82 FR 57478 - 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 82, Issue 232 (December 5, 2017)
Federal Register Volume 82, Issue 232 (December 5, 2017)
| Page Range | 57478-57484 | |
| FR Document | 2017-25390 |
[Federal Register Volume 82, Number 232 (Tuesday, December 5, 2017)] [Notices] [Pages 57478-57484] From the Federal Register Online [www.thefederalregister.org] [FR Doc No: 2017-25390] ----------------------------------------------------------------------- NUCLEAR REGULATORY COMMISSION [NRC-2017-0219] 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; notice of opportunity to comment, request a hearing, and petition for leave to intervene; order imposing procedures. ----------------------------------------------------------------------- SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) received and is considering approval of two amendment requests. The amendment requests are for Shearon Harris Nuclear Power Plant, Unit 1; and LaSalle County Station, Units 1 and 2. The NRC proposes to determine that each amendment request involves no significant hazards consideration. Because each amendment request contains sensitive unclassified non- safeguards information (SUNSI), an order imposes procedures to obtain access to SUNSI for contention preparation. DATES: Comments must be filed by January 4, 2018. A request for a hearing must be filed by February 5, 2018. 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 December 15, 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-2017-0219. Address questions about NRC dockets to Carol Gallagher; telephone: 301-415- 3463; email: [email protected]. For technical questions, contact the individual listed in the FOR FURTHER [[Page 57479]] INFORMATION CONTACT section of this document. Mail comments to: May Ma, Office of Administration, Mail Stop: OWFN-2-A13, 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: Lynn Ronewicz, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington DC 20555-0001; telephone: 301-415-1927, email: [email protected]. SUPPLEMENTARY INFORMATION: I. Obtaining Information and Submitting Comments A. Obtaining Information Please refer to Docket ID NRC-2017-0219, 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-2017-0219. NRC's Agencywide Documents Access and Management System (ADAMS): You may obtain publicly-available documents online in the ADAMS Public Documents collection at http://www.nrc.gov/reading-rm/adams.html. To begin the search, select ``ADAMS Public Documents'' and then select ``Begin Web-based ADAMS Search.'' For problems with ADAMS, please contact the NRC's Public Document Room (PDR) reference staff at 1-800-397-4209, 301-415-4737, or by email to [email protected]. The ADAMS accession number for each document referenced (if it is available in ADAMS) is provided the first time that it is mentioned in this document. NRC's PDR: You may examine and purchase copies of public documents at the NRC's PDR, Room O1-F21, One White Flint North, 11555 Rockville Pike, Rockville, Maryland 20852. B. Submitting Comments Please include Docket ID NRC-2017-0219, 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 enters 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 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 a notice of issuance in the Federal Register. 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 [[Page 57480]] the Act to be made a party to the proceeding; (3) the nature and extent of the petitioner's property, financial, or other interest in the proceeding; and (4) the possible effect of any decision or order which may be entered in the proceeding on the petitioner's interest. In accordance with 10 CFR 2.309(f), the petition must also set forth the specific contentions which the petitioner seeks to have litigated in the proceeding. Each contention must consist of a specific statement of the issue of law or fact to be raised or controverted. In addition, the petitioner must provide a brief explanation of the bases for the contention and a concise statement of the alleged facts or expert opinion which support the contention and on which the petitioner intends to rely in proving the contention at the hearing. The petitioner must also provide references to the specific sources and documents on which the petitioner intends to rely to support its position on the issue. The petition must include sufficient information to show that a genuine dispute exists with the applicant or licensee on a material issue of law or fact. Contentions must be limited to matters within the scope of the proceeding. The contention must be one which, if proven, would entitle the petitioner to relief. A petitioner who fails to satisfy the requirements at 10 CFR 2.309(f) with respect to at least one contention will not be permitted to participate as a party. Those permitted to intervene become parties to the proceeding, subject to any limitations in the order granting leave to intervene. Parties have the opportunity to participate fully in the conduct of the hearing with respect to resolution of that party's admitted contentions, including the opportunity to present evidence, consistent with the NRC's regulations, policies, and procedures. Petitions must be filed no later than 60 days from the date of publication of this notice. Petitions and motions for leave to file new or amended contentions that are filed after the deadline will not be entertained absent a determination by the presiding officer that the filing demonstrates good cause by satisfying the three factors in 10 CFR 2.309(c)(1)(i) through (iii). The petition must be filed in accordance with the filing instructions in the ``Electronic Submissions (E-Filing)'' section of this document. If a hearing is requested, and the Commission has not made a final determination on the issue of no significant hazards consideration, the Commission will make a final determination on the issue of no significant hazards consideration. The final determination will serve to establish when the hearing is held. If the final determination is that the amendment request involves no significant hazards consideration, the Commission may issue the amendment and make it immediately effective, notwithstanding the request for a hearing. Any hearing would take place after issuance of the amendment. If the final determination is that the amendment request involves a significant hazards consideration, then any hearing held would take place before the issuance of the amendment unless the Commission finds an imminent danger to the health or safety of the public, in which case it will issue an appropriate order or rule under 10 CFR part 2. A State, local governmental body, Federally-recognized Indian Tribe, or agency thereof, may submit a petition to the Commission to participate as a party under 10 CFR 2.309(h)(1). The petition should state the nature and extent of the petitioner's interest in the proceeding. The petition should be submitted to the Commission no later than 60 days from the date of publication of this notice. The petition must be filed in accordance with the filing instructions in the ``Electronic