82 FR 46094 - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Considerations and Containing Sensitive Unclassified Non-Safeguards Information and Safeguards Information and Order Imposing Procedures for Access to Sensitive Unclassified Non-Safeguards Information and Safeguards Information
NUCLEAR REGULATORY COMMISSION Federal Register Volume 82, Issue 190 (October 3, 2017)
Federal Register Volume 82, Issue 190 (October 3, 2017)
| Page Range | 46094-46102 | |
| FR Document | 2017-20084 |
[Federal Register Volume 82, Number 190 (Tuesday, October 3, 2017)] [Notices] [Pages 46094-46102] From the Federal Register Online [www.thefederalregister.org] [FR Doc No: 2017-20084] ======================================================================= ----------------------------------------------------------------------- NUCLEAR REGULATORY COMMISSION [NRC-2017-0192] Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Considerations and Containing Sensitive Unclassified Non-Safeguards Information and Safeguards Information and Order Imposing Procedures for Access to Sensitive Unclassified Non-Safeguards Information and Safeguards Information AGENCY: Nuclear Regulatory Commission. ACTION: License amendment request; 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 three amendment requests. The amendment requests are for Hope Creek Generating Station, R.E. Ginna Nuclear Power Plant, and Wolf Creek Generating Station. For each amendment request, the NRC proposes to determine that they involve no significant hazards consideration. Because the amendment requests contain sensitive unclassified non-safeguards information (SUNSI) and safeguards information (SGI), an order imposes procedures to obtain access to SUNSI and SGI for contention preparation. DATES: Comments must be filed by November 2, 2017. A request for a hearing must be filed by December 4, 2017. 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 and/or SGI is necessary to respond to this notice must request document access by October 13, 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-2017-0192. Address questions about NRC dockets to Carol Gallagher; telephone: 301-415- 3463; email: [email protected]. For technical questions, contact the individual listed in the FOR FURTHER INFORMATION CONTACT section of this document. Mail comments to: Cindy Bladey, Office of Administration, Mail Stop: TWFN-8-D36M, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001. For additional direction on obtaining information and submitting comments, see ``Obtaining Information and Submitting Comments'' in the SUPPLEMENTARY INFORMATION section of this document. FOR FURTHER INFORMATION CONTACT: 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-2017-0192, 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-2017-0192. 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-2017-0192, 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. [[Page 46095]] 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 and/or SGI. 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 Sec. 50.92 of 10 CFR, this means that operation of the facility in accordance with the proposed amendment would not (1) involve a significant increase in the probability or consequences of an accident previously evaluated, or (2) create the possibility of a new or different kind of accident from any accident previously evaluated, or (3) involve a significant reduction in a margin of safety. The basis for this proposed determination for each amendment request is shown below. The Commission is seeking public comments on this proposed determination. Any comments received within 30 days after the date of publication of this notice will be considered in making any final determination. Normally, the Commission will not issue the amendment until the expiration of 60 days after the date of publication of this notice. The Commission may issue the license amendment before expiration of the 60- day period provided that its final determination is that the amendment involves no significant hazards consideration. In addition, the Commission may issue the amendment prior to the expiration of the 30- day comment period if circumstances change during the 30-day comment period such that failure to act in a timely way would result, for example, in derating or shutdown of the facility. If the Commission takes action prior to the expiration of either the comment period or the notice period, it will publish 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 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, [[Page 46096]] 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 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 [[Page 46097]] 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. Exelon Generation Company, LLC, Docket No. 50-244, R.E. Ginna Nuclear Power Plant (Ginna), Wayne County, New York Date of amendment request: June 30, 2017. A publicly-available version is in ADAMS under Accession No. ML17186A233. Description of amendment request: This amendment request contains safeguards information (SGI). The amendment would revise the modification to install overcurrent protection for the emergency diesel generators associated with the implementation of 10 CFR 50.48(c), National Fire Protection Association Standard 805 (NFPA 805), ``Performance-Based Standard for Fire Protection for Light-Water Reactor Electric Generating Plants,'' 2001 Edition. The amendment would also update Attachment C, ``NEI 04-02 Table B-3 Fire Area Transition''; Attachment G, ``Recovery Actions Transition''; Attachment M, ``License Condition Changes''; Attachment S, ``Modifications and Implementation Items''; and Attachment W, ``Fire PRA [Probabilistic Risk Assessment] Insights,'' of the previously approved NFPA 805 amendment. 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. Further consideration of committed modifications has resulted in the conclusion that the modification to install overcurrent protection, Engineering Service Request (ESR) 12-0141 (i.e., modification), is no longer required in the NFPA 805 project modification scope. The original purpose of the overcurrent protection modifications was to reduce fire risk by protecting the emergency diesel generations (EDGs) from fire-induced overcurrent events allowing local recovery of the EDGs. Several alternative means will be made available to provide the power for decay heat removal, RCS [reactor coolant system] inventory and reactivity control, as well as providing power to the vital battery chargers, long-term indication and control power, and breaker control. Operation of Ginna in accordance with the proposed amendment does not increase the probability or consequences of accidents previously evaluated. Engineering analyses, which may include engineering evaluations, probabilistic safety assessments, and fire modeling calculations, have been performed to demonstrate that the performance-based requirements of NFPA 805 have been satisfied with the elimination of fire-induced overcurrent protection. The proposed amendment does not affect accident initiators, nor does it alter design assumptions, conditions, or configurations of the facility that would increase the probability of accidents previously evaluated. Further, the changes to be made for fire hazard protection and mitigation do not adversely affect the ability of structures, systems, or components to perform their design functions for accident mitigation, nor do they affect the postulated initiators or assumed failure models for accidents described and evaluated in the UFSAR [Updated Final Safety Analysis Report]. Structures, systems, or components required to safely shutdown the reactor and to maintain it in a safe shutdown condition will remain capable of performing their design functions. The proposed amendment will not affect the source term, containment isolation, or radiological release assumptions used in evaluating the radiological consequences of any accident previously evaluated, and equipment required to mitigate an accident remains capable of performing the assumed function(s). The applicable radiological dose criteria will continue to be met. The combination of all the proposed modifications and data updates reduces the overall calculated delta risk relative to the previously submitted information even with the removal of the fire- induced overcurrent modifications. The net Core Damage Frequency (CDF) delta risk including the internal events offset is 4E-6. The net Large Early Release Frequency (LERF) delta risk including the internal events offset is less than 1E-7. Based on the above discussion, it is concluded that the proposed amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated. 2. Does the proposed amendment create the possibility of a new or different kind of accident from any kind of accident previously evaluated? Response: No. The original purpose of the overcurrent protection modifications was to reduce the fire risk by protecting the EDGs from fire-induced overcurrent events allowing local recovery of the EDGs. Several alternative means will be made available to provide the power for decay heat