80 FR 11492 - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Considerations and Containing Sensitive Unclassified Non-Safeguards Information and Order Imposing Procedures for Access to Sensitive Unclassified Non-Safeguards Information
NUCLEAR REGULATORY COMMISSION Federal Register Volume 80, Issue 41 (March 3, 2015)
Federal Register Volume 80, Issue 41 (March 3, 2015)
| Page Range | 11492-11498 | |
| FR Document | 2015-03917 |
[Federal Register Volume 80, Number 41 (Tuesday, March 3, 2015)] [Notices] [Pages 11492-11498] From the Federal Register Online [www.thefederalregister.org] [FR Doc No: 2015-03917] ----------------------------------------------------------------------- NUCLEAR REGULATORY COMMISSION [NRC-2015-0030] Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Considerations and Containing Sensitive Unclassified Non-Safeguards Information and Order Imposing Procedures for Access to Sensitive Unclassified Non-Safeguards Information AGENCY: Nuclear Regulatory Commission. ACTION: License amendment request; opportunity to comment, request a hearing, and petition for leave to intervene; order. ----------------------------------------------------------------------- SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) received and is considering approval of four amendment requests. The amendment requests are for Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2; Peach Bottom Atomic Power Station, Unit 2; Diablo Canyon Nuclear Power Plant, Units 1 and 2; and Vogtle Electric Generating Plant, Units 1 and 2, Joseph M. Farley Nuclear Plant, Units 1 and 2, and Edwin I. Hatch Nuclear Plant, Units 1 and 2. The NRC proposes to determine that each amendment request involves no significant hazards consideration. In addition, each amendment request contains sensitive unclassified non-safeguards information (SUNSI). DATES: Comments must be filed by April 2, 2015. A request for a hearing must be filed by May 4, 2015. Any potential party as defined in Sec. 2.4 of Title 10 of the Code of Federal Regulations (10 CFR), who believes access to SUNSI is necessary to respond to this notice must request document access by March 13, 2015. ADDRESSES: You may submit comments by any of the following methods (unless this document describes a different method for submitting comments on a specific subject):Federal Rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2015-0030. Address questions about NRC dockets to Carol Gallagher; telephone: 301-415- 3463; email: [email protected]. Mail comments to: Cindy Bladey, Office of Administration, Mail Stop: O12-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: Shirley Rohrer, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; telephone: 301-415-5411; email: [email protected]. SUPPLEMENTARY INFORMATION: I. Obtaining Information and Submitting Comments A. Obtaining Information Please refer to Docket ID NRC-2015-0030 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-2015-0030. 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 the SUPPLEMENTARY INFORMATION section. 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-2015-0030, facility name, unit number(s), 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. Background Pursuant to Section 189a.(2) of the Atomic Energy Act of 1954, as amended (the Act), the NRC is publishing this 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 notice includes notices of amendments containing SUNSI. III. Notice of Consideration of Issuance of Amendments to Facility Operating Licenses and Combined Licenses, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing The Commission has made a proposed determination that the following amendment requests involve no significant hazards consideration. Under the Commission's regulations in 10 CFR 50.92, 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 [[Page 11493]] 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 should 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. Should the Commission take action prior to the expiration of either the comment period or the notice period, it will publish a notice of issuance in the Federal Register. Should the Commission make 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 person(s) whose interest may be affected by this action may file a request for a hearing and a petition to intervene with respect to issuance of the amendment to the subject facility operating license or combined license. Requests for a hearing and a petition for leave to intervene shall be filed in accordance with the Commission's ``Agency Rules of Practice and Procedure'' in 10 CFR part 2. Interested person(s) should consult a current copy of 10 CFR 2.309, which is available at the NRC's PDR, located at One White Flint North, Room O1- F21, 11555 Rockville Pike (first floor), Rockville, Maryland 20852. 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/. If a request for a hearing or petition for leave to intervene is filed within 60 days, the Commission or a presiding officer designated by the Commission or by the Chief Administrative Judge of the Atomic Safety and Licensing Board Panel, will rule on the request and/or petition; and the Secretary or the Chief Administrative Judge of the Atomic Safety and Licensing Board will issue a notice of a hearing or an appropriate order. As required by 10 CFR 2.309, a petition for leave to intervene shall set forth with particularity the interest of the petitioner in the proceeding, and how that interest may be affected by the results of the proceeding. The petition should specifically explain the reasons why intervention should be permitted with particular reference to the following general requirements: (1) The name, address, and telephone number of the requestor or petitioner; (2) the nature of the requestor's/petitioner's right under the Act to be made a party to the proceeding; (3) the nature and extent of the requestor's/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 requestor's/petitioner's interest. The petition must also set forth the specific contentions which the requestor/petitioner seeks to have litigated at 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 requestor/petitioner shall 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 requestor/ petitioner intends to rely in proving the contention at the hearing. The requestor/petitioner must also provide references to those specific sources and documents of which the petitioner is aware and on which the requestor/petitioner intends to rely to establish those facts or expert opinion. The petition must include sufficient information to show that a genuine dispute exists with the applicant on a material issue of law or fact. Contentions shall be limited to matters within the scope of the amendment under consideration. The contention must be one which, if proven, would entitle the requestor/petitioner to relief. A requestor/ petitioner who fails to satisfy these requirements 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, and have the opportunity to participate fully in the conduct of the hearing. 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 decide when the hearing is held. If the final determination is that the amendment request involves no significant hazards consideration, the Commission may issue the amendment and make it immediately effective, notwithstanding the request for a hearing. Any hearing held 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 any 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. B. Electronic Submissions (E-Filing) All documents filed in NRC adjudicatory proceedings, including a request for hearing, a petition for leave to intervene, 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 participating under 10 CFR 2.315(c), must be filed in accordance with the NRC's E-Filing rule (72 FR 49139; August 28, 2007). 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. 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 request (1) a digital identification (ID) certificate, which allows the participant (or its counsel or representative) to digitally sign documents and access the E-Submittal server for any proceeding in which it is participating; and (2) advise the Secretary that the participant will be submitting a request or petition for hearing (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/ [[Page 11494]] getting-started.html. System requirements for accessing the E-Submittal server are detailed in the NRC's ``Guidance for Electronic Submission,'' which is available on the agency's public Web site at http://www.nrc.gov/site-help/e-submittals.html. Participants may attempt to use other software not listed on the Web site, but should note that the NRC's E-Filing system does not support unlisted software, and the NRC Meta System Help Desk will not be able to offer assistance in using unlisted software. If a participant is electronically submitting a document to the NRC in accordance with the E-Filing rule, the participant must file the document using the NRC's online, Web-based submission form. In order to serve documents through the Electronic Information Exchange System, users will be required to install a Web browser plug-in from the NRC's Web site. Further information on the Web-based submission form, including the installation of the Web browser plug-in, is available on the NRC's public Web site at http://www.nrc.gov/site-help/e-submittals.html. Once a participant has obtained a digital ID certificate and a docket has been created, the participant can then submit a request for hearing or petition for leave to intervene. Submissions should be in Portable Document Format (PDF) in accordance with NRC guidance available on the NRC's public Web site at http://www.nrc.gov/site-help/e-submittals.html. A filing is considered complete at the time the documents are 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 documents on those participants separately. Therefore, applicants and other participants (or their counsel or representative) must apply for and receive a digital ID certificate before a hearing request/petition to intervene is filed so that they can obtain access to the document via the E-Filing system. A person filing electronically using the NRC's adjudicatory E- Filing system may seek assistance by contacting the NRC Meta System 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 Meta System Help Desk is available between 8 a.m. and 8 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 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, Sixteenth Floor, One White Flint North, 11555 Rockville Pike, Rockville, Maryland 20852, Attention: Rulemaking and Adjudications Staff. Participants filing a document in this manner are responsible for serving the document on all other participants. Filing is considered complete by first-class mail as of the time of deposit in the mail, or by courier, express mail, or expedited delivery service upon depositing the document with the provider of the service. A presiding officer, having granted an exemption request from using E-Filing, may require a participant or party to use E-Filing if the presiding officer subsequently determines that the reason for granting the exemption from use of E-Filing no longer exists. Documents submitted in adjudicatory proceedings will appear in the NRC's electronic hearing docket which is available to the public at http://ehd1.nrc.gov/ehd/, unless excluded pursuant to an order of the Commission, or the presiding officer. Participants are requested not to include personal privacy information, such as social security numbers, home addresses, or home phone numbers in their filings, unless an NRC regulation or other law requires submission of such information. However, a request to intervene will require including information on local residence in order to demonstrate a proximity assertion of interest in the proceeding. 