82 FR 12130 - 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 38 (February 28, 2017)
Federal Register Volume 82, Issue 38 (February 28, 2017)
| Page Range | 12130-12142 | |
| FR Document | 2017-03806 |
[Federal Register Volume 82, Number 38 (Tuesday, February 28, 2017)] [Notices] [Pages 12130-12142] From the Federal Register Online [www.thefederalregister.org] [FR Doc No: 2017-03806] ----------------------------------------------------------------------- NUCLEAR REGULATORY COMMISSION [NRC-2017-0058] 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 January 31, 2017 to February 13, 2017. The last biweekly notice was published on February 14, 2017. DATES: Comments must be filed March 30, 2017. A request for a hearing must be filed May 1, 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-2017-0058. Address questions about NRC dockets to Carol Gallagher; telephone: 301-415- 3463; email: [email protected]. For technical questions, contact the individual or individuals listed in the FOR FURTHER INFORMATION CONTACT section of this document. Mail comments to: Cindy Bladey, Office of Administration, Mail Stop: OWFN-12-H08, 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-2017-0058, 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-2017-0058. 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. [[Page 12131]] 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-2017-0058, 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. 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 [[Page 12132]] 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 by May 1, 2017. 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 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 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 [[Page 12133]] 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. Florida Power & Light Company, et al., Docket No. 50-335 and 50-389, St. Lucie Plant, Unit Nos. 1 and 2, St. Lucie County, Florida Date of amendment request: December 22, 2016. A publicly-available version is in ADAMS under Accession No. ML17006A007. Description of amendment request: The amendments would relocate the Component Cyclic or Transient Limits Program requirements to the Administrative Controls sections of the Technical Specifications (TSs), and relocate the Component Cyclic or Transient Limits tables detailing the allowable limits from the respective TSs to licensee-controlled documents. 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 relocation of Component Cyclic or Transient Limits Table 5.9-1 and Table 5.7-1 from the St. Lucie Unit 1 and Unit 2 TS[s], to the St. Lucie Unit 1 and Unit 2 UFSARs [Updated Final Safety Analysis Reports], and the relocation of the Component Cyclic or Transient Limits Program requirements within the St. Lucie Unit 1 and Unit 2 TS[s] are administrative changes in nature. The TS changes do not represent any physical change to plant systems, structures, or components, or to procedures established for plant operation. As such, the initial conditions associated with accidents previously evaluated and plant systems credited for mitigating the consequences of accidents previously evaluated remain unchanged. Therefore, facility operation in accordance with the proposed license amendments would 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 relocation of Component Cyclic or Transient Limits tables from the St. Lucie Unit 1 and Unit 2 TS[s], to the St. Lucie Unit 1 and Unit 2 UFSARs, and the relocation of the Component Cyclic or Transient Limits Program requirements within the St. Lucie Unit 1 and Unit 2 TS[s] are administrative changes in nature. No physical change to plant systems, structures, or components, or the manner in which they are operated and maintained will result from the proposed license amendments. 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 relocation of Component Cyclic or Transient Limits tables from the St. Lucie Unit 1 and Unit 2 TS[s], to the St. Lucie Unit 1 and Unit 2 UFSARs, and the relocation of the Component Cyclic or Transient Limits Program requirements within the St. Lucie Unit 1 and Unit 2 TS[s] are administrative changes in nature. As such, the proposed changes do not involve changes to any safety analyses assumptions, safety limits, or limiting safety system settings nor do they adversely impact plant operating margins or the reliability of equipment credited in safety analyses. Therefore, operation of the facility in accordance with the proposed amendment will not involve a significant reduction in the margin of safety. The NRC staff has reviewed the licensee's analysis and, based on this review, it appears that the three standards of 50.92(c) are satisfied. Therefore, the NRC staff proposes to determine that the amendment request involves no significant hazards consideration. Attorney for licensee: William S. Blair, Managing Attorney-- Nuclear, Florida Power & Light Company, 700 Universe Boulevard, MS LAW/ JB, Juno Beach, FL 33408-0420. NRC Branch Chief: Benjamin G. Beasley. Indiana Michigan Power Company (I&M), Docket Nos. 50-315 and 50-316, Donald C. Cook Nuclear Plant (CNP), Units 1 and 2, Berrien County, Michigan Date of amendment request: December 14, 2016. A publicly-available version is in ADAMS under Accession No. ML16351A198. Description of amendment request: The proposed changes would revise the note regarding applicability of the limiting condition for operation (LCO) for CNP Technical Specification (TS) 3.9.3, ``Containment Penetrations.'' 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 accident in question for this submittal is the FHA [fuel- handling accident]. The analysis for the FHA was recently reviewed and approved by the NRC for a license amendment request regarding use of alternative source term. The proposed amendment to TS 3.9.3 does not impact the assumed release pathway for the accident and has no effect on the probability of the occurrence of any accident previously evaluated. The proposed change does not alter any plant equipment or operating practices in such a manner that the probability of an accident previously evaluated is increased. The consequences of [an] FHA inside the containment building with open penetration flow paths is bounded by the current FHA analyses and administrative controls, so the probability of an accident is not affected by the status of the penetration flow paths. Therefore, the probability or consequences of an accident previously evaluated will not be significantly increased. 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated? Response: No. Allowing penetration flow paths to be open is not an initiator for any accident. The change impacts the containment requirements during refueling operations. The only accident which could result in significant releases of radioactivity during refueling is the FHA. The proposed change does not affect the design of containment, or alter plant operating practices such that it creates the possibility of a new or different [[Page 12134]] kind of accident from any accident previously evaluated. The proposed allowance to open any containment penetration under administrative controls during fuel movement will not adversely affect plant safety functions such that a new or different accident could be created. No other initiators or accident precursors are created by this change. Therefore, the possibility of a new or different kind of accident not previously evaluated is not created. 3. Does the proposed change involve a significant reduction in a margin of safety? Response: No. TS 3.9.3 closure requirements for containment penetrations ensure that the consequences of a postulated FHA inside containment during irradiated fuel handling activities are minimized. The LCO establishes containment closure requirements, which limit the potential escape paths for fission products by ensuring that there is at least one barrier to the release of radioactive material. The proposed change to allow any containment penetration flow path to be open during refueling operations under administrative controls does not significantly affect the expected dose consequences of [an] FHA because the limiting FHA does not credit containment building closure or filtration. The administrative controls provide assurance that closure of the applicable penetration flow paths will be accomplished and that the offsite dose consequences will be minimized in the event of [an] FHA inside the containment building. Therefore, this 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: Robert B. Haemer, Senior Nuclear Counsel, One Cook Place, Bridgman, MI 49106. NRC Branch Chief: David J. Wrona. South Carolina Electric & Gas Company and South Carolina Public Service Authority, Docket Nos. 52-027 and 52-028, Virgil C. Summer Nuclear Station Units 2 and 3, Fairfield County, South Carolina Date of amendment request: January 20, 2017. A publicly-available version is in ADAMS under Accession No. ML17020A097. Description of amendment request: The requested amendment proposes to depart from Tier 2* information in the Updated Final Safety Analysis Report to address the seismic Category and AP1000 equipment class of nonsafety-related instrumentation that interfaces with safety-related pressure boundaries. 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 changes to nonsafety-related instrument classification methodology will allow nonsafety-related instrumentation connected to safety-related systems to be appropriately qualified to withstand a safe shutdown earthquake without adversely affecting a safety-related pressure boundary. The safe shutdown fire analysis is not affected, and the fire protection analysis results are not adversely affected. The proposed changes do not involve any accident, initiating event or component failure; thus, the probabilities of the accidents previously evaluated are not affected. The proposed change does not adversely affect compliance with the maximum allowable reactor coolant system operational leakage rates specified in the Technical Specifications, and radiological material release source terms are not affected; thus, the radiological releases in the accident analyses 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 to nonsafety-related instrument classification methodology will allow nonsafety-related instrumentation connected to safety-related systems to be appropriately qualified to withstand a safe shutdown earthquake without adversely affecting a safety-related pressure boundary. The proposed changes do not adversely affect any safety-related system, structure, or component. The nonsafety-related instrumentation provides information for nonsafety-related display and does not control any safety-related feature. Thus, the proposed changes do not introduce a new failure mode. The proposed changes to the nonsafety-related instrument classification methodology do not create a new fault or sequence of events that could result in a radioactive material release. 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 to nonsafety-related instrument classification methodology will allow nonsafety-related instrumentation connected to safety-related systems to be appropriately qualified to withstand a safe shutdown earthquake without adversely affecting a safety-related pressure boundary. The upgrade in the qualification of the sensing lines and associated instrument isolation valves does not affect the function of the safety-related systems to which they are connected. No safety analysis or design basis acceptance limit/criterion is challenged or exceeded by the proposed change, thus no margin of safety is reduced. 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: Ms. Kathryn M. Sutton, Morgan, Lewis & Bockius, LLC, 1111 Pennsylvania Avenue NW., Washington, DC 20004-2514. NRC Branch Chief: Jennifer Dixon-Herrity. Southern Nuclear Operating Company, Inc., Docket Nos. 52-025 and 52- 026, Vogtle Electric Generating Plant Units 3 and 4, Burke County, Georgia Date of amendment request: December 16, 2016, as supplemented by letter dated January 12, 2017. A publicly-available version is in ADAMS under Accession Nos. ML16351A483 and ML17012A272, respectively. Description of amendment request: The requested amendment proposes to depart from Tier 2* information in the Updated Final Safety Analysis Report to address the seismic Category and AP1000 equipment class of nonsafety-related instrumentation that interfaces with safety-related pressure boundaries. 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 changes to nonsafety-related instrument classification methodology will allow nonsafety-related instrumentation connected to safety-related systems to be appropriately qualified to withstand a safe shutdown earthquake without adversely affecting a safety-related pressure boundary. The safe shutdown fire analysis is not affected, and the fire protection analysis results are not adversely affected. The proposed changes do not involve any accident, initiating event or component failure; thus, the probabilities of the accidents previously evaluated are not [[Page 12135]] affected. The proposed change does not adversely affect compliance with the maximum allowable reactor coolant system operational leakage rates specified in the Technical Specifications, and radiological material release source terms are not affected; thus, the radiological releases in the accident analyses 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 to nonsafety-related instrument classification methodology will allow nonsafety-related instrumentation connected to safety-related systems to be appropriately qualified to withstand a safe shutdown earthquake without adversely affecting a safety-related pressure boundary. The proposed changes do not adversely affect any safety-related system, structure, or component. The nonsafety-related instrumentation provides information for nonsafety-related display and does not control any safety-related feature. Thus, the proposed changes do not introduce a new failure mode. The proposed changes to the nonsafety-related instrument classification methodology do not create a new fault or sequence of events that could result in a radioactive material release. 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 to nonsafety-related instrument classification methodology will allow nonsafety-related instrumentation connected to safety-related systems to be appropriately qualified to withstand a safe shutdown earthquake without adversely affecting a safety-related pressure boundary. The upgrade in the qualification of the sensing lines and associated instrument isolation valves does not affect the function of the safety-related systems to which they are connected. No safety analysis or design basis acceptance limit/criterion is challenged or exceeded by the proposed change, thus no margin of safety is reduced. 