83 FR 9553 - 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 83, Issue 44 (March 6, 2018)
Federal Register Volume 83, Issue 44 (March 6, 2018)
| Page Range | 9553-9559 | |
| FR Document | 2018-03235 |
[Federal Register Volume 83, Number 44 (Tuesday, March 6, 2018)] [Notices] [Pages 9553-9559] From the Federal Register Online [www.thefederalregister.org] [FR Doc No: 2018-03235] [[Page 9553]] ----------------------------------------------------------------------- NUCLEAR REGULATORY COMMISSION [NRC-2018-0027] 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 North Anna Power Station, Units 1 and 2, and Vogtle Electric Generating Plant, Units 3 and 4. For each amendment request, the NRC proposes to determine that they involve 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 April 5, 2018. A request for a hearing must be filed by May 7, 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 March 16, 2018. ADDRESSES: You may submit comments by any of the following methods:Federal Rulemaking website: Go to http://www.regulations.gov and search for Docket ID NRC-2018-0027. Address questions about NRC dockets to Jennifer Borges; telephone: 301-287- 9127; email: [email protected]. For technical questions, contact the individual listed in the FOR FURTHER INFORMATION CONTACT section of this document. Mail comments to: May Ma, Office of Administration, Mail Stop: TWFN-3-D1, 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: Janet Burkhardt, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; telephone: 301-415-1384; email: [email protected]. SUPPLEMENTARY INFORMATION: I. Obtaining Information and Submitting Comments A. Obtaining Information Please refer to Docket ID NRC-2018-0027, facility name, unit number(s), plant docket number, application date, and subject when contacting the NRC about the availability of information for this action. You may obtain publicly-available information related to this action by any of the following methods: Federal Rulemaking Website: Go to http://www.regulations.gov and search for Docket ID NRC-2018-0027. 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-2018-0027, facility name, unit number(s), plant docket number, application date, and subject in your comment submission. The NRC cautions you not to include identifying or contact information that you do not want to be publicly disclosed in your comment submission. The NRC will post all comment submissions at http://www.regulations.gov as well as enter the comment submissions into ADAMS. The NRC does not routinely edit comment submissions to remove identifying or contact information. If you are requesting or aggregating comments from other persons for submission to the NRC, then you should inform those persons not to include identifying or contact information that they do not want to be publicly disclosed in their comment submission. Your request should state that the NRC does not routinely edit comment submissions to remove such information before making the comment submissions available to the public or entering the comment into ADAMS. II. 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- [[Page 9554]] 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 website at http://www.nrc.gov/reading-rm/doc-collections/cfr/. Alternatively, a copy of the regulations is available at the NRC's Public Document Room, located at One White Flint North, Room O1-F21, 11555 Rockville Pike (first floor), Rockville, Maryland 20852. If a petition is filed, the Commission or a presiding officer will rule on the petition and, if appropriate, a notice of a hearing will be issued. As required by 10 CFR 2.309(d) the petition should specifically explain the reasons why intervention should be permitted with particular reference to the following general requirements for standing: (1) The name, address, and telephone number of the petitioner; (2) the nature of the petitioner's right under the Act to be made a party to the proceeding; (3) the nature and extent of the petitioner's property, financial, or other interest in the proceeding; and (4) the possible effect of any decision or order which may be entered in the proceeding on the petitioner's interest. In accordance with 10 CFR 2.309(f), the petition must also set forth the specific contentions which the petitioner seeks to have litigated in the proceeding. Each contention must consist of a specific statement of the issue of law or fact to be raised or controverted. In addition, the petitioner must provide a brief explanation of the bases for the contention and a concise statement of the alleged facts or expert opinion which support the contention and on which the petitioner intends to rely in proving the contention at the hearing. The petitioner must also provide references to the specific sources and documents on which the petitioner intends to rely to support its position on the issue. The petition must include sufficient information to show that a genuine dispute exists with the applicant or licensee on a material issue of law or fact. Contentions must be limited to matters within the scope of 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 [[Page 9555]] with the NRC's E-Filing rule (72 FR 49139; August 28, 2007, as amended at 77 FR 46562; August 3, 2012). The E-Filing process requires participants to submit and serve all adjudicatory documents over the internet, or in some cases to mail copies on electronic storage media. Detailed guidance on making electronic submissions may be found in the Guidance for Electronic Submissions to the NRC and on the NRC website at http://www.nrc.gov/site-help/e-submittals.html. Participants may not submit paper copies of their filings unless they seek an exemption in accordance with the procedures described below. To comply with the procedural requirements of E-Filing, at least 10 days prior to the filing deadline, the participant should contact the Office of the Secretary by email at [email protected], or by telephone at 301-415-1677, to (1) request a digital identification (ID) certificate, which allows the participant (or its counsel or representative) to digitally sign submissions and access the E-Filing system for any proceeding in which it is participating; and (2) advise the Secretary that the participant will be submitting a petition or other adjudicatory document (even in instances in which the participant, or its counsel or representative, already holds an NRC- issued digital ID certificate). Based upon this information, the Secretary will establish an electronic docket for the hearing in this proceeding if the Secretary has not already established an electronic docket. Information about applying for a digital ID certificate is available on the NRC's public website at http://www.nrc.gov/site-help/e-submittals/getting-started.html. Once a participant has obtained a digital ID certificate and a docket has been created, the participant can then submit adjudicatory