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. Petitions for leave to intervene must be filed no later than 60 days from the date of publication of this notice. Requests for hearing, petitions for leave to intervene, and motions for leave to file new or amended contentions that are filed after the 60-day 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)-(iii). For further details with respect to this amendment action, see the application for amendment which is available for public inspection at the NRC's PDR, located at One White Flint North, Room O1-F21, 11555 Rockville Pike (first floor), Rockville, Maryland 20852. Publicly available documents created or received at the NRC are accessible electronically through ADAMS in the NRC Library at http://www.nrc.gov/reading-rm/adams.html. If you do not have access to ADAMS or if there are problems in accessing the documents located in ADAMS, contact the PDR's Reference staff at 1-800-397-4209, 301-415-4737, or by email to [email protected]. Exelon Generation Company, LLC, Docket Nos. STN 50-456 and STN 50-457, Braidwood Station, Units 1 and 2, Will County, Illinois; Docket Nos. STN 50-454 and STN 50-455, Byron Station, Units 1 and 2, Ogle County, Illinois Date of amendment request: October 16, 2014. A publicly-available version is in ADAMS under Accession No. ML14289A580. Description of amendment request: This amendment request contains sensitive unclassified non-safeguards information (SUNSI). The proposed amendment would allow utilization of WCAP-16143-P, Revision 1, ``Reactor Vessel Closure Head/Vessel Flange Requirements Evaluation for Byron/Braidwood Units 1 and 2,'' dated October 2014, as an analytical method to determine the reactor coolant system pressure and temperature (P-T) limits. 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 with NRC staff's edits in square brackets: EGC [Exelon Generation Company, LLC] has evaluated the proposed change for Braidwood Station and Byron Station, using the criteria in 10 CFR 50.92, and has determined that the proposed change does [[Page 11495]] not involve a significant hazards consideration. The following information is provided to support a finding of no significant hazards consideration. Criteria 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated? Response: No. These changes to the analysis do not adversely affect accident initiators or precursors, nor alter the design assumptions or conditions of the facility previously approved by the NRC, or the manner in which the plant is operated and maintained. The revisions to the subject WCAP [WCAP-16143[-P]] do not alter or prevent the ability of structures, systems, and components (SSCs) from performing their intended function to mitigate the consequences of an initiating event within the assumed acceptance limits. The changes also do not affect the source term, containment isolation, or radiological release assumptions used in evaluating the radiological consequences of an accident previously evaluated; do not increase the types or amounts of radioactive effluent that may be released offsite; and do not significantly increase individual or cumulative occupational/public radiation exposures. Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated. 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated? Response: No. The use of WCAP-16143[-P], Revision 1, for generation of [Reactor Pressure Vessel] RPV P-T limits, will continue to ensure that RPV integrity is maintained under all conditions. The revisions contained in WCAP-16143[-P], Revision 1, and the changes proposed to TS [Technical Specifications] Table 1.1-1 do not change the conclusions of WCAP-16143[-P], Revision 0, previously approved by the NRC; nor do they change the way the RPV is analyzed or performs its safety function. Subsequently, these changes do not result in the creation of any new accident initiators or precursors; do not result in changes to any existing accident scenarios; and do not introduce any operational changes or mechanisms that would create the possibility of a new or different kind of accident. Based on the above discussion, the proposed changes do not create the possibility of a new or different kind of accident from any previously evaluated. 3. Does the proposed change involve a significant reduction in a margin of safety? Response: No. The proposed changes do not change any safety limits or reduce the margin of safety to any safety limits. The stress analysis and fracture mechanics evaluation, documented in the revision to WCAP- 16143[-P], determined that for the RPV boltup condition, the RPV 54- stud case (i.e., all RPV head studs in-service) was more limiting than the RPV 53-stud case (i.e., one RPV head stud out-of-service). In addition, the conclusions of the updated analysis for the RPV 54- stud case confirmed the conclusions from WCAP-16143, Revision 0. This change, subsequently, has no impact on the current RPV P-T limit curves. Therefore, the proposed changes do not involve a significant reduction in a margin of safety. Based on the above, EGC concludes that the proposed changes do not involve a significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and, accordingly, a finding of ``no significant hazards consideration'' is justified. The NRC staff has reviewed the licensee's analysis and, based on this review, it appears that the three standards of 10 CFR 50.92(c) are satisfied. Therefore, the NRC staff proposes to determine that the requested amendments involve no significant hazards consideration. Attorney for licensee: Bradley J. Fewell, Associate General Counsel, Exelon Nuclear, 4300 Winfield Road, Warrenville, Illinois 60555. NRC Branch Chief: Travis L. Tate. Exelon Generation Company, LLC, and PSEG Nuclear LLC, Docket No. 50- 277, Peach Bottom Atomic Power Station (PBAPS), Unit 2, York and Lancaster Counties, Pennsylvania Date of application for amendment: December 5, 2014. A publicly- available version is in ADAMS under Accession No. ML14342A229. Description of amendment request: This amendment request contains sensitive unclassified non-safeguards information (SUNSI). The proposed amendment would revise the Technical Specifications (TSs) related to the Safety Limit Minimum Critical Power Ratios (SLMCPRs). The proposed changes result from a cycle-specific analysis performed to support the operation of PBAPS, Unit 2, in the upcoming Cycle 21. The re-analysis was performed to accommodate operation in the Maximum Extended Load Line Limit Analysis Plus (MELLLA+) operating domain based on a separate license amendment request (LAR) dated September 4, 2014 (ADAMS Accession No. ML14247A503). 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 with NRC staff's edits in square brackets: 1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated? Response: No. The derivation of the cycle specific Safety Limit Minimum Critical Power Ratios (SLMCPRs) for incorporation into the Technical Specifications (TS), and their use to determine cycle specific thermal limits, has been performed using the methodology discussed in NEDE-24011-P-A, ``General Electric Standard Application for Reactor Fuel,'' Revision 20 [ADAMS Accession No. ML13352A474]. The basis of the SLMCPR calculation is to ensure that during normal operation and during anticipated operational transients, at least 99.9% of all fuel rods in the core do not experience boiling transition if the limit is not violated. The new SLMCPRs preserve the existing margin to boiling transition. The MCPR safety limit is reevaluated for each reload using NRC- approved methodologies. The analyses for PBAPS, Unit 2 Cycle 21, with the addition of operation in the MELLLA+ operating domain, have concluded that a two recirculation loop MCPR safety limit of >=1.15, based on the application of Global Nuclear Fuel's NRC-approved MCPR safety limit methodology, will ensure that this acceptance criterion is met. For single recirculation loop operation, a MCPR safety limit of >=1.15 also ensures that this acceptance criterion is met. The MCPR operating limits are presented and controlled in accordance with the PBAPS Unit 2 Core Operating Limits Report (COLR). The requested TS changes do not involve any additional plant modifications or operational changes that could affect system reliability or performance or that could affect the probability of operator error beyond those associated with the MELLLA+ LAR [ADAMS Accession No. ML14247A503]. The requested changes do not affect any postulated accident precursors, do not affect any accident mitigating systems, and do not introduce any new accident initiation mechanisms. Therefore, the proposed TS changes do not involve a significant increase in the probability or consequences of an accident previously evaluated. 2. Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated? Response: No. The SLMCPR is a TS numerical value, calculated to ensure that during normal operation and during anticipated operational transients, at least 99.9% of all fuel rods in the core do not experience boiling transition if the limit is not violated. The new SLMCPRs are calculated using NRC-approved methodology discussed in NEDE-24011-P-A, ``General Electric Standard Application for Reactor Fuel,'' Revision 20 [ADAMS Accession No. ML13352A474]. The proposed changes do not involve any new modes of operation, any changes to setpoints, or any plant modifications beyond those associated with the MELLLA+ LAR [ADAMS Accession No. ML14247A503]. The proposed revised MCPR safety limits have been shown to be acceptable for Cycle 21 operation with the MELLLA+ operating domain. The core operating limits will continue to be developed using NRC-approved methods. The proposed MCPR safety limits or methods for establishing the core operating limits do [[Page 11496]] not result in the creation of any new precursors to an accident. Therefore, this 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. There is no significant reduction in the margin of safety previously approved by the NRC as a result of the proposed change to the SLMCPRs. The new SLMCPRs are calculated using methodology discussed in NEDE-24011-P-A, ``General Electric Standard Application for Reactor Fuel,'' Revision 20 [ADAMS Accession No. ML13352A474]. The SLMCPRs ensure that during normal operation and during anticipated operational transients, at least 99.9% of all fuel rods in the core do not experience boiling transition if the limits are not violated, thereby preserving the fuel cladding integrity. Therefore, the proposed TS changes do not involve a significant reduction in the margin of safety previously approved by the NRC. The NRC staff has reviewed the licensee's analysis and, based on this review, and with the changes noted above in square brackets, 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: J. Bradley Fewell, Esquire, Vice President and Deputy General Counsel, Exelon Generation Company, LLC, 200 Exelon Way, Kennett Square, Pennsylvania 19348. NRC Branch Chief: Meena K. Khanna. Pacific Gas and Electric Company, Docket Nos. 50-275 and 50-323, Diablo Canyon Nuclear Power Plant (DCPP), Units 1 and 2, San Luis Obispo County, California Date of amendment request: October 2, 2014. A publicly-available version is in ADAMS under Accession No. ML14275A444. Description of amendment request: This amendment request contains sensitive unclassified non-safeguards information (SUNSI). The proposed amendments request approval to perform the fuel assembly structural analyses based on a pipe break that considers the application of leak- before-break, which allows the exclusion of the dynamic effects of certain pipe breaks, consistent with 10 CFR part 50, Appendix A, General Design Criterion 4, ``Environmental and design effects design bases,'' for DCPP, Units 1 and 2. The fuel assembly structural analyses are performed to satisfy NUREG-0800, ``Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition,'' Section 4.2, ``Fuel System Design,'' Appendix A, ``Evaluation of Fuel Assembly Structural Response to Externally Applied Forces,'' Revision 3, March 2007 (ADAMS Accession No. ML070740002). Further, the licensee requests approval to use the fuel assembly structural analysis results to satisfy, in part, the emergency core cooling system performance criterion, 10 CFR 50.46(b)(4), ``Coolable geometry.'' 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 with NRC staff's edits in square brackets: 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated? Response: No. The proposed change requests approval to perform the fuel assembly structural analyses based on a pipe break that considers the application of Leak-Before-Break (LBB). Performing the fuel assembly structural analyses based on a pipe break that considers the application of LBB will not impact any accident previously evaluated. No physical changes are being made to the plant as a result of this change. DCPP will continue to satisfy the criteria of 10 CFR 50.46(b) with this change. Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated. 2. Does the proposed change create the possibility of a new or different accident from any accident previously evaluated? Response: No. The proposed change does not involve any physical changes to the plant. The best-estimate large break loss-of-coolant [accident] (BELOCA) analyses are not impacted by this change. Therefore, the proposed change does not create the possibility of a new or different accident from any accident previously evaluated. 3. Does the proposed change involve a significant reduction in a margin of safety? Response: No. The revised fuel structural integrity analysis incorporates the reduced LBB loads and therefore will not decrease the margin of safety to the 10 CFR 50.46 limits. The BELOCA analyses are not impacted by this change, and the criteria of 10 CFR 50.46(b) continue to be met. The proposed change does not involve any changes to the fuel, reactor vessel, or containment fission product barriers. Therefore there will be no impact on the accident analyses that are contained in the Updated Final Safety Analysis Report. 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 requests involve no significant hazards consideration. Attorney for licensee: Jennifer Post, Esq., Pacific Gas and Electric Company, P.O. Box 7442, San Francisco, California 94120. Acting NRC Branch Chief: Eric R. Oesterle. Southern Nuclear Operating Company, Inc. (SNC), Docket Nos. 50-424 and 50-425, Vogtle Electric Generating Plant (VEGP), Units 1 and 2, Burke County, Georgia; Docket Nos. 50-348 and 50-364, Joseph M. Farley Nuclear Plant (FNP), Units 1 and 2, Houston County, Alabama; Docket Nos. 50-321 and 50-366, Edwin I. Hatch Nuclear Plant (HNP), Units 1 and 2, City of Dalton, Georgia Date of amendment request: December 30, 2014. A publicly-available version is in ADAMS under Accession No. ML14365A352. Description of amendment request: This amendment request contains sensitive unclassified non-safeguards information (SUNSI). The amendments would revise the Cyber Security Plan (CSP) implementation schedule. 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 with NRC staff's edits in square brackets: 1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated? Response: No. The proposed license amendment request is for a change to the Milestone 8 implementation schedule for the SNC CSP, as cited by the existing FOLs [facility operating licenses] applicable to FNP, HNP and VEGP Units 1 and 2. The CSP is designed to provide high assurance that the systems within the scope of Sec. 73.54 are protected from cyber attacks. The CSP itself does not require any plant modifications, but the plan describes appropriate configuration management requirements to assure plant modifications involving digital computer systems are reviewed to provide adequate protection against cyber attacks, up to and including the design basis threat as defined in Sec. 73.54. The proposed change is a schedule change for CSP implementation only; it will modify the existing FOL for each SNC-operated facility to add citation of the license amendment establishing the new Milestone 8 completion date. This change is administrative in nature and does not alter [[Page 11497]] the plant configuration, involve the installation of new plant equipment, alter accident analysis assumptions, add any new initiators, or affect the function of plant systems or the manner in which systems are operated, maintained, modified, tested, or inspected. Based on the above, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated. 2. Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated? Response: No. The proposed change will modify the existing FOL for each SNC- operated facility to add citation of the license amendment establishing the new Milestone 8 completion date for CSP implementation. This change is administrative in nature and does not alter plant configuration, install new plant equipment, alter accident analysis assumptions, add any initiators, or affect the function of plant systems or the manner in which systems are operated, maintained, tested, or inspected. Accordingly, the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated. 3. Does the proposed amendment involve a significant reduction in a margin of safety? Response: No. The proposed SNC CSP Milestone 8 implementation date change does not alter plant configuration, install new plant equipment, alter accident analysis assumptions, add any initiators, or affect the function of plant systems or the manner in which systems are operated, maintained, tested, or inspected. Plant safety margins are established through Limiting Conditions for Operation, Limiting Safety System Settings and Safety Limits specified in the Technical Specifications. Because there is no change to these established safety margins, the proposed change does not involve a reduction in a margin of safety. The proposed change will modify the existing FOL for each SNC- operated facility to add citation of the license amendment establishing the new Milestone 8 completion date. This change is administrative in nature and does not involve a reduction in margin of safety. Based on the above, 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: Leigh D. Perry, SVP & General Counsel of Operations and Nuclear, Southern Nuclear Operating Company, 40 Iverness Center Parkway, Birmingham, Alabama 35201. NRC Branch Chief: Robert J. Pascarelli. Order Imposing Procedures for Access to Sensitive Unclassified Non- Safeguards Information for Contention Preparation. Exelon Generation Company, LLC, Docket Nos. STN 50-456 and STN 50-457, Braidwood Station, Units 1 and 2, Will County, Illinois, Docket Nos. STN 50-454 and STN 50-455, Byron Station, Units 1 and 2, Ogle County, Illinois Exelon Generation Company, LLC, and PSEG Nuclear LLC, Docket No. 50- 277, Peach Bottom Atomic Power Station, Unit 2, York and Lancaster Counties, Pennsylvania Pacific Gas and Electric Company, Docket Nos. 50-275 and 50-323, Diablo Canyon Nuclear Power Plant, Units 1 and 2, San Luis Obispo County, California 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, City of Dalton, Georgia A. This Order contains instructions regarding how potential parties to this proceeding may request access to documents containing SUNSI. B. Within 10 days after publication of this notice of hearing and opportunity to petition for leave to intervene, any potential party who believes access to SUNSI is necessary to respond to this notice may request such access. A ``potential party'' is any person who intends to participate as a party by demonstrating standing and filing an admissible contention under 10 CFR 2.309. Requests for access to SUNSI submitted later than 10 days after publication of this notice will not be considered absent a showing of good cause for the late filing, addressing why the request could not have been filed earlier. C. The requester shall submit a letter requesting permission to access SUNSI to the Office of the Secretary, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, Attention: Rulemakings and Adjudications Staff, and provide a copy to the Associate General Counsel for Hearings, Enforcement and Administration, Office of the General Counsel, Washington, DC 20555-0001. The expedited delivery or courier mail address for both offices is: U.S. Nuclear Regulatory Commission, 11555 Rockville Pike, Rockville, Maryland 20852. The email address for the Office of the Secretary and the Office of the General Counsel are [email protected] and [email protected], respectively.