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. Southern Nuclear Operating Company, Inc., Docket Nos. 50-424 and 50- 425, Vogtle Electric Generating Plant, Units 1 and 2, Burke County, Georgia; Docket Nos. 50-348 and 50-364, Joseph M. Farley Nuclear Plant, Units 1 and 2, Houston County, Alabama; Docket Nos. 50-321 and 50-366, Edwin I. Hatch Nuclear Plant, Units 1 and 2, Appling County, Georgia Date of amendment request: December 1, 2016. A publicly-available version is in ADAMS under Accession No. ML16340A005. Description of amendment request: The amendments would modify the technical specifications requirements in Section 1.3 and Section 3.0 regarding Limiting Condition for Operation (LCO) and Surveillance Requirement (SR) usage. These changes are consistent with NRC-approved Technical Specifications Task Force (TSTF) Traveler TSTF-529, ``Clarify Use and Application Rules.'' Basis for proposed no significant hazards consideration determination: As required by 10 CFR 50.91(a), the licensee has provided its analysis of the issue of no significant hazards consideration, which is presented below: 1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated? Response: No. The proposed changes to Section 1.3 and LCO 3.0.4 have no effect on the requirement for systems to be Operable and have no effect on the application of TS actions. The proposed change to SR 3.0.3 states that the allowance may only be used when there is a reasonable expectation the surveillance will be met when performed. Since the proposed change does not significantly affect system Operability, the proposed change will have no significant effect on the initiating events for accidents previously evaluated and will have no significant effect on the ability of the systems to mitigate accidents previously evaluated. Therefore, it is concluded that this change does not involve a significant increase in the probability or consequences of an accident previously evaluated. 2. Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated? The proposed change to the TS usage rules does not affect the design or function of any plant systems. The proposed change does not change the Operability requirements for plant systems or the actions taken when plant systems are not operable. Therefore, it is concluded that this change does not create the possibility of a new or different kind of accident from any accident previously evaluated. 3. Does the proposed changes involve a significant reduction in a margin of safety? The proposed change clarifies the application of Section 1.3 and LCO 3.0.4 and does not result in changes in plant operation. SR 3.0.3 is revised to allow application of SR 3.0.3 when a SR has not been previously performed if there is a reasonable expectation that the SR will be met when performed. This expands the use of SR 3.0.3 while ensuring the affected system is capable of performing its safety function. As a result, plant safety is either improved or unaffected. Therefore, it is concluded that this change does not involve a significant reduction in a margin of safety. The NRC staff has reviewed the licensee's analysis and, based on this review, it appears that the three standards of 10 CFR 50.92(c) are satisfied. Therefore, the NRC staff proposes to determine that the amendment request involves no significant hazards consideration. Attorney for licensee: Jennifer M. Buettner, Associate General Counsel of Operations and Nuclear, Southern Nuclear Operating Company, 40 Iverness Center Parkway, Birmingham, AL 35201. NRC Branch Chief: Michael T. Markley. Southern Nuclear Operating Company, Inc., Docket Nos. 50-424 and 50- 425, Vogtle Electric Generating Plant, Units 1 and 2, Burke County, Georgia Date of amendment request: November 15, 2016, as supplemented by letter dated January 13, 2017. Publicly-available versions are in ADAMS under Accession Nos. ML16320A207 and ML17013A603, respectively. Description of amendment request: The amendments would modify the TS requirements to operate ventilation systems with charcoal filters from 10 hours to 15 minutes each month in accordance with TSTF-522, Revision 0, ``Revise Ventilation System Surveillance Requirements to Operate for 10 hours per Month.'' The NRC approved TSTF-522, Revision 0, as a part of the consolidated line item improvement process on September 20, 2012 (77 FR 58421). 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 replaces an existing Surveillance Requirement to operate the Westinghouse CREFS [Control Room Emergency Filtration System] equipped with [[Page 12136]] electric heaters for a continuous 10 hour period at a frequency specified in the SFCP [Surveillance Frequency Control Program] with a requirement to operate the systems for 15 continuous minutes with heaters operating, if needed. This system is not an accident initiator and therefore, these changes do not involve a significant increase in the probability of an accident. The proposed system and filter testing changes are consistent with current regulatory guidance for these systems and will continue to assure that these systems perform their design function which may include mitigating accidents. Thus the change does not involve a significant increase in the consequences of an accident. Therefore, it is concluded that this change does not involve a significant increase in the probability or consequences of an accident previously evaluated. 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated? The proposed change replaces an existing Surveillance Requirement to operate the Westinghouse CREFS system equipped with electric heaters for a continuous 10 hour period at a frequency specified in the SFCP with a requirement to operate the system for 15 continuous minutes with heaters operating, if needed. The change proposed for these ventilation systems does not change any system operations or maintenance activities. Testing requirements will be revised and will continue to demonstrate that the Limiting Conditions for Operation are met and the system components are capable of performing their intended safety functions. The change does not create new failure modes or mechanisms and no new accident precursors are generated. Therefore, it is concluded that this change does not create the possibility of a new or different kind of accident from any accident previously evaluated. 3. Does the proposed change involve a significant reduction in a margin of safety? The proposed change replaces an existing Surveillance Requirement to operate the Westinghouse CREFS systems equipped with electric heaters for a continuous 10 hour period at a frequency specified in the SFCP with a requirement to operate the systems for 15 continuous minutes with heaters operating, if needed. The design basis for the ventilation systems' heaters is to heat the incoming air which reduces the relative humidity. The heater testing change proposed will continue to demonstrate that the heaters are capable of heating the air and will perform their design function. The proposed change is consistent with regulatory guidance. 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: Jennifer M. Buettner, Associate General Counsel, Southern Nuclear Operating Company, 40 Iverness Center Parkway, Birmingham, AL 35242. NRC Branch Chief: Michael T. Markley. Southern Nuclear Operating Company, Inc., Docket Nos. 50-424 and 50- 425, Vogtle Electric Generating Plant, Units 1 and 2, Burke County, Georgia Date of amendment request: November 15, 2016. A publicly-available version is in ADAMS under Accession No. ML16320A214. Description of amendment request: The amendments would modify the technical specifications (TS) by relocating references to specific American Society for Testing and Materials (ASTM) standards for fuel oil testing to licensee-controlled documents and adding alternate criteria to the ``clear and bright'' acceptance test for new fuel oil. These TS changes will be performed in accordance with technical specification task force (TSTF) traveler TSTF-374, Revision 0, ``Diesel Fuel Oil Testing Program.'' The NRC approved TSTF-374, Revision 0, as a part of the consolidated line item improvement process on April 21, 2006 (71 FR 20735). 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 changes relocate the specific ASTM standard references from the Administrative Controls Section of TS to a licensee-controlled document. Requirements to perform testing in accordance with applicable ASTM standards are retained in the TS as are requirements to perform surveillances of both new and stored diesel fuel oil. Future changes to the licensee-controlled document will be evaluated pursuant to the requirements of 10 CFR 50.59, ``Changes, tests and experiments,'' to ensure that such changes do not result in more than a minimal increase in the probability or consequences of an accident previously evaluated. In addition, the ``clear and bright'' test used to establish the acceptability of new fuel oil for use prior to addition to storage tanks has been expanded to recognize more rigorous testing of water and sediment content. Relocating the specific ASTM standard references from the TS to a licensee-controlled document and allowing a water and sediment content test to be performed to establish the acceptability of new fuel oil will not affect nor degrade the ability of the emergency diesel generators (DGs) to perform their specified safety function. Fuel oil quality will continue to meet ASTM requirements. The proposed changes do not adversely affect accident initiators or precursors nor alter the design assumptions, conditions, and configuration of the facility or the manner in which the plant is operated and maintained. The proposed changes do not adversely affect the ability of structures, systems, and components (SSCs) to perform their intended safety function to mitigate the consequences of an initiating event within the assumed acceptance limits. The proposed changes do not affect the source term, containment isolation, or radiological release assumptions used in evaluating the radiological consequences of any accident previously evaluated. Further, the proposed changes do not increase the types and amounts of radioactive effluent that may be released offsite, nor significantly increase individual or cumulative occupational/public radiation exposures. Therefore, the changes do not involve a significant increase in the probability or consequences of any accident previously evaluated. 2. Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated? The proposed changes relocate the specific ASTM standard references from the Administrative Controls Section of TS to a licensee-controlled document. In addition, the ``clear and bright'' test used to establish the acceptability of new fuel oil for use prior to addition to storage tanks has been expanded to allow a water and sediment content test to be performed to establish the acceptability of new fuel oil. The changes do not involve a physical alteration of the plant (i.e., no new or different type of equipment will be installed) or a change in the methods governing normal plant operation. The requirements retained in the TS continue to require testing of the diesel fuel oil to ensure the proper functioning of the DGs. Therefore, the changes do not create the possibility of a new or different kind of accident from any accident previously evaluated. 3. Does the proposed changes involve a significant reduction in a margin of safety? The proposed changes relocate the specific ASTM standard references from the Administrative Controls Section of TS to a licensee-controlled document. Instituting the proposed changes will continue to ensure the use of applicable ASTM standards to evaluate the quality of both new and stored fuel oil designated for use in the emergency DGs. Changes to the licensee-controlled document are performed in accordance with the provisions of 10 CFR 50.59. This approach provides an effective level of regulatory control and ensures that diesel fuel oil testing is conducted such that there is no significant reduction in a margin of safety. The ``clear and bright'' test used to establish the acceptability of new fuel oil for use prior to addition to storage tanks has been expanded to allow a water and sediment content test to be performed to establish the acceptability of new fuel oil. [[Page 12137]] The margin of safety provided by the DGs is unaffected by the proposed changes since there continue to be TS requirements to ensure fuel oil is of the appropriate quality for emergency DG use. The proposed changes provide the flexibility needed to improve fuel oil sampling and analysis methodologies while maintaining sufficient controls to preserve the current margins 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: Jennifer M. Buettner, Associate General Counsel, Southern Nuclear Operating Company, 40 Iverness Center Parkway, Birmingham, AL 35242. NRC Branch Chief: Michael T. Markley. Southern Nuclear Operating Company, Inc., Docket Nos. 50-424 and 50- 425, Vogtle Electric Generating Plant, Units 1 and 2, Burke County, Georgia Date of amendment request: November 15, 2016. A publicly- available version is in ADAMS under Accession No. ML16320A219. Description of amendment request: The amendments would add technical specifications (TS) Limiting Condition for Operation (LCO) 3.0.10 for unavailable barriers as described in TSTF-427, Revision 2, ``Allowance for Non Technical Specification Barrier Degradation on Supported System OPERABILITY.'' The NRC approved TSTF-427, Revision 2, as a part of the consolidated line item improvement process on October 3, 2006 (71 FR 58444). 