removal, RCS inventory and reactivity control, as well as providing power to the vital battery chargers, long-term indication and control power, and breaker control in lieu of ESR-12-0141. Operation of Ginna in accordance with the proposed amendment does not create the possibility of a new or different kind of accident from any accident previously evaluated. The proposed change does not alter the requirements or functions for systems required during accident conditions. Implementation of this change will not result in new or different accidents. The proposed amendment does not introduce new or different accident initiators, nor does it alter design assumptions, conditions, or configurations of the facility in such a manner as to introduce new or different accident initiators. The proposed amendment does not adversely affect the ability of structures, systems, or components to perform their design function. Structures, systems, or components required to safely shutdown the reactor and maintain it in a safe shutdown condition remain capable of performing their design functions. The requirements of NFPA 805 address only fire protection and the impacts of fire on the plant that have previously been evaluated. Thus, implementation of the proposed amendment would not create the possibility of a new or different kind of accident beyond those already analyzed in the UFSAR. No new accident scenarios, transient precursors, failure mechanisms, or limiting single failures will be introduced, and there will be no adverse effect or challenges imposed on any safety-related system as a result of the proposed amendment. Based on the above discussion, it is concluded that the proposed amendment does not create the possibility of a new or different kind of accident from any accident previously evaluated. 3. Does the proposed amendment involve a significant reduction in the margin of safety? Response: No. The purpose of the proposed amendment is to permit Ginna to adopt a new fire protection licensing basis which complies with the requirements in 10 CFR 50.48(a) and (c) and the guidance in Regulatory Guide 1.205, Revision 1. The NRC considers that NFPA 805 provides an acceptable methodology and performance criteria for licensees to identify fire protection systems and features that are an acceptable alternative to the 10 CFR 50, Appendix R required fire protection features (69 FR 33536; June 16, [[Page 46098]] 2004). The proposed change eliminates the overcurrent protection modifications which were intended to reduce fire risk by protecting the EDGs from fire-induced overcurrent events allowing local recovery of the EDGs. Several alternative means will be made available to provide the power for decay heat removal, RCS inventory and reactivity control, and vital auxiliaries such as providing power to the vital battery chargers, long-term indication and control power, and breaker control functions in lieu of ESR-12-0141. These alternative means will ensure that this change does not result in a significant reduction in the margin of safety. The overall approach of NFPA 805 is consistent with the key principles for evaluating license basis changes, as described in Regulatory Guide 1.174, Revision 2, is consistent with the defense- in-depth philosophy, and maintains sufficient safety margins. Engineering analysis, which may include engineering evaluations, probabilistic safety assessments, and fire modeling calculations, have been performed to demonstrate that the performance-based methods do not result in a significant reduction in the margin of safety. Operation of Ginna in accordance with the proposed amendment does not involve a significant reduction in the margin of safety. The proposed amendment does not alter the manner in which safety limits, limiting safety system settings, or limiting conditions for operation are determined. The safety analysis acceptance criteria are not affected by this change. The proposed amendment does not alter the manner in which safety limits, limiting safety system settings, or limiting conditions for operation are determined. The safety analysis acceptance criteria are not affected by this change. The proposed amendment does not adversely affect existing plant safety margins or the reliability of equipment assumed to mitigate accident sin the UFSAR. The proposed amendment does not adversely affect the ability of structures, systems, or components to perform their design function. Structures, systems, or components required to safely shut down the reactor and to maintain it in a safe shutdown condition remain capable of performing their design functions. Based on the above discussion, it is concluded that the proposed amendment does not involve a significant reduction in the margin of safety. The NRC staff has reviewed the licensee's analysis and, based on this review, it appears that the three standards of 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: Tamra Domeyer, Associate General Counsel, Exelon Generation Company, LLC, 4300 Winfield Road, Warrenville, Illinois 60555. NRC Branch Chief: James G. Danna. PSEG Nuclear LLC, Docket No. 50-354, Hope Creek Generating Station, Hancocks Bridge, New Jersey Date of amendment request: July 7, 2017. A publicly-available version is in ADAMS under Package Accession No. ML17188A259. Description of amendment request: This amendment request contains sensitive unclassified non-safeguards information (SUNSI). The amendment would revise the Renewed Facility Operating License and Technical Specifications to implement a measurement uncertainty recapture power uprate. Specifically, the amendment would authorize an increase in the maximum licensed thermal power level from 3,840 megawatts thermal (MWt) to 3,902 MWt, which is an increase of approximately 1.6 percent. 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 will increase the Hope Creek Generating Station rated thermal power (RTP) from 3840 megawatts thermal (MWt) to 3902 MWt. The reviews and evaluations performed to support the proposed uprated power conditions included all structures, systems, and components that would be affected by the proposed changes. The reviews and evaluations determined that these structures, systems, and components are capable of performing their design function at the proposed uprated RTP of 3902 MWt. Accident mitigation systems will function as designed. The performance requirements for these systems have been evaluated and found acceptable. Thus, the proposed changes do not create any new accident initiators or increase the probability of an accident previously evaluated. The primary loop components (e.g., reactor vessel, reactor internals, control rod drive housings, piping and supports, and recirculation pumps) remain within their applicable structural limits and will continue to perform their intended design function at the uprated power level. Thus, there is no increase in the probability of a structural failure from these components. The safety relief valves and containment isolation valves meet design sizing requirements at the uprated power level. Because the plant integrity will not be affected by operation at the uprated condition, PSEG Nuclear LLC (PSEG) has concluded that all structures, systems, and components required to mitigate a transient remain capable of fulfilling their intended functions. The current safety analyses were evaluated for operation at 3902 MWt. The results demonstrate that acceptance criteria for applicable analyses continue to be met at the uprated conditions. As such, applicable accident analyses continue to comply with the relevant event acceptance criteria. The analyses performed to assess the effects of mass and energy releases remain valid. Source terms used to assess radiological consequences have been determined to bound operation at the uprated power level. Power level is an input assumption to equipment design and accident analyses, but is not a transient or accident initiator. Accident initiators are not affected by the power uprate, and plant safety barrier challenges are not created by the proposed change. Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated. 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated? Response: No. No new accident scenarios, failure mechanisms, or single failures are introduced as a result of the proposed change. Structures, systems, and components previously required for transient mitigation remain capable of fulfilling their intended design functions. The proposed change has no adverse effect on any safety-related structures, systems, or components and does not challenge the performance or integrity of any safety-related system. The proposed change does not adversely affect any current system interfaces or create any new interfaces that could result in an accident or malfunction of a different kind than previously evaluated. Plant operation at 3902 MWt does not create any new accident initiators or precursors. Credible malfunctions are bounded by the current accident analyses of record or recent evaluations demonstrating that applicable criteria are still met with the proposed change. Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated. 3. Do the proposed changes involve a significant reduction in a margin of safety? Response: No. The margins of safety associated with the power uprate are those pertaining to core thermal power. Analyses of the primary fission product barriers have concluded that relevant design criteria remain satisfied, both from the standpoint of primary fission product barrier integrity and compliance with the required acceptance criteria. As appropriate, evaluations have been performed using methods that have either been reviewed and approved by the Nuclear Regulatory Commission, or are in compliance with regulatory review guidance and standards. Therefore, the proposed changes do 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 [[Page 46099]] 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: Jeffrie J. Keenan, PSEG Nuclear LLC--N21, P.O. Box 236, Hancocks Bridge, New Jersey 08038. NRC Branch Chief: James G. Danna. Wolf Creek Nuclear Operating Corporation, Docket No. 50-482, Wolf Creek Generating Station, (WCGS) Coffey County, Kansas Date of amendment request: June 28, 2017. A publicly-available version is in ADAMS under Accession No. ML17186A082. Description of amendment request: This amendment request contains sensitive unclassified non-safeguards information (SUNSI). The amendment would add new Technical Specification (TS) 3.7.20, ``Class 1E Electrical Equipment Air Conditioning (A/C) System,'' to the WCGS TSs. New TS 3.7.20 would include the limiting condition for operation (LCO) statement, Applicability during which the LCO must be met, ACTIONS (with Conditions, Required Actions, and Completion Times) to be applied when the LCO is not met, and Surveillance Requirements (SRs) with a specified Frequency to demonstrate that the LCO is met for the Class 1 E Electrical Equipment A/C System trains at WCGS. Additionally, the Table of Contents would also be revised to reflect the incorporation of new TS 3.7.20. 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 addition of TS 3.7.20 creates a[n] LCO for the Class 1E Electrical Equipment A/C System that is required to support the TS Class 1E electrical equipment. The 30 day Completion Time to restore an inoperable Class 1E electrical equipment A/C train to OPERABLE status is consistent with the Control Room Air Conditioning System (CRACS) and is supported by a plant specific calculation. The Class 1E Electrical Equipment A/C Systems' actuation, operation, or failure is not an initiator to any accident previously evaluated. As a result, the probability of an accident previously evaluated is not significantly increased. Conversely, the proposed change provides a period of time to recover an unexpected loss of cooling capability with one OPERABLE Class 1E electrical equipment A/C train providing adequate area cooling for both trains of Class 1E electrical equipment during normal and accident conditions (with mitigating actions being required). Overall protection system performance will remain within the bounds of the previously performed accident analyses since no hardware changes are proposed to the protection systems. The same Reactor Trip System (RTS) and Engineered Safety Feature Actuation System (ESFAS) instrumentation will continue to be used. The protection systems will continue to function in a manner consistent with the plant design basis. The proposed change will not adversely affect accident initiators or precursors nor adversely alter the design assumptions and conditions of the facility or the manner in which the plant is operated and maintained with respect to such initiators or precursors. The proposed change will not alter or prevent the capability of structures, systems, and components (SSCs) to perform their intended functions for mitigating the consequences of an accident and meeting applicable acceptance limits. Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated. 2. Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated? Response: No. No new accident scenarios, transient precursors, failure mechanisms, or limiting single failures will be introduced as a result of this amendment. No new or different accidents result from addition of the proposed specification. The Class 1E electrical equipment A/C trains maintain the capability to perform their specified safety function. The proposed license amendment includes regulatory commitments to achieve the capability for one OPERABLE Class 1E electrical equipment A/C train to provide adequate cooling for both trains of electrical equipment during normal and accident conditions by design changes. [The planned modifications proposed by regulatory commitments will be implemented under the requirements of 10 CFR 50.59.] The proposed amendment will not alter the design or performance of the 7300 Process Protection System, Nuclear Instrumentation System, Solid State Protection System, Balance of Plant Engineered Safety Features Actuation System, Main Steam and Feedwater Isolation System, or Load Shedder and Emergency Load Sequencers used in the plant protection systems. The proposed change adds requirements in the TSs that were previously located in plant procedures. One OPERABLE Class 1E electrical equipment A/C train is capable of providing adequate area cooling for both trains of Class 1E electrical equipment during normal and accident conditions (with mitigating actions being required). The change does not have a detrimental impact on the manner in which plant equipment operates or responds to an actuation signal. Therefore, the proposed change will not create the possibility of a new or different kind of accident from any accident previously evaluated. 3. Does the proposed amendment involve a significant reduction in a margin of safety? Response: No. The proposed specification allows for a period of time in which one Class 1E electrical equipment A/C train is capable of providing adequate area cooling for both trains of Class 1E electrical equipment during normal and accident conditions (with mitigating actions being required). The proposed change does not impact accident offsite dose, containment pressure or temperature, Emergency Core Cooling System settings or Reactor Protection System settings, or any other parameter that could affect a margin of safety. The margin of safety is enhanced by periodically verifying the area room temperatures are maintained within limit while one Class 1E electrical equipment A/C train is inoperable and allowing a reasonable period to perform preventive and corrective maintenance thus increasing system reliability. 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: Jay Silberg, Esq., Pillsbury Winthrop Shaw Pittman LLP, 2300 N Street NW., Washington, DC 20037. NRC Branch Chief: Robert J. Pascarelli. Order Imposing Procedures for Access to Sensitive Unclassified Non- Safeguards Information and Safeguards Information for Contention Preparation PSEG Nuclear LLC, Docket No. 50-354, Hope Creek Generating Station, Hancocks Bridge, New Jersey Exelon Generation Company, LLC, Docket No. 50-244, R. E. Ginna Nuclear Power Plant, Wayne County, New York Wolf Creek Nuclear Operating Corporation, Docket No. 50-482, Wolf Creek Generating Station, Coffey County, Kansas A. This Order contains instructions regarding how potential parties to this proceeding may request access to documents containing sensitive unclassified information (including Sensitive Unclassified Non- Safeguards Information (SUNSI) and Safeguards Information (SGI)). Requirements for access to SGI are primarily set forth in 10 CFR parts 2 and 73. Nothing in this Order is intended to conflict with the SGI regulations. [[Page 46100]] 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 or SGI is necessary to respond to this notice may request access to SUNSI or SGI. 