Section 5.5.8, Inservice Testing Program are eliminated because the NRC has determined [[Page 38717]] their inclusion in the TS is contrary to regulations. A new defined term, Inservice Testing Program, is added which references the requirements of 10 CFR 50.55a(f). Performance of inservice testing is not an initiator to any accident previously evaluated. As a result, the probability of occurrence of an accident is not significantly affected by the proposed change. Inservice test periods under Code Case OMN-20 are equivalent to the current testing period allowed by the TS with the exception that testing periods greater than two years may be extended by up to six months to facilitate test scheduling and consideration of plant operating conditions that may not be suitable for performance of the required testing. The testing period extension will not affect the ability of the components to mitigate any accident previously evaluated as the components are required to be operable during the testing period extension. Performance of inservice tests utilizing the allowances in Code Case OMN-20 will not significantly affect the reliability of the tested components. As a result, the availability of the affected components, as well as their ability to mitigate the consequences of accidents previously evaluated, is not affected. 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 accident previously evaluated? Response: No. The proposed change does not alter the design or configuration 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. The proposed change does not alter the types of inservice testing performed. In most cases, the frequency of inservice testing is unchanged. However, the frequency of testing would not result in a new or different kind of accident from any previously evaluated since the testing methods are not altered. 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 amendment involve a significant reduction in a margin of safety? Response: No. The proposed change eliminates some requirements from the TS in lieu of requirements in the ASME Code, as modified by use of Code Case OMN-20. Compliance with the ASME Code is required by 10 CFR 50.55a. The proposed change also allows inservice tests with periods greater than two years to be extended by six months to facilitate test scheduling and consideration of plant operating conditions that may not be suitable for performance of the required testing. The testing period extension will not affect the ability of the components to respond to an accident as the components are required to be operable during the testing period extension. The proposed change will eliminate the existing TS SR 3.0.3 allowance to defer performance of missed inservice tests up to the duration of the specified testing period, and instead will require an assessment of the missed test on equipment operability. This assessment will consider the effect on a margin of safety (equipment operability). Should the component be inoperable, the Technical Specifications provide actions to ensure that the margin of safety is protected. The proposed change also eliminates a statement that nothing in the ASME Code should be construed to supersede the requirements of any TS. The NRC has determined that statement to be incorrect. However, elimination of the statement will have no effect on plant operation or 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 request for 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, AZ 85072-2034. NRC Branch Chief: Robert J. Pascarelli. Entergy Nuclear Operations, Inc., Docket No. 50-271, Vermont Yankee Nuclear Power Station (VY), Vernon, Vermont Date of amendment request: May 1, 2017. A publicly-available version is in ADAMS under Accession No. ML17124A429. This request was supplemented by information submitted by the licensee by letter dated June 13, 2017 (ADAMS Accession No. ML17166A234). Description of amendment request: The proposed amendment would extend the scheduled implementation date for Milestone 8 of the VY Cyber Security Plan (CSP) to July 31, 2019, to support the decommissioning status of VY. 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 to the CSP implementation schedule is administrative in nature. This proposed change does not alter accident analysis assumptions, add any initiators, or affect the function of facility systems or the manner in which systems are operated, maintained, modified, tested, or Inspected. The proposed change does not require any facility modifications which affect the performance capability of the structures, systems, and components (SSCs) relied upon to mitigate the consequences of postulated accidents and has no impact on the probability or consequences of an accident previously evaluated. 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 change to the CSP implementation schedule is administrative in nature. This proposed change does not alter accident analysis assumptions, add any initiators, or affect the function of facility systems or the manner in which systems are operated, maintained, modified, tested, or inspected. The proposed change does not require any facility modifications which affect the performance capability of the SSCs relied upon to mitigate the consequences of postulated accidents and does not create the possibility of a new or different kind of accident from any accident previously evaluated. Therefore, the proposed change does 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. Plant safety margins are established through limiting conditions for operation, limiting safety system settings, and safety limits specified In the Technical Specifications. The proposed change to the CSP implementation schedule is administrative in nature. In addition, the milestone date delay for full implementation of the CSP has no substantive impact because other measures, including completing and maintaining interim Milestones 1 through 7, have been taken which provide adequate protection during this period of time. Because there is no change to established safety margins as a result of this proposed change, no significant reduction in a margin of safety is involved. 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: Ms. Susan Raimo, Senior Counsel, Entergy Services, Inc., 101 Constitution Avenue [[Page 38718]] NW., Suite 200 East, Washington, DC 20001. NRC Branch Chief: Bruce Watson. FirstEnergy Nuclear Operating Company, Docket No. 50-440, Perry Nuclear Power Plant, Unit No. 1, Lake County, Ohio Date of amendment request: June 20, 2017. A publicly-available version is in ADAMS under Accession No. ML17171A301. Description of amendment request: The proposed amendment would revise a surveillance requirement (SR) in Technical Specification 3.8.1, ``AC Sources--Operating,'' to clarify that the intent of the surveillance is to verify that only the non-critical diesel generator (DG) trips are bypassed on an emergency core cooling system initiation signal. The proposed changes are consistent with Technical Specification Task Force Improved Standard Technical Specifications Change Traveler 400-A, Revision 1, ``Clarify SR on Bypass of DG Automatic Trips.'' 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 clarifies the purpose of SR 3.8.1.13, which is to verify that non-critical automatic diesel generator (DG) trips are bypassed in an accident. The DG automatic trips and their bypasses are not initiators of any accident previously evaluated. Therefore, the probability of any accident is not significantly increased. The function of the DGs in mitigating accidents is not changed. The revised SR continues to ensure the DGs will operate as assumed in the accident analyses. Therefore, the consequences of any accident previously evaluated are not affected. 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 accident previously evaluated? Response: No. The proposed change clarifies the purpose of SR 3.8.1.13, which is to verify that non-critical automatic DG trips are bypassed in an accident. The proposed change does not involve a physical alteration of the plant (no new or different type of equipment will be installed) or a change in the methods governing normal plant operation. Thus, this change does 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 clarifies the purpose of SR 3.8.1.13, which is to verify that non-critical automatic DG trips are bypassed in an accident. Performance of the clarified SR will verify that the non- critical trips are bypassed on simulated ECCS [emergency core cooling system] actuation signals to ensure that actuation of a non- critical trip does not take a DG out of service during an emergency. The bypassing of the non-critical automatic DG trips will maintain DG availability during an emergency so that it will be able to perform its assumed safety function. As such, the safety function of the DGs remains unaffected, so the change does not affect the margin of 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 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: David W. Jenkins, Attorney, FirstEnergy Corporation, Mail Stop A-GO-15, 76 South Main Street, Akron, OH 44308. NRC Branch Chief: David J. Wrona. Omaha Public Power District, Docket No. 50-285, Fort Calhoun Station (FCS), Unit No. 1, Washington County, Nebraska Date of amendment request: June 9, 2017. A publicly-available version is in ADAMS under Accession No. ML17160A405. Description of amendment request: The proposed amendment would delete Technical Specifications (TSs) 2.8.3(6), ``Spent Fuel Cask Loading,'' and associated Figure 2-11, ``Limiting Burnup Criteria for Acceptable Storage in Spent Fuel Cask''; TS 3.2 Table 3-5(24), ``Spent Fuel Cask Loading''; TS 4.3.1.3, Design Features associated with spent fuel casks; and portions of TS 3.2, Table 3-4(5), Footnote (4) on boron concentration associated with cask loading. The deletion of the TS sections will bring the FCS TSs into conformance with 10 CFR 50.68(c) ``Criticality accident requirements.'' 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 simply bring[s] the [station's] technical specifications into compliance with the current version of 10 CFR 50.68. There is no change to probability or 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 amendment create the possibility of a new or different kind of accident from any accident previously evaluated? Response: No. The proposed change does not alter [any] safety limits, or safety analysis assumptions associated with the operation of the plant. The proposed change does not introduce any new accident initiators, nor does the change reduce or adversely affect the capabilities of any plant structure or system in the performance of its safety function. Therefore, the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated. 3. Does the proposed amendment involve a significant reduction in a margin of safety? Response: No. The proposed change does not alter the manner in which safety limits or limiting safety system settings are determined. The safety analysis acceptance criteria are not affected by the proposed change. The proposed change does not change the design function of any equipment assumed to operate in the event of an accident. 