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: Criterion 1--The Proposed Change Does Not Involve a Significant Increase in the Probability or Consequences of an Accident Previously Evaluated The proposed change allows a delay time for entering a supported system technical specification (TS) when the inoperability is due solely to an unavailable barrier if risk is assessed and managed. The postulated initiating events which may require a functional barrier are limited to those with low frequencies of occurrence, and the overall TS system safety function would still be available for the majority of anticipated challenges. Therefore, the probability of an accident previously evaluated is not significantly increased, if at all. The consequences of an accident while relying on the allowance provided by proposed LCO 3.0.9 are no different than the consequences of an accident while relying on the TS required actions in effect without the allowance provided by proposed LCO 3.0.9. Therefore, the consequences of an accident previously evaluated are not significantly affected by this change. The addition of a requirement to assess and manage the risk introduced by this change will further minimize possible concerns. Therefore, this change does not involve a significant increase in the probability or consequences of an accident previously evaluated. Criterion 2--The Proposed Change Does Not Create the Possibility of a New or Different Kind of Accident from any Previously Evaluated The proposed change does not involve a physical alteration of the plant (no new or different type of equipment will be installed). Allowing delay times for entering supported system TS when inoperability is due solely to an unavailable barrier, if risk is assessed and managed, will not introduce new failure modes or effects and will not, in the absence of other unrelated failures, lead to an accident whose consequences exceed the consequences of accidents previously evaluated. The addition of a requirement to assess and manage the risk introduced by this change will further minimize possible concerns. Thus, this change does not create the possibility of a new or different kind of accident from an accident previously evaluated. Criterion 3--The Proposed Change Does Not Involve a Significant Reduction in the Margin of Safety The proposed change allows a delay time for entering a supported system TS when the inoperability is due solely to an unavailable barrier, if risk is assessed and managed. The postulated initiating events which may require a functional barrier are limited to those with low frequencies of occurrence, and the overall TS system safety function would still be available for the majority of anticipated challenges. The risk impact of the proposed TS changes was assessed following the three-tiered approach recommended in RG [Regulatory Guide] 1.177. A bounding risk assessment was performed to justify the proposed TS changes. This application of LCO 3.0.9 is predicated upon the licensee's performance of a risk assessment and the management of plant risk. The net change to the margin of safety is insignificant as indicated by the anticipated low levels of associated risk (ICCDP [incremental conditional core damage probability] and ICLERP [incremental conditional large early release probability]) as shown in Table 1 of Section 3.1.1 in the Safety Evaluation. Therefore, this change does not involve a significant reduction in a margin of safety. The NRC staff has reviewed the licensee's analysis and, based on this review, it appears that the three standards of 10 CFR 50.92(c) are satisfied. Therefore, the NRC staff proposes to determine that the amendment request involves no significant hazards consideration. Attorney for licensee: Jennifer M. Buettner, Associate General Counsel, Southern Nuclear Operating Company, 40 Iverness Center Parkway, Birmingham, AL 35242. NRC Branch Chief: Michael T. Markley. Tennessee Valley Authority, Docket Nos. 50-390 and 50-391, Watts Bar Nuclear Plant (WBN), Units 1 and 2, Rhea County, Tennessee Date of amendment request: October 20, 2016. A publicly-available version is in ADAMS under Accession No. ML16294A551. Description of amendment request: The amendments would revise the Technical Specifications related to the auxiliary building gas treatment system (ABGTS) to provide an action for when the auxiliary building secondary containment enclosure (ABSCE) boundary is degraded, and to allow the ABSCE boundary to be open intermittently under administrative controls without entering the associated ABGTS limiting condition for operation. The proposed changes are consistent with NUREG-1431, ``Standard Technical Specifications Westinghouse Plants,'' Revision 4, dated April 2012 (ADAMS Accession No. ML12100A222). 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 consequence of an accident previously evaluated? Response: No. The proposed changes do not require physical changes to plant systems, structures, or components. The ABGTS is an accident mitigating feature. As such, ABGTS is not associated with a potential accident-initiating mechanism. Therefore, the changes do not affect accident or transient initiation or consequences. The proposed new condition for the ABGTS TS would permit a 24 hour period to restore an inoperable pressure boundary to operable status. The consequences of implementing the 24 hour completion time are reasonable based upon the low probability of a design basis accident occurring during this time period, and the availability of a functional ABGTS train to provide a filtered release to the environment (albeit with the potential for unfiltered leakage). For cases where the ABSCE boundary is opened intermittently under administrative controls, appropriate compensatory measures would be required by the proposed TS to ensure the ABSCE boundary can be rapidly restored and the dose analysis assumptions can be supported. Based on the administrative controls required to rapidly restore an opened ABSCE boundary, the accident consequences do not cause an increase in dose above the applicable General Design Criteria, Standard Review Plan, or 10 CFR 100 limits. The plant operators will [[Page 12138]] continue to maintain the ability to mitigate a design basis event. Therefore, the proposed change does not involve a significant increase in the probability or consequence 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 would not require any new or different accidents to be postulated and subsequently evaluated, since no changes are being made to the plant that would introduce any new accident causal mechanisms. This license amendment request does not impact any plant systems that are potential accident initiators; nor does it have any significantly adverse impact on any accident mitigating systems. 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 changes do not alter the permanent plant design, including instrument setpoints, nor does it change the assumptions contained in the safety analyses. Margin of safety is related to the ability of the fission product barriers to perform their design functions during and following accident conditions. These barriers include the fuel cladding, the reactor coolant system, and the containment system. The performance of these barriers will not be significantly degraded by the proposed changes. The proposed changes would allow the ABSCE boundary to be degraded for a limited period of time (24 hours). However, the probability of a design basis event occurring during this time is low. Additionally, a functional ABGTS train will be available to provide a filtered release to the environment (albeit with the potential for unfiltered leakage). When the ABSCE boundary is open on an intermittent basis, as permitted by the changes proposed in this amendment request, administrative controls would be in place to ensure that the integrity of the pressure boundaries could be rapidly restored and the dose analysis assumptions can be supported. Therefore, it is expected that the plant and the operators would maintain the ability to mitigate design basis events and none of the fission product barriers would be affected by this change. 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. Sherry A. Quirk, Executive Vice President and General Counsel, Tennessee Valley Authority, 400 West Summit Hill Drive, 6A Tower West, Knoxville, TN 37902. NRC Branch Chief: Benjamin G. Beasley. Tennessee Valley Authority, Docket Nos. 50-390 and 50-391, Watts Bar Nuclear Plant, Units 1 and 2, Rhea County, Tennessee Date of amendment request: October 17, 2016. A publicly-available version is in ADAMS under Accession No. ML16291A543. Description of amendment request: The amendments would revise the Technical Specifications (TSs) to allow a one-time extension of the frequency for performing certain TS Surveillance Requirements (SRs) related to verifying the operability of alternating current electrical power sources. 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 requested action is a one-time extension to the performance interval of a limited number of TS surveillance requirements. The performance of these surveillances, or the extension of these surveillances, is not a precursor to an accident. Performing these surveillances or failing to perform these surveillances does not affect the probability of an accident. Therefore, the proposed delay in performance of the SRs in this amendment request does not increase the probability of an accident previously evaluated. A delay in performing these surveillances does not result in a system being unable to perform its required function. In the case of this one-time extension request, the short period of additional time that the systems and components will be in service before the next performance of the surveillance will not affect the ability of those systems to operate as designed. Therefore, the systems required to mitigate accidents will remain capable of performing their required function. No new failure modes have been introduced because of this action and the consequences remain consistent with previously evaluated accidents. On this basis, the proposed delay in performance of the SRs in this amendment request does not involve a significant increase in the consequences of an accident. 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 amendment does not involve a physical alteration of any system, structure, or component (SSC) or a change in the way any SSC is operated. The proposed amendment does not involve operation of any SSCs in a manner or configuration different from those previously recognized or evaluated. No new failure mechanisms will be introduced by the one-time SR extensions being requested. 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 amendment is a one-time extension of the performance interval of a limited number of TS surveillance requirements. Extending these surveillance requirements does not involve a modification of any TS limiting conditions for operation. Extending these SRs does not involve a change to any limit on accident consequences specified in the license or regulations. Extending these SRs does not involve a change in how accidents are mitigated or a significant increase in the consequences of an accident. Extending these SRs does not involve a change in a methodology used to evaluate consequences of an accident. Extending these SRs does not involve a change in any operating procedure or process. The instrumentation and components involved in this request have exhibited reliable operation based on current test results. The current testing includes power ascension testing and surveillance testing that either partially or fully exercised the components. Some components have been evaluated for extended testing intervals greater than 18 months but are set at WBN to an 18-month frequency. Based on the limited additional period of time that the systems and components will be in service before the surveillances are next performed, as well as the operating experience that these surveillances are typically successful when performed, it is reasonable to conclude that the margins of safety associated with these SRs will not be affected by the requested extension. 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: Sherry A. Quirk, Executive Vice President and General Counsel, Tennessee Valley Authority, 400 West Summit Hill Drive, 6A West Tower, Knoxville, TN 37902. NRC Branch Chief: Benjamin G. Beasley. [[Page 12139]] TEX Operations Company LLC, Docket Nos. 50-445 and 50-446, Comanche Peak Nuclear Power Plant (CPNPP), Unit Nos. 1 and 2, Somervell County, Texas Date of amendment request: December 14, 2016. A publicly-available version is in ADAMS under Accession No. ML16351A200. Description of amendment request: The amendments would revise the licensee's name from ``TEX Operations Company LLC'' to ``Vistra Operations Company LLC'' into the CPNPP Unit 1 Operating License (NPF- 87), CPNPP Unit 2 Operating License (NPF-89), and the title page of the Environmental Protection Plan. 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. Do the proposed changes involve a significant increase in the probability or consequences of an accident previously evaluated? Response: No. The proposed amendment changes a name of a licensee. The proposed name change is purely administrative. The functions of the licensee will not change. The proposed amendment does not alter the design, function, or operation of any plant equipment. As such, the accident and transient analyses contained in the facility updated final safety analysis reports will not be impacted. Therefore, the proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated. 2. Do the proposed changes create the possibility of a new or different kind of accident from any accident previously evaluated? Response: No. The proposed amendment changes a name of a licensee. The proposed name change is purely administrative. The functions of the licensee will not change. The proposed amendment does not alter the design, function, or operation of any plant equipment. As such, the accident and transient analyses contained in the facility updated final safety analysis reports will not be impacted. Therefore, the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated. 3. Do the proposed changes involve a significant reduction in a margin of safety? Response: No. The proposed amendment changes a name of a licensee. The proposed name change is purely administrative. The functions of the licensee will not change. The proposed amendment does not alter the design, function, or operation of any plant equipment. As such, the accident and transient analyses contained in the facility updated final safety analysis reports will not be impacted. Therefore the proposed change does not involve a 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: Timothy P. Matthews, Esq., Morgan, Lewis and Bockius, 1111 Pennsylvania Avenue NW., Washington, DC 20004. NRC Branch Chief: Robert J. Pascarelli. 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 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. Dominion Nuclear Connecticut, Inc., Docket No. 50-336, Millstone Power Station, Unit No. 2 (MPS2), New London County, Connecticut Date of amendment request: December 14, 2016. Brief description of amendment: The amendment revised the MPS2 Technical Specifications (TSs) to add a note to TS Surveillance Requirement (SR) 4.1.3.1.2, control element assembly (CEA) freedom of movement surveillance, such that CEA 39 may be excluded from the remaining quarterly performance of the SR in Cycle 24. The amendment allows the licensee to delay exercising CEA 39 until after repairs can be made during the next outage. Date of issuance: February 7, 2017. Effective date: As of the date of issuance and shall be implemented within 30 days of issuance. Amendment No.: 333. A publicly-available version is in ADAMS under Accession No. ML17018A000; documents related to this amendment are listed in the Safety Evaluation enclosed with the amendment. Renewed Facility Operating License No. DPR-65: Amendment revised the Renewed Facility Operating License and TSs. Date of initial notice in Federal Register: January 3, 2017 (82 FR 157). The Commission's related evaluation of the amendment is contained in a Safety Evaluation dated February 7, 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 amendment request: September 25, 2013, as supplemented by letters dated January 13, 2015; January 28, 2015; February 27, 2015; March 30, 2015; April 28, 2015; July 15, 2015; August 14, 2015; September 3, 2015; December 11, 2015; January 7, 2016; March 23, 2016; June 15, 2016; August 2, 2016; September 7, 2016 and January 27, 2017. Brief description of amendments: The amendments revised the condition for the Fire Protection Program (FPP) in the Renewed Facility Operating Licenses such that the FPP is now based on the requirements of 10 CFR 50.48(c), ``National Fire Protection Association Standard NFPA 805.'' Date of issuance: February 8, 2017. Effective date: As of the date of issuance and shall be implemented as [[Page 12140]] stated within the revised License Condition 2.C.