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 or SGI submitted later than 10 days after publication 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 requestor shall submit a letter requesting permission to access SUNSI, SGI, or both 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 and/or SGI 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); (3) If the request is for SUNSI, the identity of the individual or entity requesting access to SUNSI and the requestor'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; and (4) If the request is for SGI, the identity of each individual who would have access to SGI if the request is granted, including the identity of any expert, consultant, or assistant who will aid the requestor in evaluating the SGI. In addition, the request must contain the following information: (a) A statement that explains each individual's ``need to know'' the SGI, as required by 10 CFR 73.2 and 10 CFR 73.22(b)(1). Consistent with the definition of ``need to know'' as stated in 10 CFR 73.2, the statement must explain: (i) Specifically why the requestor believes that the information is necessary to enable the requestor to proffer and/or adjudicate a specific contention in this proceeding; \2\ and --------------------------------------------------------------------------- \2\ Broad SGI requests under these procedures are unlikely to meet the standard for need to know; furthermore, NRC staff redaction of information from requested documents before their release may be appropriate to comport with this requirement. These procedures do not authorize unrestricted disclosure or less scrutiny of a requestor's need to know than ordinarily would be applied in connection with an already-admitted contention or non-adjudicatory access to SGI. --------------------------------------------------------------------------- (ii) The technical competence (demonstrable knowledge, skill, training or education) of the requestor to effectively utilize the requested SGI to provide the basis and specificity for a proffered contention. The technical competence of a potential party or its counsel may be shown by reliance on a qualified expert, consultant, or assistant who satisfies these criteria. (b) A completed Form SF-85, ``Questionnaire for Non-Sensitive Positions,'' for each individual who would have access to SGI. The completed Form SF-85 will be used by the Office of Administration to conduct the background check required for access to SGI, as required by 10 CFR part 2, subpart C, and 10 CFR 73.22(b)(2), to determine the requestor's trustworthiness and reliability. For security reasons, Form SF-85 can only be submitted electronically through the electronic questionnaire for investigations processing (e-QIP) Web site, a secure Web site that is owned and operated by the Office of Personnel Management. To obtain online access to the form, the requestor should contact the NRC's Office of Administration at 301-415-3710.\3\ --------------------------------------------------------------------------- \3\ The requestor will be asked to provide his or her full name, social security number, date and place of birth, telephone number, and email address. After providing this information, the requestor usually should be able to obtain access to the online form within one business day. --------------------------------------------------------------------------- (c) A completed Form FD-258 (fingerprint card), signed in original ink, and submitted in accordance with 10 CFR 73.57(d). Copies of Form FD-258 may be obtained by writing the Office of Administrative Services, Mail Services Center, Mail Stop P1-37, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by email to [email protected]. The fingerprint card will be used to satisfy the requirements of 10 CFR part 2, subpart C, 10 CFR 73.22(b)(1), and Section 149 of the Atomic Energy Act of 1954, as amended, which mandates that all persons with access to SGI must be fingerprinted for an FBI identification and criminal history records check. (d) A check or money order payable in the amount of $324.00 \4\ to the U.S. Nuclear Regulatory Commission for each individual for whom the request for access has been submitted. --------------------------------------------------------------------------- \4\ This fee is subject to change pursuant to the Office of Personnel Management's adjustable billing rates. --------------------------------------------------------------------------- (e) If the requestor or any individual(s) who will have access to SGI believes they belong to one or more of the categories of individuals that are exempt from the criminal history records check and background check requirements in 10 CFR 73.59, the requestor should also provide a statement identifying which exemption the requestor is invoking and explaining the requestor's basis for believing that the exemption applies. While processing the request, the Office of Administration, Personnel Security Branch, will make a final determination whether the claimed exemption applies. Alternatively, the requestor may contact the Office of Administration for an evaluation of their exemption status prior to submitting their request. Persons who are exempt from the background check are not required to complete the SF-85 or Form FD-258; however, all other requirements for access to SGI, including the need to know, are still applicable. Note: Copies of documents and materials required by paragraphs C.(4)(b), (c), and (d) of this Order must be sent to the following address: U.S. Nuclear Regulatory Commission, ATTN: Personnel Security Branch, Mail Stop TWFN-03-B46M, 11555 Rockville Pike, Rockville, MD 20852. These documents and materials should not be included with the request letter to the Office of the Secretary, but the request letter should state that the forms and fees have been submitted as required. D. To avoid delays in processing requests for access to SGI, the requestor should review all submitted materials for completeness and accuracy (including legibility) before submitting them to the NRC. The NRC will return incomplete packages to the sender without processing. E. Based on an evaluation of the information submitted under paragraphs C.(3) or C.(4) above, as applicable, the [[Page 46101]] 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 or need to know the SGI requested. F. For requests for access to SUNSI, if the NRC staff determines that the requestor satisfies both E.(1) and E.(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 setting forth terms and conditions to prevent the unauthorized or inadvertent disclosure of SUNSI by each individual who will be granted access to SUNSI.\5\ --------------------------------------------------------------------------- \5\ 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. --------------------------------------------------------------------------- G. For requests for access to SGI, if the NRC staff determines that the requestor has satisfied both E.(1) and E.(2) above, the Office of Administration will then determine, based upon completion of the background check, whether the proposed recipient is trustworthy and reliable, as required for access to SGI by 10 CFR 73.22(b). If the Office of Administration determines that the individual or individuals are trustworthy and reliable, the NRC will promptly notify the requestor in writing. The notification will provide the names of approved individuals as well as the conditions under which the SGI will be provided. Those conditions may include, but are not limited to, the signing of a Non-Disclosure Agreement or Affidavit, or Protective Order \6\ by each individual who will be granted access to SGI. --------------------------------------------------------------------------- \6\ Any motion for Protective Order or draft Non-Disclosure Agreement or Affidavit for SGI must be filed with the presiding officer or the Chief Administrative Judge if the presiding officer has not yet been designated, within 180 days of the deadline for the receipt of the written access request. --------------------------------------------------------------------------- H. Release and Storage of SGI. Prior to providing SGI to the requestor, the NRC staff will conduct (as necessary) an inspection to confirm that the recipient's information protection system is sufficient to satisfy the requirements of 10 CFR 73.22. Alternatively, recipients may opt to view SGI at an approved SGI storage location rather than establish their own SGI protection program to meet SGI protection requirements. I. Filing of Contentions. Any contentions in these proceedings that are based upon the information received as a result of the request made for SUNSI or SGI 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 or SGI contentions by that later deadline. J. Review of Denials of Access. (1) If the request for access to SUNSI or SGI is denied by the NRC staff either after a determination on standing and requisite need, or after a determination on trustworthiness and reliability, the NRC staff shall immediately notify the requestor in writing, briefly stating the reason or reasons for the denial. (2) Before the Office of Administration makes a final adverse determination regarding the trustworthiness and reliability of the proposed recipient(s) for access to SGI, the Office of Administration, in accordance with 10 CFR 2.336(f)(1)(iii), must provide the proposed recipient(s) any records that were considered in the trustworthiness and reliability determination, including those required to be provided under 10 CFR 73.57(e)(1), so that the proposed recipient(s) have an opportunity to correct or explain the record. (3) The requestor may challenge the NRC staff's adverse determination with respect to access to SUNSI or with respect to standing or need to know for SGI 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. (4) The requestor may challenge the Office of Administration's final adverse determination with respect to trustworthiness and reliability for access to SGI by filing a request for review in accordance with 10 CFR 2.336(f)(1)(iv). (5) Further appeals of decisions under this paragraph must be made pursuant to 10 CFR 2.311. K. Review of Grants of Access. A party other than the requestor 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.