documents. Submissions must be in Portable Document Format (PDF). Additional guidance on PDF submissions is available on the NRC's public website at http://www.nrc.gov/site-help/electronic-sub-ref-mat.html. A filing is considered complete at the time the document is submitted through the NRC's E-Filing system. To be timely, an electronic filing must be submitted to the E-Filing system no later than 11:59 p.m. Eastern Time on the due date. Upon receipt of a transmission, the E-Filing system time-stamps the document and sends the submitter an email notice confirming receipt of the document. The E-Filing system also distributes an email notice that provides access to the document to the NRC's Office of the General Counsel and any others who have advised the Office of the Secretary that they wish to participate in the proceeding, so that the filer need not serve the document on those participants separately. Therefore, applicants and other participants (or their counsel or representative) must apply for and receive a digital ID certificate before adjudicatory documents are filed so that they can obtain access to the documents via the E-Filing system. A person filing electronically using the NRC's adjudicatory E- Filing system may seek assistance by contacting the NRC's Electronic Filing Help Desk through the ``Contact Us'' link located on the NRC's public website at http://www.nrc.gov/site-help/e-submittals.html, by email to [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. Southern Nuclear Operating Company, Docket Nos. 52-025 and 52-026, Vogtle Electric Generating Plant, Units 3 and 4, Burke County, Georgia Date of amendment request: December 15, 2017. A publicly-available version is in ADAMS under Accession No. ML17349A924. Description of amendment request: This amendment request contains sensitive unclassified non-safeguards information (SUNSI). The requested amendment proposes consistency changes to combined license Appendix C (and to plant-specific Tier 1 information) and associated Tier 2* and Tier 2 information to clarify the thickness of the Nuclear Island (NI) Basemat, to revise wall thicknesses and descriptions in the Auxiliary Building, and to clarify floor thicknesses in the Annex Building. Pursuant to the provisions of 10 CFR 52.63(b)(1), an exemption from elements of the design as certified in the 10 CFR part 52, Appendix D, design certification rule is also requested for the plant-specific Design Control Document Tier 1 material departures. Basis for proposed no significant hazards consideration determination: As required by 10 CFR 50.91(a), the licensee has provided its analysis of the issue of no significant hazards consideration, which is presented below: 1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated? Response: No. The proposed changes do not affect the operation or reliability of any system, [[Page 9556]] structure or component (SSC) required to maintain a normal power operating condition or to mitigate anticipated transients without safety-related systems. The change to the NI Basemat and Auxiliary Building dimensions is a consistency change, and involves no design changes or technical reanalysis. The change to the Annex Building concrete thickness acceptance criteria is a clarification and does not involve a change to the design of the Annex Building or reanalysis of the Annex Building. The change to the Annex Building kitchen and restroom floor thickness involves only structural changes, and does not affect the performance of any SSC relied upon to maintain normal power operation, or to effect safe shutdown using nonsafety-related equipment. The change to the Annex Building kitchen and restroom floor thickness does not adversely affect occupational radiation dose to personnel in these areas because calculations show the dose rates in the Annex Building during normal operations and in post-accident conditions are maintained within regulatory limits. Therefore, the requested amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated. 2. Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated? Response: No. The proposed changes do not affect the operation of any safety- related SSC relied upon to mitigate design basis accidents. The proposed changes to the NI Basemat and the Auxiliary Building resolve inconsistencies to reflect NI existing structural design, which has been analyzed and shown to comply with seismic and structural criteria. The change to the Annex Building concrete thickness acceptance criteria is a clarification, and does not involve a change to the design of the Annex Building or reanalysis of the Annex Building. The seismic Category II section of the Annex Building has been shown to maintain its structural integrity following a design basis earthquake. The proposed changes to the Annex Building kitchen and restroom floor thickness do not affect the structural integrity or seismic response of the Annex Building. The design of these structures continues to meet the requirements of 10 CFR 50 Appendix A General Design Criterion 2, Design Bases for Protection Against Natural Phenomena. Therefore, the proposed changes do not create the possibility of a new or different kind of accident from any previously evaluated. 3. Does the proposed amendment involve a significant reduction in a margin of safety? Response: No. The proposed changes do not affect existing safety margins. The proposed changes to the NI Basemat and the Auxiliary Building resolve inconsistencies to reflect NI existing structural design. The change to the Annex Building concrete thickness acceptance criteria is a clarification, and does not involve a change to the design of the Annex Building or reanalysis of the Annex Building. The proposed changes to the Annex Building kitchen and restroom floor thickness do not involve a reduction to the structural integrity of the seismic Category II portion of the building, as adequate reinforcement is provided in the floor of the kitchen and restroom areas of the [Control Support Area (CSA)] to support the design function of the Annex Building. No margin to the specified acceptable fuel design limits is affected by the proposed changes. 