(5). Amendment Nos.: 287 (Unit 1) and 283 (Unit 2). A publicly-available version is in ADAMS under Accession No. ML16137A308; 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: The amendments revised the Renewed Facility Operating Licenses. Date of initial notice in Federal Register: February 4, 2014 (79 FR 6641). The supplemental letters dated January 13, 2015; January 28, 2015; February 27, 2015; March 30, 2015; April 28, 2015; July 15, 2015; August 14, 2015; September 3, 2015; December 11, 2015; January 7, 2016; March 23, 2016; June 15, 2016; August 2, 2016; September 7, 2016 and January 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 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 February 8, 2017. No significant hazards consideration comments received: No. Duke Energy Progress, LLC, Docket No. 50-261, H. B. Robinson Steam Electric Plant, Unit No. 2, Darlington County, South Carolina Date of amendment request: September 16, 2013, as supplemented by letters dated November 24, and December 22, 2014; January 22, March 16, April 1, May 19, and July 31, 2015; March 16, May 25, July 25, and October 5, 2016. Brief description of amendment: The amendment authorized the transition of the fire protection licensing basis, from 10 CFR 50.50.48(b) to 10 CFR 50.48(c), National Fire Protection Association (NFPA) 805, ``Performance-Based Standard for Fire Protection for Light- water Reactor Electric Generating Plants,'' 2001 edition. The revised fire protection licensing basis complies with the requirements in 10 CFR 50.48(a), 10 CFR 50.48(c), the guidance in Regulatory Guide 1.205, Revision 1, ``Risk-Informed Performance-Based Fire protection for Existing Light-water Nuclear Power Plants, and NFPA 805, and follows the applicable guidance in Nuclear Energy Institute 04-02, Revision 2. Date of issuance: February 3, 2017. Effective date: As of the date of issuance and shall be implemented as described in the transition license conditions. Amendment No.: 249. A publicly-available version is in ADAMS under Accession No. ML16337A264; documents related to this amendment are listed in the Safety Evaluation enclosed with the amendment. Renewed Facility Operating License No. DPR-23: Amendment revised the Renewed Facility Operating License and Technical Specifications. Date of initial notice in Federal Register: December 26, 2013 (78 FR 78405). The supplemental letters dated November 24, and December 22, 2014; January 22, March 16, April 1, May 19, and July 31, 2015; March 16, May 25, July 25, and October 5, 2016, 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 February 3, 2017. No significant hazards consideration comments received: No. Energy Northwest, Docket No. 50-397, Columbia Generating Station, Benton County, Washington Date of application for amendment: March 3, 2016, as supplemented by letter dated January 19, 2017. Brief description of amendment: The amendment revised the Technical Specification (TS) Surveillance Requirements for heaters in the Standby Gas Treatment and Control Room Emergency Filtration ventilation systems. The proposed amendment is consistent with NRC-approved Technical Specifications Task Force (TSTF) Traveler TSTF-522, Revision 0, ``Revise Ventilation System Surveillance Requirements to Operate for 10 hours per Month,'' as published in the Federal Register on September 20, 2012 (77 FR 58421), with variations due to plant-specific nomenclature. Date of issuance: January 31, 2017. Effective date: As of its date of issuance and shall be implemented within 60 days from the date of issuance. Amendment No.: 239. A publicly-available version is in ADAMS under Accession No. ML16357A646; documents related to this amendment 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: May 24, 2016 (81 FR 32805). The supplemental letter dated January 19, 2017, provided additional information that clarified the application, did not change the scope of the application as originally noticed, and did not change the staff's original proposed no significant hazards consideration determination published in the Federal Register. The Commission's related evaluation of the amendment is contained in a Safety Evaluation dated January 31, 2017. No significant hazards consideration comments received: No. Exelon Generation Company, LLC, Docket No. 50-244, R. E. Ginna Nuclear Power Plant, Wayne County, New York Date of amendment request: February 4, 2016, as supplemented by letters dated April 14, June 28, and November 30, 2016. Brief description of amendment: The amendment revised the Reactor Coolant System (RCS) Specific Activity definition and associated surveillance requirements in the R. E. Ginna Nuclear Power Plant Technical Specifications (TSs). The amendment replaced the current TS limit for RCS gross specific activity with a new limit for RCS noble gas specific activity. The changes are consistent with Technical Specification Task Force (TSTF) Improved Standard Technical Specifications Change Traveler, TSTF-490, Revision 0, ``Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec.'' Date of issuance: February 9, 2017. Effective date: As of the date of issuance and shall be implemented within 60 days of issuance. Amendment No.: 123. A publicly-available version is in ADAMS under Accession No. ML16358A424; documents related to this amendment are listed in the Safety Evaluation enclosed with the amendment. Renewed Facility Operating License No. DPR-18: Amendment revised the Renewed Facility Operating License and TSs. Date of initial notice in Federal Register: March 29, 2016 (81 FR 17506). The supplemental letters dated April 4, June 28, and November 30, 2016, 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 [[Page 12141]] consideration determination as published in the Federal Register. The Commission's related evaluation of the amendment is contained in a Safety Evaluation dated February 9, 2017. No significant hazards consideration comments received: No. Florida Power & Light Company, Docket Nos. 50-250 and 50-251, Turkey Point Nuclear Generating Unit Nos. 3 and 4, Miami-Dade County, Florida Date of application for amendments: April 4, 2016, as supplemented by letters dated September 1, November 10, and December 2, 2016. Brief description of amendments: The amendments revised the Technical Specifications (TSs) for snubbers and added a new TS to the Administrative Controls section of the TSs describing the licensee's Snubber Testing Program. The amendments revised the snubber TS surveillance requirement (SR) by deleting specific requirements from the SR and replacing them with a requirement to demonstrate snubber operability in accordance with the licensee-controlled Snubber Testing Program. The amendments deleted a portion of the SR that requires inspections per another TS that is no longer applicable to snubbers. The amendments included additions to, deletions from, and conforming administrative changes to the TSs. Date of issuance: February 9, 2017. Effective date: As of the date of issuance and shall be implemented within 60 days of issuance. Amendment Nos: 272 and 267. A publicly-available version is in ADAMS under Accession No. ML17004A292; documents related to these amendments are listed in the Safety Evaluation enclosed with the amendments. Renewed Facility Operating License Nos. DPR-31 and DPR-41: Amendments revised the Renewed Facility Operating Licenses and TSs. Date of initial notice in Federal Register: July 5, 2016 (81 FR 43652). The supplement dated September 1, 2016, 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 (NSHC) determination as published in the Federal Register (FR). The licensee's letter dated November 10, 2016, expanded the scope of its request as originally noticed; therefore, the NRC published another notice in the FR on December 6, 2016 (81 FR 87971), which replaced the original notice in its entirety. The licensee's letter dated December 2, 2016, did not expand the scope of the application as renoticed and did not change the staff's NSHC determination that was published in the FR on December 6, 2016. The Commission's related evaluation of the amendments is contained in a safety evaluation dated February 9, 2017. No significant hazards consideration comments received: No. NextEra Energy Point Beach, LLC, Docket Nos. 50-266 and 50-301, Point Beach Nuclear Plant (PBNP), Units 1 and 2, Town of Two Creeks, Manitowoc County, Wisconsin Date of amendment requests: January 15, 2016, as supplemented by letters dated April 27, 2016 and July 27, 2016. Brief description of amendments: The amendments eliminate technical specification (TS) 3.7.14, Primary Auxiliary Building Ventilation (VNPAB), for PBNP, Units 1 and 2. The amendments delete TS 3.7.14, VNPAB in its entirety on the basis that the VNPAB is not credited for accident mitigation and therefore does not meet the 10 CFR 50.36 criteria for inclusion in the TS. Date of issuance: January 30, 2017. Effective date: As of the date of issuance and shall be implemented within 90 days of issuance. Amendment Nos.: 257 and 261. A publicly-available version is in ADAMS under Accession No. ML16349A080; documents related to these amendments are listed in the Safety Evaluation enclosed with the amendments. Renewed Facility Operating License Nos. DPR-24 and DPR-27: Amendments revised the Renewed Facility Operating License and Technical Specifications. Date of initial notice in Federal Register: April 26, 2016 (81 FR 24662). The supplemental letters dated April 27, 2016 and July 27, 2016, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the staff's original proposed no significant hazards consideration determination as published in the Federal Register. The Commission's related evaluation of the amendments is contained in a Safety Evaluation dated January 30, 2017. No significant hazards consideration comments received: No. NextEra Energy Seabrook, LLC, Docket No. 50-443, Seabrook Station, Unit No. 1, Rockingham County, New Hampshire Date of amendment request: February 27, 2016, as supplemented by letters dated October 27, 2016, and December 15, 2016. Description of amendment request: The amendment revised the current emergency action level scheme to one based on Nuclear Energy Institute (NEI) guidance in NEI 99-01, Revision 6, ``Development of Emergency Action Levels for Non-Passive Reactors,'' dated November 2012. Date of issuance: February 10, 2017. Effective date: As of the date of issuance and shall be implemented within 180 days of issuance. Amendment No.: 152. A publicly-available version is in ADAMS under Accession No. ML16358A411; documents related to this amendment are listed in the Safety Evaluation enclosed with the amendment. Facility Operating License No. NPF-86: Amendment revised the Facility Operating License. Date of initial notice in Federal Register: May 24, 2016 (81 FR 32808). The supplemental letters dated October 27, 2016, and December 15, 2016, 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 February 10, 2017. No significant hazards consideration comments received: No. PSEG Nuclear LLC, Docket Nos. 50-354, 50-272 and 50-311, Hope Creek Generating Station (Hope Creek), and Salem Nuclear Generating Station (Salem), Unit Nos. 1 and 2, Salem County, New Jersey Date of amendment request: October 17, 2016, as supplemented by letter dated December 19, 2016. Brief description of amendments: The amendments revised the technical specifications (TSs) by removing certain training program requirements. Specifically, the amendments removed TS requirements that are redundant to, or superseded by, the requirements contained in 10 CFR part 55 and 10 CFR 50.120. Date of issuance: February 6, 2017. Effective date: As of the date of issuance and shall be implemented within 60 days. Amendment Nos.: 201 (Hope Creek), 317 (Salem, Unit No. 1), and 298 (Salem, Unit No. 2). A publicly-available version is in ADAMS under Accession No. ML17012A292; documents related to these amendments [[Page 12142]] are listed in the Safety Evaluation enclosed with the amendments. Renewed Facility Operating License Nos. NPF-57, DPR-70, and DPR-75: The amendments revised the Renewed Facility Operating Licenses and the TSs. Date of initial notice in Federal Register: November 22, 2016 (81 FR 83877). The supplemental letter dated December 19, 2016, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the staff's original proposed no significant hazards consideration determination as published in the Federal Register. The Commission's related evaluation of the amendments is contained in a Safety Evaluation dated February 6, 2017. No significant hazards consideration comments received: No. Southern Nuclear Operating Company, Docket No. 52-025, Vogtle Electric Generating Plant (VEGP), Unit 3, Burke County, Georgia Date of amendment request: September 13, 2016. Description of amendment: The amendment authorizes changes to the VEGP Units 3 and 4 Updated Final Safety Analysis Report in the form of departures from the incorporated plant specific Design Control Document Tier 2* information. The departures change the provided minimum reinforcement area in the VEGP Unit 3 column line 7.3 wall from elevation 82'-6'' to elevation 100'-0''. Date of issuance: January 30, 2017. Effective date: As of the date of issuance and shall be implemented within 30 days of issuance. Amendment No.: 68. A publicly-available version is in ADAMS under Accession No. ML16350A060; documents related to this amendment are listed in the Safety Evaluation enclosed with the amendment. Facility Combined Licenses No. NPF-91: Amendment revised the Facility Combined License. Date of initial notice in Federal Register: October 11, 2016 (81 FR 70175). The Commission's related evaluation of the amendment is contained in the Safety Evaluation dated January 30, 2017. No significant hazards consideration comments received: No. 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: May 27, 2016. Description of amendment: The amendment authorizes changes to the VEGP Units 3 and 4 Updated Final Safety Analysis Report in the form of departures from the incorporated plant specific Design Control Document Tier 2 information and involves changes to COL Appendix A Technical Specifications and associated Bases. The changes add reactor coolant density compensation to the reactor coolant flow input signal to the Reactor Trip System instrumentation for the low reactor coolant flow reactor trip function and add Technical Specification Surveillance Requirement 3.3.1.3 to the surveillances required for the Reactor Coolant Flow-Low reactor trip. Date of issuance: January 13, 2017. Effective date: As of the date of issuance and shall be implemented within 30 days of issuance. Amendment No.: 65. A publicly-available version is in ADAMS under Accession No. ML16348A073; documents related to this amendment are listed in the Safety Evaluation enclosed with the amendment. Facility Combined Licenses Nos. NPF-91 and NPF-92: Amendment revised the Facility Combined License. Date of initial notice in Federal Register: August 2, 2016 (81 FR 50729). The Commission's related evaluation of the amendment is contained in the Safety Evaluation dated January 13, 2017. No significant hazards consideration comments received: No. Dated at Rockville, Maryland, this 17th day of February 2017. For the Nuclear Regulatory Commission. Kathryn M. Brock, Deputy Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation. [FR Doc. 2017-03806 Filed 2-27-17; 8:45 am] BILLING CODE 7590-01-P
![12130 Federal Register / Vol. 82, No. 38 / Tuesday, February 28, 2017 / Notices
I. Introduction holders of current operating licenses or biweekly notice was published on
The NRC is issuing a revision to an combined licenses. February 14, 2017.
