Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Considerations and Containing Sensitive Unclassified Non-Safeguards Information and Order Imposing Procedures for Access to Sensitive Unclassified Non-Safeguards Information
Federal Register, Volume 77 Issue 214 (Monday, November 5, 2012)
Federal Register Volume 77, Number 214 (Monday, November 5, 2012)
Notices
Pages 66486-66492
From the Federal Register Online via the Government Printing Office www.gpo.gov
FR Doc No: 2012-26762
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NUCLEAR REGULATORY COMMISSION
NRC-2012-0259
Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Considerations and Containing Sensitive Unclassified Non-Safeguards Information and Order Imposing Procedures for Access to Sensitive Unclassified Non-Safeguards Information
AGENCY: Nuclear Regulatory Commission.
ACTION: License amendment request, opportunity to comment, and opportunity to request a hearing, order.
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DATES: Comments must be filed by December 5, 2012. A request for a hearing must be filed by January 4, 2013. Any potential party as defined in section 2.4 of Title of the Code of Federal Regulations (10 CFR), who believes access to Sensitive Unclassified Non-Safeguards Information (SUNSI) is necessary to respond to this notice must request document access by November 15, 2012.
ADDRESSES: You may access information and comment submissions related to this document, which the NRC possesses and are publicly available, by searching on http://www.regulations.gov under Docket ID NRC-2012-
0259. 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-2012-0259. Address questions about NRC dockets to Carol Gallagher; telephone: 301-492-
3668; email: Carol.Gallagher@nrc.gov.
Mail comments to: Cindy Bladey, Chief, Rules, Announcements, and Directives Branch (RADB), Office of Administration, Mail Stop: TWB-05-B01M, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001.
Fax comments to: RADB at 301-492-3446.
For additional direction on accessing information and submitting comments, see ``Accessing Information and Submitting Comments'' in the SUPPLEMENTARY INFORMATION section of this document.
SUPPLEMENTARY INFORMATION:
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Accessing Information and Submitting Comments
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Accessing Information
Please refer to Docket ID NRC-2012-0259 when contacting the NRC about the availability of information regarding this document. You may access information related to this document, which the NRC possesses and is publicly available, by the following methods:
Federal Rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2012-0259.
NRC's Agencywide Documents Access and Management System (ADAMS): You may access publicly available documents online in the NRC Library 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 pdr.resource@nrc.gov. The ADAMS accession number for each document referenced in this notice (if that document is available in ADAMS) is provided the first time that a document is referenced.
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.
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Submitting Comments
Please include Docket ID NRC-2012-0259 in the subject line of your comment submission, in order to ensure that the NRC is able to make your comment submission available to the public in this docket.
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 entering the comment submissions into ADAMS. The NRC does not routinely edit comment submissions to remove identifying or contact information.
If you are requesting or aggregating comments from other persons for submission to the NRC, then you should inform those persons not to include identifying or contact information that they do not want to be publicly disclosed in their comment submission. Your request should state that the NRC does not routinely edit comment submissions to remove such information before making the comment submissions available to the public or entering the comment submissions into ADAMS.
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Background
Pursuant to Section 189a.(2) of the Atomic Energy Act of 1954, as amended
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(the Act), the U.S. Nuclear Regulatory Commission (the Commission or NRC staff) is publishing this notice. The Act requires the Commission 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.
Notice of Consideration of Issuance of Amendments to Facility Operating Licenses and Combined Licenses, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing
The Commission has made a proposed determination that the following amendment requests involve no significant hazards consideration. Under the Commission's regulations in 10 CFR 50.92, this means that operation of the facility in accordance with the proposed amendment would not (1) involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety. The basis for this proposed determination for each amendment request is shown below.
The Commission is seeking public comments on this proposed determination. Any comments received within 30 days after the date of publication of this notice will be considered in making any final determination.