\7\ --------------------------------------------------------------------------- \7\ Requestors 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/SGI request submitted to the NRC staff under these procedures. --------------------------------------------------------------------------- L. The Commission expects that the NRC staff and presiding officers (and any other reviewing officers) will consider and resolve requests for access to SUNSI or SGI, 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 15th day of September 2017. For the Nuclear Regulatory Commission. Rochelle C. Bavol, Acting, Secretary of the Commission. [[Page 46102]] Attachment 1--General Target Schedule for Processing and Resolving Requests for Access to Sensitive Unclassified Non-Safeguards Information and 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) and/or Safeguards Information (SGI) 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; demonstrating that access should be granted (e.g., showing technical competence for access to SGI); and, for SGI, including application fee for fingerprint/ background check. 60............................ Deadline for submitting petition for intervention containing: (i) Demonstration of standing; (ii) all contentions whose formulation does not require access to SUNSI and/or SGI (+25 Answers to petition for intervention; +7 requestor/petitioner reply). 20............................ U.S. Nuclear Regulatory Commission (NRC) staff informs the requestor of the staff's determination whether the request for access provides a reasonable basis to believe standing can be established and shows (1) need for SUNSI or (2) need to know for SGI. (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). If NRC staff makes the finding of need to know for SGI and likelihood of standing, NRC staff begins background check (including fingerprinting for a criminal history records check), information processing (preparation of redactions or review of redacted documents), and readiness inspections. 25............................ If NRC staff finds no ``need,'' no ``need to know,'' or no likelihood of standing, the deadline for requestor/ petitioner 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. 190........................... (Receipt +180) If NRC staff finds standing, need to know for SGI, and trustworthiness and reliability, deadline for NRC staff to file motion for Protective Order and draft Non- disclosure Affidavit (or to make a determination that the proposed recipient of SGI is not trustworthy or reliable). Note: Before the Office of Administration makes a final adverse determination regarding access to SGI, the proposed recipient must be provided an opportunity to correct or explain information. 205........................... Deadline for petitioner to seek reversal of a final adverse NRC staff trustworthiness or reliability determination under 10 CFR 2.336(f)(1)(iv). A............................. If access granted: Issuance of a decision by a presiding officer or other designated officer 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 and/or SGI consistent with decision issuing the protective order. A + 28........................ Deadline for submission of contentions whose development depends upon access to SUNSI and/or SGI. 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 or SGI contentions by that later deadline. A + 53........................ (Contention receipt +25) Answers to contentions whose development depends upon access to SUNSI and/or SGI. A + 60........................ (Answer receipt +7) Petitioner/ Intervenor reply to answers. >A + 60....................... Decision on contention admission. ------------------------------------------------------------------------ [FR Doc. 2017-20084 Filed 10-2-17; 8:45 am] BILLING CODE 7590-01-P
![46094 Federal Register / Vol. 82, No. 190 / Tuesday, October 3, 2017 / Notices
Foundation (NSF) announces the NUCLEAR REGULATORY see ‘‘Obtaining Information and
following meeting: COMMISSION Submitting Comments’’ in the
Name and Committee Code: SUPPLEMENTARY INFORMATION section of
[NRC–2017–0192]
Astronomy and Astrophysics Advisory this document.
Committee (#13883) meeting Applications and Amendments to FOR FURTHER INFORMATION CONTACT:
(Teleconference). Facility Operating Licenses and Lynn Ronewicz, Office of Nuclear
Combined Licenses Involving Reactor Regulation, U.S. Nuclear
Date and Time: October 23, 2017; 3:00
Proposed No Significant Hazards Regulatory Commission, Washington,
p.m.–4:00 p.m. EDT. Considerations and Containing DC 20555–0001; telephone: 301–415–
Place: National Science Foundation, Sensitive Unclassified Non-Safeguards 1927, email: lynn.ronewicz@nrc.gov.
2415 Eisenhower Avenue, Alexandria, Information and Safeguards SUPPLEMENTARY INFORMATION:
VA 22314 (Teleconference). Information and Order Imposing
Procedures for Access to Sensitive I. Obtaining Information and
Type of Meeting: Open.
Unclassified Non-Safeguards Submitting Comments
http://www.nsf.gov/mps/ast/aaac.jsp Information and Safeguards A. Obtaining Information
To join via Browser: Information
Please refer to Docket ID NRC–2017–
https://bluejeans.com/996692403/ AGENCY: Nuclear Regulatory 0192, facility name, unit number(s),
Commission. plant docket number, application date,
browser
ACTION: License amendment request; and subject when contacting the NRC
To join via phone: opportunity to comment, request a about the availability of information for
(1) Dial: hearing, and petition for leave to this action. You may obtain publicly-
intervene; order imposing procedures. available information related to this
+1.408.740.7256
SUMMARY: The U.S. Nuclear Regulatory action by any of the following methods:
+1.888.240.2560
Commission (NRC) received and is • Federal Rulemaking Web site: Go to
+1.408.317.9253 considering approval of three http://www.regulations.gov and search
(see all numbers—http:// amendment requests. The amendment for Docket ID NRC–2017–0192.
bluejeans.com/numbers) requests are for Hope Creek Generating • NRC’s Agencywide Documents
Station, R.E. Ginna Nuclear Power Access and Management System
(2) Enter Conference ID: 996692403 (ADAMS): You may obtain publicly-
Plant, and Wolf Creek Generating
Contact Person: Dr. Christopher Station. For each amendment request, available documents online in the
Davis, Program Director, Division of the NRC proposes to determine that they ADAMS Public Documents collection at
Astronomical Sciences, Suite W9136, involve no significant hazards http://www.nrc.gov/reading-rm/
National Science Foundation, 2415 consideration. Because the amendment adams.html. To begin the search, select
Eisenhower Avenue, Alexandria, VA requests contain sensitive unclassified ‘‘ADAMS Public Documents’’ and then
22314; Telephone: 703–292–7165. non-safeguards information (SUNSI) select ‘‘Begin Web-based ADAMS
and safeguards information (SGI), an Search.’’ For problems with ADAMS,
Purpose of Meeting: The AAAC order imposes procedures to obtain please contact the NRC’s Public
commissioned a subcommittee to access to SUNSI and SGI for contention Document Room (PDR) reference staff at
develop a concept for implementing a preparation. 1–800–397–4209, 301–415–4737, or by
ground-based Cosmic Microwave DATES: Comments must be filed by email to pdr.resource@nrc.gov. The
Background Stage 4 experiment. The November 2, 2017. A request for a ADAMS accession number for each
Conceptual Design Team (CDT) will hearing must be filed by December 4, document referenced (if it is available in
take as input the community CMB–S4 2017. Any potential party as defined in ADAMS) is provided the first time that
Science Book and any further § 2.4 of title 10 of the Code of Federal it is mentioned in this document.
community information as appropriate, Regulations (10 CFR), who believes • NRC’s PDR: You may examine and
will consider the global landscape of access to SUNSI and/or SGI is necessary purchase copies of public documents at
CMB experiments, and provide a project to respond to this notice must request the NRC’s PDR, Room O1–F21, One
strawman concept with options and document access by October 13, 2017. White Flint North, 11555 Rockville
alternatives. The purpose of the meeting ADDRESSES: You may submit comments Pike, Rockville, Maryland 20852.
is to discuss and accept the by any of the following methods: B. Submitting Comments
subcommittee report. • Federal Rulemaking Web site: Go to
http://www.regulations.gov and search Please include Docket ID NRC–2017–
Agenda: To discuss and accept the 0192, facility name, unit number(s),
for Docket ID NRC–2017–0192. Address
CMB Stage 4 CDT Task Force Report on plant docket number, application date,
questions about NRC dockets to Carol
behalf of NSF and DOE. and subject in your comment
Gallagher; telephone: 301–415–3463;
Dated: September 27, 2017. email: Carol.Gallagher@nrc.gov. For submission.
Crystal Robinson, technical questions, contact the The NRC cautions you not to include
Committee Management Officer. individual listed in the FOR FURTHER identifying or contact information that
asabaliauskas on DSKBBXCHB2PROD with NOTICES
INFORMATION CONTACT section of this you do not want to be publicly
[FR Doc. 2017–21125 Filed 10–2–17; 8:45 am]
document. disclosed in your comment submission.