existing guide in the NRC’s ‘‘Regulatory This RG may be applied to DATES: Comments must be filed March
Guide’’ series. This series was applications for operating licenses, 30, 2017. A request for a hearing must
developed to describe and make combined licenses, early site permits, be filed May 1, 2017.
available to the public information and certified design rules docketed by ADDRESSES: You may submit comments
regarding methods that are acceptable to the NRC as of the date of issuance of the by any of the following methods:
the NRC staff for implementing specific final regulatory guide, as well as future • Federal Rulemaking Web site: Go to
parts of the agency’s regulations, applications submitted after the http://www.regulations.gov and search
techniques that the staff uses in issuance of the regulatory guide. Such for Docket ID NRC–2017–0058. Address
evaluating specific issues or postulated action would not constitute backfitting questions about NRC dockets to Carol
events, and data that the staff needs in as defined in the Backfit Rule or be Gallagher; telephone: 301–415–3463;
its review of applications for permits otherwise inconsistent with the email: Carol.Gallagher@nrc.gov. For
and licenses. applicable issue finality provision in 10 technical questions, contact the
Revision 5 of RG 1.26 was issued with CFR part 52, inasmuch as such individual or individuals listed in the
a temporary identification as Draft applicants or potential applicants are FOR FURTHER INFORMATION CONTACT
Regulatory Guide, DG–1314. This not within the scope of entities section of this document.
protected by the Backfit Rule or the • Mail comments to: Cindy Bladey,
guidance has been revised to update
relevant issue finality provisions in part Office of Administration, Mail Stop:
references to related NRC guidance, to
52. OWFN–12–H08, U.S. Nuclear
incorporate lessons learned from recent
Dated at Rockville, Maryland, this 22nd Regulatory Commission, Washington,
NRC reviews and regulatory activities,
day of February, 2017. DC 20555–0001.
and to align the format and content of For additional direction on obtaining
the guide with the current program For the Nuclear Regulatory Commission.
information and submitting comments,
guidance for regulatory guides (RGs) Harriet Karagiannis,
see ‘‘Obtaining Information and
which was developed since Revision 4 Acting Chief, Regulatory Guidance and Submitting Comments’’ in the
of RG 1.26 was issued. Generic Issues Branch, Division of
SUPPLEMENTARY INFORMATION section of
Engineering, Office of Nuclear Regulatory
II. Additional Information Research. this document.
FOR FURTHER INFORMATION CONTACT:
The DG–1314, was published in the [FR Doc. 2017–03890 Filed 2–27–17; 8:45 am]
Federal Register on April 16, 2015 (80 BILLING CODE 7590–01–P
Beverly Clayton, Office of Nuclear
FR 20511), for a 60-day public comment Reactor Regulation, U.S. Nuclear
period. The public comment period Regulatory Commission, Washington DC
closed on June 15, 2015. No public NUCLEAR REGULATORY 20555–0001; telephone: 301–415–3475,
comments were received on DG–1314. COMMISSION email: Beverly.Clayton@nrc.gov.
SUPPLEMENTARY INFORMATION:
III. Congressional Review Act [NRC–2017–0058]
I. Obtaining Information and
This regulatory guide is a rule as Biweekly Notice; Applications and Submitting Comments
defined in the Congressional Review Amendments to Facility Operating
Act (5 U.S.C. 801–808). However, the A. Obtaining Information
Licenses and Combined Licenses
Office of Management and Budget has Involving No Significant Hazards Please refer to Docket ID NRC–2017–
not found it to be a major rule as Considerations 0058, facility name, unit number(s),
defined in the Congressional Review plant docket number, application date,
Act. AGENCY: Nuclear Regulatory and subject when contacting the NRC
Commission. about the availability of information for
IV. Backfitting and Issue Finality
ACTION: Biweekly notice. this action. You may obtain publicly-
Revision 5 of RG 1.26 describes a available information related to this
quality classification system related to SUMMARY: Pursuant to Section 189a. (2) action by any of the following methods:
specified national standards that may be of the Atomic Energy Act of 1954, as • Federal Rulemaking Web site: Go to
used to determine quality standards amended (the Act), the U.S. Nuclear http://www.regulations.gov and search
acceptable to the NRC staff for satisfying Regulatory Commission (NRC) is for Docket ID NRC–2017–0058.
General Design Criterion (GDC) 1, publishing this regular biweekly notice. • NRC’s Agencywide Documents
‘‘Quality Standards and Records,’’ as set The Act requires the Commission to Access and Management System
forth in appendix A, ‘‘General Design publish notice of any amendments (ADAMS): You may obtain publicly-
Criteria for Nuclear Power Plants,’’ to issued, or proposed to be issued, and available documents online in the
part 50 title 10 of the Code of Federal grants the Commission the authority to ADAMS Public Documents collection at
Regulations (10 CFR), ‘‘Domestic issue and make immediately effective http://www.nrc.gov/reading-rm/
Licensing of Production and Utilization any amendment to an operating license adams.html. To begin the search, select
Facilities,’’ for components containing or combined license, as applicable, ‘‘ADAMS Public Documents’’ and then
water, steam, or radioactive material in upon a determination by the select ‘‘Begin Web-based ADAMS
light-water-cooled nuclear power plants. Commission that such amendment Search.’’ For problems with ADAMS,
Issuance of this RG does not constitute involves no significant hazards please contact the NRC’s Public
mstockstill on DSK3G9T082PROD with NOTICES
backfitting as defined in 10 CFR 50.109 consideration, notwithstanding the Document Room (PDR) reference staff at
(the Backfit Rule) and is not otherwise pendency before the Commission of a 1–800–397–4209, 301–415–4737, or by
inconsistent with the issue finality request for a hearing from any person. email to pdr.resource@nrc.gov. The
provisions in 10 CFR part 52. As This biweekly notice includes all ADAMS accession number for each
discussed in the ‘‘Implementation’’ notices of amendments issued, or document referenced (if it is available in
section of this RG, the NRC has no proposed to be issued, from January 31, ADAMS) is provided the first time that
current intention to impose this RG on 2017 to February 13, 2017. The last it is mentioned in this document.
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![Federal Register / Vol. 82, No. 38 / Tuesday, February 28, 2017 / Notices 12133
electronic hearing docket which is consequences of an accident previously Attorney for licensee: William S.
available to the public at https:// evaluated? Blair, Managing Attorney—Nuclear,
adams.nrc.gov/ehd, unless excluded Response: No. Florida Power & Light Company, 700
The relocation of Component Cyclic or
pursuant to an order of the Commission Transient Limits Table 5.9–1 and Table 5.7–
Universe Boulevard, MS LAW/JB, Juno
or the presiding officer. If you do not 1 from the St. Lucie Unit 1 and Unit 2 TS[s], Beach, FL 33408–0420.
have an NRC-issued digital ID certificate to the St. Lucie Unit 1 and Unit 2 UFSARs NRC Branch Chief: Benjamin G.
as described above, click cancel when [Updated Final Safety Analysis Reports], and Beasley.
the link requests certificates and you the relocation of the Component Cyclic or Indiana Michigan Power Company
will be automatically directed to the Transient Limits Program requirements (I&M), Docket Nos. 50–315 and 50–316,
NRC’s electronic hearing dockets where within the St. Lucie Unit 1 and Unit 2 TS[s]
Donald C. Cook Nuclear Plant (CNP),
are administrative changes in nature. The TS
you will be able to access any publicly Units 1 and 2, Berrien County, Michigan
changes do not represent any physical
available documents in a particular change to plant systems, structures, or Date of amendment request:
hearing docket. Participants are components, or to procedures established for December 14, 2016. A publicly-available
requested not to include personal plant operation. As such, the initial version is in ADAMS under Accession
privacy information, such as social conditions associated with accidents No. ML16351A198.
security numbers, home addresses, or previously evaluated and plant systems Description of amendment request:
personal phone numbers in their filings, credited for mitigating the consequences of
accidents previously evaluated remain The proposed changes would revise the
unless an NRC regulation or other law note regarding applicability of the
unchanged.
requires submission of such Therefore, facility operation in accordance limiting condition for operation (LCO)
information. For example, in some with the proposed license amendments for CNP Technical Specification (TS)
instances, individuals provide home would not involve a significant increase in 3.9.3, ‘‘Containment Penetrations.’’
addresses in order to demonstrate the probability or consequences of an Basis for proposed no significant
proximity to a facility or site. With accident previously evaluated. hazards consideration determination:
respect to copyrighted works, except for 2. Does the proposed amendment create
As required by 10 CFR 50.91(a), the
limited excerpts that serve the purpose the possibility of a new or different kind of
accident from any accident previously licensee has provided its analysis of the
of the adjudicatory filings and would evaluated? issue of no significant hazards
constitute a Fair Use application, Response: No. consideration, which is presented
participants are requested not to include The relocation of Component Cyclic or below:
copyrighted materials in their Transient Limits tables from the St. Lucie
1. Does the proposed change involve a
submission. Unit 1 and Unit 2 TS[s], to the St. Lucie Unit
significant increase in the probability or
For further details with respect to 1 and Unit 2 UFSARs, and the relocation of
the Component Cyclic or Transient Limits consequences of an accident previously
these license amendment applications, evaluated?
Program requirements within the St. Lucie
see the application for amendment Unit 1 and Unit 2 TS[s] are administrative Response: No.
which is available for public inspection changes in nature. No physical change to The accident in question for this submittal
in ADAMS and at the NRC’s PDR. For plant systems, structures, or components, or is the FHA [fuel-handling accident]. The
additional direction on accessing the manner in which they are operated and analysis for the FHA was recently reviewed
information related to this document, maintained will result from the proposed and approved by the NRC for a license
license amendments. amendment request regarding use of
see the ‘‘Obtaining Information and alternative source term. The proposed
Submitting Comments’’ section of this Therefore, the proposed change does not
create the possibility of a new or different amendment to TS 3.9.3 does not impact the
document. kind of accident from any previously assumed release pathway for the accident
Florida Power & Light Company, et al., evaluated. and has no effect on the probability of the
3. Does the proposed amendment involve occurrence of any accident previously
Docket No. 50–335 and 50–389, St. evaluated. The proposed change does not
a significant reduction in a margin of safety?
Lucie Plant, Unit Nos. 1 and 2, St. Lucie alter any plant equipment or operating
Response: No.
County, Florida The relocation of Component Cyclic or practices in such a manner that the
Date of amendment request: Transient Limits tables from the St. Lucie probability of an accident previously
December 22, 2016. A publicly-available Unit 1 and Unit 2 TS[s], to the St. Lucie Unit evaluated is increased. The consequences of
version is in ADAMS under Accession 1 and Unit 2 UFSARs, and the relocation of [an] FHA inside the containment building
the Component Cyclic or Transient Limits with open penetration flow paths is bounded
No. ML17006A007.