Normally, the Commission will not issue the amendment until the expiration of 60 days after the date of publication of this notice. The Commission may issue the license amendment before expiration of the 60-
day period provided that its final determination is that the amendment involves no significant hazards consideration. In addition, the Commission may issue the amendment prior to the expiration of the 30-
day comment period should circumstances change during the 30-day comment period such that failure to act in a timely way would result, for example in derating or shutdown of the facility. Should the Commission take action prior to the expiration of either the comment period or the notice period, it will publish in the Federal Register a notice of issuance. Should the Commission make a final No Significant Hazards Consideration Determination, any hearing will take place after issuance. The Commission expects that the need to take this action will occur very infrequently.
Within 60 days after the date of publication of this notice, any person(s) whose interest may be affected by this action may file a request for a hearing and a petition to intervene with respect to issuance of the amendment to the subject facility operating license or combined license. Requests for a hearing and a petition for leave to intervene shall be filed in accordance with the Commission's ``Rules of Practice for Domestic Licensing Proceedings'' in 10 CFR Part 2. Interested person(s) should consult a current copy of 10 CFR 2.309, which is available at the NRC's PDR, located at One White Flint North, Room O1-F21, 11555 Rockville Pike (first floor), Rockville, Maryland 20852. The NRC regulations are accessible electronically from the NRC Library on the NRC's Web site at http://www.nrc.gov/reading-rm/doc-collections/cfr/. If a request for a hearing or petition for leave to intervene is filed within 60 days, the Commission or a presiding officer designated by the Commission or by the Chief Administrative Judge of the Atomic Safety and Licensing Board Panel, will rule on the request and/or petition; and the Secretary or the Chief Administrative Judge of the Atomic Safety and Licensing Board will issue a notice of a hearing or an appropriate order.
As required by 10 CFR 2.309, a petition for leave to intervene shall set forth with particularity the interest of the petitioner in the proceeding, and how that interest may be affected by the results of the proceeding. The petition should specifically explain the reasons why intervention should be permitted with particular reference to the following general requirements: (1) The name, address, and telephone number of the requestor or petitioner; (2) the nature of the requestor's/petitioner's right under the Act to be made a party to the proceeding; (3) the nature and extent of the requestor's/petitioner's property, financial, or other interest in the proceeding; and (4) the possible effect of any decision or order which may be entered in the proceeding on the requestor's/petitioner's interest. The petition must also set forth the specific contentions which the requestor/petitioner seeks to have litigated at the proceeding.
Each contention must consist of a specific statement of the issue of law or fact to be raised or controverted. In addition, the requestor/petitioner shall provide a brief explanation of the bases for the contention and a concise statement of the alleged facts or expert opinion which support the contention and on which the requestor/
petitioner intends to rely in proving the contention at the hearing. The requestor/petitioner must also provide references to those specific sources and documents of which the petitioner is aware and on which the requestor/petitioner intends to rely to establish those facts or expert opinion. The petition must include sufficient information to show that a genuine dispute exists with the applicant on a material issue of law or fact. Contentions shall be limited to matters within the scope of the amendment under consideration. The contention must be one which, if proven, would entitle the requestor/petitioner to relief. A requestor/
petitioner who fails to satisfy these requirements with respect to at least one contention will not be permitted to participate as a party.
Those permitted to intervene become parties to the proceeding, subject to any limitations in the order granting leave to intervene, and have the opportunity to participate fully in the conduct of the hearing.
If a hearing is requested, and the Commission has not made a final determination on the issue of no significant hazards consideration, the Commission will make a final determination on the issue of no significant hazards consideration. The final determination will serve to decide when the hearing is held. If the final determination is that the amendment request involves no significant hazards consideration, the Commission may issue the amendment and make it immediately effective, notwithstanding the request for a hearing. Any hearing held would take place after issuance of the amendment. If the final determination is that the amendment request involves a significant hazards consideration, then any hearing held would take place before the issuance of any amendment.
All documents filed in the NRC adjudicatory proceedings, including a request for hearing, a petition for leave to intervene, any motion or other document filed in the proceeding prior to the submission of a request for hearing or petition to intervene, and documents filed by interested governmental entities participating under 10 CFR 2.315(c), must be filed in accordance with the NRC's E-Filing rule
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(72 FR 49139; August 28, 2007). The E-Filing process requires participants to submit and serve all adjudicatory documents over the internet, or in some cases to mail copies on electronic storage media. Participants may not submit paper copies of their filings unless they seek an exemption in accordance with the procedures described below.