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: David A. Repka, Esq., Winston & Strawn, 1700 K Street NW., Washington, DC 20006-3817. NRC Branch Chief: Douglas A. Broaddus. Omaha Public Power District, Docket No. 50-285, Fort Calhoun Station (FCS), Unit No. 1, Washington County, Nebraska Date of amendment request: June 16, 2017. A publicly-available version is in ADAMS under Accession No. ML17167A057. Description of amendment request: The proposed amendment would remove the FCS Cyber Security Plan (CSP) from the FCS Operating License Condition. Basis for proposed no significant hazards consideration determination: [[Page 38719]] 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 to remove the [FCS CSP] requirement does not alter accident analysis assumptions, add any initiators, or affect the function of plant systems or the manner in which systems are operated, maintained, modified, tested, or inspected. The proposed change does not require any plant modifications which affect the performance capability of the structures, systems, and components [SSCs] relied upon to mitigate the consequences of postulated accidents, and has no impact on the probability or consequences of an 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 amendment create the possibility of a new or different kind of accident from any accident previously evaluated? Response: No. The proposed change to remove the [FCS CSP] requirement does not alter accident analysis assumptions, add any initiators, or affect the function of plant systems or the manner in which systems are operated, maintained, modified, tested, or inspected. The proposed change does not require any plant modifications which affect the performance capability of the [SSCs] relied upon to mitigate the consequences of postulated accidents, and has no impact on the probability or consequences of an accident previously evaluated. Therefore, the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated. 3. Does the proposed amendment involve a significant reduction in a margin of safety? Response: No. The amendment proposes the elimination of the CSP as set forth in the CSP Implementation Schedule and associated regulatory commitments. The elimination of the CSP does not involve modifications to any safety-related SSCs. The proposed amendment is based on the comparison of the risks at an operating nuclear power reactor as opposed to a nuclear power reactor that has permanently ceased operations and has removed all fuel from the reactor vessel. The spectrum of possible accidents are significantly fewer and the risk of an offsite radiological release is significantly lower for a permanently defueled reactor. 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: David A. Repka, Esq., Winston & Strawn, 1700 K Street NW., Washington, DC 20006-3817. NRC Branch Chief: Douglas A. Broaddus. Southern Nuclear Operating Company, Inc., Docket Nos. 52-025 and 52- 026, Vogtle Electric Generating Plant (VEGP), Units 3 and 4, Burke County, Georgia Date of amendment request: June 23, 2017. A publicly-available version is in ADAMS under Accession No. ML17179A171. Description of amendment request: The requested amendment requires changes to the Updated Final Safety Analysis Report (UFSAR) in the form of departures from the plant-specific Design Control Document Tier 2 information and involves changes to the VEGP Units 3 and 4 COL Appendix A, Technical Specifications (TS). Specifically, the proposed changes revise plant-specific Tier 2 information to add the time delay assumed in the safety analysis for the reactor trip on a safeguards actuation (``S'') signal to UFSAR Table 15.0-4a. This is also reflected in the proposed revision to TS 3.3.4, Reactor Trip System (RTS) Engineered Safety Feature Actuation System (ESFAS) Instrumentation, to add a surveillance requirement to verify the RTS response time for this ``S'' signal. The request also includes proposed changes to TS 3.3.7, RTS Trip Actuation Devices, to clarify that the requirements for reactor trip breaker (RTB) undervoltage and shunt trip mechanisms apply only to in- service RTBs. In addition, the request includes proposed changes to TS 3.3.9, ESFAS Manual Initiation, to correct the nomenclature for the Chemical and Volume Control System, which is advertently stated as the Chemical Volume and Control System. 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 NRC staff edits in square brackets: 1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated? Response: No. The changes do not involve an interface with any [structure, system, and component (SSC)] accident initiator or initiating sequence of events, and thus, the probabilities of the accidents evaluated in the plant-specific UFSAR are not affected. The proposed changes do not involve a change to any mitigation sequence or the predicted radiological releases due to postulated accident conditions, thus, the consequences of the accidents evaluated in the UFSAR are not affected. 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 changes do not adversely affect any system or design function or equipment qualification as the change does not modify any SSCs that prevent safety functions from being performed. The changes do not introduce a new failure mode, malfunction or sequence of events that could adversely affect safety or safety- related equipment. Therefore, the proposed amendment does 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 changes would not affect any safety-related design code, function, design analysis, safety analysis input or result, or existing design/safety margin. No safety analysis or design basis acceptance limit/criterion is challenged or exceeded by the requested changes. 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: Mr. M. Stanford Blanton, Balch & Bingham LLP, 1710 Sixth Avenue North Birmingham, AL 35203-2015. NRC Branch Chief: Jennifer Dixon-Herrity. III. 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 [[Page 38720]] 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. Arizona Public Service Company, et al., Docket Nos. STN 50-528, STN 50- 529, and STN 50-530, Palo Verde Nuclear Generating Station (PVNGS), Units 1, 2, and 3, Maricopa County, Arizona Date of application for amendment: November 25, 2015, as supplemented by letters dated January 29, June 30, October 6, November 9, and November 23, 2016; and March 3 and May 24, 2017. Brief Description of amendment: The amendments revised the Technical Specifications (TSs) for PVNGS, by modifying the requirements to incorporate the results of an updated criticality safety analysis for both new and spent fuel storage. Date of issuance: July 28, 2017. Effective date: As of the date of issuance and shall be implemented within 90 days from the date of issuance. Amendment Nos.: Unit 1--203, Unit 2--203, and Unit 3--203. A publicly-available version is in ADAMS under Accession No. ML17188A412; documents related to these amendments are listed in the Safety Evaluation enclosed with the amendments. Renewed Facility Operating License Nos. NPF-41, NPF-51, and NPF-74: The amendments revised the Operating Licenses and TSs. Date of initial notice in Federal Register: April 5, 2016 (81 FR 19644). The supplements dated June 30, October 6, November 9, and November 23, 2016; and March 3 and May 24, 2017, 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 28, 2017. No significant hazards consideration comments received: No. Duke Energy Carolinas, LLC, Docket Nos. 50-413 and 50-414, Catawba Nuclear Station, Units 1 and 2, York County, South Carolina Date of application for amendments: December 15, 2016. Brief description of amendments: The amendments modified Technical Specification (TS) 3.6.3, ``Containment Isolation Valves,'' to add a Note to TS Limiting Condition for Operation (LCO) 3.6.3 Required Actions A.2, C.2, and E.2 to allow isolation devices that are locked, sealed, or otherwise secured to be verified by use of administrative means. The changes are consistent with NRC-approved Technical Specifications Task Force (TSTF) Traveler TSTF-269-A, Revision 2, ``Allow administrative means of position verification for locked or sealed valves.'' Date of issuance: July 21, 2017. Effective date: These license amendments are effective as of their date of issuance and shall be implemented within 120 days of issuance. Amendment Nos.: 290 and 286. A publicly available version is in ADAMS under Accession No. ML17165A441; documents related to these amendments are listed in the Safety Evaluation enclosed with the amendments. Renewed Facility Operating License Nos. NPF-35 and NPF-52: Amendments revised the licenses and TSs. Date of initial notice in Federal Register: April 25, 2017 (82 FR 19098). The Commission's related evaluation of the amendments is contained in a Safety Evaluation dated July 21, 2017. No significant hazards consideration comments received: No. Duke Energy Carolinas, LLC, Docket Nos. 50-413 and 50-414, Catawba Nuclear Station, Units 1 and 2, York County, South Carolina Date of application for amendments: December 15, 2016. Brief description of amendments: The amendments modified Technical Specification (TS) 3.1.8, ``PHYSICS TESTS Exceptions,'' to allow the numbers of channels required by the Limiting Condition of Operation (LCO) section of TS 3.3.1, ``Reactor Trip System (RTS) Instrumentation,'' to be reduced from ``4'' to ``3'' to allow one nuclear instrumentation channel to be used as an input to the reactivity computer for physics testing without placing the nuclear instrumentation channel in a tripped condition. The changes are consistent with Technical Specifications Task Force (TSTF) Traveler TSTF-315-A, Revision 0, ``Reduce plant trips due to spurious signals to the NIS [Nuclear Instrumentation System] during physics testing.'' Date of issuance: July 26, 2017. Effective date: These license amendments are effective as of its date of issuance and shall be implemented within 120 days of issuance. Amendment Nos.: 291 (Unit 1) and 287 (Unit 2). A publicly-available version is in ADAMS under Accession No. ML17172A428; documents related to these amendments are listed in the Safety Evaluation enclosed with the amendments. Renewed Facility Operating License Nos. NPF-35 and NPF-52: Amendments revised the licenses and TSs. Date of initial notice in Federal Register: April 25, 2017 (82 FR 19098). The Commission's related evaluation of the amendments is contained in a Safety Evaluation dated July 26, 2017. No significant hazards consideration comments received: No. Energy Northwest, Docket No. 50-397, Columbia Generating Station (Columbia), Benton County, Washington Date of application for amendment: July 14, 2016, as supplemented by letter dated July 5, 2017. Brief description of amendment: The amendment changed the Columbia Technical Specifications (TSs) consistent with TS Task Force (TSTF) Standard Technical Specifications Change Traveler TSTF-545, Revision 3, ``TS Inservice Testing Program Removal & Clarify SR [Surveillance Requirement] Usage Rule Application to Section 5.5 Testing,'' dated October 21, 2015. Date of issuance: July 24, 2017. Effective date: As of its date of issuance and shall be implemented within 60 days from the date of issuance. Amendment No.: 243. A publicly-available version is in ADAMS under Accession No. ML17187A257; documents related to this amendment [[Page 38721]] are listed in the Safety Evaluation enclosed with the amendment. Renewed Facility Operating License No. NPF-21: The amendment revised the Facility Operating License and TSs. Date of initial notice in Federal Register: September 27, 2016 (81 FR 66304). The supplemental letter dated