Submissions (E-Filing)'' section of this document, and should meet the requirements for petitions set forth in this section, except that under 10 CFR 2.309(h)(2) a State, local governmental body, or Federally-recognized Indian Tribe, or agency thereof does not need to address the standing requirements in 10 CFR 2.309(d) if the facility is located within its boundaries. Alternatively, a State, local governmental body, Federally-recognized Indian Tribe, or agency thereof may participate as a non-party under 10 CFR 2.315(c). If a hearing is granted, any person who is not a party to the proceeding and is not affiliated with or represented by a party may, at the discretion of the presiding officer, be permitted to make a limited appearance pursuant to the provisions of 10 CFR 2.315(a). A person making a limited appearance may make an oral or written statement of his or her position on the issues but may not otherwise participate in the proceeding. A limited appearance may be made at any session of the hearing or at any prehearing conference, subject to the limits and conditions as may be imposed by the presiding officer. Details regarding the opportunity to make a limited appearance will be provided by the presiding officer if such sessions are scheduled. B. Electronic Submissions (E-Filing) All documents filed in NRC adjudicatory proceedings, including a request for hearing and petition for leave to intervene (petition), any motion or other document filed in the proceeding prior to the submission of a request for hearing or petition to intervene, and documents filed by interested governmental entities that request to participate under 10 CFR 2.315(c), must be filed in accordance with the NRC's E-Filing rule (72 FR 49139; August 28, 2007, as amended at 77 FR 46562; August 3, 2012). The E-Filing process requires participants to submit and serve all adjudicatory documents over the internet, or in some cases to mail copies on electronic storage media. Detailed guidance on making electronic submissions may be found in the Guidance for Electronic Submissions to the NRC and on the NRC 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 [[Page 57481]] the document is submitted through the NRC's E-Filing system. To be timely, an electronic filing must be submitted to the E-Filing system no later than 11:59 p.m. Eastern Time on the due date. Upon receipt of a transmission, the E-Filing system time-stamps the document and sends the submitter an email notice confirming receipt of the document. The E-Filing system also distributes an email notice that provides access to the document to the NRC's Office of the General Counsel and any others who have advised the Office of the Secretary that they wish to participate in the proceeding, so that the filer need not serve the document on those participants separately. Therefore, applicants and other participants (or their counsel or representative) must apply for and receive a digital ID certificate before adjudicatory documents are filed so that they can obtain access to the documents via the E-Filing system. A person filing electronically using the NRC's adjudicatory E- Filing system may seek assistance by contacting the NRC's Electronic Filing Help Desk through the ``Contact Us'' link located on the NRC's public Web site at http://www.nrc.gov/site-help/e-submittals.html, by email to [email protected], or by a toll-free call at 1-866-672- 7640. The NRC Electronic Filing Help Desk is available between 9 a.m. and 6 p.m., Eastern Time, Monday through Friday, excluding government holidays. Participants who believe that they have a good cause for not submitting documents electronically must file an exemption request, in accordance with 10 CFR 2.302(g), with their initial paper filing stating why there is good cause for not filing electronically and requesting authorization to continue to submit documents in paper format. Such filings must be submitted by: (1) First class mail addressed to the Office of the Secretary of the Commission, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, Attention: Rulemaking and Adjudications Staff; or (2) courier, express mail, or expedited delivery service to the Office of the Secretary, 11555 Rockville Pike, Rockville, Maryland, 20852, Attention: Rulemaking and Adjudications Staff. Participants filing adjudicatory documents in this manner are responsible for serving the document on all other participants. Filing is considered complete by first-class mail as of the time of deposit in the mail, or by courier, express mail, or expedited delivery service upon depositing the document with the provider of the service. A presiding officer, having granted an exemption request from using E-Filing, may require a participant or party to use E-Filing if the presiding officer subsequently determines that the reason for granting the exemption from use of E-Filing no longer exists. Documents submitted in adjudicatory proceedings will appear in the NRC's electronic hearing docket which is available to the public at https://adams.nrc.gov/ehd, unless excluded pursuant to an order of the Commission or the presiding officer. If you do not have an NRC-issued digital ID certificate as described above, click cancel when the link requests certificates and you will be automatically directed to the NRC's electronic hearing dockets where you will be able to access any publicly available documents in a particular hearing docket. Participants are requested not to include personal privacy information, such as social security numbers, home addresses, or personal phone numbers in their filings, unless an NRC regulation or other law requires submission of such information. For example, in some instances, individuals provide home addresses in order to demonstrate proximity to a facility or site. With respect to copyrighted works, except for limited excerpts that serve the purpose of the adjudicatory filings and would constitute a Fair Use application, participants are requested not to include copyrighted materials in their submission. Duke Energy Progress, LLC, Docket No. 50-400, Shearon Harris Nuclear Power Plant, Unit 1 (HNP), Wake and Chatham Counties, North Carolina Date of amendment request: June 28, 2017, as supplemented by letter dated September 14, 2017. Publicly-available versions are in ADAMS under Accession Nos. ML17193B165 and ML17257A245, respectively. Description of amendment request: This amendment request contains sensitive unclassified non-safeguards information (SUNSI). The amendment would modify the Technical Specifications (TSs) for fuel storage criticality to account for the use of neutron absorbing spent fuel pool (SFP) rack inserts and soluble boron for the purpose of criticality control in the boiling water reactor (BWR) storage racks that currently credit Boraflex. 