BILLING CODE 7555–01–P
• Mail comments to: Cindy Bladey, The NRC will post all comment
Office of Administration, Mail Stop: submissions at http://
TWFN–8–D36M, U.S. Nuclear www.regulations.gov, as well as enter
Regulatory Commission, Washington, the comment submissions into ADAMS.
DC 20555–0001. The NRC does not routinely edit
For additional direction on obtaining comment submissions to remove
information and submitting comments, identifying or contact information.
VerDate Sep<11>2014 16:49 Oct 02, 2017 Jkt 244001 PO 00000 Frm 00061 Fmt 4703 Sfmt 4703 E:\FR\FM\03OCN1.SGM 03OCN1](https://thefederalregister.org/doc/82_FR_46284/page/1.svg)
![Federal Register / Vol. 82, No. 190 / Tuesday, October 3, 2017 / Notices 46097
available to the public at https:// 1. Does the proposed amendment involve does not involve a significant increase in the
adams.nrc.gov/ehd, unless excluded a significant increase in the probability or probability or consequences of an accident
pursuant to an order of the Commission consequences of an accident previously previously evaluated.
evaluated? 2. Does the proposed amendment create
or the presiding officer. If you do not
Response: No. the possibility of a new or different kind of
have an NRC-issued digital ID certificate Further consideration of committed accident from any kind of accident
as described above, click cancel when modifications has resulted in the conclusion previously evaluated?
the link requests certificates and you that the modification to install overcurrent Response: No.
will be automatically directed to the protection, Engineering Service Request The original purpose of the overcurrent
NRC’s electronic hearing dockets where (ESR) 12–0141 (i.e., modification), is no protection modifications was to reduce the
you will be able to access any publicly- longer required in the NFPA 805 project fire risk by protecting the EDGs from fire-
available documents in a particular modification scope. The original purpose of induced overcurrent events allowing local
hearing docket. Participants are the overcurrent protection modifications was recovery of the EDGs. Several alternative
to reduce fire risk by protecting the means will be made available to provide the
requested not to include personal
emergency diesel generations (EDGs) from power for decay heat removal, RCS inventory
privacy information, such as social fire-induced overcurrent events allowing and reactivity control, as well as providing
security numbers, home addresses, or local recovery of the EDGs. Several power to the vital battery chargers, long-term
personal phone numbers in their filings, alternative means will be made available to indication and control power, and breaker
unless an NRC regulation or other law provide the power for decay heat removal, control in lieu of ESR–12–0141. Operation of
requires submission of such RCS [reactor coolant system] inventory and Ginna in accordance with the proposed
information. For example, in some reactivity control, as well as providing power amendment does not create the possibility of
instances, individuals provide home to the vital battery chargers, long-term a new or different kind of accident from any
addresses in order to demonstrate indication and control power, and breaker accident previously evaluated. The proposed
control. change does not alter the requirements or
proximity to a facility or site. With
Operation of Ginna in accordance with the functions for systems required during
respect to copyrighted works, except for proposed amendment does not increase the accident conditions. Implementation of this
limited excerpts that serve the purpose probability or consequences of accidents change will not result in new or different
of the adjudicatory filings and would previously evaluated. Engineering analyses, accidents.
constitute a Fair Use application, which may include engineering evaluations, The proposed amendment does not
participants are requested not to include probabilistic safety assessments, and fire introduce new or different accident initiators,
copyrighted materials in their modeling calculations, have been performed nor does it alter design assumptions,
submission. to demonstrate that the performance-based conditions, or configurations of the facility in
requirements of NFPA 805 have been such a manner as to introduce new or
Exelon Generation Company, LLC, satisfied with the elimination of fire-induced different accident initiators. The proposed
Docket No. 50–244, R.E. Ginna Nuclear overcurrent protection. The proposed amendment does not adversely affect the
Power Plant (Ginna), Wayne County, amendment does not affect accident ability of structures, systems, or components
New York initiators, nor does it alter design to perform their design function. Structures,
assumptions, conditions, or configurations of systems, or components required to safely
Date of amendment request: June 30, the facility that would increase the shutdown the reactor and maintain it in a
2017. A publicly-available version is in probability of accidents previously evaluated. safe shutdown condition remain capable of
ADAMS under Accession No. Further, the changes to be made for fire performing their design functions.
ML17186A233. hazard protection and mitigation do not The requirements of NFPA 805 address
Description of amendment request: adversely affect the ability of structures, only fire protection and the impacts of fire
This amendment request contains systems, or components to perform their on the plant that have previously been
safeguards information (SGI). The design functions for accident mitigation, nor evaluated. Thus, implementation of the
amendment would revise the do they affect the postulated initiators or proposed amendment would not create the
modification to install overcurrent assumed failure models for accidents possibility of a new or different kind of
protection for the emergency diesel described and evaluated in the UFSAR accident beyond those already analyzed in
[Updated Final Safety Analysis Report]. the UFSAR. No new accident scenarios,
generators associated with the
Structures, systems, or components required transient precursors, failure mechanisms, or
implementation of 10 CFR 50.48(c), to safely shutdown the reactor and to limiting single failures will be introduced,
National Fire Protection Association maintain it in a safe shutdown condition will and there will be no adverse effect or
Standard 805 (NFPA 805), remain capable of performing their design challenges imposed on any safety-related
‘‘Performance-Based Standard for Fire functions. system as a result of the proposed
Protection for Light-Water Reactor The proposed amendment will not affect amendment.
Electric Generating Plants,’’ 2001 the source term, containment isolation, or Based on the above discussion, it is
Edition. The amendment would also radiological release assumptions used in concluded that the proposed amendment
update Attachment C, ‘‘NEI 04–02 Table evaluating the radiological consequences of does not create the possibility of a new or
B–3 Fire Area Transition’’; Attachment any accident previously evaluated, and different kind of accident from any accident
equipment required to mitigate an accident previously evaluated.
G, ‘‘Recovery Actions Transition’’; remains capable of performing the assumed 3. Does the proposed amendment involve
Attachment M, ‘‘License Condition function(s). The applicable radiological dose a significant reduction in the margin of
Changes’’; Attachment S, criteria will continue to be met. safety?
‘‘Modifications and Implementation The combination of all the proposed Response: No.