Program requirements within the St. Lucie by the current FHA analyses and
Description of amendment request: Unit 1 and Unit 2 TS[s] are administrative administrative controls, so the probability of
The amendments would relocate the changes in nature. As such, the proposed an accident is not affected by the status of the
Component Cyclic or Transient Limits changes do not involve changes to any safety penetration flow paths.
Program requirements to the analyses assumptions, safety limits, or Therefore, the probability or consequences
Administrative Controls sections of the limiting safety system settings nor do they of an accident previously evaluated will not
Technical Specifications (TSs), and adversely impact plant operating margins or be significantly increased.
the reliability of equipment credited in safety 2. Does the proposed change create the
relocate the Component Cyclic or analyses. possibility of a new or different kind of
Transient Limits tables detailing the Therefore, operation of the facility in accident from any accident previously
allowable limits from the respective TSs accordance with the proposed amendment evaluated?
to licensee-controlled documents. will not involve a significant reduction in the Response: No.
Basis for proposed no significant margin of safety. Allowing penetration flow paths to be open
hazards consideration determination: The NRC staff has reviewed the is not an initiator for any accident. The
mstockstill on DSK3G9T082PROD with NOTICES
As required by 10 CFR 50.91(a), the licensee’s analysis and, based on this change impacts the containment
licensee has provided its analysis of the review, it appears that the three requirements during refueling operations.
issue of no significant hazards The only accident which could result in
standards of 50.92(c) are satisfied. significant releases of radioactivity during
consideration, which is presented Therefore, the NRC staff proposes to refueling is the FHA. The proposed change
below: determine that the amendment request does not affect the design of containment, or
1. Does the proposed amendment involve involves no significant hazards alter plant operating practices such that it
a significant increase in the probability or consideration. creates the possibility of a new or different
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![12134 Federal Register / Vol. 82, No. 38 / Tuesday, February 28, 2017 / Notices
kind of accident from any accident Basis for proposed no significant affecting a safety-related pressure boundary.
previously evaluated. The proposed hazards consideration determination: The upgrade in the qualification of the
allowance to open any containment As required by 10 CFR 50.91(a), the sensing lines and associated instrument
penetration under administrative controls isolation valves does not affect the function
licensee has provided its analysis of the
during fuel movement will not adversely of the safety-related systems to which they
affect plant safety functions such that a new
issue of no significant hazards are connected. No safety analysis or design
or different accident could be created. No consideration, which is presented basis acceptance limit/criterion is challenged
other initiators or accident precursors are below: or exceeded by the proposed change, thus no
created by this change. 1. Does the proposed amendment involve margin of safety is reduced.
Therefore, the possibility of a new or a significant increase in the probability or Therefore, the proposed amendment does
different kind of accident not previously consequences of an accident previously not involve a significant reduction in a
evaluated is not created. evaluated? margin of safety.
3. Does the proposed change involve a Response: No.
The proposed changes to nonsafety-related
The NRC staff has reviewed the
significant reduction in a margin of safety?
Response: No. instrument classification methodology will licensee’s analysis and, based on this
TS 3.9.3 closure requirements for allow nonsafety-related instrumentation review, it appears that the three
containment penetrations ensure that the connected to safety-related systems to be standards of 10 CFR 50.92(c) are
consequences of a postulated FHA inside appropriately qualified to withstand a safe satisfied. Therefore, the NRC staff
containment during irradiated fuel handling shutdown earthquake without adversely proposes to determine that the
activities are minimized. The LCO affecting a safety-related pressure boundary. amendment request involves no
establishes containment closure The safe shutdown fire analysis is not significant hazards consideration.
requirements, which limit the potential affected, and the fire protection analysis
Attorney for licensee: Ms. Kathryn M.
escape paths for fission products by ensuring results are not adversely affected. The
proposed changes do not involve any Sutton, Morgan, Lewis & Bockius, LLC,
that there is at least one barrier to the release
of radioactive material. The proposed change accident, initiating event or component 1111 Pennsylvania Avenue NW.,
to allow any containment penetration flow failure; thus, the probabilities of the Washington, DC 20004–2514.
path to be open during refueling operations accidents previously evaluated are not NRC Branch Chief: Jennifer Dixon-
under administrative controls does not affected. The proposed change does not Herrity.
significantly affect the expected dose adversely affect compliance with the
consequences of [an] FHA because the maximum allowable reactor coolant system Southern Nuclear Operating Company,
limiting FHA does not credit containment operational leakage rates specified in the Inc., Docket Nos. 52–025 and 52–026,
building closure or filtration. The Technical Specifications, and radiological Vogtle Electric Generating Plant Units 3
administrative controls provide assurance material release source terms are not affected; and 4, Burke County, Georgia
that closure of the applicable penetration thus, the radiological releases in the accident
analyses are not affected. Date of amendment request:
flow paths will be accomplished and that the
offsite dose consequences will be minimized Therefore, the proposed amendment does December 16, 2016, as supplemented by
in the event of [an] FHA inside the not involve a significant increase in the letter dated January 12, 2017. A
containment building. probability or consequences of an accident publicly-available version is in ADAMS
Therefore, this proposed change does not previously evaluated. under Accession Nos. ML16351A483
involve a significant reduction in a margin of 2. Does the proposed amendment create and ML17012A272, respectively.
safety. the possibility of a new or different kind of Description of amendment request:
accident from any accident previously The requested amendment proposes to
The NRC staff has reviewed the evaluated?
licensee’s analysis and, based on this Response: No.
depart from Tier 2* information in the
review, it appears that the three The proposed changes to nonsafety-related Updated Final Safety Analysis Report to
standards of 10 CFR 50.92(c) are instrument classification methodology will address the seismic Category and
satisfied. Therefore, the NRC staff allow nonsafety-related instrumentation AP1000 equipment class of nonsafety-
proposes to determine that the connected to safety-related systems to be related instrumentation that interfaces
amendment request involves no appropriately qualified to withstand a safe with safety-related pressure boundaries.
shutdown earthquake without adversely Basis for proposed no significant
significant hazards consideration. affecting a safety-related pressure boundary.
Attorney for licensee: Robert B. hazards consideration determination:
The proposed changes do not adversely affect As required by 10 CFR 50.91(a), the
Haemer, Senior Nuclear Counsel, One any safety-related system, structure, or
Cook Place, Bridgman, MI 49106. licensee has provided its analysis of the
component. The nonsafety-related
NRC Branch Chief: David J. Wrona. instrumentation provides information for issue of no significant hazards
nonsafety-related display and does not consideration, which is presented
South Carolina Electric & Gas Company control any safety-related feature. Thus, the below:
and South Carolina Public Service proposed changes do not introduce a new 1. Does the proposed amendment involve
Authority, Docket Nos. 52–027 and 52– failure mode. The proposed changes to the a significant increase in the probability or
028, Virgil C. Summer Nuclear Station nonsafety-related instrument classification consequences of an accident previously
Units 2 and 3, Fairfield County, South methodology do not create a new fault or evaluated?
Carolina sequence of events that could result in a Response: No.
radioactive material release. The proposed changes to nonsafety-related
Date of amendment request: January Therefore, the proposed amendment does instrument classification methodology will
20, 2017. A publicly-available version is not create the possibility of a new or different allow nonsafety-related instrumentation
in ADAMS under Accession No. kind of accident from any accident connected to safety-related systems to be
ML17020A097. previously evaluated. appropriately qualified to withstand a safe
Description of amendment request: 3. Does the proposed amendment involve shutdown earthquake without adversely
mstockstill on DSK3G9T082PROD with NOTICES
The requested amendment proposes to a significant reduction in a margin of safety? affecting a safety-related pressure boundary.
Response: No. The safe shutdown fire analysis is not
depart from Tier 2* information in the
The proposed changes to nonsafety-related affected, and the fire protection analysis
Updated Final Safety Analysis Report to instrument classification methodology will results are not adversely affected. The
address the seismic Category and allow nonsafety-related instrumentation proposed changes do not involve any
AP1000 equipment class of nonsafety- connected to safety-related systems to be accident, initiating event or component
related instrumentation that interfaces appropriately qualified to withstand a safe failure; thus, the probabilities of the
with safety-related pressure boundaries. shutdown earthquake without adversely accidents previously evaluated are not
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![Federal Register / Vol. 82, No. 38 / Tuesday, February 28, 2017 / Notices 12135
affected. The proposed change does not Southern Nuclear Operating Company, The proposed change clarifies the
adversely affect compliance with the Inc., Docket Nos. 50–424 and 50–425, application of Section 1.3 and LCO 3.0.4 and
maximum allowable reactor coolant system Vogtle Electric Generating Plant, Units 1 does not result in changes in plant operation.
operational leakage rates specified in the SR 3.0.3 is revised to allow application of SR
Technical Specifications, and radiological
and 2, Burke County, Georgia; Docket
3.0.3 when a SR has not been previously
material release source terms are not affected; Nos. 50–348 and 50–364, Joseph M. performed if there is a reasonable expectation
thus, the radiological releases in the accident Farley Nuclear Plant, Units 1 and 2, that the SR will be met when performed. This
analyses are not affected. Houston County, Alabama; Docket Nos. expands the use of SR 3.0.3 while ensuring
Therefore, the proposed amendment does 50–321 and 50–366, Edwin I. Hatch the affected system is capable of performing
not involve a significant increase in the Nuclear Plant, Units 1 and 2, Appling its safety function. As a result, plant safety
probability or consequences of an accident County, Georgia is either improved or unaffected.
previously evaluated. Therefore, it is concluded that this change
2. Does the proposed amendment create Date of amendment request: does not involve a significant reduction in a
the possibility of a new or different kind of December 1, 2016. A publicly-available margin of safety.
accident from any accident previously version is in ADAMS under Accession
evaluated? No. ML16340A005. The NRC staff has reviewed the
Response: No. Description of amendment request: licensee’s analysis and, based on this
The proposed changes to nonsafety-related The amendments would modify the review, it appears that the three
instrument classification methodology will standards of 10 CFR 50.92(c) are
allow nonsafety-related instrumentation technical specifications requirements in
Section 1.3 and Section 3.0 regarding satisfied. Therefore, the NRC staff
connected to safety-related systems to be
appropriately qualified to withstand a safe Limiting Condition for Operation (LCO) proposes to determine that the
shutdown earthquake without adversely and Surveillance Requirement (SR) amendment request involves no
affecting a safety-related pressure boundary. usage. These changes are consistent significant hazards consideration.
The proposed changes do not adversely affect with NRC-approved Technical Attorney for licensee: Jennifer M.
any safety-related system, structure, or Specifications Task Force (TSTF) Buettner, Associate General Counsel of
component. The nonsafety-related Operations and Nuclear, Southern
instrumentation provides information for
Traveler TSTF–529, ‘‘Clarify Use and
Application Rules.’’ Nuclear Operating Company, 40
nonsafety-related display and does not Iverness Center Parkway, Birmingham,
control any safety-related feature. Thus, the Basis for proposed no significant
proposed changes do not introduce a new hazards consideration determination: AL 35201.
failure mode. The proposed changes to the As required by 10 CFR 50.91(a), the NRC Branch Chief: Michael T.
nonsafety-related instrument classification licensee has provided its analysis of the Markley.
methodology do not create a new fault or issue of no significant hazards Southern Nuclear Operating Company,
sequence of events that could result in a consideration, which is presented
radioactive material release. Inc., Docket Nos. 50–424 and 50–425,
below: Vogtle Electric Generating Plant, Units 1
Therefore, the proposed amendment does
not create the possibility of a new or different 1. Does the proposed amendment involve and 2, Burke County, Georgia
kind of accident from any accident a significant increase in the probability or
Date of amendment request:
previously evaluated. consequences of an accident previously
evaluated? November 15, 2016, as supplemented by
3. Does the proposed amendment involve
a significant reduction in a margin of safety? Response: No. letter dated January 13, 2017. Publicly-
Response: No. The proposed changes to Section 1.3 and available versions are in ADAMS under
The proposed changes to nonsafety-related LCO 3.0.4 have no effect on the requirement Accession Nos. ML16320A207 and
instrument classification methodology will for systems to be Operable and have no effect ML17013A603, respectively.
allow nonsafety-related instrumentation on the application of TS actions. The Description of amendment request:
connected to safety-related systems to be proposed change to SR 3.0.3 states that the The amendments would modify the TS
appropriately qualified to withstand a safe allowance may only be used when there is requirements to operate ventilation
shutdown earthquake without adversely a reasonable expectation the surveillance will
be met when performed. Since the proposed systems with charcoal filters from 10
affecting a safety-related pressure boundary.