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? The proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated. As this amendment request pertains only to the spent fuel pool, only those accidents that are related to movement and storage of fuel assemblies in the SFP could potentially be affected by the proposed change. The proposed change modifies HNP TS 5.6.1.3 to reflect the respective design features of the two BWR rack types utilized in these pools, including adjusted requirements for the Boraflex racks that account for use of neutron absorbing inserts. The change is necessary to ensure that, with continued Boraflex degradation over time, the effective neutron multiplication factor, k eff , is less than or equal to 0.95 if the spent fuel pool is flooded with borated water, and that it is less than 1.0 if flooded with unborated water, as required by 10 CFR 50.68(b)(4). The installation of DREAM [Device for Reactivity Mitigation] rack inserts and credit for soluble boron does not result in a significant increase in the probability of an accident previously analyzed because there are no changes in the manner in which spent fuel is handled, moved, or stored in the rack cells. The probability that a fuel assembly would be dropped or misloaded is unchanged by the installation of the DREAM rack inserts and use of additional administrative controls on BWR fuel storage in these racks. These events involve failures of administrative controls, human performance, and equipment failures that are unaffected by the presence or absence of Boraflex and the rack inserts. The probability of a SFP dilution event is also unchanged. The soluble boron is already present in SFPs A and B and no changes are proposed regarding the manner in which soluble boron is managed. The current controls in place remain applicable. The installation of the DREAM rack inserts and crediting of soluble boron does not result in a significant increase in the consequences of an accident previously analyzed because there is no change in the fuel assemblies that provide the source terms used in calculating the radiological consequences of a fuel handling accident. In addition, consistent with the current design, only one fuel assembly will be moved at a time. Thus, the consequences of dropping a fuel assembly onto any other fuel assembly or other structure remain bounded by the previously analyzed fuel handling accident. The proposed change does not affect the effectiveness of the other engineered design features, such as filtration systems, that limit the offsite dose consequences of a fuel handling 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 change create the possibility of a new or different kind of accident from any previously evaluated? The proposed change does not create the possibility of a new or different kind of [[Page 57482]] accident from any accident previously evaluated. The rack inserts are passive devices that, when inside a spent fuel storage rack cell, perform the same function as the previously licensed Boraflex neutron absorber panels in that cell. These devices do not add any limiting structural loads or affect the removal of decay heat from the assemblies. No change in total heat load in the spent fuel pool is being made. The inserts will maintain their design function over the life of the spent fuel pool. The existing fuel handling accident, which assumes the drop of a fuel assembly, bounds the drop of a rack insert and/or rack insert installation tool. This proposed change does not create the possibility of misloading an assembly into a spent fuel storage rack cell. Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated. 3. Does the proposed change involve a significant reduction in a margin of safety? The proposed change does not involve a significant reduction in a margin of safety. The DREAM rack inserts are being installed to restore the spent fuel pool criticality margin, compensating for the degraded Boraflex neutron absorber. The DREAM rack inserts, once approved for crediting, will replace the existing Boraflex as the credited neutron absorber for controlling spent fuel pool reactivity, even though the Boraflex absorber will remain in place. The proposed HNP TS 5.6.1.3.a.1 requires that the BWR spent fuel storage racks with Metamic rack inserts maintain the effective neutron multiplication factor, keff , less than or equal to 0.95 when flooded with water borated to 1000 ppm [parts per million]. This includes an allowance for uncertainties in such that the TS limit for boron concentration in the SFPs, HNP TS 3.7.14, shall be greater than or equal to 2000 ppm at all times for pools that contain nuclear fuel. Therefore, for criticality, the required safety margin is 5% including a conservative margin to account for engineering and manufacturing uncertainties. The proposed change provides a method to ensure that keff continues to be less than or equal to 0.95, thus preserving the required safety margin of 5%. The criticality analyses demonstrate that the required margin to 5%, including a conservative margin to account for engineering and manufacturing uncertainties, is maintained. In addition, the radiological consequences of a dropped fuel assembly onto a spent fuel storage rack cell containing a fuel assembly with a rack insert is bounded by the radiological consequences of a dropped fuel assembly without a rack insert. The proposed change also maintains the capacity of the HNP spent fuel pools. 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: Kathryn B. Nolan, Deputy General Counsel, Duke Energy Corporation, 550 South Tryon St., M/C DEC454, Charlotte, NC 28202. NRC Branch Chief: Undine Shoop. Exelon Generation Company, LLC, Docket Nos. 50-373 and 50-374, LaSalle County Station (LSCS), Units 1 and 2, LaSalle County, Illinois Date of amendment request: August 29, 2017. A publicly-available version is in ADAMS under Accession No. ML17241A278. Description of amendment request: This amendment request contains sensitive unclassified non-safeguards information (SUNSI). The amendments would revise Technical Specification (TS) 2.1.1, ``Reactor Core SLs [Safety Limits].'' Specifically, this change would incorporate revised LSCS, Units 1 and 2, safety limit for minimum critical power ratio (MCPR) for two circulation loop MCPR and single circulation loop MCPR values for Unit 1 and Unit 2, based on the results of the cycle- specific analyses performed by Global Nuclear Fuel for LSCS, Unit 1, Cycle 17, and LSCS, Unit 2, Cycle 17. 