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: M. Stanford Blanton, Balch & Bingham LLP, 1710 Sixth Avenue North, Birmingham, Alabama 35203-2015. NRC Branch Chief: Jennifer Dixon-Herrity. Virginia Electric and Power Company, Docket Nos. 50-338 and 50-339, North Anna Power Station (NAPS), Units 1 and 2, Louisa County, Virginia Date of amendment request: May 2, 2017. A publicly-available version is in ADAMS under Accession No. ML17129A446. Description of amendment request: This amendment request contains sensitive unclassified non-safeguards information (SUNSI). The amendments would revise Technical Specification (TS) 3.7.18, ``Spent Fuel Pool Storage,'' and TS 4.3.1, ``Criticality,'' to allow the storage of fuel assemblies with a maximum enrichment of up to 5.0 weight percent uranium 235 (U-235) in the NAPS spent fuel pool (SFP) storage racks and the new fuel storage racks (NFSR). The amendments would further revise the allowable fuel assembly parameters and storage patterns for fuel in the SFP. Basis for proposed no significant hazards consideration determination: As required by 10 CFR 50.91(a), the licensee has provided its analysis of the issue of no significant hazards consideration, which is presented below: 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated? Response: No. The proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated. The proposed change will not affect the plant equipment or structure, including the SFP, NFSR, or fuel handling equipment, including how equipment is operated and maintained. There are no changes to the equipment for fuel handling or how fuel assemblies are handled, including how fuel assemblies are inserted into and removed from SFP and NFSR storage locations. There will be no changes to administrative means to verify correct fuel assembly storage in the SFP, which will now also be used to verify required [Rod Cluster Control Assembly (RCCA)] storage in selected Region 2 assemblies, or the required response to a fuel assembly misloading or drop event. There are no changes to how RCCAs will be handled, including how RCCAs are inserted into or removed from a fuel assembly or other location such as a[n] SFP storage location. Also, since the proposed change does not modify plant equipment or its operation and maintenance, including equipment used to maintain SFP soluble boron levels, the proposed change will not impact a boron dilution event or plant response to it. The criticality safety evaluation concluded that the NFSR limiting accident is the optimum moderation condition with each storage location loaded with a maximum reactivity fuel assembly. The NFSR will maintain k eff <0.98 for this postulated scenario including all uncertainties and biases. The NFSR also maintains keff <=0.95 for the fully flooded scenario including all uncertainties and biases. Thus, the consequences of an accident previously evaluated regarding the NFSR is not significantly increased. There is no change to the plant equipment or its operation and maintenance due to the proposed change. Thus, the probability of a flooding accident that could impact the NFSR is not significantly increased. Regarding the SFP, there will now be two storage Regions. The process of choosing fuel assembly storage locations will not change, except that the storage arrangement (checkerboard) and burnup requirements will be revised and assemblies containing an RCCA can be stored in Region 2 without consideration of the burnup curves. The physical handling, insertion, removal, and storage of fuel assemblies in SFP racks will not change. The NAPS program for choosing fuel assembly storage locations, for fuel handling, and for assuring that the fuel assemblies are placed into correct locations will remain in place. Thus, the probability of a fuel assembly misloading or a fuel assembly drop in the SFP will not significantly increase due to the proposed change. A number of postulated accidents for the SFP were reviewed for the proposed change which included postulated fuel assembly misloading and drop scenarios. The criticality safety evaluation for the SFP concluded that the limiting accident, which bounds all other scenarios, is a multiple misload of a maximum reactivity fuel assembly into each SFP storage location. The criticality safety evaluation concluded that a[n] SFP soluble boron concentration of 2600 [parts per million (ppm)] will maintain keff <=0.95 including all uncertainties and biases for this postulated scenario. The current TS, which is not being changed, requires a minimum concentration of 2600 ppm soluble boron at all times that fuel is in the SFP. Since there is no change to the plant equipment that maintains boron concentration or how the boron [[Page 9557]] concentration is maintained, the probability of an accident involving an incorrect amount of SFP soluble boron is not significantly increased. Also, since keff would remain <=0.95, there is no significant increase in the consequences of a postulated accident. There are no changes to plant equipment, including its operation and maintenance, as a result of the proposed change, including equipment associated with maintaining SFP soluble boron concentration or possible flow paths that could contribute to a boron dilution event. Thus, no new avenues for a boron dilution event will be created. There will be no change regarding how the plant maintains boron concentration or responds to a boron dilution event. The criticality safety evaluation for the postulated boron dilution event shows that, like the existing analysis, the SFP maintains keff <=0.95 at 900 ppm soluble boron. Thus, there is no significant increase in the probability or consequences of a boron dilution accident. In each of the above scenarios the proposed change does not significantly increase the probability of an accident previously evaluated. In each postulated accident keff continues to be less than or equal to the licensing limit of 0.95, or less than 0.98 for the NFSR optimum moderation scenario. The NAPS SFP is currently licensed to store a fuel assembly in each of the 1737 spent fuel rack storage locations. Thus, the SFP seismic/structural loading requirements for the proposed change are bounded by the existing TS which have been shown to protect the fuel during normal and accident conditions, including during a postulated seismic event. Thus, there is no increase in the consequences of a seismic event. The proposed license amendment makes no changes to any safety analysis limits, including core power level, operating temperature or pressure, or peaking factors. There are no changes being made to any fuel burnup limits. Thus, it is concluded that:There is no increase in the radiological consequences in response to postulated accidents, there is no change to the maximum allowable SFP heat load, there is no impact on fuel rod integrity during normal or accident conditions, and there is no impact on the ability of RCCAs to fully insert during normal or accident conditions. Thus, it is concluded that the probability or consequences of a previously evaluated accident do not significantly increase. 