To comply with the procedural requirements of E-Filing, at least 10 days prior to the filing deadline, the participant should contact the Office of the Secretary by email at hearing.docket@nrc.gov, or by telephone at 301-415-1677, to request (1) a digital identification (ID) certificate, which allows the participant (or its counsel or representative) to digitally sign documents and access the E-Submittal server for any proceeding in which it is participating; and (2) advise the Secretary that the participant will be submitting a request or petition for hearing (even in instances in which the participant, or its counsel or representative, already holds an NRC-issued digital ID certificate). Based upon this information, the Secretary will establish an electronic docket for the hearing in this proceeding if the Secretary has not already established an electronic docket.
Information about applying for a digital ID certificate is available on the NRC's public Web site at http://www.nrc.gov/site-help/e-submittals/apply-certificates.html. System requirements for accessing the E-Submittal server are detailed in the NRC's ``Guidance for Electronic Submission,'' which is available on the agency's public Web site at http://www.nrc.gov/site-help/e-submittals.html. Participants may attempt to use other software not listed on the Web site, but should note that the NRC's E-Filing system does not support unlisted software, and the NRC Meta System Help Desk will not be able to offer assistance in using unlisted software.
If a participant is electronically submitting a document to the NRC in accordance with the E-Filing rule, the participant must file the document using the NRC's online, Web-based submission form. In order to serve documents through the Electronic Information Exchange System, users will be required to install a Web browser plug-in from the NRC's Web site. Further information on the Web-based submission form, including the installation of the Web browser plug-in, is available on the NRC's public Web site at http://www.nrc.gov/site-help/e-submittals.html.
Once a participant has obtained a digital ID certificate and a docket has been created, the participant can then submit a request for hearing or petition for leave to intervene. Submissions should be in Portable Document Format (PDF) in accordance with the NRC guidance available on the NRC's public Web site at http://www.nrc.gov/site-help/e-submittals.html. A filing is considered complete at the time the documents are submitted through the NRC's E-Filing system. To be timely, an electronic filing must be submitted to the E-Filing system no later than 11:59 p.m. Eastern Time on the due date. Upon receipt of a transmission, the E-Filing system time-stamps the document and sends the submitter an email notice confirming receipt of the document. The E-Filing system also distributes an email notice that provides access to the document to the NRC's Office of the General Counsel and any others who have advised the Office of the Secretary that they wish to participate in the proceeding, so that the filer need not serve the documents on those participants separately. Therefore, applicants and other participants (or their counsel or representative) must apply for and receive a digital ID certificate before a hearing request/petition to intervene is filed so that they can obtain access to the document via the E-Filing system.
A person filing electronically using the agency's adjudicatory E-
Filing system may seek assistance by contacting the NRC Meta System Help Desk through the ``Contact Us'' link located on the NRC's Web site at http://www.nrc.gov/site-help/e-submittals.html, by email at MSHD.Resource@nrc.gov, or by a toll-free call at 1-866-672-7640. The NRC Meta System Help Desk is available between 8 a.m. and 8 p.m., Eastern Time, Monday through Friday, excluding government holidays.
Participants who believe that they have a good cause for not submitting documents electronically must file an exemption request, in accordance with 10 CFR 2.302(g), with their initial paper filing requesting authorization to continue to submit documents in paper format. Such filings must be submitted by: (1) First class mail addressed to the Office of the Secretary of the Commission, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, Attention: Rulemaking and Adjudications Staff; or (2) courier, express mail, or expedited delivery service to the Office of the Secretary, Sixteenth Floor, One White Flint North, 11555 Rockville Pike, Rockville, Maryland, 20852, Attention: Rulemaking and Adjudications Staff. Participants filing a document in this manner are responsible for serving the document on all other participants. Filing is considered complete by first-class mail as of the time of deposit in the mail, or by courier, express mail, or expedited delivery service upon depositing the document with the provider of the service. A presiding officer, having granted an exemption request from using E-Filing, may require a participant or party to use E-Filing if the presiding officer subsequently determines that the reason for granting the exemption from use of E-Filing no longer exists.