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 Safety Limit Minimum Critical Power Ratio (SLMCPR) is defined as the lowest ratio of that power which results in the onset of transition boiling to the actual bundle power at the same location. The Global Nuclear Fuel (GNF) methodology is applied for each reload to assure that more than 99.9% of the fuel rods in the core are expected to avoid boiling transition for the most severe abnormal operational transient described in LaSalle UFSAR [Updated Final Safety Analysis Report] Chapter 15.0. The new SLMCPRs preserve the existing margin to transition boiling. The SLMCPR satisfies the requirements of General Design Criterion 10 of Appendix A to 10 CFR 50 regarding acceptable fuel design limits. The MCPR safety limit is re-evaluated for each reload using NRC- approved methodologies. The analyses for LSCS, Unit 1, Cycle 17, have concluded that a two recirculation loop SLMCPR of >= 1.11, based on the application of GNF's NRC-approved SLMCPR methodology, will ensure that this acceptance criterion is met. For single recirculation loop operation, a SLMCPR of >= 1.13 also ensures that this acceptance criterion is met. The MCPR operating limits are presented and controlled in accordance with the LSCS, Unit 1 Core Operating Limits Report (COLR). Similarly, the analyses for LSCS, Unit 2, Cycle 17, have concluded that a two recirculation loop SLMCPR of >= 1.12, based on the application of GNF's NRC-approved SLMCPR methodology, will ensure that this acceptance criterion is met. For single recirculation loop operation, a SLMCPR of >= 1.15 also ensures that this acceptance criterion is met. The MCPR operating limits are presented and controlled in accordance with the LSCS, Unit 2 Core Operating Limits Report (COLR). The requested TS changes do not involve any plant modifications or operational changes that could affect system reliability or performance or that could affect the probability of operator error. 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 any 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 SLMCPR is a TS numerical value, calculated to ensure that during normal operating and during abnormal operational transients, at least 99.9% of all fuel rods in the core do not experience transition boiling 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 22. The proposed changes do not involve any new modes of operation, any changes to setpoints, or any plant modifications. The proposed revised MCPR safety limits have been shown to be acceptable for Unit 1 Cycle 17 and Unit 2 Cycle 17 operation and will be confirmed in the future on a cycle-specific basis. 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 not result in the creation of any new precursors to an accident. 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. There is no 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 22. The SLMCPRs ensure that during normal operation and during abnormal operational transients, at least 99.9% of all fuel rods in the core do not experience transition boiling if the limit is not violated, thereby preserving the fuel cladding integrity. The proposed TS changes do not involve a significant [[Page 57483]] reduction in the margin of safety previously approved by the NRC. 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 requested amendments involve no significant hazards consideration. Attorney for licensee: Tamra Domeyer, Associate General Counsel, Exelon Generation Company, 4300 Winfield Road, Warrenville, IL 60555. NRC Branch Chief: David J. Wrona. Order Imposing Procedures for Access to Sensitive Unclassified Non- Safeguards Information for Contention Preparation Duke Energy Progress, LLC, Docket No. 50-400, Shearon Harris Nuclear Power Plant, Unit 1, Wake and Chatham Counties, North Carolina Exelon Generation Company, LLC, Docket Nos. 50-373 and 50-374, LaSalle County Station, Units 1 and 2, LaSalle County, Illinois A. This Order contains instructions regarding how potential parties to this proceeding may request access to documents containing Sensitive Unclassified Non-Safeguards Information (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 access to SUNSI. 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, U.S. Nuclear Regulatory Commission, 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 receipt of (or access to) that information. 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. 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 requisite need, 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) if another officer has been designated to rule on information access issues, with that officer. (3) Further appeals of decisions under this paragraph must be made pursuant to 10 CFR 2.311. 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 within 5 days of the notification by the NRC staff of its grant of access and must be filed 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) if another officer has been designated to rule on information access issues, with that officer. 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 [[Page 57484]] 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, as amended at 77 FR 46562; August 3, 2012) 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. The attachment 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 17th day of November, 2017. 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 opportunity to request a hearing and petition for leave to intervene), 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. 2017-25390 Filed 12-4-17; 8:45 am] BILLING CODE 7590-01-P
![57478 Federal Register / Vol. 82, No. 232 / Tuesday, December 5, 2017 / Notices
Brief description of amendment: The Amendment Nos.: 301 (Unit 1), 325 Dated at Rockville, Maryland, this 27th day
amendment modified Hope Creek (Unit 2), and 285 (Unit 3). A publicly- of November 2017.
Generating Station Technical available version is in ADAMS under For the Nuclear Regulatory Commission.
Specification 6.8.4.f, ‘‘Primary Accession No. ML17277A207; Kathryn M. Brock,
Containment Leakage Rate Testing documents related to these amendments Acting Director, Division of Operating Reactor
Program,’’ to extend the Type A reactor are listed in the Safety Evaluation Licensing, Office of Nuclear Reactor
containment pressure test interval from enclosed with the amendments. Regulation.
one test in 10 years to one test in 15 Renewed Facility Operating License [FR Doc. 2017–25901 Filed 12–4–17; 8:45 am]
years, and extend the Type C test Nos. DPR–33, DPR–52, and DPR–68: BILLING CODE 7590–01–P
interval up to 75 months, with a Amendments revised the Renewed
permissible extension period of 9 Facility Operating Licenses and TSs.
months (total of 84 months) for non- Date of initial notice in Federal NUCLEAR REGULATORY
routine emergency conditions. Register: April 25, 2017 (82 FR 19106). COMMISSION
Date of issuance: November 8, 2017. The supplemental letter dated June 29, [NRC–2017–0219]
Effective date: As of the date of 2017, provided additional information
issuance and shall be implemented that clarified the application, did not Applications and Amendments to
within 60 days of issuance. expand the scope of the application as Facility Operating Licenses and
Amendment No.: 207. A publicly- originally noticed, and did not change Combined Licenses Involving
available version is in ADAMS under the staff’s original proposed no Proposed No Significant Hazards
Accession No. ML17291A209; significant hazards consideration Considerations and Containing
documents related to this amendment determination as published in the Sensitive Unclassified Non-Safeguards
are listed in the Safety Evaluation Federal Register. Information and Order Imposing
enclosed with the amendment. The Commission’s related evaluation Procedures for Access to Sensitive
Renewed Facility Operating License of the amendment is contained in a Unclassified Non-Safeguards
No. NPF–57: Amendment revised the Safety Evaluation dated November 8, Information
Renewed Facility Operating License and 2017.