Items’’; and Attachment W, ‘‘Fire PRA modifications and data updates reduces the The purpose of the proposed amendment
[Probabilistic Risk Assessment] overall calculated delta risk relative to the is to permit Ginna to adopt a new fire
previously submitted information even with protection licensing basis which complies
asabaliauskas on DSKBBXCHB2PROD with NOTICES
Insights,’’ of the previously approved
NFPA 805 amendment. the removal of the fire-induced overcurrent with the requirements in 10 CFR 50.48(a) and
Basis for proposed no significant modifications. The net Core Damage (c) and the guidance in Regulatory Guide
Frequency (CDF) delta risk including the 1.205, Revision 1. The NRC considers that
hazards consideration determination:
internal events offset is 4E–6. The net Large NFPA 805 provides an acceptable
As required by 10 CFR 50.91(a), the Early Release Frequency (LERF) delta risk methodology and performance criteria for
licensee has provided its analysis of the including the internal events offset is less licensees to identify fire protection systems
issue of no significant hazards than 1E–7. and features that are an acceptable alternative
consideration, which is presented Based on the above discussion, it is to the 10 CFR 50, Appendix R required fire
below: concluded that the proposed amendment protection features (69 FR 33536; June 16,
VerDate Sep<11>2014 16:49 Oct 02, 2017 Jkt 244001 PO 00000 Frm 00064 Fmt 4703 Sfmt 4703 E:\FR\FM\03OCN1.SGM 03OCN1](https://thefederalregister.org/doc/82_FR_46284/page/4.svg)
![Federal Register / Vol. 82, No. 190 / Tuesday, October 3, 2017 / Notices 46099
standards of 10 CFR 50.92(c) are providing adequate area cooling for both kind of accident from any accident
satisfied. Therefore, the NRC staff trains of Class 1E electrical equipment during previously evaluated.
proposes to determine that the normal and accident conditions (with 3. Does the proposed amendment involve
mitigating actions being required). a significant reduction in a margin of safety?
amendment request involves no
Overall protection system performance will Response: No.
significant hazards consideration. remain within the bounds of the previously The proposed specification allows for a
Attorney for licensee: Jeffrie J. Keenan, performed accident analyses since no period of time in which one Class 1E
PSEG Nuclear LLC—N21, P.O. Box 236, hardware changes are proposed to the electrical equipment A/C train is capable of
Hancocks Bridge, New Jersey 08038. protection systems. The same Reactor Trip providing adequate area cooling for both
NRC Branch Chief: James G. Danna. System (RTS) and Engineered Safety Feature trains of Class 1E electrical equipment during
Actuation System (ESFAS) instrumentation normal and accident conditions (with
Wolf Creek Nuclear Operating will continue to be used. The protection mitigating actions being required). The
Corporation, Docket No. 50–482, Wolf systems will continue to function in a proposed change does not impact accident
Creek Generating Station, (WCGS) manner consistent with the plant design offsite dose, containment pressure or
Coffey County, Kansas basis. The proposed change will not temperature, Emergency Core Cooling System
adversely affect accident initiators or settings or Reactor Protection System
Date of amendment request: June 28,
precursors nor adversely alter the design settings, or any other parameter that could
2017. A publicly-available version is in assumptions and conditions of the facility or affect a margin of safety. The margin of safety
ADAMS under Accession No. the manner in which the plant is operated is enhanced by periodically verifying the area
ML17186A082. and maintained with respect to such room temperatures are maintained within
Description of amendment request: initiators or precursors. limit while one Class 1E electrical equipment
This amendment request contains The proposed change will not alter or A/C train is inoperable and allowing a
sensitive unclassified non-safeguards prevent the capability of structures, systems, reasonable period to perform preventive and
information (SUNSI). The amendment and components (SSCs) to perform their corrective maintenance thus increasing
would add new Technical Specification intended functions for mitigating the system reliability.
(TS) 3.7.20, ‘‘Class 1E Electrical consequences of an accident and meeting Therefore, the proposed change does not
applicable acceptance limits. involve a significant reduction in a margin of
Equipment Air Conditioning (A/C) Therefore, the proposed change does not
System,’’ to the WCGS TSs. New TS safety.
involve a significant increase in the
3.7.20 would include the limiting probability or consequences of an accident The NRC staff has reviewed the
condition for operation (LCO) statement, previously evaluated. licensee’s analysis and, based on this
Applicability during which the LCO 2. Does the proposed amendment create review, it appears that the three
must be met, ACTIONS (with the possibility of a new or different kind of standards of 10 CFR 50.92(c) are
Conditions, Required Actions, and accident from any accident previously satisfied. Therefore, the NRC staff
Completion Times) to be applied when evaluated?
proposes to determine that the
the LCO is not met, and Surveillance Response: No.
No new accident scenarios, transient amendment request involves no
Requirements (SRs) with a specified precursors, failure mechanisms, or limiting significant hazards consideration.
Frequency to demonstrate that the LCO single failures will be introduced as a result Attorney for licensee: Jay Silberg, Esq.,
is met for the Class 1 E Electrical of this amendment. No new or different Pillsbury Winthrop Shaw Pittman LLP,
Equipment A/C System trains at WCGS. accidents result from addition of the 2300 N Street NW., Washington, DC
Additionally, the Table of Contents proposed specification. The Class 1E 20037.
would also be revised to reflect the electrical equipment A/C trains maintain the
NRC Branch Chief: Robert J.
incorporation of new TS 3.7.20. capability to perform their specified safety
function. The proposed license amendment Pascarelli.
Basis for proposed no significant
hazards consideration determination: includes regulatory commitments to achieve Order Imposing Procedures for Access
As required by 10 CFR 50.91(a), the the capability for one OPERABLE Class 1E to Sensitive Unclassified Non-
electrical equipment A/C train to provide
licensee has provided its analysis of the Safeguards Information and Safeguards
adequate cooling for both trains of electrical
issue of no significant hazards equipment during normal and accident Information for Contention Preparation
consideration, which is presented conditions by design changes. [The planned PSEG Nuclear LLC, Docket No. 50–354,
below: modifications proposed by regulatory Hope Creek Generating Station,
1. Does the proposed amendment involve commitments will be implemented under the
Hancocks Bridge, New Jersey
a significant increase in the probability or requirements of 10 CFR 50.59.]
consequences of an accident previously The proposed amendment will not alter the Exelon Generation Company, LLC,
evaluated? design or performance of the 7300 Process Docket No. 50–244, R. E. Ginna Nuclear
Response: No. Protection System, Nuclear Instrumentation Power Plant, Wayne County, New York
The proposed addition of TS 3.7.20 creates System, Solid State Protection System,
a[n] LCO for the Class 1E Electrical Balance of Plant Engineered Safety Features Wolf Creek Nuclear Operating
Equipment A/C System that is required to Actuation System, Main Steam and Corporation, Docket No. 50–482, Wolf
support the TS Class 1E electrical equipment. Feedwater Isolation System, or Load Shedder Creek Generating Station, Coffey
The 30 day Completion Time to restore an and Emergency Load Sequencers used in the County, Kansas
inoperable Class 1E electrical equipment A/ plant protection systems.
C train to OPERABLE status is consistent The proposed change adds requirements in A. This Order contains instructions
with the Control Room Air Conditioning the TSs that were previously located in plant regarding how potential parties to this
System (CRACS) and is supported by a plant procedures. One OPERABLE Class 1E proceeding may request access to
electrical equipment A/C train is capable of
asabaliauskas on DSKBBXCHB2PROD with NOTICES
specific calculation. The Class 1E Electrical documents containing sensitive
Equipment A/C Systems’ actuation, providing adequate area cooling for both unclassified information (including
operation, or failure is not an initiator to any trains of Class 1E electrical equipment during Sensitive Unclassified Non-Safeguards
accident previously evaluated. As a result, normal and accident conditions (with
Information (SUNSI) and Safeguards
the probability of an accident previously mitigating actions being required). The
evaluated is not significantly increased. change does not have a detrimental impact Information (SGI)). Requirements for
Conversely, the proposed change provides a on the manner in which plant equipment access to SGI are primarily set forth in
period of time to recover an unexpected loss operates or responds to an actuation signal. 10 CFR parts 2 and 73. Nothing in this
of cooling capability with one OPERABLE Therefore, the proposed change will not Order is intended to conflict with the
Class 1E electrical equipment A/C train create the possibility of a new or different SGI regulations.