July 5, 2017, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the staff's original proposed no significant hazards consideration determination as published in the Federal Register. The Commission's related evaluation of the amendment is contained in a Safety Evaluation dated July 24, 2017. No significant hazards consideration comments received: No. Entergy Operations, Inc., Docket No. 50-382, Waterford Steam Electric Station, Unit 3 (Waterford 3), St. Charles Parish, Louisiana Date of amendment request: July 25, 2016. Brief description of amendment: The amendment changed the Waterford 3 Technical Specifications (TSs) consistent with Technical Specifications Task Force (TSTF) Standard Technical Specifications Change Traveler TSTF-545, Revision 3, ``TS Inservice Testing Program Removal & Clarify SR [Surveillance Requirement] Usage Rule Application to Section 5.5 Testing,'' dated October 21, 2015. Date of issuance: July 27, 2017. Effective date: As of the date of issuance and shall be implemented 90 days from the date of issuance. Amendment No.: 250. A publicly-available version is in ADAMS under Accession No. ML17192A007; 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 Facility Operating License and TSs. Date of initial notice in Federal Register: November 8, 2016 (81 FR 78647). The Commission's related evaluation of the amendment is contained in a Safety Evaluation dated July 27, 2017. No significant hazards consideration comments received: No. NextEra Energy, Point Beach, LLC, Docket No. 50-266, Point Beach Nuclear Plant (PBNP), Unit 1, Town of Two Creeks, Manitowoc County, Wisconsin Date amendment request: July 29, 2016, as supplemented by letter dated April 20, 2017. Publicly-available versions of these documents are in ADAMS under Accession Nos. ML16237A066 and ML17110A068, respectively. Brief description of amendments: The amendment consists of changes to the technical specifications (TSs) for PBNP, Unit 1. The amendment makes changes to TS 3.4.13, ``RCS Operational LEAKAGE,'' TS 5.5.8, ``Steam Generator (SG) Program,'' and TS 5.6.8, ``Steam Generator Tube Inspection Report,'' in order to implement the H* (pronounced H-star) alternate repair criteria on a permanent basis. Date of issuance: July 27, 2017. Effective date: As of the date of issuance and shall be implemented within 90 days of issuance. Amendment No.: 260. A publicly-available version is in ADAMS under Accession No. ML17159A778; documents related to this amendment are listed in the Safety Evaluation enclosed with the amendment. Renewed Facility Operating License No. DPR-24: Amendment revised the Facility Operating License and TSs. Date of initial notice in Federal Register: December 6, 2016 (81 FR 87961). The supplemental letter dated April 20, 2017, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the staff's original proposed no significant hazards consideration determination as published in the Federal Register. The Commission's related evaluation of the amendment is contained in a Safety Evaluation dated July 27, 2017. No significant hazards consideration comments received: No. Omaha Public Power District, Docket No. 50-285, Fort Calhoun Station (FCS), Unit 1, Washington County, Nebraska Date of amendment request: September 2, 2016, as supplemented by letters dated March 3 and April 5, 2017. Brief description of amendment: The amendment revised the Nuclear Radiological Emergency Response Plan for FCS for the plant condition following permanent cessation of power operations and defueling to reflect changes in the shift staffing and Emergency Response Organization staffing. Date of issuance: July 27, 2017. Effective date: As of the date of issuance and shall be implemented within 60 days from the date of issuance. Amendment No.: 291. A publicly-available version is in ADAMS under Accession No. ML17123A348; documents related to this amendment are listed in the Safety Evaluation enclosed with the amendment. Renewed Facility Operating License No. DPR-40: The amendment revised the license. Date of initial notice in Federal Register: November 8, 2016 (81 FR 78650). The supplemental letters dated March 3 and April 5, 2017, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the staff's 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, 2017. No significant hazards consideration comments received: No. Omaha Public Power District, Docket No. 50-285, Fort Calhoun Station (FCS), Unit 1, Washington County, Nebraska Date of amendment request: September 28, 2016, as supplemented by letter dated April 27, 2017. Brief description of amendment: The amendment revised the Technical Specifications (TSs) to make administrative changes to align staffing for permanently defueled condition at FCS. Date of issuance: July 28, 2017. Effective date: As of the date of issuance and shall be implemented within 90 days from the date of issuance. Amendment No.: 292. A publicly-available version is in ADAMS under Accession No. ML17165A465; documents related to this amendment are listed in the Safety Evaluation enclosed with the amendment. Renewed Facility Operating License No. DPR-40: The amendment revised the Renewed Facility Operating License and TSs. Date of initial notice in Federal Register: November 8, 2016 (81 FR 78650). The supplemental letter dated April 27, 2017, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the 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 28, 2017. No significant hazards consideration comments received: No. [[Page 38722]] Southern Nuclear Operating Company, Docket Nos. 52-025 and 52-026, Vogtle Electric Generating Plant (VEGP), Units 3 and 4, Burke County, Georgia Date of amendment request: January 20, 2017, and supplemented by letter dated June 6, 2017. Description of amendment: The amendments consist of changes to the VEGP Units 3 and 4 Updated Final Safety Analysis Report (UFSAR) in the form of departures from plant-specific Design Control Document Tier 2 information, Combined License (COL) Appendix A Technical Specifications, and COL Appendix C information. The departures consist of in-containment refueling water storage tank (IRWST) minimum volume changes in plant-specific UFSAR Table 14.3-2, COL Appendix A Technical Specifications 3.5.6, 3.5.7 and 3.5.8 and Surveillance Requirements 3.5.6.2 and 3.5.8.2 and COL Appendix C (and associated plant-specific Tier 1) Table 2.2.3-4. The changes restore the desired consistency of these sections with the UFSAR IRWST minimum volume value in other locations. Date of issuance: July 6, 2017. Effective date: As of the date of issuance and shall be implemented within 30 days of issuance. Amendment Nos.: 81 and 80. A publicly-available version is in ADAMS under Accession No. ML17171A137; documents related to this amendment are listed in the Safety Evaluation enclosed with the amendment. Facility Combined Licenses No. NPF-91 and NPF-92: Amendment revised the Facility Combined Licenses. Date of initial notice in Federal Register: March 14, 2017 (82 FR 13662). The supplemental letter dated June 6, 2017, provided additional information that clarified the application, did not expand the scope of the application request as originally noticed, and did not change the staff's original proposed no significant hazards consideration determination as published in the Federal Register. The Commission's related evaluation of the amendment is contained in the Safety Evaluation dated July 6, 2017. No significant hazards consideration comments received: No. Susquehanna Nuclear, LLC, Docket Nos. 50-387 and 50-388, Susquehanna Steam Electric Station, Units 1 and 2, Luzerne County, Pennsylvania Date of amendment request: February 1, 2017, as supplemented by letter dated May 17, 2017. Brief description of amendments: The amendments revised Technical Specification (TS) 3.6.4.3, ``Standby Gas Treatment (SGT) System,'' and TS 3.7.3, ``Control Room Emergency Outside Air Supply (CREOAS) System,'' by changing the run time of monthly surveillance requirements for the standby gas treatment and control room emergency outside air supply systems from 10 hours to 15 minutes. This change is consistent with Technical Specifications Task Force (TSTF) Traveler TSTF-522, Revision 0, ``Revise Ventilation System Surveillance Requirements to Operate for 10 hours per Month,'' with minor variations. The notice of availability and model safety evaluation of TSTF-522, Revision 0, were published in the Federal Register on September 20, 2012 (77 FR 58421). Date of issuance: July 28, 2017. Effective date: As of the date of issuance and shall be implemented within 60 days of issuance. Amendment Nos.: 268 (Unit 1) and 250 (Unit 2). A publicly-available version is in ADAMS under Accession No. ML17187A297; documents related to these amendments are listed in the Safety Evaluation enclosed with the amendments. Renewed Facility Operating License Nos. NPF-14 and NPF-22: The amendments revised the Renewed Facility Operating Licenses and TSs. Date of initial notice in Federal Register: April 11, 2017 (82 FR 17461). The supplemental letter dated May 17, 2017, 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 28, 2017. No significant hazards consideration comments received: No. Virginia Electric and Power Company, Docket Nos. 50-280 and 50-281, Surry Power Station, Units No. 1 and No. 2, Surry County, Virginia Date of amendment request: July 14, 2016, as supplemented by letters dated January 31, 2017, March 1, 2017 and March 10, 2017. Brief description of amendments: The amendments would extend the Technical Specification (TS) 3.14.B allowed outage time for one inoperable emergency service water (ESW) pump from 7 to 14 days to provide operational flexibility for ESW pump maintenance and repairs. Date of issuance: July 28, 2017. Effective date: As of the date of issuance and shall be implemented within 60 days of issuance. Amendment Nos.: 290 and 290. A publicly-available version is in ADAMS under Accession No. ML17170A183; documents related to these amendments are listed in the Safety Evaluation enclosed with the amendments. Facility Operating License No. NPF-4 and NPF-7: Amendments revised the Facility Operating Licenses and TSs. Date of initial notice in Federal Register: October 25, 2016 (81 FR 73443). The letters dated January 31, 2017, March 1, 2017 and March 10, 2017, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the staff's original proposed no significant hazards consideration determination as published in the Federal Register. The Commission's related evaluation of the amendment is contained in a Safety Evaluation dated July 28, 2017. No significant hazards consideration comments received: No. Dated at Rockville, Maryland, this 4th day of August 2017. For the Nuclear Regulatory Commission. Anne T. Boland, Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation. [FR Doc. 2017-16998 Filed 8-14-17; 8:45 am] BILLING CODE 7590-01-P
![38714 Federal Register / Vol. 82, No. 156 / Tuesday, August 15, 2017 / Notices
Dated: August 9, 2017. Submitting Comments’’ in the submission to the NRC, then you should
Suzanne M. Barnett, SUPPLEMENTARY INFORMATION section of inform those persons not to include
Chief U.S. Copyright Royalty Judge. this document. identifying or contact information that
[FR Doc. 2017–17166 Filed 8–14–17; 8:45 am] FOR FURTHER INFORMATION CONTACT: they do not want to be publicly
BILLING CODE 1410–72–P Beverly Clayton, Office of Nuclear disclosed in their comment submission.