Technical Specifications. No significant hazards consideration AGENCY: Nuclear Regulatory
Date of initial notice in Federal Commission.
comments received: No.
Register: December 20, 2016 (81 FR ACTION: License amendment request;
92869). The supplemental letters dated Tennessee Valley Authority, Docket No. notice of opportunity to comment,
March 27, 2017, and July 13, 2017, 50–391, Watts Bar Nuclear Plant, Unit 2, request a hearing, and petition for leave
provided additional information that Rhea County, Tennessee to intervene; order imposing
clarified the application, did not expand Date of amendment request: March procedures.
the scope of the application as originally 28, 2017.
noticed, and did not change the NRC Brief description of amendment: The SUMMARY: The U.S. Nuclear Regulatory
staff’s original proposed no significant amendment revised the completion date Commission (NRC) received and is
hazards consideration determination as for License Condition 2.C.(5) for Watts considering approval of two amendment
published in the Federal Register. Bar Nuclear Plant, Unit 2, regarding the requests. The amendment requests are
The Commission’s related evaluation for Shearon Harris Nuclear Power Plant,
completion of action to resolve the
of the amendment is contained in a Unit 1; and LaSalle County Station,
issues identified in Bulletin 2012–01,
Safety Evaluation dated November 8, Units 1 and 2. The NRC proposes to
‘‘Design Vulnerability in Electric Power
2017. determine that each amendment request
System’’ (ADAMS Accession No.
No significant hazards consideration involves no significant hazards
ML12074A115), from December 31,
comments received: No. consideration. Because each amendment
2017, to December 31, 2018, to align
Tennessee Valley Authority, Docket with the remainder of the Tennessee request contains sensitive unclassified
Nos. 50–259, 50–260, and 50–296, Valley Authority fleet and with the non-safeguards information (SUNSI), an
Browns Ferry Nuclear Plant, Units 1, 2 nuclear industry. order imposes procedures to obtain
and 3, Limestone County, Alabama Date of issuance: November 6, 2017. access to SUNSI for contention
Effective date: As of the date of preparation.
Date of amendment request: January
17, 2017, as supplemented by letter issuance and shall be implemented DATES: Comments must be filed by
dated June 29, 2017. within 15 days of issuance. January 4, 2018. A request for a hearing
Brief description of amendments: The Amendment No.: 17. A publicly- must be filed by February 5, 2018. Any
amendments change technical available version is in ADAMS under potential party as defined in § 2.4 of title
specifications (TSs) consistent with Accession No. ML17258A328; 10 of the Code of Federal Regulations
Technical Specifications Task Force documents related to this amendment is (10 CFR), who believes access to SUNSI
(TSTF) Standard Technical listed in the Safety Evaluation enclosed is necessary to respond to this notice
Specifications Change Traveler TSTF– with the amendment. must request document access by
545, Revision 3, ‘‘TS Inservice Testing Facility Operating License No. NPF– December 15, 2017.
Program Removal & Clarify SR 96: Amendment revised the Facility ADDRESSES: You may submit comments
[Surveillance Requirement] Usage Rule Operating License. by any of the following methods:
Date of initial notice in Federal • Federal Rulemaking Web site: Go to
sradovich on DSK3GMQ082PROD with NOTICES
Application to Section 5.5 Testing,’’ and
TSTF–299, Revision 0, ‘‘Administrative Register: July 5, 2017 (82 FR 31103). http://www.regulations.gov and search
Controls Program 5.5.2.b Test Interval The Commission’s related evaluation for Docket ID NRC–2017–0219. Address
and Exception.’’ of the amendment is contained in a questions about NRC dockets to Carol
Date of issuance: November 8, 2017. Safety Evaluation dated November 6, Gallagher; telephone: 301–415–3463;
Effective date: As of the date of 2017. email: Carol.Gallagher@nrc.gov. For
issuance and shall be implemented No significant hazards consideration technical questions, contact the
within 60 days of issuance. comments received: No. individual listed in the FOR FURTHER
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![Federal Register / Vol. 82, No. 232 / Tuesday, December 5, 2017 / Notices 57481
the document is submitted through the granted an exemption request from 1. Does the proposed change involve a
NRC’s E-Filing system. To be timely, an using E-Filing, may require a participant significant increase in the probability or
electronic filing must be submitted to or party to use E-Filing if the presiding consequences of an accident previously
evaluated?
the E-Filing system no later than 11:59 officer subsequently determines that the The proposed change does not involve a
p.m. Eastern Time on the due date. reason for granting the exemption from significant increase in the probability or
Upon receipt of a transmission, the E- use of E-Filing no longer exists. consequences of an accident previously
Filing system time-stamps the document Documents submitted in adjudicatory evaluated. As this amendment request
and sends the submitter an email notice proceedings will appear in the NRC’s pertains only to the spent fuel pool, only
confirming receipt of the document. The electronic hearing docket which is those accidents that are related to movement
E-Filing system also distributes an email available to the public at https:// and storage of fuel assemblies in the SFP
notice that provides access to the could potentially be affected by the proposed
adams.nrc.gov/ehd, unless excluded change. The proposed change modifies HNP
document to the NRC’s Office of the pursuant to an order of the Commission TS 5.6.1.3 to reflect the respective design
General Counsel and any others who or the presiding officer. If you do not features of the two BWR rack types utilized
have advised the Office of the Secretary have an NRC-issued digital ID certificate in these pools, including adjusted
that they wish to participate in the as described above, click cancel when requirements for the Boraflex racks that
proceeding, so that the filer need not the link requests certificates and you account for use of neutron absorbing inserts.