Documents submitted in adjudicatory proceedings will appear in NRC's electronic hearing docket which is available to the public at http://ehd1.nrc.gov/ehd/, unless excluded pursuant to an order of the Commission, or the presiding officer. Participants are requested not to include personal privacy information, such as social security numbers, home addresses, or home phone numbers in their filings, unless an NRC regulation or other law requires submission of such information. With respect to copyrighted works, except for limited excerpts that serve the purpose of the adjudicatory filings and would constitute a Fair Use application, participants are requested not to include copyrighted materials in their submission.
Petitions for leave to intervene must be filed no later than 60 days from the date of publication of this notice. Requests for hearing, petitions for leave to intervene, and motions for leave to file new or amended contentions that are filed after the 60-day deadline will not be entertained absent a determination by the presiding officer that the filing demonstrates good cause by satisfying the following three factors in 10 CFR 2.309(c)(1): (i) The information upon which the filing is based was not previously available; (ii) the information upon which the filing is based is materially different from information previously available; and (iii) the filing has been submitted in a timely fashion based on the availability of the subsequent information.
For further details with respect to this amendment action, see the application for amendment which is available for public inspection at the NRC's PDR, located at One White Flint North, Room O1-F21, 11555 Rockville Pike (first floor), Rockville, Maryland 20852. Publicly available documents created or received at the NRC are accessible electronically through ADAMS in the NRC Library at http://www.nrc.gov/
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reading-rm/adams.html. If you do not have access to ADAMS or if there are problems in accessing the documents located in ADAMS, contact the PDR's Reference staff at 1-800-397-4209, 301-415-4737, or by email to pdr.resource@nrc.gov.
Exelon Generation Company, LLC, Docket No. 50-374, LaSalle County Station (LSCS), Unit 2, LaSalle County, Illinois
Date of amendment request: October 11, 2012. A publicly available version is in ADAMS under Accession No. ML12285A387.
Description of amendment request: This amendment request contains sensitive unclassified non-safeguards information (SUNSI). The proposed amendment would revise Technical Specifications (TS) Section 2.1.1, ``Reactor Core SLs Safety Limits,'' to reflect an increase of: 1) The two-recirculation loop minimum critical power ratio (MCPR) SL from >= 1.11 to >= 1.14 and, 2) an increase in the single recirculation loop MCPR SL from >= 1.12 to >= 1.17. The change is required to support the LSCS, Unit 2, Cycle 15, operation. Cycle 15 will be the first cycle of operation with a mixed core containing the following fuel types: Global Nuclear Fuel (GNF) 2 fuel, and Areva ATRIUM-10 fuel.
Basis for proposed no significant hazards consideration determination: In support of the no significant hazards consideration determination, an evaluation of each of the criteria set forth in 10 CFR 50.92, ``Issuance of Amendment'' is provided below:
1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No.
The MCPR SL is defined in the TS Bases Section B 2.1.1 as that limit ``that, in the event of an AOO Anticipated Operational Occurrence from the limiting condition of operation, at least 99.9% of the fuel rods in the core would be expected to avoid boiling transition.'' The MCPR SL satisfies the requirements of General Design Criterion 10 of Appendix A to 10 CFR Part 50 regarding acceptable fuel design limits. The MCPR SL is reevaluated for each reload using NRC-approved methodologies. The analyses for LSCS, Unit 2, Cycle 15 have concluded that a two-loop MCPR SL of >= 1.14, based on the application of GNF's NRC-approved MCPR SL methodology, will ensure that this acceptance criterion is met. For single-loop operation, a MCPR SL of >= 1.17 also ensures that this acceptance criterion is met. The MCPR operating limits are presented and controlled in accordance with the LSCS, Unit 2, Core Operating Limits Report (COLR).
The requested TS changes do not involve any plant modifications or operational changes that could affect system reliability or performance, or that could affect the probability of operator error. The requested changes do not affect any postulated accident precursors, do not affect any accident mitigating systems, and do not introduce any new accident initiation mechanisms.
Therefore, the changes to the MCPR SL do not involve a significant increase in the probability or consequences of any accident previously evaluated.