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated? Response: No. The proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated. There is no change to any plant equipment, including how equipment is operated and maintained. Equipment used to handle fuel assemblies (or any heavy load) over the NFSR or the SFP, or how the fuel assemblies are stored, inserted into and removed from fuel storage locations is not changed. There is no change to how RCCAs will be inserted into or removed from a fuel assembly or other location, or otherwise how RCCAs are handled. Any fuel assemblies containing a[n] RCCA may now be stored in Region 2 without being in the ``Acceptable'' region of the burnup curves. However, if such an assembly was stored in Region 2 without the RCCA, it would be treated as any other fuel misload event in which an assembly is stored in Region 2 without meeting the requirements of the burnup curves. Thus, there are no new accidents created over and above the existing postulated accidents of a fuel misload or a fuel assembly drop in the SFP, or a flooding event in the NFSR area. Also, since there is no change to the plant equipment or how equipment is operated and maintained, the probability of a new type of accident that could impact the SFP or NFSR is not significantly increased. Since the proposed change will not change fuel/RCCA handling equipment or how fuel assemblies and RCCAs are handled and stored, nor will it change any other plant equipment, there is no mechanism for creating a new or different kind of accident not previously evaluated. Thus, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated. 3. Does the proposed change involve a significant reduction in a margin of safety? Response: No. The proposed change does not involve a significant reduction in a margin of safety. The licensing requirement for the SFP is that k eff remain <=0.95 under normal and all postulated accident conditions with credit for soluble boron. The criticality safety evaluation concluded that this requirement is met for the bounding postulated accident of a multiple misload of a maximum reactivity fuel assembly into each SFP storage location, and for the postulated boron dilution event. In addition the criticality safety evaluation concluded the following regarding normal conditions with 0 ppm soluble boron in the SFP:The SFP will maintain k eff <1.0.For a fuel handling event that brings two fresh 5.0 weight percent U-235 fuel assemblies, not stored in a spent fuel rack or dry shielded container, [near] each other, k eff is maintained <0.95 with 0 ppm of soluble boron in the SFP water for a distance >12 inches. With credit for soluble boron keff is maintained <0.95 for any distance less than 12 inches apart. The criticality safety evaluation also allows the following storage configurations. In each case the storage configuration either reduces or does not increase reactivity assuring that keff margin is maintained:Storing a[n] RCCA and/or cell blocker in a Region 1 empty location. Storing non-fuel components in any spent fuel rack storage location where fuel assemblies are allowed. Storing non-fuel components in the guide tubes of any fuel assembly. The criticality safety evaluation evaluated Non-standard Fuel Assemblies stored in the NAPS SFP to determine whether they need to contain a[n] RCCA for Region 2 storage. This information is used to maintain k eff margin when storing Non-standard Fuel Assemblies. The licensing requirements for the NFSR is that keff remain <=0.95 for the fully flooded scenario, and <0.98 for the optimum moderation scenario. The criticality safety evaluation concluded that these requirements are met assuming each storage location is loaded with a maximum reactivity fuel assembly. Thus, all the margins of safety are maintained, and 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: Lillian M. Cuoco, Senior Counsel, Dominion Resources Services, Inc., 120 Tredegar Street, RS-2, Richmond, Virginia 23219. NRC Branch Chief: Michael T. Markley. Order Imposing Procedures for Access to Sensitive Unclassified Non- Safeguards Information for Contention Preparation Southern Nuclear Operating Company, Docket Nos. 52-025 and 52-026, Vogtle Electric Generating Plant, Units 3 and 4, Burke County, Georgia Virginia Electric and Power Company, Docket Nos. 50-338 and 50-339, North Anna Power Station, Units 1 and 2, Louisa County, Virginia 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 [[Page 9558]] 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 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, on February 12, 2018. 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. [[Page 9559]] 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. 2018-03235 Filed 3-5-18; 8:45 am] BILLING CODE 7590-01-P
![Federal Register / Vol. 83, No. 44 / Tuesday, March 6, 2018 / Notices 9553
NUCLEAR REGULATORY Submitting Comments’’ in the submission to the NRC, then you should
COMMISSION SUPPLEMENTARY INFORMATION section of inform those persons not to include
this document. identifying or contact information that
[NRC–2018–0027]
FOR FURTHER INFORMATION CONTACT: they do not want to be publicly
Applications and Amendments to Janet Burkhardt, Office of Nuclear disclosed in their comment submission.
Facility Operating Licenses and Reactor Regulation, U.S. Nuclear Your request should state that the NRC
Combined Licenses Involving Regulatory Commission, Washington, does not routinely edit comment
Proposed No Significant Hazards DC 20555–0001; telephone: 301–415– submissions to remove such information
Considerations and Containing 1384; email: Janet.Burkhardt@nrc.gov. before making the comment
Sensitive Unclassified Non-Safeguards SUPPLEMENTARY INFORMATION:
submissions available to the public or
Information and Order Imposing entering the comment into ADAMS.
I. Obtaining Information and
Procedures for Access to Sensitive Submitting Comments II. Background
Unclassified Non-Safeguards Pursuant to Section 189a.(2) of the
Information A. Obtaining Information Atomic Energy Act of 1954, as amended
AGENCY: Nuclear Regulatory Please refer to Docket ID NRC–2018– (the Act), the NRC is publishing this
Commission. 0027, facility name, unit number(s), notice. The Act requires the
ACTION: License amendment request;
plant docket number, application date, Commission to publish notice of any
notice of opportunity to comment, and subject when contacting the NRC amendments issued, or proposed to be
request a hearing, and petition for leave about the availability of information for issued and grants the Commission the
to intervene; order imposing this action. You may obtain publicly- authority to issue and make
procedures. available information related to this immediately effective any amendment
action by any of the following methods: to an operating license or combined
SUMMARY: The U.S. Nuclear Regulatory • Federal Rulemaking Website: Go to license, as applicable, upon a
Commission (NRC) received and is http://www.regulations.gov and search determination by the Commission that
considering approval of two amendment for Docket ID NRC–2018–0027. such amendment involves no significant
requests. The amendment requests are • NRC’s Agencywide Documents hazards consideration, notwithstanding
for North Anna Power Station, Units 1 Access and Management System the pendency before the Commission of
and 2, and Vogtle Electric Generating (ADAMS): You may obtain publicly- a request for a hearing from any person.