serve the document on those will be automatically directed to the The change is necessary to ensure that, with
participants separately. Therefore, continued Boraflex degradation over time,
NRC’s electronic hearing dockets where the effective neutron multiplication factor,
applicants and other participants (or you will be able to access any publicly keff, is less than or equal to 0.95 if the spent
their counsel or representative) must available documents in a particular fuel pool is flooded with borated water, and
apply for and receive a digital ID hearing docket. Participants are that it is less than 1.0 if flooded with
certificate before adjudicatory requested not to include personal unborated water, as required by 10 CFR
documents are filed so that they can privacy information, such as social 50.68(b)(4).
obtain access to the documents via the security numbers, home addresses, or The installation of DREAM [Device for
E-Filing system. Reactivity Mitigation] rack inserts and credit
personal phone numbers in their filings,
A person filing electronically using for soluble boron does not result in a
unless an NRC regulation or other law significant increase in the probability of an
the NRC’s adjudicatory E-Filing system requires submission of such
may seek assistance by contacting the accident previously analyzed because there
information. For example, in some are no changes in the manner in which spent
NRC’s Electronic Filing Help Desk instances, individuals provide home fuel is handled, moved, or stored in the rack
through the ‘‘Contact Us’’ link located addresses in order to demonstrate cells. The probability that a fuel assembly
on the NRC’s public Web site at http:// proximity to a facility or site. With would be dropped or misloaded is
www.nrc.gov/site-help/e- unchanged by the installation of the DREAM
respect to copyrighted works, except for
submittals.html, by email to rack inserts and use of additional
limited excerpts that serve the purpose administrative controls on BWR fuel storage
MSHD.Resource@nrc.gov, or by a toll-
of the adjudicatory filings and would in these racks. These events involve failures
free call at 1–866–672–7640. The NRC
constitute a Fair Use application, of administrative controls, human
Electronic Filing Help Desk is available
participants are requested not to include performance, and equipment failures that are
between 9 a.m. and 6 p.m., Eastern
copyrighted materials in their unaffected by the presence or absence of
Time, Monday through Friday, Boraflex and the rack inserts. The probability
submission.
excluding government holidays. of a SFP dilution event is also unchanged.
Participants who believe that they Duke Energy Progress, LLC, Docket No. The soluble boron is already present in SFPs
have a good cause for not submitting 50–400, Shearon Harris Nuclear Power A and B and no changes are proposed
documents electronically must file an Plant, Unit 1 (HNP), Wake and Chatham regarding the manner in which soluble boron
exemption request, in accordance with Counties, North Carolina is managed. The current controls in place
10 CFR 2.302(g), with their initial paper remain applicable.
filing stating why there is good cause for Date of amendment request: June 28, The installation of the DREAM rack inserts
not filing electronically and requesting 2017, as supplemented by letter dated and crediting of soluble boron does not result
September 14, 2017. Publicly-available in a significant increase in the consequences
authorization to continue to submit of an accident previously analyzed because
documents in paper format. Such filings versions are in ADAMS under
Accession Nos. ML17193B165 and there is no change in the fuel assemblies that
must be submitted by: (1) First class provide the source terms used in calculating
mail addressed to the Office of the ML17257A245, respectively. the radiological consequences of a fuel
Secretary of the Commission, U.S. Description of amendment request: handling accident. In addition, consistent
Nuclear Regulatory Commission, This amendment request contains with the current design, only one fuel
Washington, DC 20555–0001, Attention: sensitive unclassified non-safeguards assembly will be moved at a time. Thus, the
Rulemaking and Adjudications Staff; or information (SUNSI). The amendment consequences of dropping a fuel assembly
(2) courier, express mail, or expedited would modify the Technical onto any other fuel assembly or other
Specifications (TSs) for fuel storage structure remain bounded by the previously
delivery service to the Office of the analyzed fuel handling accident. The
Secretary, 11555 Rockville Pike, criticality to account for the use of
proposed change does not affect the
Rockville, Maryland, 20852, Attention: neutron absorbing spent fuel pool (SFP) effectiveness of the other engineered design
Rulemaking and Adjudications Staff. rack inserts and soluble boron for the features, such as filtration systems, that limit
Participants filing adjudicatory purpose of criticality control in the the offsite dose consequences of a fuel
documents in this manner are boiling water reactor (BWR) storage handling accident.
racks that currently credit Boraflex. Therefore, the proposed change does not
sradovich on DSK3GMQ082PROD with NOTICES
responsible for serving the document on
all other participants. Filing is Basis for proposed no significant involve a significant increase in the
considered complete by first-class mail hazards consideration determination: probability or consequences of an accident
previously evaluated.
as of the time of deposit in the mail, or As required by 10 CFR 50.91(a), the 2. Does the proposed change create the
by courier, express mail, or expedited licensee has provided its analysis of the possibility of a new or different kind of
delivery service upon depositing the issue of no significant hazards accident from any previously evaluated?
document with the provider of the consideration, which is presented The proposed change does not create the
service. A presiding officer, having below: possibility of a new or different kind of
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![57482 Federal Register / Vol. 82, No. 232 / Tuesday, December 5, 2017 / Notices
accident from any accident previously Attorney for licensee: Kathryn B. with the LSCS, Unit 1 Core Operating Limits
evaluated. The rack inserts are passive Nolan, Deputy General Counsel, Duke Report (COLR).