\1\ The request must include the following information: --------------------------------------------------------------------------- \1\ While a request for hearing or petition to intervene in this proceeding must comply with the filing requirements of the NRC's ``E-Filing Rule,'' the initial request to access SUNSI under these procedures should be submitted as described in this paragraph. --------------------------------------------------------------------------- (1) A description of the licensing action with a citation to this Federal Register notice; (2) The name and address of the potential party and a description of the potential party's particularized interest that could be harmed by the action identified in C.(1); and (3) The identity of the individual or entity requesting access to SUNSI and the requester's basis for the need for the information in order to meaningfully participate in this adjudicatory proceeding. In particular, the request must explain why publicly-available versions of the information requested would not be sufficient to provide the basis and specificity for a proffered contention. D. Based on an evaluation of the information submitted under paragraph C.(3) the NRC staff will determine within 10 days of receipt of the request whether: (1) There is a reasonable basis to believe the petitioner is likely to establish standing to participate in this NRC proceeding; and (2) The requestor has established a legitimate need for access to SUNSI. E. If the NRC staff determines that the requestor satisfies both D.(1) and D.(2) above, the NRC staff will notify the requestor in writing that access to SUNSI has been granted. The written notification will contain instructions on how the requestor may obtain copies of the requested documents, and any other conditions that may apply to access to those documents. These conditions may include, but are not limited to, the signing of a Non-Disclosure Agreement or Affidavit, or Protective Order \2\ setting forth terms and conditions to prevent the unauthorized or inadvertent disclosure of SUNSI by each individual who will be granted access to SUNSI. --------------------------------------------------------------------------- \2\ Any motion for Protective Order or draft Non-Disclosure Affidavit or Agreement for SUNSI must be filed with the presiding officer or the Chief Administrative Judge if the presiding officer has not yet been designated, within 30 days of the deadline for the receipt of the written access request. --------------------------------------------------------------------------- F. Filing of Contentions. Any contentions in these proceedings that are based upon the information received as a result of the request made for SUNSI must be filed by the requestor no later than 25 days after the requestor is [[Page 11498]] granted access to that information. However, if more than 25 days remain between the date the petitioner is granted access to the information and the deadline for filing all other contentions (as established in the notice of hearing or opportunity for hearing), the petitioner may file its SUNSI contentions by that later deadline. This provision does not extend the time for filing a request for a hearing and petition to intervene, which must comply with the requirements of 10 CFR 2.309. G. Review of Denials of Access. (1) If the request for access to SUNSI is denied by the NRC staff after a determination on standing and need for access, the NRC staff shall immediately notify the requestor in writing, briefly stating the reason or reasons for the denial. (2) The requester may challenge the NRC staff's adverse determination by filing a challenge within 5 days of receipt of that determination with: (a) the presiding officer designated in this proceeding; (b) if no presiding officer has been appointed, the Chief Administrative Judge, or if he or she is unavailable, another administrative judge, or an administrative law judge with jurisdiction pursuant to 10 CFR 2.318(a); or (c) officer if that officer has been designated to rule on information access issues. H. Review of Grants of Access. A party other than the requester may challenge an NRC staff determination granting access to SUNSI whose release would harm that party's interest independent of the proceeding. Such a challenge must be filed with the Chief Administrative Judge within 5 days of the notification by the NRC staff of its grant of access. If challenges to the NRC staff determinations are filed, these procedures give way to the normal process for litigating disputes concerning access to information. The availability of interlocutory review by the Commission of orders ruling on such NRC staff determinations (whether granting or denying access) is governed by 10 CFR 2.311.\3\ --------------------------------------------------------------------------- \3\ Requesters should note that the filing requirements of the NRC's E-Filing Rule (72 FR 49139; August 28, 2007) apply to appeals of NRC staff determinations (because they must be served on a presiding officer or the Commission, as applicable), but not to the initial SUNSI request submitted to the NRC staff under these procedures. --------------------------------------------------------------------------- I. The Commission expects that the NRC staff and presiding officers (and any other reviewing officers) will consider and resolve requests for access to SUNSI, and motions for protective orders, in a timely fashion in order to minimize any unnecessary delays in identifying those petitioners who have standing and who have propounded contentions meeting the specificity and basis requirements in 10 CFR part 2. Attachment 1 to this Order summarizes the general target schedule for processing and resolving requests under these procedures. It is so ordered. Dated at Rockville, Maryland, this 18th day of February, 2015. For the Nuclear Regulatory Commission. Annette L. Vietti-Cook, Secretary of the Commission. Attachment 1--General Target Schedule for Processing and Resolving Requests for Access to Sensitive Unclassified Non-Safeguards Information in This Proceeding ------------------------------------------------------------------------ Day Event/activity ------------------------------------------------------------------------ 0............................ Publication of Federal Register notice of hearing and opportunity to petition for leave to intervene, including order with instructions for access requests. 10........................... Deadline for submitting requests for access to Sensitive Unclassified Non- Safeguards Information (SUNSI) with information: supporting the standing of a potential party identified by name and address; describing the need for the information in order for the potential party to participate meaningfully in an adjudicatory proceeding. 60........................... Deadline for submitting petition for intervention containing: (i) Demonstration of standing; and (ii) all contentions whose formulation does not require access to SUNSI (+25 Answers to petition for intervention; +7 petitioner/ requestor reply). 20........................... U.S. Nuclear Regulatory Commission (NRC) staff informs the requester of the staff's determination whether the request for access provides a reasonable basis to believe standing can be established and shows need for SUNSI. (NRC staff also informs any party to the proceeding whose interest independent of the proceeding would be harmed by the release of the information.) If NRC staff makes the finding of need for SUNSI and likelihood of standing, NRC staff begins document processing (preparation of redactions or review of redacted documents). 25........................... If NRC staff finds no ``need'' or no likelihood of standing, the deadline for petitioner/requester to file a motion seeking a ruling to reverse the NRC staff's denial of access; NRC staff files copy of access determination with the presiding officer (or Chief Administrative Judge or other designated officer, as appropriate). If NRC staff finds ``need'' for SUNSI, the deadline for any party to the proceeding whose interest independent of the proceeding would be harmed by the release of the information to file a motion seeking a ruling to reverse the NRC staff's grant of access. 30........................... Deadline for NRC staff reply to motions to reverse NRC staff determination(s). 40........................... (Receipt +30) If NRC staff finds standing and need for SUNSI, deadline for NRC staff to complete information processing and file motion for Protective Order and draft Non-Disclosure Affidavit. Deadline for applicant/licensee to file Non- Disclosure Agreement for SUNSI. A............................ If access granted: Issuance of presiding officer or other designated officer decision on motion for protective order for access to sensitive information (including schedule for providing access and submission of contentions) or decision reversing a final adverse determination by the NRC staff. A + 3........................ Deadline for filing executed Non- Disclosure Affidavits. Access provided to SUNSI consistent with decision issuing the protective order. A + 28....................... Deadline for submission of contentions whose development depends upon access to SUNSI. However, if more than 25 days remain between the petitioner's receipt of (or access to) the information and the deadline for filing all other contentions (as established in the notice of hearing or opportunity for hearing), the petitioner may file its SUNSI contentions by that later deadline. A + 53....................... (Contention receipt +25) Answers to contentions whose development depends upon access to SUNSI. A + 60....................... (Answer receipt +7) Petitioner/Intervenor reply to answers. >A + 60...................... Decision on contention admission. ------------------------------------------------------------------------ [FR Doc. 2015-03917 Filed 3-2-15; 8:45 am] BILLING CODE 7590-01-P
![11492 Federal Register / Vol. 80, No. 41 / Tuesday, March 3, 2015 / Notices
For the Nuclear Regulatory Commission. Gallagher; telephone: 301–415–3463; submissions at http://
Michele G. Evans, email: Carol.Gallagher@nrc.gov. www.regulations.gov as well as entering
Director, Division of Operating Reactor • Mail comments to: Cindy Bladey, the comment submissions into ADAMS.