Plant, Units 3 and 4. For each available documents online in the This notice includes notices of
amendment request, the NRC proposes ADAMS Public Documents collection at amendments containing SUNSI.
to determine that they involve no http://www.nrc.gov/reading-rm/
III. Notice of Consideration of Issuance
significant hazards consideration. adams.html. To begin the search, select
of Amendments to Facility Operating
Because each amendment request ‘‘ADAMS Public Documents’’ and then
Licenses and Combined Licenses,
contains sensitive unclassified non- select ‘‘Begin Web-based ADAMS
Proposed No Significant Hazards
safeguards information (SUNSI), an Search.’’ For problems with ADAMS,
Consideration Determination, and
order imposes procedures to obtain please contact the NRC’s Public
Opportunity for a Hearing
access to SUNSI for contention Document Room (PDR) reference staff at
preparation. 1–800–397–4209, 301–415–4737, or by The Commission has made a
email to pdr.resource@nrc.gov. The proposed determination that the
DATES: Comments must be filed by April ADAMS accession number for each following amendment requests involve
5, 2018. A request for a hearing must be document referenced (if it is available in no significant hazards consideration.
filed by May 7, 2018. Any potential ADAMS) is provided the first time that Under the Commission’s regulations in
party as defined in § 2.4 of title 10 of the it is mentioned in this document. 10 CFR 50.92, this means that operation
Code of Federal Regulations (10 CFR), • NRC’s PDR: You may examine and of the facility in accordance with the
who believes access to SUNSI is purchase copies of public documents at proposed amendment would not (1)
necessary to respond to this notice must the NRC’s PDR, Room O1–F21, One involve a significant increase in the
request document access by March 16, White Flint North, 11555 Rockville probability or consequences of an
2018. Pike, Rockville, Maryland 20852. accident previously evaluated, or (2)
ADDRESSES: You may submit comments create the possibility of a new or
by any of the following methods: B. Submitting Comments different kind of accident from any
• Federal Rulemaking website: Go to Please include Docket ID NRC–2018– accident previously evaluated, or (3)
http://www.regulations.gov and search 0027, facility name, unit number(s), involve a significant reduction in a
for Docket ID NRC–2018–0027. Address plant docket number, application date, margin of safety. The basis for this
questions about NRC dockets to Jennifer and subject in your comment proposed determination for each
Borges; telephone: 301–287–9127; submission. amendment request is shown below.
email: Jennifer.Borges@nrc.gov. For The NRC cautions you not to include The Commission is seeking public
technical questions, contact the identifying or contact information that comments on this proposed
individual listed in the FOR FURTHER you do not want to be publicly determination. Any comments received
INFORMATION CONTACT section of this disclosed in your comment submission. within 30 days after the date of
document. The NRC will post all comment publication of this notice will be
• Mail comments to: May Ma, Office
sradovich on DSK3GMQ082PROD with NOTICES
submissions at http:// considered in making any final
of Administration, Mail Stop: TWFN–3– www.regulations.gov as well as enter the determination.
D1, U.S. Nuclear Regulatory comment submissions into ADAMS. Normally, the Commission will not
Commission, Washington, DC 20555– The NRC does not routinely edit issue the amendment until the
0001. comment submissions to remove expiration of 60 days after the date of
For additional direction on obtaining identifying or contact information. publication of this notice. The
information and submitting comments, If you are requesting or aggregating Commission may issue the license
see ‘‘Obtaining Information and comments from other persons for amendment before expiration of the 60-
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![9556 Federal Register / Vol. 83, No. 44 / Tuesday, March 6, 2018 / Notices
structure or component (SSC) required to thickness do not involve a reduction to the assemblies are handled, including how fuel
maintain a normal power operating condition structural integrity of the seismic Category II assemblies are inserted into and removed
or to mitigate anticipated transients without portion of the building, as adequate from SFP and NFSR storage locations. There
safety-related systems. The change to the NI reinforcement is provided in the floor of the will be no changes to administrative means
Basemat and Auxiliary Building dimensions kitchen and restroom areas of the [Control to verify correct fuel assembly storage in the
is a consistency change, and involves no Support Area (CSA)] to support the design SFP, which will now also be used to verify
design changes or technical reanalysis. The function of the Annex Building. No margin required [Rod Cluster Control Assembly
change to the Annex Building concrete to the specified acceptable fuel design limits (RCCA)] storage in selected Region 2
thickness acceptance criteria is a clarification is affected by the proposed changes. assemblies, or the required response to a fuel
and does not involve a change to the design assembly misloading or drop event. There are
of the Annex Building or reanalysis of the The NRC staff has reviewed the no changes to how RCCAs will be handled,
Annex Building. The change to the Annex licensee’s analysis and, based on this including how RCCAs are inserted into or
Building kitchen and restroom floor review, it appears that the three removed from a fuel assembly or other
thickness involves only structural changes, standards of 10 CFR 50.92(c) are location such as a[n] SFP storage location.
and does not affect the performance of any satisfied. Therefore, the NRC staff Also, since the proposed change does not
SSC relied upon to maintain normal power proposes to determine that the modify plant equipment or its operation and
operation, or to effect safe shutdown using amendment request involves no maintenance, including equipment used to
nonsafety-related equipment. The change to maintain SFP soluble boron levels, the
the Annex Building kitchen and restroom
significant hazards consideration. proposed change will not impact a boron
floor thickness does not adversely affect Attorney for licensee: M. Stanford dilution event or plant response to it.