Reactor Regulation, U.S. Nuclear Your request should state that the NRC
Regulatory Commission, Washington, does not routinely edit comment
DC 20555–0001; telephone: 301–415– submissions to remove such information
NUCLEAR REGULATORY
3475, email: Beverly.Clayton@nrc.gov. before making the comment
COMMISSION
SUPPLEMENTARY INFORMATION:
submissions available to the public or
[NRC–2017–0175] entering the comment submissions into
I. Obtaining Information and ADAMS.
Biweekly Notice: Applications and Submitting Comments
Amendments to Facility Operating II. Notice of Consideration of Issuance
Licenses and Combined Licenses A. Obtaining Information of Amendments to Facility Operating
Involving No Significant Hazards Please refer to Docket ID NRC–2017– Licenses and Combined Licenses and
Considerations 0175, facility name, unit number(s), Proposed No Significant Hazards
plant docket number, application date, Consideration Determination
AGENCY: Nuclear Regulatory
and subject, when contacting the NRC The Commission has made a
Commission.
about the availability of information for proposed determination that the
ACTION: Biweekly notice. this action. You may obtain publicly- following amendment requests involve
SUMMARY: Pursuant to Section 189a. (2) available information related to this no significant hazards consideration.
of the Atomic Energy Act of 1954, as action by any of the following methods: Under the Commission’s regulations in
amended (the Act), the U.S. Nuclear • Federal Rulemaking Web site: Go to § 50.92 of title 10 of the Code of Federal
Regulatory Commission (NRC) is http://www.regulations.gov and search Regulations (10 CFR), this means that
publishing this regular biweekly notice. for Docket ID NRC–2017–0175. operation of the facility in accordance
• NRC’s Agencywide Documents with the proposed amendment would
The Act requires the Commission to
Access and Management System not (1) involve a significant increase in
publish notice of any amendments
(ADAMS): You may obtain publicly- the probability or consequences of an
issued, or proposed to be issued, and
available documents online in the accident previously evaluated, or (2)
grants the Commission the authority to
ADAMS Public Documents collection at create the possibility of a new or
issue and make immediately effective
http://www.nrc.gov/reading-rm/ different kind of accident from any
any amendment to an operating license
adams.html. To begin the search, select accident previously evaluated; or (3)
or combined license, as applicable,
‘‘ADAMS Public Documents’’ and then involve a significant reduction in a
upon a determination by the
select ‘‘Begin Web-based ADAMS margin of safety. The basis for this
Commission that such amendment
Search.’’ For problems with ADAMS, proposed determination for each
involves no significant hazards
please contact the NRC’s Public amendment request is shown below.
consideration, notwithstanding the The Commission is seeking public
Document Room (PDR) reference staff at
pendency before the Commission of a comments on this proposed
1–800–397–4209, 301–415–4737, or by
request for a hearing from any person. determination. Any comments received
This biweekly notice includes all email to pdr.resource@nrc.gov. The
ADAMS accession number for each within 30 days after the date of
notices of amendments issued, or publication of this notice will be
proposed to be issued, from July 18 to document referenced (if it is available in
ADAMS) is provided the first time that considered in making any final
July 31, 2017. The last biweekly notice determination.
was published on August 1, 2017. it is mentioned in this document.
• NRC’s PDR: You may examine and Normally, the Commission will not
DATES: Comments must be filed by issue the amendment until the
purchase copies of public documents at
September 14, 2017. A request for a the NRC’s PDR, Room O1–F21, One expiration of 60 days after the date of
hearing must be filed by October 16, White Flint North, 11555 Rockville publication of this notice. The
2017. Pike, Rockville, Maryland 20852. Commission may issue the license
ADDRESSES: You may submit comments amendment before expiration of the 60-
by any of the following methods: B. Submitting Comments day period provided that its final
• Federal Rulemaking Web site: Go to Please include Docket ID NRC–2017– determination is that the amendment
http://www.regulations.gov and search 0175, facility name, unit number(s), involves no significant hazards
for Docket ID NRC–2017–0175. Address plant docket number, application date, consideration. In addition, the
questions about NRC dockets to Carol and subject, in your comment Commission may issue the amendment
Gallagher; telephone: 301–415–3463; submission. prior to the expiration of the 30-day
email: Carol.Gallagher@nrc.gov. For The NRC cautions you not to include comment period if circumstances
technical questions, contact the identifying or contact information that change during the 30-day comment
individual listed in the FOR FURTHER you do not want to be publicly period such that failure to act in a
INFORMATION CONTACT section of this disclosed in your comment submission. timely way would result, for example in
document. The NRC posts all comment derating or shutdown of the facility. If
• Mail comments to: Cindy Bladey, submissions at http:// the Commission takes action prior to the
mstockstill on DSK30JT082PROD with NOTICES
Office of Administration, Mail Stop: www.regulations.gov as well as entering expiration of either the comment period
TWFN–8–D36M, U.S. Nuclear the comment submissions into ADAMS. or the notice period, it will publish in
Regulatory Commission, Washington, The NRC does not routinely edit the Federal Register a notice of
DC 20555–0001. comment submissions to remove issuance. If the Commission makes a
For additional direction on obtaining identifying or contact information. final no significant hazards
information and submitting comments, If you are requesting or aggregating consideration determination, any
see ‘‘Obtaining Information and comments from other persons for hearing will take place after issuance.
VerDate Sep<11>2014 17:15 Aug 14, 2017 Jkt 241001 PO 00000 Frm 00046 Fmt 4703 Sfmt 4703 E:\FR\FM\15AUN1.SGM 15AUN1](https://thefederalregister.org/doc/82_FR_38870/page/1.svg)
![38716 Federal Register / Vol. 82, No. 156 / Tuesday, August 15, 2017 / Notices
days prior to the filing deadline, the submittals.html, by email to limited excerpts that serve the purpose
participant should contact the Office of MSHD.Resource@nrc.gov, or by a toll- of the adjudicatory filings and would
the Secretary by email at free call at 1–866–672–7640. The NRC constitute a Fair Use application,
hearing.docket@nrc.gov, or by telephone Electronic Filing Help Desk is available participants are requested not to include
at 301–415–1677, to (1) request a digital between 9 a.m. and 6 p.m., Eastern copyrighted materials in their
identification (ID) certificate, which Time, Monday through Friday, submission.
allows the participant (or its counsel or excluding government holidays. For further details with respect to
representative) to digitally sign Participants who believe that they these license amendment applications,
submissions and access the E-Filing have a good cause for not submitting see the application for amendment
system for any proceeding in which it documents electronically must file an which is available for public inspection
is participating; and (2) advise the exemption request, in accordance with in ADAMS and at the NRC’s PDR. For
Secretary that the participant will be 10 CFR 2.302(g), with their initial paper additional direction on accessing
submitting a petition or other filing stating why there is good cause for information related to this document,
adjudicatory document (even in not filing electronically and requesting see the ‘‘Obtaining Information and
instances in which the participant, or its authorization to continue to submit Submitting Comments’’ section of this
counsel or representative, already holds documents in paper format. Such filings document.
an NRC-issued digital ID certificate). must be submitted by: (1) First class
Based upon this information, the mail addressed to the Office of the Arizona Public Service Company, et al.,
Secretary will establish an electronic Secretary of the Commission, U.S. Docket Nos. STN 50–528, STN 50–529,
docket for the hearing in this proceeding Nuclear Regulatory Commission, and STN 50–530, Palo Verde Nuclear
if the Secretary has not already Washington, DC 20555–0001, Attention: Generating Station, Units 1, 2, and 3
established an electronic docket. Rulemaking and Adjudications Staff; or (PVNGS), Maricopa County, Arizona
Information about applying for a (2) courier, express mail, or expedited Date of amendment request: June 22,
digital ID certificate is available on the delivery service to the Office of the 2017. A publicly-available version is in
NRC’s public Web site at http:// Secretary, 11555 Rockville Pike, ADAMS under Accession No.
www.nrc.gov/site-help/e-submittals/ Rockville, Maryland, 20852, Attention: ML17173A877.