Licensing, Office of Nuclear Reactor Office of Administration, Mail Stop: The NRC does not routinely edit
Regulation. O12–H08, U.S. Nuclear Regulatory comment submissions to remove
[FR Doc. 2015–04298 Filed 3–2–15; 8:45 am] Commission, Washington, DC 20555– identifying or contact information.
BILLING CODE 7590–01–P 0001. If you are requesting or aggregating
For additional direction on obtaining comments from other persons for
information and submitting comments, submission to the NRC, then you should
NUCLEAR REGULATORY see ‘‘Obtaining Information and inform those persons not to include
COMMISSION Submitting Comments’’ in the identifying or contact information that
SUPPLEMENTARY INFORMATION section of they do not want to be publicly
[NRC–2015–0030] disclosed in their comment submission.
this document.
FOR FURTHER INFORMATION CONTACT: Your request should state that the NRC
Applications and Amendments to
Shirley Rohrer, Office of Nuclear does not routinely edit comment
Facility Operating Licenses and
Reactor Regulation, U.S. Nuclear submissions to remove such information
Combined Licenses Involving
Regulatory Commission, Washington, before making the comment
Proposed No Significant Hazards
DC 20555–0001; telephone: 301–415– submissions available to the public or
Considerations and Containing
5411; email: Shirley.Rohrer@nrc.gov. entering the comment submissions into
Sensitive Unclassified Non-Safeguards
SUPPLEMENTARY INFORMATION:
ADAMS.
Information and Order Imposing
Procedures for Access to Sensitive II. Background
I. Obtaining Information and
Unclassified Non-Safeguards Submitting Comments Pursuant to Section 189a.(2) of the
Information Atomic Energy Act of 1954, as amended
A. Obtaining Information (the Act), the NRC is publishing this
AGENCY: Nuclear Regulatory
Commission. Please refer to Docket ID NRC–2015– notice. The Act requires the
0030 when contacting the NRC about Commission to publish notice of any
ACTION: License amendment request;
the availability of information for this amendments issued, or proposed to be
opportunity to comment, request a
action. You may obtain publicly- issued and grants the Commission the
hearing, and petition for leave to
available information related to this authority to issue and make
intervene; order.
action by any of the following methods: immediately effective any amendment
SUMMARY: The U.S. Nuclear Regulatory • Federal Rulemaking Web site: Go to to an operating license or combined
Commission (NRC) received and is http://www.regulations.gov and search license, as applicable, upon a
considering approval of four for Docket ID NRC–2015–0030. determination by the Commission that
amendment requests. The amendment • NRC’s Agencywide Documents such amendment involves no significant
requests are for Braidwood Station, Access and Management System hazards consideration, notwithstanding
Units 1 and 2, and Byron Station, Units (ADAMS): You may obtain publicly- the pendency before the Commission of
1 and 2; Peach Bottom Atomic Power available documents online in the a request for a hearing from any person.
Station, Unit 2; Diablo Canyon Nuclear ADAMS Public Documents collection at This notice includes notices of
Power Plant, Units 1 and 2; and Vogtle http://www.nrc.gov/reading-rm/ amendments containing SUNSI.
Electric Generating Plant, Units 1 and 2, adams.html. To begin the search, select
III. Notice of Consideration of Issuance
Joseph M. Farley Nuclear Plant, Units 1 ‘‘ADAMS Public Documents’’ and then
of Amendments to Facility Operating
and 2, and Edwin I. Hatch Nuclear select ‘‘Begin Web-based ADAMS
Licenses and Combined Licenses,
Plant, Units 1 and 2. The NRC proposes Search.’’ For problems with ADAMS,
Proposed No Significant Hazards
to determine that each amendment please contact the NRC’s Public
Consideration Determination, and
request involves no significant hazards Document Room (PDR) reference staff at
Opportunity for a Hearing
consideration. In addition, each 1–800–397–4209, 301–415–4737, or by
email to pdr.resource@nrc.gov. The The Commission has made a
amendment request contains sensitive
ADAMS accession number for each proposed determination that the
unclassified non-safeguards information
document referenced (if it is available in following amendment requests involve
(SUNSI).
ADAMS) is provided the first time that no significant hazards consideration.
DATES: Comments must be filed by April Under the Commission’s regulations in
it is mentioned in the SUPPLEMENTARY
2, 2015. A request for a hearing must be 10 CFR 50.92, this means that operation
INFORMATION section.
filed by May 4, 2015. Any potential • NRC’s PDR: You may examine and of the facility in accordance with the
party as defined in § 2.4 of Title 10 of purchase copies of public documents at proposed amendment would not (1)
the Code of Federal Regulations (10 the NRC’s PDR, Room O1–F21, One involve a significant increase in the
CFR), who believes access to SUNSI is White Flint North, 11555 Rockville probability or consequences of an
necessary to respond to this notice must Pike, Rockville, Maryland 20852. accident previously evaluated, or (2)
request document access by March 13, create the possibility of a new or
2015. B. Submitting Comments different kind of accident from any
ADDRESSES: You may submit comments Please include Docket ID NRC–2015– accident previously evaluated, or (3)
mstockstill on DSK4VPTVN1PROD with NOTICES
by any of the following methods (unless 0030, facility name, unit number(s), involve a significant reduction in a
this document describes a different application date, and subject in your margin of safety. The basis for this
method for submitting comments on a comment submission. proposed determination for each
specific subject): The NRC cautions you not to include amendment request is shown below.
• Federal Rulemaking Web site: Go to identifying or contact information that The Commission is seeking public
http://www.regulations.gov and search you do not want to be publicly comments on this proposed
for Docket ID NRC–2015–0030. Address disclosed in your comment submission. determination. Any comments received
questions about NRC dockets to Carol The NRC posts all comment within 30 days after the date of
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![11494 Federal Register / Vol. 80, No. 41 / Tuesday, March 3, 2015 / Notices
getting-started.html. System may seek assistance by contacting the participants are requested not to include
requirements for accessing the E- NRC Meta System Help Desk through copyrighted materials in their
Submittal server are detailed in the the ‘‘Contact Us’’ link located on the submission.
NRC’s ‘‘Guidance for Electronic NRC’s public Web site at http:// Petitions for leave to intervene must
Submission,’’ which is available on the www.nrc.gov/site-help/e- be filed no later than 60 days from the
agency’s public Web site at http:// submittals.html, by email to date of publication of this notice.
www.nrc.gov/site-help/e- MSHD.Resource@nrc.gov, or by a toll- Requests for hearing, petitions for leave
submittals.html. Participants may free call at 1–866–672–7640. The NRC to intervene, and motions for leave to
attempt to use other software not listed Meta System Help Desk is available file new or amended contentions that
on the Web site, but should note that the between 8 a.m. and 8 p.m., Eastern are filed after the 60-day deadline will
NRC’s E-Filing system does not support Time, Monday through Friday, not be entertained absent a
unlisted software, and the NRC Meta excluding government holidays. determination by the presiding officer
System Help Desk will not be able to Participants who believe that they that the filing demonstrates good cause
offer assistance in using unlisted have a good cause for not submitting by satisfying the three factors in 10 CFR
software. documents electronically must file an 2.309(c)(1)(i)–(iii).
If a participant is electronically exemption request, in accordance with For further details with respect to this
submitting a document to the NRC in 10 CFR 2.302(g), with their initial paper amendment action, see the application
accordance with the E-Filing rule, the filing requesting authorization to for amendment which is available for
participant must file the document continue to submit documents in paper public inspection at the NRC’s PDR,
using the NRC’s online, Web-based format. Such filings must be submitted located at One White Flint North, Room
submission form. In order to serve by: (1) First class mail addressed to the O1–F21, 11555 Rockville Pike (first
documents through the Electronic Office of the Secretary of the floor), Rockville, Maryland 20852.