occupational radiation dose to personnel in Blanton, Balch & Bingham LLP, 1710 The criticality safety evaluation concluded
these areas because calculations show the Sixth Avenue North, Birmingham, that the NFSR limiting accident is the
dose rates in the Annex Building during Alabama 35203–2015. optimum moderation condition with each
normal operations and in post-accident NRC Branch Chief: Jennifer Dixon- storage location loaded with a maximum
conditions are maintained within regulatory Herrity. reactivity fuel assembly. The NFSR will
limits. Therefore, the requested amendment maintain keff <0.98 for this postulated
does not involve a significant increase in the Virginia Electric and Power Company, scenario including all uncertainties and
probability or consequences of an accident Docket Nos. 50–338 and 50–339, North biases. The NFSR also maintains keff ≤0.95 for
previously evaluated. Anna Power Station (NAPS), Units 1 the fully flooded scenario including all
2. Does the proposed amendment create and 2, Louisa County, Virginia uncertainties and biases. Thus, the
the possibility of a new or different kind of consequences of an accident previously
accident from any accident previously Date of amendment request: May 2, evaluated regarding the NFSR is not
evaluated? 2017. A publicly-available version is in significantly increased. There is no change to
Response: No. ADAMS under Accession No. the plant equipment or its operation and
The proposed changes do not affect the ML17129A446. maintenance due to the proposed change.
operation of any safety-related SSC relied Description of amendment request: Thus, the probability of a flooding accident
upon to mitigate design basis accidents. The This amendment request contains that could impact the NFSR is not
proposed changes to the NI Basemat and the sensitive unclassified non-safeguards significantly increased.
Auxiliary Building resolve inconsistencies to Regarding the SFP, there will now be two
information (SUNSI). The amendments
reflect NI existing structural design, which storage Regions. The process of choosing fuel
has been analyzed and shown to comply with would revise Technical Specification assembly storage locations will not change,
seismic and structural criteria. The change to (TS) 3.7.18, ‘‘Spent Fuel Pool Storage,’’ except that the storage arrangement
the Annex Building concrete thickness and TS 4.3.1, ‘‘Criticality,’’ to allow the (checkerboard) and burnup requirements will
acceptance criteria is a clarification, and does storage of fuel assemblies with a be revised and assemblies containing an
not involve a change to the design of the maximum enrichment of up to 5.0 RCCA can be stored in Region 2 without
Annex Building or reanalysis of the Annex weight percent uranium 235 (U–235) in consideration of the burnup curves. The
Building. The seismic Category II section of the NAPS spent fuel pool (SFP) storage physical handling, insertion, removal, and
the Annex Building has been shown to racks and the new fuel storage racks storage of fuel assemblies in SFP racks will
maintain its structural integrity following a not change. The NAPS program for choosing
(NFSR). The amendments would further
design basis earthquake. The proposed fuel assembly storage locations, for fuel
changes to the Annex Building kitchen and revise the allowable fuel assembly handling, and for assuring that the fuel
restroom floor thickness do not affect the parameters and storage patterns for fuel assemblies are placed into correct locations
structural integrity or seismic response of the in the SFP. will remain in place. Thus, the probability of
Annex Building. The design of these Basis for proposed no significant a fuel assembly misloading or a fuel assembly
structures continues to meet the hazards consideration determination: drop in the SFP will not significantly
requirements of 10 CFR 50 Appendix A As required by 10 CFR 50.91(a), the increase due to the proposed change.
General Design Criterion 2, Design Bases for licensee has provided its analysis of the A number of postulated accidents for the
Protection Against Natural Phenomena. issue of no significant hazards SFP were reviewed for the proposed change
Therefore, the proposed changes do not which included postulated fuel assembly
consideration, which is presented
create the possibility of a new or different misloading and drop scenarios. The
kind of accident from any previously below: criticality safety evaluation for the SFP
evaluated. 1. Does the proposed change involve a concluded that the limiting accident, which
3. Does the proposed amendment involve significant increase in the probability or bounds all other scenarios, is a multiple
a significant reduction in a margin of safety? consequences of an accident previously misload of a maximum reactivity fuel
Response: No. evaluated? assembly into each SFP storage location. The
The proposed changes do not affect Response: No. criticality safety evaluation concluded that
existing safety margins. The proposed The proposed change does not involve a a[n] SFP soluble boron concentration of 2600
changes to the NI Basemat and the Auxiliary significant increase in the probability or [parts per million (ppm)] will maintain keff
sradovich on DSK3GMQ082PROD with NOTICES
Building resolve inconsistencies to reflect NI consequences of an accident previously ≤0.95 including all uncertainties and biases
existing structural design. The change to the evaluated. for this postulated scenario. The current TS,
Annex Building concrete thickness The proposed change will not affect the which is not being changed, requires a
acceptance criteria is a clarification, and does plant equipment or structure, including the minimum concentration of 2600 ppm soluble
not involve a change to the design of the SFP, NFSR, or fuel handling equipment, boron at all times that fuel is in the SFP.