getting-started.html. Once a participant Rulemaking and Adjudications Staff. Description of amendment request:
has obtained a digital ID certificate and Participants filing adjudicatory The amendment would revise the
a docket has been created, the documents in this manner are PVNGS Technical Specifications (TSs)
participant can then submit responsible for serving the document on to eliminate TS Section 5.5.8, ‘‘Inservice
adjudicatory documents. Submissions all other participants. Filing is Testing Program.’’ A new defined term,
must be in Portable Document Format considered complete by first-class mail ‘‘Inservice Testing Program,’’ will be
(PDF). Additional guidance on PDF as of the time of deposit in the mail, or added to the TS definitions section.
submissions is available on the NRC’s by courier, express mail, or expedited This request is consistent with
public Web site at http://www.nrc.gov/ delivery service upon depositing the Technical Specification Task Force
site-help/electronic-sub-ref-mat.html. A document with the provider of the (TSTF) Traveler TSTF–545, Revision 3,
filing is considered complete at the time service. A presiding officer, having ‘‘TS Inservice Testing Program Removal
the document is submitted through the granted an exemption request from & Clarify SR [Surveillance Requirement]
NRC’s E-Filing system. To be timely, an using E-Filing, may require a participant Usage Rule Application to Section 5.5
electronic filing must be submitted to or party to use E-Filing if the presiding Testing.’’ The proposed change
the E-Filing system no later than 11:59 officer subsequently determines that the eliminates the PVNGS TS, Section 5.5.8,
p.m. Eastern Time on the due date. reason for granting the exemption from to remove requirements duplicated in
Upon receipt of a transmission, the E- use of E-Filing no longer exists. the American Society of Mechanical
Filing system time-stamps the document Documents submitted in adjudicatory Engineers Code for Operations and
and sends the submitter an email notice proceedings will appear in the NRC’s Maintenance of Nuclear Power Plants
confirming receipt of the document. The electronic hearing docket which is (ASME OM Code) Code Case OMN–20,
E-Filing system also distributes an email available to the public at https:// ‘‘Inservice Test Frequency.’’
notice that provides access to the adams.nrc.gov/ehd, unless excluded Basis for proposed no significant
document to the NRC’s Office of the pursuant to an order of the Commission hazards consideration determination:
General Counsel and any others who or the presiding officer. If you do not As required by 10 CFR 50.91(a), the
have advised the Office of the Secretary have an NRC-issued digital ID certificate licensee has provided its analysis of the
that they wish to participate in the as described above, click cancel when issue of no significant hazards
proceeding, so that the filer need not the link requests certificates and you consideration, which is presented
serve the document on those will be automatically directed to the below:
participants separately. Therefore, NRC’s electronic hearing dockets where
1. Does the proposed amendment involve
applicants and other participants (or you will be able to access any publicly a significant increase in the probability or
their counsel or representative) must available documents in a particular consequences of an accident previously
apply for and receive a digital ID hearing docket. Participants are evaluated?
certificate before adjudicatory requested not to include personal Response: No.
documents are filed so that they can privacy information, such as social The proposed change revises Chapter 5,
obtain access to the documents via the security numbers, home addresses, or Administrative Controls, Section 5.5,
E-Filing system. personal phone numbers in their filings, Programs and Manuals, by eliminating the
mstockstill on DSK30JT082PROD with NOTICES
A person filing electronically using unless an NRC regulation or other law Inservice Testing Program specification.
the NRC’s adjudicatory E-Filing system requires submission of such Requirements in the IST [Inservice Testing]
Program are removed, as they are duplicative
may seek assistance by contacting the information. For example, in some of requirements in the ASME OM Code, as
NRC’s Electronic Filing Help Desk instances, individuals provide home clarified by Code Case OMN–20, Inservice
through the ‘‘Contact Us’’ link located addresses in order to demonstrate Test Frequency. Other requirements in
on the NRC’s public Web site at http:// proximity to a facility or site. With Section 5.5.8, Inservice Testing Program are
www.nrc.gov/site-help/e- respect to copyrighted works, except for eliminated because the NRC has determined
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![38718 Federal Register / Vol. 82, No. 156 / Tuesday, August 15, 2017 / Notices
NW., Suite 200 East, Washington, DC accident from any accident previously consequences of an accident previously
20001. evaluated. evaluated?
NRC Branch Chief: Bruce Watson. 3. Does the proposed amendment involve Response: No.
a significant reduction in a margin of safety? The proposed change simply bring[s] the
FirstEnergy Nuclear Operating Response: No. [station’s] technical specifications into
Company, Docket No. 50–440, Perry The proposed change clarifies the purpose compliance with the current version of 10
Nuclear Power Plant, Unit No. 1, Lake of SR 3.8.1.13, which is to verify that non- CFR 50.68. There is no change to probability
County, Ohio critical automatic DG trips are bypassed in an or consequences of any accident previously
accident. Performance of the clarified SR will evaluated.
Date of amendment request: June 20, verify that the non-critical trips are bypassed Therefore, the proposed change does not
2017. A publicly-available version is in on simulated ECCS [emergency core cooling involve a significant increase in the
ADAMS under Accession No. system] actuation signals to ensure that probability or consequences of an accident
ML17171A301. actuation of a non-critical trip does not take previously evaluated.
Description of amendment request: a DG out of service during an emergency. The 2. Does the proposed amendment create
The proposed amendment would revise bypassing of the non-critical automatic DG the possibility of a new or different kind of
trips will maintain DG availability during an accident from any accident previously
a surveillance requirement (SR) in emergency so that it will be able to perform evaluated?
Technical Specification 3.8.1, ‘‘AC its assumed safety function. As such, the Response: No.
Sources—Operating,’’ to clarify that the safety function of the DGs remains The proposed change does not alter [any]
intent of the surveillance is to verify unaffected, so the change does not affect the safety limits, or safety analysis assumptions
that only the non-critical diesel margin of safety. associated with the operation of the plant.
generator (DG) trips are bypassed on an Therefore, the proposed change does not The proposed change does not introduce any
emergency core cooling system involve a significant reduction in a margin of new accident initiators, nor does the change
initiation signal. The proposed changes safety. reduce or adversely affect the capabilities of
are consistent with Technical The NRC staff has reviewed the any plant structure or system in the
Specification Task Force Improved licensee’s analysis and, based on this performance of its safety function.
Standard Technical Specifications Therefore, the proposed change does not
review, it appears that the three create the possibility of a new or different
Change Traveler 400–A, Revision 1, standards of 10 CFR 50.92(c) are kind of accident from any previously
‘‘Clarify SR on Bypass of DG Automatic satisfied. Therefore, the NRC staff evaluated.
Trips.’’ proposes to determine that the 3. Does the proposed amendment involve
Basis for proposed no significant amendment request involves no a significant reduction in a margin of safety?
hazards consideration determination: significant hazards consideration. Response: No.
As required by 10 CFR 50.91(a), the Attorney for licensee: David W. The proposed change does not alter the
licensee has provided its analysis of the Jenkins, Attorney, FirstEnergy manner in which safety limits or limiting
issue of no significant hazards Corporation, Mail Stop A–GO–15, 76 safety system settings are determined. The
consideration, which is presented South Main Street, Akron, OH 44308. safety analysis acceptance criteria are not
below: NRC Branch Chief: David J. Wrona. affected by the proposed change. The
proposed change does not change the design
1. Does the proposed amendment involve Omaha Public Power District, Docket function of any equipment assumed to
a significant increase in the probability or No. 50–285, Fort Calhoun Station (FCS), operate in the event of an accident.
consequences of an accident previously Therefore, the proposed change does not
evaluated?
Unit No. 1, Washington County,
Nebraska involve a significant reduction in a margin of
Response: No. safety.
The proposed change clarifies the purpose Date of amendment request: June 9,
of SR 3.8.1.13, which is to verify that non- The NRC staff has reviewed the
2017. A publicly-available version is in
critical automatic diesel generator (DG) trips licensee’s analysis and, based on this
ADAMS under Accession No.
are bypassed in an accident. The DG review, it appears that the three
automatic trips and their bypasses are not ML17160A405.
Description of amendment request: standards of 10 CFR 50.92(c) are
initiators of any accident previously satisfied. Therefore, the NRC staff
evaluated. Therefore, the probability of any The proposed amendment would delete
Technical Specifications (TSs) 2.8.3(6), proposes to determine that the
accident is not significantly increased. The
function of the DGs in mitigating accidents ‘‘Spent Fuel Cask Loading,’’ and amendment request involves no
is not changed. The revised SR continues to associated Figure 2–11, ‘‘Limiting significant hazards consideration.
ensure the DGs will operate as assumed in Attorney for licensee: David A. Repka,
Burnup Criteria for Acceptable Storage
the accident analyses. Therefore, the Esq., Winston & Strawn, 1700 K Street
in Spent Fuel Cask’’; TS 3.2 Table 3–
consequences of any accident previously NW., Washington, DC 20006–3817.
evaluated are not affected. 5(24), ‘‘Spent Fuel Cask Loading’’; TS NRC Branch Chief: Douglas A.