Information Exchange System, users Commission, U.S. Nuclear Regulatory Publicly available documents created or
will be required to install a Web Commission, Washington, DC 20555– received at the NRC are accessible
browser plug-in from the NRC’s Web 0001, Attention: Rulemaking and electronically through ADAMS in the
site. Further information on the Web- Adjudications Staff; or (2) courier, NRC Library at http://www.nrc.gov/
based submission form, including the express mail, or expedited delivery reading-rm/adams.html. If you do not
installation of the Web browser plug-in, service to the Office of the Secretary, have access to ADAMS or if there are
is available on the NRC’s public Web Sixteenth Floor, One White Flint North, problems in accessing the documents
site at http://www.nrc.gov/site-help/e- 11555 Rockville Pike, Rockville, located in ADAMS, contact the PDR’s
submittals.html. Maryland 20852, Attention: Rulemaking Reference staff at 1–800–397–4209, 301–
Once a participant has obtained a and Adjudications Staff. Participants 415–4737, or by email to pdr.resource@
digital ID certificate and a docket has filing a document in this manner are nrc.gov.
been created, the participant can then responsible for serving the document on
submit a request for hearing or petition all other participants. Filing is Exelon Generation Company, LLC,
for leave to intervene. Submissions considered complete by first-class mail Docket Nos. STN 50–456 and STN 50–
should be in Portable Document Format as of the time of deposit in the mail, or 457, Braidwood Station, Units 1 and 2,
(PDF) in accordance with NRC guidance by courier, express mail, or expedited Will County, Illinois; Docket Nos. STN
available on the NRC’s public Web site delivery service upon depositing the 50–454 and STN 50–455, Byron Station,
at http://www.nrc.gov/site-help/e- document with the provider of the Units 1 and 2, Ogle County, Illinois
submittals.html. A filing is considered service. A presiding officer, having Date of amendment request: October
complete at the time the documents are granted an exemption request from 16, 2014. A publicly-available version is
submitted through the NRC’s E-Filing using E-Filing, may require a participant in ADAMS under Accession No.
system. To be timely, an electronic or party to use E-Filing if the presiding ML14289A580.
filing must be submitted to the E-Filing officer subsequently determines that the Description of amendment request:
system no later than 11:59 p.m. Eastern reason for granting the exemption from This amendment request contains
Time on the due date. Upon receipt of use of E-Filing no longer exists. sensitive unclassified non-safeguards
a transmission, the E-Filing system Documents submitted in adjudicatory information (SUNSI). The proposed
time-stamps the document and sends proceedings will appear in the NRC’s amendment would allow utilization of
the submitter an email notice electronic hearing docket which is WCAP–16143–P, Revision 1, ‘‘Reactor
confirming receipt of the document. The available to the public at http:// Vessel Closure Head/Vessel Flange
E-Filing system also distributes an email ehd1.nrc.gov/ehd/, unless excluded Requirements Evaluation for Byron/
notice that provides access to the pursuant to an order of the Commission, Braidwood Units 1 and 2,’’ dated
document to the NRC’s Office of the or the presiding officer. Participants are October 2014, as an analytical method
General Counsel and any others who requested not to include personal to determine the reactor coolant system
have advised the Office of the Secretary privacy information, such as social pressure and temperature (P–T) limits.
that they wish to participate in the security numbers, home addresses, or Basis for proposed no significant
proceeding, so that the filer need not home phone numbers in their filings, hazards consideration determination:
serve the documents on those unless an NRC regulation or other law As required by 10 CFR 50.91(a), the
participants separately. Therefore, requires submission of such licensee has provided its analysis of the
applicants and other participants (or information. However, a request to issue of no significant hazards
mstockstill on DSK4VPTVN1PROD with NOTICES
their counsel or representative) must intervene will require including consideration, which is presented below
apply for and receive a digital ID information on local residence in order with NRC staff’s edits in square
certificate before a hearing request/ to demonstrate a proximity assertion of brackets:
petition to intervene is filed so that they interest in the proceeding. With respect
EGC [Exelon Generation Company, LLC]
can obtain access to the document via to copyrighted works, except for limited has evaluated the proposed change for
the E-Filing system. excerpts that serve the purpose of the Braidwood Station and Byron Station, using
A person filing electronically using adjudicatory filings and would the criteria in 10 CFR 50.92, and has
the NRC’s adjudicatory E-Filing system constitute a Fair Use application, determined that the proposed change does
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![Federal Register / Vol. 80, No. 41 / Tuesday, March 3, 2015 / Notices 11495
not involve a significant hazards out-of-service). In addition, the conclusions The derivation of the cycle specific Safety
consideration. The following information is of the updated analysis for the RPV 54-stud Limit Minimum Critical Power Ratios
provided to support a finding of no case confirmed the conclusions from WCAP– (SLMCPRs) for incorporation into the
significant hazards consideration. 16143, Revision 0. This change, Technical Specifications (TS), and their use
Criteria subsequently, has no impact on the current to determine cycle specific thermal limits,
1. Does the proposed change involve a RPV P–T limit curves. has been performed using the methodology
significant increase in the probability or Therefore, the proposed changes do not discussed in NEDE–24011–P–A, ‘‘General
consequences of an accident previously involve a significant reduction in a margin of Electric Standard Application for Reactor
evaluated? safety. Fuel,’’ Revision 20 [ADAMS Accession No.
Response: No. Based on the above, EGC concludes that ML13352A474].
These changes to the analysis do not the proposed changes do not involve a The basis of the SLMCPR calculation is to
adversely affect accident initiators or significant hazards consideration under the ensure that during normal operation and
precursors, nor alter the design assumptions standards set forth in 10 CFR 50.92(c), and, during anticipated operational transients, at
or conditions of the facility previously accordingly, a finding of ‘‘no significant least 99.9% of all fuel rods in the core do not
approved by the NRC, or the manner in hazards consideration’’ is justified. experience boiling transition if the limit is
which the plant is operated and maintained. not violated. The new SLMCPRs preserve the
The revisions to the subject WCAP [WCAP– The NRC staff has reviewed the existing margin to boiling transition.
16143[–P]] do not alter or prevent the ability licensee’s analysis and, based on this The MCPR safety limit is reevaluated for
of structures, systems, and components review, it appears that the three each reload using NRC-approved
(SSCs) from performing their intended standards of 10 CFR 50.92(c) are methodologies. The analyses for PBAPS, Unit
function to mitigate the consequences of an satisfied. Therefore, the NRC staff 2 Cycle 21, with the addition of operation in
initiating event within the assumed proposes to determine that the the MELLLA+ operating domain, have
acceptance limits. The changes also do not requested amendments involve no concluded that a two recirculation loop
affect the source term, containment isolation, MCPR safety limit of ≥1.15, based on the
significant hazards consideration.
or radiological release assumptions used in application of Global Nuclear Fuel’s NRC-
Attorney for licensee: Bradley J.
evaluating the radiological consequences of approved MCPR safety limit methodology,
an accident previously evaluated; do not Fewell, Associate General Counsel, will ensure that this acceptance criterion is
increase the types or amounts of radioactive Exelon Nuclear, 4300 Winfield Road, met. For single recirculation loop operation,
effluent that may be released offsite; and do Warrenville, Illinois 60555. a MCPR safety limit of ≥1.15 also ensures that
not significantly increase individual or NRC Branch Chief: Travis L. Tate. this acceptance criterion is met. The MCPR
cumulative occupational/public radiation operating limits are presented and controlled
Exelon Generation Company, LLC, and
exposures. in accordance with the PBAPS Unit 2 Core
Therefore, the proposed change does not PSEG Nuclear LLC, Docket No. 50–277, Operating Limits Report (COLR).
involve a significant increase in the Peach Bottom Atomic Power Station The requested TS changes do not involve
probability or consequences of an accident (PBAPS), Unit 2, York and Lancaster any additional plant modifications or
previously evaluated. Counties, Pennsylvania operational changes that could affect system
2. Does the proposed change create the Date of application for amendment: reliability or performance or that could affect
possibility of a new or different kind of the probability of operator error beyond those
accident from any accident previously
December 5, 2014. A publicly-available associated with the MELLLA+ LAR [ADAMS
evaluated? version is in ADAMS under Accession Accession No. ML14247A503]. The requested
Response: No. No. ML14342A229. changes do not affect any postulated accident
The use of WCAP–16143[–P], Revision 1, Description of amendment request: precursors, do not affect any accident
for generation of [Reactor Pressure Vessel] This amendment request contains mitigating systems, and do not introduce any
RPV P–T limits, will continue to ensure that sensitive unclassified non-safeguards new accident initiation mechanisms.