VerDate Sep<11>2014 16:49 Oct 02, 2017 Jkt 244001 PO 00000 Frm 00066 Fmt 4703 Sfmt 4703 E:\FR\FM\03OCN1.SGM 03OCN1](https://thefederalregister.org/doc/82_FR_46284/page/6.svg)
![46102 Federal Register / Vol. 82, No. 190 / Tuesday, October 3, 2017 / Notices
ATTACHMENT 1—GENERAL TARGET SCHEDULE FOR PROCESSING AND RESOLVING REQUESTS FOR ACCESS TO SENSITIVE
UNCLASSIFIED NON-SAFEGUARDS INFORMATION AND 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) and/or Safeguards Information (SGI)
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; demonstrating that access should be granted (e.g., showing
technical competence for access to SGI); and, for SGI, including application fee for fingerprint/background check.
60 .......................... Deadline for submitting petition for intervention containing: (i) Demonstration of standing; (ii) all contentions whose formulation does not require
access to SUNSI and/or SGI (+25 Answers to petition for intervention; +7 requestor/petitioner reply).
20 .......................... U.S. Nuclear Regulatory Commission (NRC) staff informs the requestor of the staff’s determination whether the request for access provides a
reasonable basis to believe standing can be established and shows (1) need for SUNSI or (2) need to know for SGI. (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). If NRC staff makes the finding of need to know for SGI and likelihood of standing, NRC staff begins back-
ground check (including fingerprinting for a criminal history records check), information processing (preparation of redactions or review of re-
dacted documents), and readiness inspections.
25 .......................... If NRC staff finds no ‘‘need,’’ no ‘‘need to know,’’ or no likelihood of standing, the deadline for requestor/petitioner to file a motion seeking a rul-
ing 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 in-
terest 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.
190 ........................ (Receipt +180) If NRC staff finds standing, need to know for SGI, and trustworthiness and reliability, deadline for NRC staff to file motion for
Protective Order and draft Non-disclosure Affidavit (or to make a determination that the proposed recipient of SGI is not trustworthy or reli-
able). Note: Before the Office of Administration makes a final adverse determination regarding access to SGI, the proposed recipient must be
provided an opportunity to correct or explain information.
205 ........................ Deadline for petitioner to seek reversal of a final adverse NRC staff trustworthiness or reliability determination under 10 CFR 2.336(f)(1)(iv).
A ........................... If access granted: Issuance of a decision by a presiding officer or other designated officer 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 and/or SGI consistent with decision issuing the protective
order.
A + 28 ................... Deadline for submission of contentions whose development depends upon access to SUNSI and/or SGI. 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 or SGI contentions by that later dead-
line.
A + 53 ................... (Contention receipt +25) Answers to contentions whose development depends upon access to SUNSI and/or SGI.
A + 60 ................... (Answer receipt +7) Petitioner/Intervenor reply to answers.
>A + 60 ................. Decision on contention admission.
[FR Doc. 2017–20084 Filed 10–2–17; 8:45 am] policies and practices. The document is adams.html. To begin the search, select
BILLING CODE 7590–01–P intended for use by applicants, ‘‘ADAMS Public Documents’’ and then
licensees, and the NRC staff. select ‘‘Begin Web-based ADAMS
DATES: NUREG 1556, Volume 18, Search.’’ For problems with ADAMS,
NUCLEAR REGULATORY Revision 1 was published in August please contact the NRC’s Public
COMMISSION 2017. Document Room (PDR) reference staff at
[NRC–2014–0124] 1–800–397–4209, 301–415–4737, or by
ADDRESSES: Please refer to Docket ID
email to pdr.resource@nrc.gov. The
NRC–2014–0124 when contacting the
Consolidated Guidance About NUREG–1556, Volume 18, Revision 1 is
NRC about the availability of
Materials Licenses: Program-Specific available in ADAMS under Accession
information regarding this document.
Guidance About Service Provider No. ML17242A055.
You may obtain publicly-available
Licenses information related to this document • NRC’s PDR: You may examine and
using any of the following methods: purchase copies of public documents at
AGENCY: Nuclear Regulatory the NRC’s PDR, Room O1–F21, One
Commission. • Federal Rulemaking Web site: Go to
http://www.regulations.gov and search White Flint North, 11555 Rockville
ACTION: NUREG; issuance. Pike, Rockville, Maryland 20852.
for Docket ID NRC–2014–0124. Address
SUMMARY: The U.S. Nuclear Regulatory questions about NRC dockets to Carol This NUREG–1556 volume is also
Commission (NRC) has issued Revision Gallagher; telephone: 301–415–3463; available on the NRC’s public Web site
1 to NUREG–1556, Volume 18, email: Carol.Gallagher@nrc.gov. For at http://www.nrc.gov/reading-rm/doc-
‘‘Consolidated Guidance about Materials technical questions, contact the collections/nuregs/staff/sr1556/ under
‘‘Consolidated Guidance About
asabaliauskas on DSKBBXCHB2PROD with NOTICES
Licenses: Program-Specific Guidance individual listed in the FOR FURTHER
about Service Provider Licenses,’’ which INFORMATION CONTACT section of this Materials Licenses (NUREG–1556).’’
updates licensing guidance for service document. FOR FURTHER INFORMATION CONTACT:
provider licenses. This document has • NRC’s Agencywide Documents Anthony McMurtray, Office of Nuclear
been revised to include information on Access and Management System Material Safety and Safeguards; U.S.
updated regulatory requirements, safety (ADAMS): You may obtain publicly- Nuclear Regulatory Commission,
culture, security of radioactive available documents online in the Washington, DC 20555–0001; telephone:
materials, protection of sensitive ADAMS Public Documents collection at 301–415–2746; email:
information, and changes in regulatory http://www.nrc.gov/reading-rm/ Anthony.McMurtray@nrc.gov.
VerDate Sep<11>2014 16:49 Oct 02, 2017 Jkt 244001 PO 00000 Frm 00069 Fmt 4703 Sfmt 4703 E:\FR\FM\03OCN1.SGM 03OCN1](https://thefederalregister.org/doc/82_FR_46284/page/9.svg)
Document Created: 2017-10-03 01:01:45
Document Modified: 2017-10-03 01:01:45
| 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; opportunity to comment, request a hearing, and petition for leave to intervene; order imposing procedures. | |
| Dates | Comments must be filed by November 2, 2017. A request for a hearing must be filed by December 4, 2017. 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 and/or SGI is necessary to respond to this notice must request document access by October 13, 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 46094 |
2025 Federal Register | Disclaimer | Privacy Policy
USC | CFR | eCFR