Therefore, the proposed change does not 4.3.1.3, Design Features associated with Broaddus.
involve a significant increase in the spent fuel casks; and portions of TS 3.2,
probability or consequences of an accident Table 3–4(5), Footnote (4) on boron Omaha Public Power District, Docket
previously evaluated. concentration associated with cask No. 50–285, Fort Calhoun Station (FCS),
2. Does the proposed amendment create loading. The deletion of the TS sections Unit No. 1, Washington County,
the possibility of a new or different kind of will bring the FCS TSs into Nebraska
accident from any accident previously
evaluated?
conformance with 10 CFR 50.68(c) Date of amendment request: June 16,
Response: No. ‘‘Criticality accident requirements.’’ 2017. A publicly-available version is in
The proposed change clarifies the purpose Basis for proposed no significant ADAMS under Accession No.
of SR 3.8.1.13, which is to verify that non- hazards consideration determination: ML17167A057.
mstockstill on DSK30JT082PROD with NOTICES
critical automatic DG trips are bypassed in an As required by 10 CFR 50.91(a), the Description of amendment request:
accident. The proposed change does not licensee has provided its analysis of the The proposed amendment would
involve a physical alteration of the plant (no issue of no significant hazards
new or different type of equipment will be
remove the FCS Cyber Security Plan
consideration, which is presented (CSP) from the FCS Operating License
installed) or a change in the methods
governing normal plant operation.
below: Condition.
Thus, this change does not create the 1. Does the proposed amendment involve Basis for proposed no significant
possibility of a new or different kind of a significant increase in the probability or hazards consideration determination:
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![Federal Register / Vol. 82, No. 156 / Tuesday, August 15, 2017 / Notices 38719
As required by 10 CFR 50.91(a), the standards of 10 CFR 50.92(c) are probabilities of the accidents evaluated in the
licensee has provided its analysis of the satisfied. Therefore, the NRC staff plant-specific UFSAR are not affected. The
issue of no significant hazards proposes to determine that the proposed changes do not involve a change to
any mitigation sequence or the predicted
consideration, which is presented amendment request involves no radiological releases due to postulated
below: significant hazards consideration. accident conditions, thus, the consequences
1. Does the proposed amendment involve Attorney for licensee: David A. Repka, of the accidents evaluated in the UFSAR are
a significant increase in the probability or Esq., Winston & Strawn, 1700 K Street not affected.
consequences of an accident previously NW., Washington, DC 20006–3817. Therefore, the proposed amendment does
evaluated? NRC Branch Chief: Douglas A. not involve a significant increase in the
Response: No. Broaddus. probability or consequences of an accident
The proposed change to remove the [FCS previously evaluated.
CSP] requirement does not alter accident Southern Nuclear Operating Company, 2. Does the proposed amendment create
analysis assumptions, add any initiators, or Inc., Docket Nos. 52–025 and 52–026, the possibility of a new or different kind of
affect the function of plant systems or the Vogtle Electric Generating Plant (VEGP), accident from any accident previously
manner in which systems are operated, Units 3 and 4, Burke County, Georgia evaluated?
maintained, modified, tested, or inspected. Response: No.
The proposed change does not require any
Date of amendment request: June 23, The proposed changes do not adversely
plant modifications which affect the 2017. A publicly-available version is in affect any system or design function or
performance capability of the structures, ADAMS under Accession No. equipment qualification as the change does
systems, and components [SSCs] relied upon ML17179A171. not modify any SSCs that prevent safety
to mitigate the consequences of postulated Description of amendment request: functions from being performed. The changes
accidents, and has no impact on the The requested amendment requires do not introduce a new failure mode,
probability or consequences of an accident malfunction or sequence of events that could
changes to the Updated Final Safety adversely affect safety or safety-related
previously evaluated. Analysis Report (UFSAR) in the form of
Therefore, the proposed change does not equipment.
departures from the plant-specific Therefore, the proposed amendment does
involve a significant increase in the
probability or consequences of an accident
Design Control Document Tier 2 not create the possibility of a new or different
previously evaluated. information and involves changes to the kind of accident from any accident
2. Does the proposed amendment create VEGP Units 3 and 4 COL Appendix A, previously evaluated.
the possibility of a new or different kind of Technical Specifications (TS). 3. Does the proposed amendment involve
accident from any accident previously Specifically, the proposed changes a significant reduction in a margin of safety?
Response: No.
evaluated? revise plant-specific Tier 2 information
Response: No. The proposed changes would not affect any
to add the time delay assumed in the safety-related design code, function, design
The proposed change to remove the [FCS safety analysis for the reactor trip on a analysis, safety analysis input or result, or
CSP] requirement does not alter accident safeguards actuation (‘‘S’’) signal to existing design/safety margin. No safety
analysis assumptions, add any initiators, or
affect the function of plant systems or the
UFSAR Table 15.0–4a. This is also analysis or design basis acceptance limit/
reflected in the proposed revision to TS criterion is challenged or exceeded by the
manner in which systems are operated,
3.3.4, Reactor Trip System (RTS) requested changes.
maintained, modified, tested, or inspected.
Engineered Safety Feature Actuation Therefore, the proposed amendment does
The proposed change does not require any
not involve a significant reduction in a
plant modifications which affect the System (ESFAS) Instrumentation, to add
margin of safety.
performance capability of the [SSCs] relied a surveillance requirement to verify the
upon to mitigate the consequences of RTS response time for this ‘‘S’’ signal. The NRC staff has reviewed the
postulated accidents, and has no impact on The request also includes proposed licensee’s analysis and, based on this
the probability or consequences of an changes to TS 3.3.7, RTS Trip Actuation review, it appears that the three
accident previously evaluated. standards of 10 CFR 50.92(c) are
Devices, to clarify that the requirements
Therefore, the proposed change does not satisfied. Therefore, the NRC staff
create the possibility of a new or different for reactor trip breaker (RTB)
undervoltage and shunt trip proposes to determine that the
kind of accident from any previously
evaluated. mechanisms apply only to in-service amendment request involves no
3. Does the proposed amendment involve RTBs. In addition, the request includes significant hazards consideration.
a significant reduction in a margin of safety? proposed changes to TS 3.3.9, ESFAS Attorney for licensee: Mr. M. Stanford
Response: No. Manual Initiation, to correct the Blanton, Balch & Bingham LLP, 1710
The amendment proposes the elimination nomenclature for the Chemical and Sixth Avenue North Birmingham, AL
of the CSP as set forth in the CSP Volume Control System, which is 35203–2015.
Implementation Schedule and associated NRC Branch Chief: Jennifer Dixon-
advertently stated as the Chemical
regulatory commitments. The elimination of Herrity.
the CSP does not involve modifications to Volume and Control System.
any safety-related SSCs. The proposed Basis for proposed no significant III. Notice of Issuance of Amendments
amendment is based on the comparison of hazards consideration determination: to Facility Operating Licenses and
the risks at an operating nuclear power As required by 10 CFR 50.91(a), the Combined Licenses
reactor as opposed to a nuclear power reactor licensee has provided its analysis of the
that has permanently ceased operations and
During the period since publication of
issue of no significant hazards
has removed all fuel from the reactor vessel. the last biweekly notice, the
consideration, which is presented below
The spectrum of possible accidents are Commission has issued the following
NRC staff edits in square brackets:
significantly fewer and the risk of an offsite amendments. The Commission has
radiological release is significantly lower for 1. Does the proposed amendment involve determined for each of these
mstockstill on DSK30JT082PROD with NOTICES
a permanently defueled reactor. a significant increase in the probability or amendments that the application
Therefore, the proposed change does not consequences of an accident previously complies with the standards and
involve a significant reduction in a margin of evaluated?
Response: No.
requirements of the Atomic Energy Act
safety. of 1954, as amended (the Act), and the
The changes do not involve an interface
The NRC staff has reviewed the with any [structure, system, and component Commission’s rules and regulations.
licensee’s analysis and, based on this (SSC)] accident initiator or initiating The Commission has made appropriate
review, it appears that the three sequence of events, and thus, the findings as required by the Act and the
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![38720 Federal Register / Vol. 82, No. 156 / Tuesday, August 15, 2017 / Notices
Commission’s rules and regulations in amendments revised the Operating Brief description of amendments: The
10 CFR chapter I, which are set forth in Licenses and TSs. amendments modified Technical
the license amendment. Date of initial notice in Federal Specification (TS) 3.1.8, ‘‘PHYSICS
A notice of consideration of issuance Register: April 5, 2016 (81 FR 19644). TESTS Exceptions,’’ to allow the
of amendment to facility operating The supplements dated June 30, October numbers of channels required by the
license or combined license, as 6, November 9, and November 23, 2016; Limiting Condition of Operation (LCO)
applicable, proposed no significant and March 3 and May 24, 2017, section of TS 3.3.1, ‘‘Reactor Trip
hazards consideration determination, provided additional information that System (RTS) Instrumentation,’’ to be
and opportunity for a hearing in clarified the application, did not expand reduced from ‘‘4’’ to ‘‘3’’ to allow one
connection with these actions, was the scope of the application as originally nuclear instrumentation channel to be
published in the Federal Register as noticed, and did not change the NRC used as an input to the reactivity
indicated. staff’s original proposed no significant computer for physics testing without
Unless otherwise indicated, the hazards consideration determination as placing the nuclear instrumentation
Commission has determined that these published in the Federal Register. channel in a tripped condition. The
amendments satisfy the criteria for The Commission’s related evaluation changes are consistent with Technical
categorical exclusion in accordance of the amendments is contained in a Specifications Task Force (TSTF)
with 10 CFR 51.22. Therefore, pursuant Safety Evaluation dated July 28, 2017. Traveler TSTF–315–A, Revision 0,
to 10 CFR 51.22(b), no environmental No significant hazards consideration ‘‘Reduce plant trips due to spurious
impact statement or environmental comments received: No. signals to the NIS [Nuclear
assessment need be prepared for these Duke Energy Carolinas, LLC, Docket Instrumentation System] during physics
amendments. If the Commission has Nos. 50–413 and 50–414, Catawba testing.’’
prepared an environmental assessment Nuclear Station, Units 1 and 2, York Date of issuance: July 26, 2017.
under the special circumstances County, South Carolina Effective date: These license
provision in 10 CFR 51.22(b) and has amendments are effective as of its date
Date of application for amendments:
made a determination based on that of issuance and shall be implemented
December 15, 2016.
assessment, it is so indicated. Brief description of amendments: The within 120 days of issuance.