RPV integrity is maintained under all information (SUNSI). The proposed Therefore, the proposed TS changes do not
conditions. The revisions contained in amendment would revise the Technical involve a significant increase in the
WCAP–16143[–P], Revision 1, and the Specifications (TSs) related to the Safety probability or consequences of an accident
changes proposed to TS [Technical Limit Minimum Critical Power Ratios previously evaluated.
Specifications] Table 1.1–1 do not change the 2. Does the proposed amendment create
conclusions of WCAP–16143[–P], Revision 0,
(SLMCPRs). The proposed changes the possibility of a new or different kind of
previously approved by the NRC; nor do they result from a cycle-specific analysis accident from any accident previously
change the way the RPV is analyzed or performed to support the operation of evaluated?
performs its safety function. Subsequently, PBAPS, Unit 2, in the upcoming Cycle Response: No.
these changes do not result in the creation of 21. The re-analysis was performed to The SLMCPR is a TS numerical value,
any new accident initiators or precursors; do accommodate operation in the calculated to ensure that during normal
not result in changes to any existing accident Maximum Extended Load Line Limit operation and during anticipated operational
scenarios; and do not introduce any Analysis Plus (MELLLA+) operating transients, at least 99.9% of all fuel rods in
operational changes or mechanisms that domain based on a separate license the core do not experience boiling transition
would create the possibility of a new or if the limit is not violated. The new
different kind of accident.
amendment request (LAR) dated SLMCPRs are calculated using NRC-
Based on the above discussion, the September 4, 2014 (ADAMS Accession approved methodology discussed in NEDE–
proposed changes do not create the No. ML14247A503). 24011–P–A, ‘‘General Electric Standard
possibility of a new or different kind of Basis for proposed no significant Application for Reactor Fuel,’’ Revision 20
accident from any previously evaluated. hazards consideration determination: [ADAMS Accession No. ML13352A474]. The
3. Does the proposed change involve a As required by 10 CFR 50.91(a), the proposed changes do not involve any new
significant reduction in a margin of safety? licensee has provided its analysis of the modes of operation, any changes to setpoints,
Response: No. issue of no significant hazards or any plant modifications beyond those
The proposed changes do not change any associated with the MELLLA+ LAR [ADAMS
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consideration, which is presented below
safety limits or reduce the margin of safety Accession No. ML14247A503]. The proposed
with NRC staff’s edits in square
to any safety limits. The stress analysis and revised MCPR safety limits have been shown
fracture mechanics evaluation, documented brackets: to be acceptable for Cycle 21 operation with
in the revision to WCAP–16143[–P], 1. Does the proposed amendment involve the MELLLA+ operating domain. The core
determined that for the RPV boltup a significant increase in the probability or operating limits will continue to be
condition, the RPV 54-stud case (i.e., all RPV consequences of an accident previously developed using NRC-approved methods.
head studs in-service) was more limiting than evaluated? The proposed MCPR safety limits or methods
the RPV 53-stud case (i.e., one RPV head stud Response: No. for establishing the core operating limits do
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![11496 Federal Register / Vol. 80, No. 41 / Tuesday, March 3, 2015 / Notices
not result in the creation of any new 4.2, ‘‘Fuel System Design,’’ Appendix A, review, it appears that the three
precursors to an accident. ‘‘Evaluation of Fuel Assembly Structural standards of 10 CFR 50.92(c) are
Therefore, this proposed change does not Response to Externally Applied Forces,’’ satisfied. Therefore, the NRC staff
create the possibility of a new or different Revision 3, March 2007 (ADAMS proposes to determine that the
kind of accident from any previously
evaluated.
Accession No. ML070740002). Further, amendment requests involve no
3. Does the proposed amendment involve the licensee requests approval to use the significant hazards consideration.
a significant reduction in a margin of safety? fuel assembly structural analysis results Attorney for licensee: Jennifer Post,
Response: No. to satisfy, in part, the emergency core Esq., Pacific Gas and Electric Company,
There is no significant reduction in the cooling system performance criterion, P.O. Box 7442, San Francisco, California
margin of safety previously approved by the 10 CFR 50.46(b)(4), ‘‘Coolable 94120.
NRC as a result of the proposed change to the geometry.’’ Acting NRC Branch Chief: Eric R.
SLMCPRs. The new SLMCPRs are calculated Basis for proposed no significant Oesterle.
using methodology discussed in NEDE– hazards consideration determination:
24011–P–A, ‘‘General Electric Standard Southern Nuclear Operating Company,
As required by 10 CFR 50.91(a), the
Application for Reactor Fuel,’’ Revision 20 Inc. (SNC), Docket Nos. 50–424 and 50–
[ADAMS Accession No. ML13352A474]. The licensee has provided its analysis of the
425, Vogtle Electric Generating Plant
SLMCPRs ensure that during normal issue of no significant hazards
(VEGP), Units 1 and 2, Burke County,
operation and during anticipated operational consideration, which is presented below
Georgia; Docket Nos. 50–348 and 50–
transients, at least 99.9% of all fuel rods in with NRC staff’s edits in square
364, Joseph M. Farley Nuclear Plant
the core do not experience boiling transition brackets:
if the limits are not violated, thereby (FNP), Units 1 and 2, Houston County,
1. Does the proposed change involve a Alabama; Docket Nos. 50–321 and 50–
preserving the fuel cladding integrity. significant increase in the probability or
Therefore, the proposed TS changes do not 366, Edwin I. Hatch Nuclear Plant
consequences of an accident previously
involve a significant reduction in the margin (HNP), Units 1 and 2, City of Dalton,
evaluated?
of safety previously approved by the NRC. Response: No. Georgia
The NRC staff has reviewed the The proposed change requests approval to Date of amendment request:
licensee’s analysis and, based on this perform the fuel assembly structural analyses December 30, 2014. A publicly-available
review, and with the changes noted based on a pipe break that considers the version is in ADAMS under Accession
above in square brackets, it appears that application of Leak-Before-Break (LBB). No. ML14365A352.
the three standards of 10 CFR 50.92(c) Performing the fuel assembly structural
analyses based on a pipe break that considers
Description of amendment request:
are satisfied. Therefore, the NRC staff This amendment request contains
the application of LBB will not impact any
proposes to determine that the accident previously evaluated. sensitive unclassified non-safeguards
amendment request involves no No physical changes are being made to the information (SUNSI). The amendments
significant hazards consideration. plant as a result of this change. DCPP will would revise the Cyber Security Plan
Attorney for Licensee: J. Bradley continue to satisfy the criteria of 10 CFR (CSP) implementation schedule.
Fewell, Esquire, Vice President and 50.46(b) with this change. Basis for proposed no significant
Deputy General Counsel, Exelon Therefore, the proposed change does not hazards consideration determination:
Generation Company, LLC, 200 Exelon involve a significant increase in the As required by 10 CFR 50.91(a), the
Way, Kennett Square, Pennsylvania probability or consequences of an accident
licensee has provided its analysis of the
19348. previously evaluated.
2. Does the proposed change create the issue of no significant hazards
NRC Branch Chief: Meena K. Khanna. consideration, which is presented below
possibility of a new or different accident
Pacific Gas and Electric Company, from any accident previously evaluated? with NRC staff’s edits in square
Docket Nos. 50–275 and 50–323, Diablo Response: No. brackets:
Canyon Nuclear Power Plant (DCPP), The proposed change does not involve any 1. Does the proposed amendment involve
Units 1 and 2, San Luis Obispo County, physical changes to the plant. The best- a significant increase in the probability or
estimate large break loss-of-coolant [accident] consequences of an accident previously
California
(BELOCA) analyses are not impacted by this evaluated?
Date of amendment request: October change. Response: No.