Annex Building or reanalysis of the Annex including how equipment is operated and Since there is no change to the plant
Building. The proposed changes to the maintained. There are no changes to the equipment that maintains boron
Annex Building kitchen and restroom floor equipment for fuel handling or how fuel concentration or how the boron
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![Federal Register / Vol. 83, No. 44 / Tuesday, March 6, 2018 / Notices 9557
concentration is maintained, the probability or removed from a fuel assembly or other The licensing requirements for the NFSR is
of an accident involving an incorrect amount location, or otherwise how RCCAs are that keff remain ≤0.95 for the fully flooded
of SFP soluble boron is not significantly handled. Any fuel assemblies containing a[n] scenario, and <0.98 for the optimum
increased. Also, since keff would remain RCCA may now be stored in Region 2 moderation scenario. The criticality safety
≤0.95, there is no significant increase in the without being in the ‘‘Acceptable’’ region of evaluation concluded that these requirements
consequences of a postulated accident. the burnup curves. However, if such an are met assuming each storage location is
There are no changes to plant equipment, assembly was stored in Region 2 without the loaded with a maximum reactivity fuel
including its operation and maintenance, as RCCA, it would be treated as any other fuel assembly.
a result of the proposed change, including misload event in which an assembly is stored Thus, all the margins of safety are
equipment associated with maintaining SFP in Region 2 without meeting the maintained, and the proposed change does
soluble boron concentration or possible flow requirements of the burnup curves. Thus, not involve a significant reduction in a
paths that could contribute to a boron there are no new accidents created over and margin of safety.
dilution event. Thus, no new avenues for a above the existing postulated accidents of a
fuel misload or a fuel assembly drop in the
The NRC staff has reviewed the
boron dilution event will be created. There
SFP, or a flooding event in the NFSR area. licensee’s analysis and, based on this
will be no change regarding how the plant
maintains boron concentration or responds to Also, since there is no change to the plant review, it appears that the three
a boron dilution event. The criticality safety equipment or how equipment is operated and standards of 10 CFR 50.92(c) are
evaluation for the postulated boron dilution maintained, the probability of a new type of satisfied. Therefore, the NRC staff
event shows that, like the existing analysis, accident that could impact the SFP or NFSR proposes to determine that the
the SFP maintains keff ≤0.95 at 900 ppm is not significantly increased. amendment request involves no
soluble boron. Thus, there is no significant Since the proposed change will not change significant hazards consideration.
increase in the probability or consequences fuel/RCCA handling equipment or how fuel Attorney for licensee: Lillian M.
of a boron dilution accident. assemblies and RCCAs are handled and
stored, nor will it change any other plant Cuoco, Senior Counsel, Dominion
In each of the above scenarios the proposed Resources Services, Inc., 120 Tredegar
change does not significantly increase the equipment, there is no mechanism for
probability of an accident previously creating a new or different kind of accident Street, RS–2, Richmond, Virginia 23219.
evaluated. In each postulated accident keff not previously evaluated. Thus, the proposed NRC Branch Chief: Michael T.
continues to be less than or equal to the change does not create the possibility of a Markley.
licensing limit of 0.95, or less than 0.98 for new or different kind of accident from any
accident previously evaluated. Order Imposing Procedures for Access
the NFSR optimum moderation scenario. to Sensitive Unclassified Non-
The NAPS SFP is currently licensed to 3. Does the proposed change involve a
store a fuel assembly in each of the 1737
significant reduction in a margin of safety? Safeguards Information for Contention
Response: No. Preparation
spent fuel rack storage locations. Thus, the
The proposed change does not involve a
SFP seismic/structural loading requirements Southern Nuclear Operating Company,
significant reduction in a margin of safety.
for the proposed change are bounded by the Docket Nos. 52–025 and 52–026, Vogtle
The licensing requirement for the SFP is
existing TS which have been shown to that keff remain ≤0.95 under normal and all
protect the fuel during normal and accident
Electric Generating Plant, Units 3 and 4,
postulated accident conditions with credit Burke County, Georgia
conditions, including during a postulated for soluble boron. The criticality safety
seismic event. Thus, there is no increase in evaluation concluded that this requirement is Virginia Electric and Power Company,
the consequences of a seismic event. met for the bounding postulated accident of Docket Nos. 50–338 and 50–339, North
The proposed license amendment makes a multiple misload of a maximum reactivity Anna Power Station, Units 1 and 2,
no changes to any safety analysis limits, fuel assembly into each SFP storage location, Louisa County, Virginia
including core power level, operating and for the postulated boron dilution event.
temperature or pressure, or peaking factors. In addition the criticality safety evaluation A. This Order contains instructions
There are no changes being made to any fuel concluded the following regarding normal regarding how potential parties to this
burnup limits. Thus, it is concluded that: conditions with 0 ppm soluble boron in the proceeding may request access to
• There is no increase in the radiological SFP: documents containing Sensitive
consequences in response to postulated • The SFP will maintain keff <1.0. Unclassified Non-Safeguards
accidents, • For a fuel handling event that brings two
• there is no change to the maximum
Information (SUNSI).
fresh 5.0 weight percent U–235 fuel B. Within 10 days after publication of
allowable SFP heat load, assemblies, not stored in a spent fuel rack or
• there is no impact on fuel rod integrity this notice of hearing and opportunity to
dry shielded container, [near] each other, keff
during normal or accident conditions, and petition for leave to intervene, any
is maintained <0.95 with 0 ppm of soluble
• there is no impact on the ability of boron in the SFP water for a distance >12 potential party who believes access to
RCCAs to fully insert during normal or inches. With credit for soluble boron keff is SUNSI is necessary to respond to this
accident conditions. maintained <0.95 for any distance less than notice may request access to SUNSI. A
Thus, it is concluded that the probability 12 inches apart. ‘‘potential party’’ is any person who
or consequences of a previously evaluated The criticality safety evaluation also allows intends to participate as a party by
accident do not significantly increase. the following storage configurations. In each demonstrating standing and filing an
2. Does the proposed change create the case the storage configuration either reduces
possibility of a new or different kind of
admissible contention under 10 CFR
or does not increase reactivity assuring that
accident from any accident previously 2.309. Requests for access to SUNSI
keff margin is maintained:
evaluated? • Storing a[n] RCCA and/or cell blocker in submitted later than 10 days after
Response: No. a Region 1 empty location. publication of this notice will not be
The proposed change does not create the • Storing non-fuel components in any considered absent a showing of good
possibility of a new or different kind of spent fuel rack storage location where fuel cause for the late filing, addressing why
accident from any accident previously assemblies are allowed. the request could not have been filed
evaluated. • Storing non-fuel components in the
sradovich on DSK3GMQ082PROD with NOTICES
earlier.