The upgrade in the qualification of the change does not significantly affect system hours to 15 minutes each month in
sensing lines and associated instrument Operability, the proposed change will have accordance with TSTF–522, Revision 0,
isolation valves does not affect the function no significant effect on the initiating events ‘‘Revise Ventilation System Surveillance
of the safety-related systems to which they for accidents previously evaluated and will Requirements to Operate for 10 hours
are connected. No safety analysis or design have no significant effect on the ability of the per Month.’’ The NRC approved TSTF–
basis acceptance limit/criterion is challenged systems to mitigate accidents previously 522, Revision 0, as a part of the
or exceeded by the proposed change, thus no evaluated. consolidated line item improvement
margin of safety is reduced. Therefore, it is concluded that this change
does not involve a significant increase in the
process on September 20, 2012 (77 FR
Therefore, the proposed amendment does
not involve a significant reduction in a probability or consequences of an accident 58421).
margin of safety. previously evaluated. Basis for proposed no significant
2. Does the proposed amendment create hazards consideration determination:
The NRC staff has reviewed the the possibility of a new or different kind of As required by 10 CFR 50.91(a), the
licensee’s analysis and, based on this accident from any accident previously licensee has provided its analysis of the
review, it appears that the three evaluated? issue of no significant hazards
standards of 10 CFR 50.92(c) are The proposed change to the TS usage rules consideration, which is presented
satisfied. Therefore, the NRC staff does not affect the design or function of any
plant systems. The proposed change does not
below:
proposes to determine that the
change the Operability requirements for plant 1. Does the proposed change involve a
mstockstill on DSK3G9T082PROD with NOTICES
amendment request involves no
systems or the actions taken when plant significant increase in the probability or
significant hazards consideration. systems are not operable. consequences of an accident previously
Attorney for licensee: Mr. M. Stanford Therefore, it is concluded that this change evaluated?
Blanton, Balch & Bingham LLP, 1710 does not create the possibility of a new or Response: No.
Sixth Avenue North Birmingham, AL different kind of accident from any accident The proposed change replaces an existing
35203–2015. previously evaluated. Surveillance Requirement to operate the
NRC Branch Chief: Jennifer Dixon- 3. Does the proposed changes involve a Westinghouse CREFS [Control Room
Herrity. significant reduction in a margin of safety? Emergency Filtration System] equipped with
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![12136 Federal Register / Vol. 82, No. 38 / Tuesday, February 28, 2017 / Notices
electric heaters for a continuous 10 hour Southern Nuclear Operating Company, (DGs) to perform their specified safety
period at a frequency specified in the SFCP 40 Iverness Center Parkway, function. Fuel oil quality will continue to
[Surveillance Frequency Control Program] Birmingham, AL 35242. meet ASTM requirements.
with a requirement to operate the systems for The proposed changes do not adversely
NRC Branch Chief: Michael T.
15 continuous minutes with heaters affect accident initiators or precursors nor
operating, if needed. Markley. alter the design assumptions, conditions, and
This system is not an accident initiator and Southern Nuclear Operating Company, configuration of the facility or the manner in
therefore, these changes do not involve a which the plant is operated and maintained.
Inc., Docket Nos. 50–424 and 50–425,
significant increase in the probability of an The proposed changes do not adversely affect
accident. The proposed system and filter Vogtle Electric Generating Plant, Units 1 the ability of structures, systems, and
testing changes are consistent with current and 2, Burke County, Georgia components (SSCs) to perform their intended
regulatory guidance for these systems and safety function to mitigate the consequences
will continue to assure that these systems
Date of amendment request:
of an initiating event within the assumed
perform their design function which may November 15, 2016. A publicly- acceptance limits. The proposed changes do
include mitigating accidents. Thus the available version is in ADAMS under not affect the source term, containment
change does not involve a significant Accession No. ML16320A214. isolation, or radiological release assumptions
increase in the consequences of an accident. Description of amendment request: used in evaluating the radiological
Therefore, it is concluded that this change The amendments would modify the consequences of any accident previously
does not involve a significant increase in the technical specifications (TS) by evaluated. Further, the proposed changes do
probability or consequences of an accident relocating references to specific not increase the types and amounts of
previously evaluated. radioactive effluent that may be released
2. Does the proposed change create the American Society for Testing and
offsite, nor significantly increase individual
possibility of a new or different kind of Materials (ASTM) standards for fuel oil
or cumulative occupational/public radiation
accident from any accident previously testing to licensee-controlled documents exposures.
evaluated? and adding alternate criteria to the Therefore, the changes do not involve a
The proposed change replaces an existing ‘‘clear and bright’’ acceptance test for significant increase in the probability or
Surveillance Requirement to operate the new fuel oil. These TS changes will be consequences of any accident previously
Westinghouse CREFS system equipped with performed in accordance with technical evaluated.
electric heaters for a continuous 10 hour 2. Does the proposed amendment create
period at a frequency specified in the SFCP
specification task force (TSTF) traveler
TSTF–374, Revision 0, ‘‘Diesel Fuel Oil the possibility of a new or different kind of
with a requirement to operate the system for accident from any accident previously
15 continuous minutes with heaters Testing Program.’’ The NRC approved
evaluated?
operating, if needed. TSTF–374, Revision 0, as a part of the
The proposed changes relocate the specific
The change proposed for these ventilation consolidated line item improvement ASTM standard references from the
systems does not change any system process on April 21, 2006 (71 FR Administrative Controls Section of TS to a
operations or maintenance activities. Testing 20735).
requirements will be revised and will licensee-controlled document. In addition,
Basis for proposed no significant the ‘‘clear and bright’’ test used to establish
continue to demonstrate that the Limiting
Conditions for Operation are met and the hazards consideration determination: the acceptability of new fuel oil for use prior
system components are capable of As required by 10 CFR 50.91(a), the to addition to storage tanks has been
performing their intended safety functions. licensee has provided its analysis of the expanded to allow a water and sediment
The change does not create new failure issue of no significant hazards content test to be performed to establish the
modes or mechanisms and no new accident acceptability of new fuel oil. The changes do
consideration, which is presented
precursors are generated. not involve a physical alteration of the plant
below: (i.e., no new or different type of equipment
Therefore, it is concluded that this change
does not create the possibility of a new or 1. Does the proposed amendment involve will be installed) or a change in the methods
different kind of accident from any accident a significant increase in the probability or governing normal plant operation. The
previously evaluated. consequences of an accident previously requirements retained in the TS continue to
3. Does the proposed change involve a evaluated? require testing of the diesel fuel oil to ensure
significant reduction in a margin of safety? Response: No. the proper functioning of the DGs.
The proposed change replaces an existing The proposed changes relocate the specific Therefore, the changes do not create the
Surveillance Requirement to operate the ASTM standard references from the possibility of a new or different kind of
Westinghouse CREFS systems equipped with Administrative Controls Section of TS to a accident from any accident previously
electric heaters for a continuous 10 hour licensee-controlled document. Requirements evaluated.
period at a frequency specified in the SFCP to perform testing in accordance with 3. Does the proposed changes involve a
with a requirement to operate the systems for applicable ASTM standards are retained in significant reduction in a margin of safety?
15 continuous minutes with heaters the TS as are requirements to perform The proposed changes relocate the specific
operating, if needed. surveillances of both new and stored diesel ASTM standard references from the
The design basis for the ventilation fuel oil. Future changes to the licensee- Administrative Controls Section of TS to a
systems’ heaters is to heat the incoming air controlled document will be evaluated licensee-controlled document. Instituting the
which reduces the relative humidity. The pursuant to the requirements of 10 CFR proposed changes will continue to ensure the
heater testing change proposed will continue 50.59, ‘‘Changes, tests and experiments,’’ to use of applicable ASTM standards to
to demonstrate that the heaters are capable of ensure that such changes do not result in evaluate the quality of both new and stored
heating the air and will perform their design more than a minimal increase in the fuel oil designated for use in the emergency
function. The proposed change is consistent probability or consequences of an accident DGs. Changes to the licensee-controlled
with regulatory guidance. previously evaluated. In addition, the ‘‘clear document are performed in accordance with
The NRC staff has reviewed the and bright’’ test used to establish the the provisions of 10 CFR 50.59. This
licensee’s analysis and, based on this acceptability of new fuel oil for use prior to approach provides an effective level of
review, it appears that the three addition to storage tanks has been expanded regulatory control and ensures that diesel
mstockstill on DSK3G9T082PROD with NOTICES
standards of 10 CFR 50.92(c) are to recognize more rigorous testing of water fuel oil testing is conducted such that there
and sediment content. Relocating the specific is no significant reduction in a margin of
satisfied. Therefore, the NRC staff ASTM standard references from the TS to a safety. The ‘‘clear and bright’’ test used to
proposes to determine that the licensee-controlled document and allowing a establish the acceptability of new fuel oil for
amendment request involves no water and sediment content test to be use prior to addition to storage tanks has
significant hazards consideration. performed to establish the acceptability of been expanded to allow a water and
Attorney for licensee: Jennifer M. new fuel oil will not affect nor degrade the sediment content test to be performed to
Buettner, Associate General Counsel, ability of the emergency diesel generators establish the acceptability of new fuel oil.
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![Federal Register / Vol. 82, No. 38 / Tuesday, February 28, 2017 / Notices 12137
The margin of safety provided by the DGs is introduced by this change will further Tennessee Valley Authority, Docket
unaffected by the proposed changes since minimize possible concerns. Nos. 50–390 and 50–391, Watts Bar
there continue to be TS requirements to Therefore, this change does not involve a Nuclear Plant (WBN), Units 1 and 2,
ensure fuel oil is of the appropriate quality significant increase in the probability or
consequences of an accident previously
Rhea County, Tennessee
for emergency DG use. The proposed changes
provide the flexibility needed to improve fuel evaluated. Date of amendment request: October
oil sampling and analysis methodologies Criterion 2—The Proposed Change Does
Not Create the Possibility of a New or
20, 2016. A publicly-available version is
while maintaining sufficient controls to
Different Kind of Accident from any in ADAMS under Accession No.
preserve the current margins of safety.
Previously Evaluated ML16294A551.
The NRC staff has reviewed the The proposed change does not involve a Description of amendment request:
licensee’s analysis and, based on this physical alteration of the plant (no new or The amendments would revise the
review, it appears that the three different type of equipment will be installed). Technical Specifications related to the
standards of 10 CFR 50.92(c) are Allowing delay times for entering supported auxiliary building gas treatment system
satisfied. Therefore, the NRC staff system TS when inoperability is due solely
to an unavailable barrier, if risk is assessed
(ABGTS) to provide an action for when
proposes to determine that the and managed, will not introduce new failure the auxiliary building secondary
amendment request involves no modes or effects and will not, in the absence containment enclosure (ABSCE)
significant hazards consideration. of other unrelated failures, lead to an boundary is degraded, and to allow the
Attorney for licensee: Jennifer M. Buettner, accident whose consequences exceed the ABSCE boundary to be open
Associate General Counsel, Southern Nuclear consequences of accidents previously intermittently under administrative
Operating Company, 40 Iverness Center evaluated. The addition of a requirement to controls without entering the associated
assess and manage the risk introduced by this
Parkway, Birmingham, AL 35242. ABGTS limiting condition for operation.