devices that, when inside a spent fuel storage Energy Corporation, 550 South Tryon Similarly, the analyses for LSCS, Unit 2,
rack cell, perform the same function as the Cycle 17, have concluded that a two
St., M/C DEC454, Charlotte, NC 28202.
previously licensed Boraflex neutron recirculation loop SLMCPR of ≥ 1.12, based
absorber panels in that cell. These devices do NRC Branch Chief: Undine Shoop. on the application of GNF’s NRC-approved
not add any limiting structural loads or affect Exelon Generation Company, LLC, SLMCPR methodology, will ensure that this
the removal of decay heat from the acceptance criterion is met. For single
assemblies. No change in total heat load in Docket Nos. 50–373 and 50–374, LaSalle recirculation loop operation, a SLMCPR of ≥
the spent fuel pool is being made. The inserts County Station (LSCS), Units 1 and 2, 1.15 also ensures that this acceptance
will maintain their design function over the LaSalle County, Illinois criterion is met. The MCPR operating limits
life of the spent fuel pool. The existing fuel are presented and controlled in accordance
handling accident, which assumes the drop
Date of amendment request: August
with the LSCS, Unit 2 Core Operating Limits
of a fuel assembly, bounds the drop of a rack 29, 2017. A publicly-available version is Report (COLR).
insert and/or rack insert installation tool. in ADAMS under Accession No. The requested TS changes do not involve
This proposed change does not create the ML17241A278. any plant modifications or operational
possibility of misloading an assembly into a Description of amendment request: changes that could affect system reliability or
spent fuel storage rack cell. This amendment request contains performance or that could affect the
Therefore, the proposed change does not sensitive unclassified non-safeguards probability of operator error. The requested
create the possibility of a new or different changes do not affect any postulated accident
kind of accident from any accident information (SUNSI). The amendments
precursors, do not affect any accident
previously evaluated. would revise Technical Specification
mitigating systems, and do not introduce any
3. Does the proposed change involve a (TS) 2.1.1, ‘‘Reactor Core SLs [Safety new accident initiation mechanisms.
significant reduction in a margin of safety? Limits].’’ Specifically, this change Therefore, the proposed TS changes do not
The proposed change does not involve a would incorporate revised LSCS, Units involve a significant increase in the
significant reduction in a margin of safety. 1 and 2, safety limit for minimum probability or consequences of any accident
The DREAM rack inserts are being installed critical power ratio (MCPR) for two previously evaluated.
to restore the spent fuel pool criticality 2. Do the proposed changes create the
margin, compensating for the degraded
circulation loop MCPR and single
circulation loop MCPR values for Unit possibility of a new or different kind of
Boraflex neutron absorber. The DREAM rack accident from any accident previously
inserts, once approved for crediting, will 1 and Unit 2, based on the results of the
evaluated?
replace the existing Boraflex as the credited cycle-specific analyses performed by
Response: No.
neutron absorber for controlling spent fuel Global Nuclear Fuel for LSCS, Unit 1, The SLMCPR is a TS numerical value,
pool reactivity, even though the Boraflex Cycle 17, and LSCS, Unit 2, Cycle 17. calculated to ensure that during normal
absorber will remain in place. Basis for proposed no significant operating and during abnormal operational
The proposed HNP TS 5.6.1.3.a.1 requires
that the BWR spent fuel storage racks with hazards consideration determination: transients, at least 99.9% of all fuel rods in
Metamic rack inserts maintain the effective As required by 10 CFR 50.91(a), the the core do not experience transition boiling
neutron multiplication factor, k eff, less than licensee has provided its analysis of the if the limit is not violated. The new
or equal to 0.95 when flooded with water issue of no significant hazards SLMCPRs are calculated using NRC-
borated to 1000 ppm [parts per million]. This approved methodology discussed in NEDE–
consideration, which is presented
includes an allowance for uncertainties in 24011–P–A, ‘‘General Electric Standard
below: Application for Reactor Fuel,’’ Revision 22.
such that the TS limit for boron
concentration in the SFPs, HNP TS 3.7.14, 1. Do the proposed changes involve a The proposed changes do not involve any
shall be greater than or equal to 2000 ppm significant increase in the probability or new modes of operation, any changes to
at all times for pools that contain nuclear consequences of an accident previously setpoints, or any plant modifications. The
fuel. Therefore, for criticality, the required evaluated? proposed revised MCPR safety limits have
safety margin is 5% including a conservative Response: No. been shown to be acceptable for Unit 1 Cycle
margin to account for engineering and The Safety Limit Minimum Critical Power 17 and Unit 2 Cycle 17 operation and will
manufacturing uncertainties. Ratio (SLMCPR) is defined as the lowest ratio be confirmed in the future on a cycle-specific
The proposed change provides a method to of that power which results in the onset of basis. The core operating limits will continue
ensure that k eff continues to be less than or transition boiling to the actual bundle power to be developed using NRC-approved
equal to 0.95, thus preserving the required at the same location. The Global Nuclear Fuel methods. The proposed MCPR safety limits
safety margin of 5%. The criticality analyses (GNF) methodology is applied for each reload or methods for establishing the core
demonstrate that the required margin to 5%, to assure that more than 99.9% of the fuel operating limits do not result in the creation
including a conservative margin to account rods in the core are expected to avoid boiling of any new precursors to an accident.