2, 2014. A publicly-available version is Therefore, the proposed change does not The proposed license amendment request
in ADAMS under Accession No. create the possibility of a new or different is for a change to the Milestone 8
ML14275A444. accident from any accident previously implementation schedule for the SNC CSP, as
Description of amendment request: evaluated. cited by the existing FOLs [facility operating
3. Does the proposed change involve a licenses] applicable to FNP, HNP and VEGP
This amendment request contains
significant reduction in a margin of safety? Units 1 and 2.
sensitive unclassified non-safeguards Response: No.
information (SUNSI). The proposed The CSP is designed to provide high
The revised fuel structural integrity assurance that the systems within the scope
amendments request approval to analysis incorporates the reduced LBB loads of § 73.54 are protected from cyber attacks.
perform the fuel assembly structural and therefore will not decrease the margin of The CSP itself does not require any plant
analyses based on a pipe break that safety to the 10 CFR 50.46 limits. The modifications, but the plan describes
considers the application of leak-before- BELOCA analyses are not impacted by this appropriate configuration management
break, which allows the exclusion of the change, and the criteria of 10 CFR 50.46(b) requirements to assure plant modifications
dynamic effects of certain pipe breaks, continue to be met. The proposed change involving digital computer systems are
does not involve any changes to the fuel, reviewed to provide adequate protection
consistent with 10 CFR part 50,
reactor vessel, or containment fission product against cyber attacks, up to and including the
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Appendix A, General Design Criterion 4, barriers. Therefore there will be no impact on
‘‘Environmental and design effects design basis threat as defined in § 73.54.
the accident analyses that are contained in The proposed change is a schedule change
design bases,’’ for DCPP, Units 1 and 2. the Updated Final Safety Analysis Report. for CSP implementation only; it will modify
The fuel assembly structural analyses Therefore, the proposed change does not the existing FOL for each SNC-operated
are performed to satisfy NUREG–0800, involve a significant reduction in a margin of facility to add citation of the license
‘‘Standard Review Plan for the Review safety. amendment establishing the new Milestone 8
of Safety Analysis Reports for Nuclear The NRC staff has reviewed the completion date. This change is
Power Plants: LWR Edition,’’ Section licensee’s analysis and, based on this administrative in nature and does not alter
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![11498 Federal Register / Vol. 80, No. 41 / Tuesday, March 3, 2015 / Notices
granted access to that information. has been appointed, the Chief I. The Commission expects that the
However, if more than 25 days remain Administrative Judge, or if he or she is NRC staff and presiding officers (and
between the date the petitioner is unavailable, another administrative any other reviewing officers) will
granted access to the information and judge, or an administrative law judge consider and resolve requests for access
the deadline for filing all other with jurisdiction pursuant to 10 CFR to SUNSI, and motions for protective
contentions (as established in the notice 2.318(a); or (c) officer if that officer has orders, in a timely fashion in order to
of hearing or opportunity for hearing), been designated to rule on information minimize any unnecessary delays in
the petitioner may file its SUNSI access issues. identifying those petitioners who have
contentions by that later deadline. This H. Review of Grants of Access. A standing and who have propounded
provision does not extend the time for party other than the requester may contentions meeting the specificity and
filing a request for a hearing and challenge an NRC staff determination basis requirements in 10 CFR part 2.
petition to intervene, which must granting access to SUNSI whose release Attachment 1 to this Order summarizes
comply with the requirements of 10 CFR would harm that party’s interest the general target schedule for
2.309. independent of the proceeding. Such a processing and resolving requests under
G. Review of Denials of Access. challenge must be filed with the Chief these procedures.
(1) If the request for access to SUNSI Administrative Judge within 5 days of
It is so ordered.
is denied by the NRC staff after a the notification by the NRC staff of its
determination on standing and need for grant of access. Dated at Rockville, Maryland, this 18th day
access, the NRC staff shall immediately If challenges to the NRC staff of February, 2015.
notify the requestor in writing, briefly determinations are filed, these For the Nuclear Regulatory Commission.
stating the reason or reasons for the procedures give way to the normal Annette L. Vietti-Cook,
denial. process for litigating disputes Secretary of the Commission.
(2) The requester may challenge the concerning access to information. The
NRC staff’s adverse determination by availability of interlocutory review by Attachment 1—General Target
filing a challenge within 5 days of the Commission of orders ruling on Schedule for Processing and Resolving
receipt of that determination with: (a) such NRC staff determinations (whether Requests for Access to Sensitive
the presiding officer designated in this granting or denying access) is governed Unclassified Non-Safeguards
proceeding; (b) if no presiding officer by 10 CFR 2.311.3 Information in This Proceeding
Day Event/activity
0 ........................ Publication of Federal Register notice of hearing and opportunity to petition for leave to intervene, including order with in-
structions for access requests.
10 ...................... Deadline for submitting requests for access to Sensitive Unclassified Non-Safeguards Information (SUNSI) with information:
supporting the standing of a potential party identified by name and address; describing the need for the information in order
for the potential party to participate meaningfully in an adjudicatory proceeding.
60 ...................... Deadline for submitting petition for intervention containing: (i) Demonstration of standing; and (ii) all contentions whose formu-
lation does not require access to SUNSI (+25 Answers to petition for intervention; +7 petitioner/requestor reply).
20 ...................... U.S. Nuclear Regulatory Commission (NRC) staff informs the requester of the staff’s determination whether the request for
access provides a reasonable basis to believe standing can be established and shows need for SUNSI. (NRC staff also in-
forms any party to the proceeding whose interest independent of the proceeding would be harmed by the release of the in-
formation.) If NRC staff makes the finding of need for SUNSI and likelihood of standing, NRC staff begins document proc-
essing (preparation of redactions or review of redacted documents).
25 ...................... If NRC staff finds no ‘‘need’’ or no likelihood of standing, the deadline for petitioner/requester to file a motion seeking a ruling
to reverse the NRC staff’s denial of access; NRC staff files copy of access determination with the presiding officer (or Chief
Administrative Judge or other designated officer, as appropriate). If NRC staff finds ‘‘need’’ for SUNSI, the deadline for any
party to the proceeding whose interest independent of the proceeding would be harmed by the release of the information to
file a motion seeking a ruling to reverse the NRC staff’s grant of access.
30 ...................... Deadline for NRC staff reply to motions to reverse NRC staff determination(s).
40 ...................... (Receipt +30) If NRC staff finds standing and need for SUNSI, deadline for NRC staff to complete information processing and
file motion for Protective Order and draft Non-Disclosure Affidavit. Deadline for applicant/licensee to file Non-Disclosure
Agreement for SUNSI.
A ....................... If access granted: Issuance of presiding officer or other designated officer decision on motion for protective order for access
to sensitive information (including schedule for providing access and submission of contentions) or decision reversing a
final adverse determination by the NRC staff.
A + 3 ................. Deadline for filing executed Non-Disclosure Affidavits. Access provided to SUNSI consistent with decision issuing the protec-
tive order.
A + 28 ............... Deadline for submission of contentions whose development depends upon access to SUNSI. However, if more than 25 days
remain between the petitioner’s receipt of (or access to) the information and the deadline for filing all other contentions (as
established in the notice of hearing or opportunity for hearing), the petitioner may file its SUNSI contentions by that later
deadline.
A + 53 ............... (Contention receipt +25) Answers to contentions whose development depends upon access to SUNSI.
A + 60 ............... (Answer receipt +7) Petitioner/Intervenor reply to answers.
>A + 60 ............. Decision on contention admission.
[FR Doc. 2015–03917 Filed 3–2–15; 8:45 am]
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BILLING CODE 7590–01–P
3 Requesters should note that the filing staff determinations (because they must be served applicable), but not to the initial SUNSI request
requirements of the NRC’s E-Filing Rule (72 FR on a presiding officer or the Commission, as submitted to the NRC staff under these procedures.
49139; August 28, 2007) apply to appeals of NRC
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Document Created: 2015-12-18 11:55:40
Document Modified: 2015-12-18 11:55:40
| 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 | License amendment request; opportunity to comment, request a hearing, and petition for leave to intervene; order. | |
| Dates | Comments must be filed by April 2, 2015. A request for a hearing must be filed by May 4, 2015. Any potential party as defined in Sec. 2.4 of Title 10 of the Code of Federal Regulations (10 CFR), who believes access to SUNSI is necessary to respond to this notice must request document access by March 13, 2015. | |
| Contact | Shirley Rohrer, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; telephone: 301-415-5411; email: [email protected] | |
| FR Citation | 80 FR 11492 |
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