NRC Branch Chief: Michael T. Markley. change will further minimize possible
concerns. The proposed changes are consistent
Southern Nuclear Operating Company, Inc., Thus, this change does not create the with NUREG–1431, ‘‘Standard
Docket Nos. 50–424 and 50–425, Vogtle possibility of a new or different kind of Technical Specifications Westinghouse
Electric Generating Plant, Units 1 and 2, accident from an accident previously Plants,’’ Revision 4, dated April 2012
Burke County, Georgia evaluated. (ADAMS Accession No. ML12100A222).
Date of amendment request: November 15, Basis for proposed no significant
2016. A publicly-available version is in
Criterion 3—The Proposed Change
Does Not Involve a Significant hazards consideration determination:
ADAMS under Accession No. ML16320A219.
Description of amendment request: The Reduction in the Margin of Safety As required by 10 CFR 50.91(a), the
amendments would add technical The proposed change allows a delay time
licensee has provided its analysis of the
specifications (TS) Limiting Condition for for entering a supported system TS when the issue of no significant hazards
Operation (LCO) 3.0.10 for unavailable inoperability is due solely to an unavailable consideration, which is presented
barriers as described in TSTF–427, Revision barrier, if risk is assessed and managed. The below:
2, ‘‘Allowance for Non Technical postulated initiating events which may 1. Does the proposed amendment involve
Specification Barrier Degradation on require a functional barrier are limited to a significant increase in the probability or
Supported System OPERABILITY.’’ The NRC those with low frequencies of occurrence, consequence of an accident previously
approved TSTF–427, Revision 2, as a part of and the overall TS system safety function
evaluated?
the consolidated line item improvement would still be available for the majority of
Response: No.
process on October 3, 2006 (71 FR 58444). anticipated challenges. The risk impact of the
The proposed changes do not require
Basis for proposed no significant hazards proposed TS changes was assessed following
physical changes to plant systems, structures,
consideration determination: As required by the three-tiered approach recommended in
RG [Regulatory Guide] 1.177. A bounding or components. The ABGTS is an accident
10 CFR 50.91(a), the licensee has provided its mitigating feature. As such, ABGTS is not
analysis of the issue of no significant hazards risk assessment was performed to justify the
proposed TS changes. This application of associated with a potential accident-initiating
consideration, which is presented below: mechanism.
LCO 3.0.9 is predicated upon the licensee’s
Criterion 1—The Proposed Change performance of a risk assessment and the Therefore, the changes do not affect
Does Not Involve a Significant Increase management of plant risk. The net change to accident or transient initiation or
in the Probability or Consequences of an the margin of safety is insignificant as consequences.
indicated by the anticipated low levels of The proposed new condition for the
Accident Previously Evaluated ABGTS TS would permit a 24 hour period to
associated risk (ICCDP [incremental
The proposed change allows a delay time conditional core damage probability] and restore an inoperable pressure boundary to
for entering a supported system technical ICLERP [incremental conditional large early operable status. The consequences of
specification (TS) when the inoperability is release probability]) as shown in Table 1 of implementing the 24 hour completion time
due solely to an unavailable barrier if risk is Section 3.1.1 in the Safety Evaluation. are reasonable based upon the low
assessed and managed. The postulated Therefore, this change does not involve a probability of a design basis accident
initiating events which may require a significant reduction in a margin of safety. occurring during this time period, and the
functional barrier are limited to those with availability of a functional ABGTS train to
low frequencies of occurrence, and the The NRC staff has reviewed the provide a filtered release to the environment
overall TS system safety function would still licensee’s analysis and, based on this (albeit with the potential for unfiltered
be available for the majority of anticipated review, it appears that the three leakage).
challenges. Therefore, the probability of an standards of 10 CFR 50.92(c) are For cases where the ABSCE boundary is
accident previously evaluated is not satisfied. Therefore, the NRC staff opened intermittently under administrative
significantly increased, if at all. The proposes to determine that the controls, appropriate compensatory measures
consequences of an accident while relying on amendment request involves no would be required by the proposed TS to
the allowance provided by proposed LCO ensure the ABSCE boundary can be rapidly
mstockstill on DSK3G9T082PROD with NOTICES
significant hazards consideration.
3.0.9 are no different than the consequences Attorney for licensee: Jennifer M. restored and the dose analysis assumptions
of an accident while relying on the TS can be supported. Based on the
required actions in effect without the
Buettner, Associate General Counsel, administrative controls required to rapidly
allowance provided by proposed LCO 3.0.9. Southern Nuclear Operating Company, restore an opened ABSCE boundary, the
Therefore, the consequences of an accident 40 Iverness Center Parkway, accident consequences do not cause an
previously evaluated are not significantly Birmingham, AL 35242. increase in dose above the applicable General
affected by this change. The addition of a NRC Branch Chief: Michael T. Design Criteria, Standard Review Plan, or 10
requirement to assess and manage the risk Markley. CFR 100 limits. The plant operators will
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![12142 Federal Register / Vol. 82, No. 38 / Tuesday, February 28, 2017 / Notices
are listed in the Safety Evaluation Description of amendment: The Control.’’ This RG is being withdrawn
enclosed with the amendments. amendment authorizes changes to the because the term ‘‘limit of error’’ is no
Renewed Facility Operating License VEGP Units 3 and 4 Updated Final longer used in the material control and
Nos. NPF–57, DPR–70, and DPR–75: The Safety Analysis Report in the form of accounting (MC&A) requirements in
amendments revised the Renewed departures from the incorporated plant NRC’s regulations, and therefore the RG
Facility Operating Licenses and the TSs. specific Design Control Document Tier 5.18 guidance is no longer needed. The
Date of initial notice in Federal 2 information and involves changes to MC&A requirements now include the
Register: November 22, 2016 (81 FR COL Appendix A Technical term ‘‘standard error’’ in place of the
83877). The supplemental letter dated Specifications and associated Bases. The term ‘‘limit of error.’’ The ‘‘standard
December 19, 2016, provided additional changes add reactor coolant density error’’ term is used in evaluating the
information that clarified the compensation to the reactor coolant significance of an inventory difference
application, did not expand the scope of flow input signal to the Reactor Trip (ID). The NRC has issued guidance
the application as originally noticed, System instrumentation for the low separately for the term ‘‘standard error.’’
and did not change the staff’s original reactor coolant flow reactor trip DATES: The effective date of the
proposed no significant hazards function and add Technical withdrawal of RG 5.18 is February 28,
consideration determination as Specification Surveillance Requirement 2017.
published in the Federal Register. 3.3.1.3 to the surveillances required for
The Commission’s related evaluation ADDRESSES: Please refer to Docket ID
the Reactor Coolant Flow-Low reactor NRC–2017–0059 when contacting the
of the amendments is contained in a trip.
Safety Evaluation dated February 6, NRC about the availability of
Date of issuance: January 13, 2017. information regarding this document.
2017. Effective date: As of the date of
No significant hazards consideration You may obtain publically-available
issuance and shall be implemented information related to this document,
comments received: No.
within 30 days of issuance. using the following methods:
Southern Nuclear Operating Company, Amendment No.: 65. A publicly- • Federal Rulemaking Web site: Go to
Docket No. 52–025, Vogtle Electric available version is in ADAMS under http://www.regulations.gov and search
Generating Plant (VEGP), Unit 3, Burke Accession No. ML16348A073; for Docket ID NRC–2017–0059. Address
County, Georgia documents related to this amendment questions about NRC dockets to Carol
Date of amendment request: are listed in the Safety Evaluation Gallagher; telephone: 301–415–3463;
September 13, 2016. enclosed with the amendment. email: Carol.Gallagher@nrc.gov. For
Description of amendment: The Facility Combined Licenses Nos. NPF– technical questions, contact the
amendment authorizes changes to the 91 and NPF–92: Amendment revised the individuals listed in the FOR FURTHER
VEGP Units 3 and 4 Updated Final Facility Combined License. INFORMATION CONTACT section of this
Safety Analysis Report in the form of Date of initial notice in Federal document.
departures from the incorporated plant Register: August 2, 2016 (81 FR 50729). • NRC’s Agencywide Documents
specific Design Control Document Tier The Commission’s related evaluation Access and Management System
2* information. The departures change of the amendment is contained in the (ADAMS): You may obtain publicly-
the provided minimum reinforcement Safety Evaluation dated January 13, available documents online in the
area in the VEGP Unit 3 column line 7.3 2017. ADAMS Public Document collection at
wall from elevation 82′-6″ to elevation No significant hazards consideration http://www.nrc.gov/reading-rm/
100′-0″. comments received: No. adams.html. To begin the search, select
Date of issuance: January 30, 2017. Dated at Rockville, Maryland, this 17th day ‘‘ADAMS Public Documents’’ and then
Effective date: As of the date of of February 2017. select ‘‘Begin Web-based ADAMS
issuance and shall be implemented For the Nuclear Regulatory Commission. Search.’’ For problems with ADAMS,
within 30 days of issuance. please contact the NRC’s Public
Kathryn M. Brock,
Amendment No.: 68. A publicly- Document Room (PDR) reference staff at
available version is in ADAMS under Deputy Director, Division of Operating
Reactor Licensing, Office of Nuclear Reactor 1–800–397–4209, 301–415–4737, or by
Accession No. ML16350A060; email to pdr.resource@nrc.gov. The
Regulation.
documents related to this amendment ADAMS accession number for each
[FR Doc. 2017–03806 Filed 2–27–17; 8:45 am]
are listed in the Safety Evaluation document referenced (if it is available in
enclosed with the amendment. BILLING CODE 7590–01–P
ADAMS) is provided the first time that
Facility Combined Licenses No. NPF–
it is mentioned in this document. The
91: Amendment revised the Facility
NUCLEAR REGULATORY basis for the withdrawal of this guide is
Combined License.
Date of initial notice in Federal COMMISSION in ADAMS under Accession No.
Register: October 11, 2016 (81 FR ML16244A672.
[NRC–2017–0059] • NRC’s PDR: You may examine and
70175).
The Commission’s related evaluation purchase copies of public documents at
Limit of Error Concepts and Principles the NRC’s PDR, Room O1–F21, One
of the amendment is contained in the of Calculation in Nuclear Materials
Safety Evaluation dated January 30, White Flint North, 11555 Rockville
Control Pike, Rockville, Maryland 20852.
2017.
No significant hazards consideration AGENCY: Nuclear Regulatory Regulatory guides are not
Commission. copyrighted, and NRC approval is not
mstockstill on DSK3G9T082PROD with NOTICES
comments received: No.
ACTION: Regulatory guide: withdrawal.
required to reproduce them.
Southern Nuclear Operating Company, FOR FURTHER INFORMATION CONTACT:
Docket Nos. 52–025 and 52–026, Vogtle SUMMARY: The U.S. Nuclear Regulatory Glenn Tuttle, Office of Nuclear
Electric Generating Plant (VEGP), Units Commission (NRC) is withdrawing Materials Safety and Safeguards,
3 and 4, Burke County, Georgia Regulatory Guide (RG) 5.18, ‘‘Limit of telephone: 301–415–7230, email:
Date of amendment request: May 27, Error Concepts and Principles of Glenn.Tuttle@nrc.gov; and Harriet
2016. Calculation in Nuclear Materials Karagiannis, Office of Nuclear
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Document Created: 2017-02-27 23:53:33
Document Modified: 2017-02-27 23:53:33
| 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 March 30, 2017. A request for a hearing must be filed May 1, 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 12130 |
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