for engineering and manufacturing transition for the most severe abnormal Therefore, the proposed change does not
uncertainties, is maintained. In addition, the operational transient described in LaSalle create the possibility of a new or different
radiological consequences of a dropped fuel UFSAR [Updated Final Safety Analysis kind of accident from any previously
assembly onto a spent fuel storage rack cell Report] Chapter 15.0. The new SLMCPRs evaluated.
containing a fuel assembly with a rack insert preserve the existing margin to transition 3. Do the proposed changes involve a
is bounded by the radiological consequences boiling. The SLMCPR satisfies the significant reduction in a margin of safety?
of a dropped fuel assembly without a rack requirements of General Design Criterion 10 Response: No.
insert. The proposed change also maintains of Appendix A to 10 CFR 50 regarding There is no reduction in the margin of
the capacity of the HNP spent fuel pools. acceptable fuel design limits. safety previously approved by the NRC as a
Therefore, the proposed change does not The MCPR safety limit is re-evaluated for result of the proposed change to the
involve a significant reduction in a margin of each reload using NRC-approved SLMCPRs. The new SLMCPRs are calculated
safety. methodologies. The analyses for LSCS, Unit using methodology discussed in NEDE–
The NRC staff has reviewed the 1, Cycle 17, have concluded that a two 24011–P–A, ‘‘General Electric Standard
sradovich on DSK3GMQ082PROD with NOTICES
licensee’s analysis and, based on this recirculation loop SLMCPR of ≥ 1.11, based Application for Reactor Fuel,’’ Revision 22.
on the application of GNF’s NRC-approved The SLMCPRs ensure that during normal
review, it appears that the three
SLMCPR methodology, will ensure that this operation and during abnormal operational
standards of 10 CFR 50.92(c) are acceptance criterion is met. For single transients, at least 99.9% of all fuel rods in
satisfied. Therefore, the NRC staff recirculation loop operation, a SLMCPR of ≥ the core do not experience transition boiling
proposes to determine that the 1.13 also ensures that this acceptance if the limit is not violated, thereby preserving
amendment request involves no criterion is met. The MCPR operating limits the fuel cladding integrity. The proposed TS
significant hazards consideration. are presented and controlled in accordance changes do not involve a significant
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![57484 Federal Register / Vol. 82, No. 232 / Tuesday, December 5, 2017 / Notices
granting or denying access) is governed minimize any unnecessary delays in for processing and resolving requests
by 10 CFR 2.311.3 identifying those petitioners who have under these procedures.
I. The Commission expects that the standing and who have propounded It is so ordered.
NRC staff and presiding officers (and contentions meeting the specificity and Dated at Rockville, Maryland, this 17th day
any other reviewing officers) will basis requirements in 10 CFR part 2. of November, 2017.
consider and resolve requests for access The attachment to this Order For the Nuclear Regulatory Commission.
to SUNSI, and motions for protective summarizes the general target schedule Annette L. Vietti-Cook,
orders, in a timely fashion in order to 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 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 opportunity to request a hearing and petition for leave to intervene), 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. 2017–25390 Filed 12–4–17; 8:45 am] Personnel Management proposes to the routine uses, which are effective
BILLING CODE 7590–01–P establish a new OPM system of records January 9, 2018.
titled ‘‘OPM/Central-20 National CFC
ADDRESSES: You may submit written
System of Records.’’ This system of
comments by one of the following
OFFICE OF PERSONNEL records contains information that OPM
methods:
MANAGEMENT collects and maintains about
individuals who make charitable • Mail: Keith Willingham, Director,
Privacy Act of 1974; System of contributions to eligible non-profit Office of CFC, Office of Personnel
Records organizations through the Combined Management, 1900 E Street NW., Suite
Federal Campaign (CFC). This newly 6484, Washington, DC 20415.
AGENCY: U.S. Office of Personnel established system of records will be • Email: cfc@opm.gov.
Management, Merit Systems included in the Office of Personnel
Accountability and Compliance, Office Management’s inventory of record FOR FURTHER INFORMATION, CONTACT: For
of the Combined Federal Campaign. systems. general questions, please contact: Keith
ACTION: Notice of a new system of Willingham, 202–606–2564, Director,
sradovich on DSK3GMQ082PROD with NOTICES
records. DATES: Please submit comments on or Office of the Combined Federal
before January 4, 2018. This new system Campaign, Office of Personnel
SUMMARY: In accordance with the is effective upon publication in today’s Management. For privacy questions,
Privacy Act of 1974, the Office of Federal Register, with the exception of please contact: Kellie Cosgrove Riley,
3 Requesters should note that the filing 46562; August 3, 2012) apply to appeals of NRC applicable), but not to the initial SUNSI request
requirements of the NRC’s E-Filing Rule (72 FR staff determinations (because they must be served submitted to the NRC staff under these procedures.
49139; August 28, 2007, as amended at 77 FR on a presiding officer or the Commission, as
VerDate Sep<11>2014 18:13 Dec 04, 2017 Jkt 244001 PO 00000 Frm 00062 Fmt 4703 Sfmt 4703 E:\FR\FM\05DEN1.SGM 05DEN1](https://thefederalregister.org/doc/82_FR_57710/page/7.svg)
Document Created: 2017-12-04 23:44:45
Document Modified: 2017-12-04 23:44:45
| 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; notice of opportunity to comment, request a hearing, and petition for leave to intervene; order imposing procedures. | |
| Dates | Comments must be filed by January 4, 2018. A request for a hearing must be filed by February 5, 2018. 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 December 15, 2017. | |
| Contact | Lynn Ronewicz, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington DC 20555-0001; telephone: 301-415-1927, email: [email protected] | |
| FR Citation | 82 FR 57478 |
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