For further details with respect to the Amendment Nos.: 291 (Unit 1) and
amendments modified Technical
action see (1) the applications for 287 (Unit 2). A publicly-available
Specification (TS) 3.6.3, ‘‘Containment
amendment, (2) the amendment, and (3) version is in ADAMS under Accession
Isolation Valves,’’ to add a Note to TS
the Commission’s related letter, Safety No. ML17172A428; documents related
Limiting Condition for Operation (LCO)
Evaluation and/or Environmental to these amendments are listed in the
3.6.3 Required Actions A.2, C.2, and E.2
Assessment as indicated. All of these Safety Evaluation enclosed with the
to allow isolation devices that are
items can be accessed as described in amendments.
locked, sealed, or otherwise secured to
the ‘‘Obtaining Information and Renewed Facility Operating License
be verified by use of administrative
Submitting Comments’’ section of this means. The changes are consistent with Nos. NPF–35 and NPF–52: Amendments
document. NRC-approved Technical Specifications revised the licenses and TSs.
Date of initial notice in Federal
Arizona Public Service Company, et al., Task Force (TSTF) Traveler TSTF–269–
Register: April 25, 2017 (82 FR 19098).
Docket Nos. STN 50–528, STN 50–529, A, Revision 2, ‘‘Allow administrative
The Commission’s related evaluation
and STN 50–530, Palo Verde Nuclear means of position verification for locked
of the amendments is contained in a
Generating Station (PVNGS), Units 1, 2, or sealed valves.’’
Date of issuance: July 21, 2017. Safety Evaluation dated July 26, 2017.
and 3, Maricopa County, Arizona No significant hazards consideration
Effective date: These license
Date of application for amendment: amendments are effective as of their comments received: No.
November 25, 2015, as supplemented by date of issuance and shall be Energy Northwest, Docket No. 50–397,
letters dated January 29, June 30, implemented within 120 days of Columbia Generating Station
October 6, November 9, and November issuance. (Columbia), Benton County, Washington
23, 2016; and March 3 and May 24, Amendment Nos.: 290 and 286. A
2017. publicly available version is in ADAMS Date of application for amendment:
Brief Description of amendment: The under Accession No. ML17165A441; July 14, 2016, as supplemented by letter
amendments revised the Technical documents related to these amendments dated July 5, 2017.
Specifications (TSs) for PVNGS, by Brief description of amendment: The
are listed in the Safety Evaluation
modifying the requirements to amendment changed the Columbia
enclosed with the amendments.
incorporate the results of an updated Renewed Facility Operating License Technical Specifications (TSs)
criticality safety analysis for both new Nos. NPF–35 and NPF–52: Amendments consistent with TS Task Force (TSTF)
and spent fuel storage. revised the licenses and TSs. Standard Technical Specifications
Date of issuance: July 28, 2017. Date of initial notice in Federal Change Traveler TSTF–545, Revision 3,
Effective date: As of the date of Register: April 25, 2017 (82 FR 19098). ‘‘TS Inservice Testing Program Removal
issuance and shall be implemented The Commission’s related evaluation & Clarify SR [Surveillance Requirement]
within 90 days from the date of of the amendments is contained in a Usage Rule Application to Section 5.5
issuance. Safety Evaluation dated July 21, 2017. Testing,’’ dated October 21, 2015.
Amendment Nos.: Unit 1—203, Unit No significant hazards consideration Date of issuance: July 24, 2017.
2—203, and Unit 3—203. A publicly- Effective date: As of its date of
mstockstill on DSK30JT082PROD with NOTICES
comments received: No.
available version is in ADAMS under issuance and shall be implemented
Accession No. ML17188A412; Duke Energy Carolinas, LLC, Docket within 60 days from the date of
documents related to these amendments Nos. 50–413 and 50–414, Catawba issuance.
are listed in the Safety Evaluation Nuclear Station, Units 1 and 2, York Amendment No.: 243. A publicly-
enclosed with the amendments. County, South Carolina available version is in ADAMS under
Renewed Facility Operating License Date of application for amendments: Accession No. ML17187A257;
Nos. NPF–41, NPF–51, and NPF–74: The December 15, 2016. documents related to this amendment
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![Federal Register / Vol. 82, No. 156 / Tuesday, August 15, 2017 / Notices 38721
are listed in the Safety Evaluation ADAMS under Accession Nos. are listed in the Safety Evaluation
enclosed with the amendment. ML16237A066 and ML17110A068, enclosed with the amendment.
Renewed Facility Operating License respectively. Renewed Facility Operating License
No. NPF–21: The amendment revised Brief description of amendments: The No. DPR–40: The amendment revised
the Facility Operating License and TSs. amendment consists of changes to the the license.
Date of initial notice in Federal technical specifications (TSs) for PBNP, Date of initial notice in Federal
Register: September 27, 2016 (81 FR Unit 1. The amendment makes changes Register: November 8, 2016 (81 FR
66304). The supplemental letter dated to TS 3.4.13, ‘‘RCS Operational 78650). The supplemental letters dated
July 5, 2017, provided additional LEAKAGE,’’ TS 5.5.8, ‘‘Steam Generator March 3 and April 5, 2017, provided
information that clarified the (SG) Program,’’ and TS 5.6.8, ‘‘Steam additional information that clarified the
application, did not expand the scope of Generator Tube Inspection Report,’’ in application, did not expand the scope of
the application as originally noticed, order to implement the H* (pronounced the application as originally noticed,
and did not change the staff’s original H-star) alternate repair criteria on a and did not change the staff’s proposed
proposed no significant hazards permanent basis. no significant hazards consideration
consideration determination as Date of issuance: July 27, 2017. determination as published in the
published in the Federal Register. Effective date: As of the date of Federal Register.
The Commission’s related evaluation issuance and shall be implemented
of the amendment is contained in a The Commission’s related evaluation
within 90 days of issuance. of the amendment is contained in a
Safety Evaluation dated July 24, 2017. Amendment No.: 260. A publicly-
No significant hazards consideration Safety Evaluation dated July 27, 2017.
available version is in ADAMS under
comments received: No. Accession No. ML17159A778; No significant hazards consideration
documents related to this amendment comments received: No.
Entergy Operations, Inc., Docket No. 50–
382, Waterford Steam Electric Station, are listed in the Safety Evaluation Omaha Public Power District, Docket
Unit 3 (Waterford 3), St. Charles Parish, enclosed with the amendment. No. 50–285, Fort Calhoun Station (FCS),
Louisiana Renewed Facility Operating License Unit 1, Washington County, Nebraska
No. DPR–24: Amendment revised the
Date of amendment request: July 25, Date of amendment request:
Facility Operating License and TSs.
2016. September 28, 2016, as supplemented
Date of initial notice in Federal
Brief description of amendment: The by letter dated April 27, 2017.
Register: December 6, 2016 (81 FR
amendment changed the Waterford 3 Brief description of amendment: The
87961). The supplemental letter dated
Technical Specifications (TSs) amendment revised the Technical
April 20, 2017, provided additional
consistent with Technical Specifications Specifications (TSs) to make
information that clarified the
Task Force (TSTF) Standard Technical administrative changes to align staffing
application, did not expand the scope of
Specifications Change Traveler TSTF– for permanently defueled condition at
the application as originally noticed,
545, Revision 3, ‘‘TS Inservice Testing FCS.
and did not change the staff’s original
Program Removal & Clarify SR Date of issuance: July 28, 2017.
proposed no significant hazards
[Surveillance Requirement] Usage Rule
consideration determination as Effective date: As of the date of
Application to Section 5.5 Testing,’’
published in the Federal Register. issuance and shall be implemented
dated October 21, 2015.