There is no change to any plant equipment, guide tubes of any fuel assembly. C. The requester shall submit a letter
including how equipment is operated and The criticality safety evaluation evaluated requesting permission to access SUNSI
maintained. Equipment used to handle fuel Non-standard Fuel Assemblies stored in the
assemblies (or any heavy load) over the NFSR NAPS SFP to determine whether they need
to the Office of the Secretary, U.S.
or the SFP, or how the fuel assemblies are to contain a[n] RCCA for Region 2 storage. Nuclear Regulatory Commission,
stored, inserted into and removed from fuel This information is used to maintain keff Washington, DC 20555–0001, Attention:
storage locations is not changed. There is no margin when storing Non-standard Fuel Rulemakings and Adjudications Staff,
change to how RCCAs will be inserted into Assemblies. and provide a copy to the Associate
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![Federal Register / Vol. 83, No. 44 / Tuesday, March 6, 2018 / Notices 9559
ATTACHMENT 1—GENERAL TARGET SCHEDULE FOR PROCESSING AND RESOLVING REQUESTS FOR ACCESS TO SENSITIVE
UNCLASSIFIED NON-SAFEGUARDS INFORMATION IN THIS PROCEEDING—Continued
Day Event/activity
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. 2018–03235 Filed 3–5–18; 8:45 am] 10:45 a.m.–12:15 p.m.: Topical Report 4:00 p.m.–6:00 p.m.: Preparation of
BILLING CODE 7590–01–P ANP–10333P, Revision 0, ‘‘AURORA–B: ACRS Reports (Open/Closed)—The
An Evaluation Model for Boiling Water Committee will continue its discussion
Reactors; Application to Control Rod of proposed ACRS reports. [Note: A
NUCLEAR REGULATORY Drop Accident (CRDA)’’ (Closed)—The portion of this session may be closed in
COMMISSION Committee will hear briefings by and order to discuss and protect information
discussion with representatives of the designated as proprietary, pursuant to 5
Advisory Committee on Reactor NRC staff and Framatome regarding the U.S.C. 552b(c)(4)].
Safeguards; Notice of Meeting, subject topical report. [Note: This
Revised Friday, March 9, 2018, Conference
session is closed in order to discuss and
Room T–2B1, 11545 Rockville Pike,
In accordance with the purposes of protect information designated as
Rockville, Maryland 20852
Sections 29 and 182b of the Atomic proprietary, pursuant to 5 U.S.C.
Energy Act (42 U.S.C. 2039, 2232b), the 552b(c)(4)]. 8:30 a.m.–10:00 a.m.: Future ACRS
Advisory Committee on Reactor 1:15 p.m.–2:45 p.m.: Preparation of Activities/Report of the Planning and
Safeguards (ACRS) will hold a meeting ACRS Reports (Open/Closed)—The Procedures Subcommittee and
March 8–10, 2018, 11545 Rockville Committee will continue its discussion Reconciliation of ACRS Comments and
Pike, Rockville, Maryland 20852. of proposed ACRS reports. [Note: A Recommendations (Open/Closed)—The
portion of this session may be closed in Committee will hear discussion of the
Thursday, March 8, 2018, Conference order to discuss and protect information recommendations of the Planning and
Room T–2B1, 11545 Rockville Pike, designated as proprietary, pursuant to 5 Procedures Subcommittee regarding
Rockville, Maryland 20852 U.S.C. 552b(c)(4)]. items proposed for consideration by the
8:30 a.m.–8:35 a.m.: Opening 3:00 p.m.–4:00 p.m.: Topical Report Full Committee during future ACRS
Remarks by the ACRS Chairman APR1400–F–M–TR–13001–P, Revision 1, meetings. [Note: A portion of this
(Open)—The ACRS Chairman will make ‘‘PLUS7 Fuel Design for the APR1400’’ meeting may be closed pursuant to 5
opening remarks regarding the conduct (Open/Closed)—The Committee will U.S.C. 552b(c)(2) and (6) to discuss
hear briefings by and discussion with organizational and personnel matters
sradovich on DSK3GMQ082PROD with NOTICES
of the meeting.
8:35 a.m.–10:30 a.m.: Regulatory representatives of the NRC staff and that relate solely to internal personnel
Guide 1.232, ‘‘Guidance for Developing KNHP regarding the subject topical rules and practices of the ACRS, and
Principal Design Criteria for Non-Light reports. [Note: A portion of this session information the release of which would
Water Reactors’’ (Open)—The may be closed in order to discuss and constitute a clearly unwarranted
Committee will hear briefings by and protect information designated as invasion of personal privacy].
discussion with representatives of the proprietary, pursuant to 5 U.S.C. 10:00 a.m.–11:00 a.m.: Preparation for
NRC staff regarding the subject guide. 552b(c)(4)]. Meeting with Commission (Open)—The
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Document Created: 2018-11-01 08:49:02
Document Modified: 2018-11-01 08:49:02
| 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 April 5, 2018. A request for a hearing must be filed by May 7, 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 March 16, 2018. | |
| Contact | Janet Burkhardt, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; telephone: 301-415-1384; email: [email protected] | |
| FR Citation | 83 FR 9553 |
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