Date of issuance: July 27, 2017. The Commission’s related evaluation within 90 days from the date of
Effective date: As of the date of of the amendment is contained in a issuance.
issuance and shall be implemented 90 Safety Evaluation dated July 27, 2017. Amendment No.: 292. A publicly-
days from the date of issuance. No significant hazards consideration available version is in ADAMS under
Amendment No.: 250. A publicly- comments received: No. Accession No. ML17165A465;
available version is in ADAMS under Omaha Public Power District, Docket documents related to this amendment
Accession No. ML17192A007; No. 50–285, Fort Calhoun Station (FCS), are listed in the Safety Evaluation
documents related to this amendment Unit 1, Washington County, Nebraska enclosed with the amendment.
are listed in the Safety Evaluation Renewed Facility Operating License
enclosed with the amendment. Date of amendment request: No. DPR–40: The amendment revised
Facility Operating License No. NPF– September 2, 2016, as supplemented by the Renewed Facility Operating License
38: The amendment revised the Facility letters dated March 3 and April 5, 2017. and TSs.
Operating License and TSs. Brief description of amendment: The
amendment revised the Nuclear Date of initial notice in Federal
Date of initial notice in Federal Register: November 8, 2016 (81 FR
Register: November 8, 2016 (81 FR Radiological Emergency Response Plan
for FCS for the plant condition 78650).
78647). The supplemental letter dated April
The Commission’s related evaluation following permanent cessation of power
operations and defueling to reflect 27, 2017, provided additional
of the amendment is contained in a
changes in the shift staffing and information that clarified the
Safety Evaluation dated July 27, 2017.
Emergency Response Organization application, did not expand the scope of
No significant hazards consideration
staffing. the application as originally noticed,
comments received: No.
Date of issuance: July 27, 2017. and did not change the original
NextEra Energy, Point Beach, LLC, Effective date: As of the date of proposed no significant hazards
mstockstill on DSK30JT082PROD with NOTICES
Docket No. 50–266, Point Beach Nuclear issuance and shall be implemented consideration determination as
Plant (PBNP), Unit 1, Town of Two within 60 days from the date of published in the Federal Register.
Creeks, Manitowoc County, Wisconsin issuance. The Commission’s related evaluation
Date amendment request: July 29, Amendment No.: 291. A publicly- of the amendment is contained in a
2016, as supplemented by letter dated available version is in ADAMS under Safety Evaluation dated July 28, 2017.
April 20, 2017. Publicly-available Accession No. ML17123A348; No significant hazards consideration
versions of these documents are in documents related to this amendment comments received: No.
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![38722 Federal Register / Vol. 82, No. 156 / Tuesday, August 15, 2017 / Notices
Southern Nuclear Operating Company, Specification (TS) 3.6.4.3, ‘‘Standby Gas Effective date: As of the date of
Docket Nos. 52–025 and 52–026, Vogtle Treatment (SGT) System,’’ and TS 3.7.3, issuance and shall be implemented
Electric Generating Plant (VEGP), Units ‘‘Control Room Emergency Outside Air within 60 days of issuance.
3 and 4, Burke County, Georgia Supply (CREOAS) System,’’ by changing Amendment Nos.: 290 and 290. A
the run time of monthly surveillance publicly-available version is in ADAMS
Date of amendment request: January
requirements for the standby gas under Accession No. ML17170A183;
20, 2017, and supplemented by letter
treatment and control room emergency documents related to these amendments
dated June 6, 2017.
outside air supply systems from 10 are listed in the Safety Evaluation
Description of amendment: The
hours to 15 minutes. This change is enclosed with the amendments.
amendments consist of changes to the Facility Operating License No. NPF–4
VEGP Units 3 and 4 Updated Final consistent with Technical Specifications
Task Force (TSTF) Traveler TSTF–522, and NPF–7: Amendments revised the
Safety Analysis Report (UFSAR) in the Facility Operating Licenses and TSs.
form of departures from plant-specific Revision 0, ‘‘Revise Ventilation System
Surveillance Requirements to Operate Date of initial notice in Federal
Design Control Document Tier 2 Register: October 25, 2016 (81 FR
information, Combined License (COL) for 10 hours per Month,’’ with minor
variations. The notice of availability and 73443). The letters dated January 31,
Appendix A Technical Specifications, 2017, March 1, 2017 and March 10,
and COL Appendix C information. The model safety evaluation of TSTF–522,
Revision 0, were published in the 2017, provided additional information
departures consist of in-containment that clarified the application, did not
refueling water storage tank (IRWST) Federal Register on September 20, 2012
(77 FR 58421). expand the scope of the application as
minimum volume changes in plant- originally noticed, and did not change
specific UFSAR Table 14.3–2, COL Date of issuance: July 28, 2017.
Effective date: As of the date of the staff’s original proposed no
Appendix A Technical Specifications significant hazards consideration
3.5.6, 3.5.7 and 3.5.8 and Surveillance issuance and shall be implemented
within 60 days of issuance. determination as published in the
Requirements 3.5.6.2 and 3.5.8.2 and Federal Register.
COL Appendix C (and associated plant- Amendment Nos.: 268 (Unit 1) and
250 (Unit 2). A publicly-available The Commission’s related evaluation
specific Tier 1) Table 2.2.3–4. The of the amendment is contained in a
changes restore the desired consistency version is in ADAMS under Accession
No. ML17187A297; documents related Safety Evaluation dated July 28, 2017.
of these sections with the UFSAR No significant hazards consideration
IRWST minimum volume value in other to these amendments are listed in the
comments received: No.
locations. Safety Evaluation enclosed with the
amendments. Dated at Rockville, Maryland, this 4th day
Date of issuance: July 6, 2017. of August 2017.
Effective date: As of the date of Renewed Facility Operating License
Nos. NPF–14 and NPF–22: The For the Nuclear Regulatory Commission.
issuance and shall be implemented
within 30 days of issuance. amendments revised the Renewed Anne T. Boland,
Amendment Nos.: 81 and 80. A Facility Operating Licenses and TSs. Director, Division of Operating Reactor
publicly-available version is in ADAMS Date of initial notice in Federal Licensing, Office of Nuclear Reactor
Register: April 11, 2017 (82 FR 17461). Regulation.
under Accession No. ML17171A137;
documents related to this amendment The supplemental letter dated May 17, [FR Doc. 2017–16998 Filed 8–14–17; 8:45 am]
are listed in the Safety Evaluation 2017, provided additional information BILLING CODE 7590–01–P
enclosed with the amendment. that clarified the application, did not
Facility Combined Licenses No. NPF– expand the scope of the application as
91 and NPF–92: Amendment revised the originally noticed, and did not change OVERSEAS PRIVATE INVESTMENT
Facility Combined Licenses. the NRC staff’s original proposed no CORPORATION
Date of initial notice in Federal significant hazards consideration
Register: March 14, 2017 (82 FR determination as published in the Sunshine Notice—September 6, 2017
13662). The supplemental letter dated Federal Register. Public Hearing
June 6, 2017, provided additional The Commission’s related evaluation
TIME AND DATE: 2:00 p.m., Wednesday,
information that clarified the of the amendments is contained in a
September 6, 2017.
application, did not expand the scope of Safety Evaluation dated July 28, 2017.
No significant hazards consideration PLACE: Offices of the Corporation,
the application request as originally
comments received: No. Twelfth Floor Board Room, 1100 New
noticed, and did not change the staff’s
York Avenue NW., Washington, DC.
original proposed no significant hazards Virginia Electric and Power Company, STATUS: Hearing OPEN to the Public at
consideration determination as Docket Nos. 50–280 and 50–281, Surry
published in the Federal Register. 2:00 p.m.
Power Station, Units No. 1 and No. 2, PURPOSE: Public Hearing in conjunction
The Commission’s related evaluation Surry County, Virginia
of the amendment is contained in the with each meeting of OPIC’s Board of
Safety Evaluation dated July 6, 2017. Date of amendment request: July 14, Directors, to afford an opportunity for
No significant hazards consideration 2016, as supplemented by letters dated any person to present views regarding
comments received: No. January 31, 2017, March 1, 2017 and the activities of the Corporation.
March 10, 2017. PROCEDURES: Individuals wishing to
Susquehanna Nuclear, LLC, Docket Nos. Brief description of amendments: The address the hearing orally must provide
50–387 and 50–388, Susquehanna amendments would extend the advance notice to OPIC’s Corporate
mstockstill on DSK30JT082PROD with NOTICES
Steam Electric Station, Units 1 and 2, Technical Specification (TS) 3.14.B Secretary no later than 5 p.m.
Luzerne County, Pennsylvania allowed outage time for one inoperable Wednesday, August 30, 2017. The
Date of amendment request: February emergency service water (ESW) pump notice must include the individual’s
1, 2017, as supplemented by letter dated from 7 to 14 days to provide operational name, title, organization, address, and
May 17, 2017. flexibility for ESW pump maintenance telephone number, and a concise
Brief description of amendments: The and repairs. summary of the subject matter to be
amendments revised Technical Date of issuance: July 28, 2017. presented.
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Document Created: 2017-08-15 01:12:47
Document Modified: 2017-08-15 01:12:47
| 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 14, 2017. A request for a hearing must be filed by October 16, 2017. | |
| Contact | Beverly Clayton, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; telephone: 301-415-3475, email: [email protected] | |
| FR Citation | 82 FR 38714 |
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