2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No.
The GNF2 fuel to be used in Cycle 15 is of a design compatible with the co-resident Areva ATRIUM-10 fuel. Therefore, the introduction of GNF2 fuel into the Cycle 15 core will not create the possibility of a new or different kind of accident. The proposed change does not involve any new modes of operation, any changes to setpoints, or any plant modifications. The proposed revised MCPR SLs have accounted for the mixed fuel core and have been shown to be acceptable for Cycle 15 operation. Compliance with the criterion for incipient boiling transition continues to be ensured. The core operating limits will continue to be developed using NRC approved methods which also account for the mixed fuel core design. The proposed MCPR SLs or methods for establishing the core operating limits do not result in the creation of any new precursors to an accident.
Therefore, this change does not create the possibility of a new or different kind of accident from any previously evaluated.
3. Does the proposed change involve a significant reduction in a margin of safety?
Response: No.
The MCPR SLs have been evaluated in accordance with GNF's NRC-
approved cycle-specific limit methodology to ensure that during normal operation and during AOO's at least 99.9% of the fuel rods in the core are not expected to experience transition boiling. The proposed revised MCPR SLs have accounted for the mixed fuel core and have been shown to be acceptable for Cycle 15 operation. Compliance with the criterion for incipient boiling transition continues to be ensured. On this basis, the implementation of the change to the MCPR SLs does not involve a significant reduction in a margin of safety.
Therefore, the proposed change does not involve a significant reduction in a margin of safety.
The NRC staff has reviewed the licensee's analysis and, based on this review, it appears that the three standards of 10 CFR 50.92(c) are satisfied. Therefore, the NRC staff proposes to determine that the requested amendments involve no significant hazards consideration.
Attorney for licensee: Ms. Tamra Domeyer, Associate General Counsel, Exelon Nuclear, 4300 Winfield Road, Warrenville, IL 60555.
NRC Acting Branch Chief: Michael I. Dudek.
Nebraska Public Power District, Docket No. 50-298, Cooper Nuclear Station, Nemaha County, Nebraska
Date of amendment request: May 30, 2012, as supplemented by letter dated October 3, 2012. Public versions of the May 30 and October 3, 2012, letters are available in ADAMS under Accession Nos. ML121570406 and ML12285A356, respectively.
Description of amendment request: This amendment request contains sensitive unclassified non-safeguards information (SUNSI). This amendment request was originally noticed on August 7, 2012 (77 FR 47127); however, it is being re-noticed because the original notice did not provide information about accessing SUNSI information or include the Order Imposing Procedures for Access to Sensitive Unclassified Non-
Safeguards Information for Contention Preparation. The proposed amendment would revise Technical Specification Section 2.0, ``Safety Limits.'' Specifically, the proposed amendment would revise two recirculation loop and single recirculation loop Safety Limit Minimum Critical Power Ratio (SLMCPR) values to reflect results of a cycle-
specific calculation.
Basis for proposed no significant hazards consideration determination: As required by 10 CFR 50.91(a), the licensee has provided its analysis of the issue of no significant hazards consideration, which is presented below:
1. Do the proposed changes involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No.
Four accidents have been evaluated previously as reflected in the CNS Cooper Nuclear Station Updated Safety Analysis Report (USAR). These four accidents are (1) loss-of-coolant, (2) control rod drop, (3) main steam line break, and (4) fuel handling. The probability of an evaluated accident is derived from the probabilities of the individual precursors to that accident. Changing the SLMCPR values does not increase the probability of an evaluated accident. The change does not require any physical modifications to the plant or any components, nor does it require a change in plant operation. Therefore, no individual precursors of an accident are affected.
The consequences of an evaluated accident are determined by the operability of plant systems designed to mitigate those consequences. This proposed change makes no modification to the design or operation of the systems that are used in mitigation of accidents. Limits have been established, consistent with Nuclear Regulatory Commission (NRC) approved methods, to ensure that fuel performance during normal, transient, and accident conditions is
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acceptable. The proposed change to the values of the SLMCPR continues to conservatively establish this safety limit such that the fuel is protected during normal operation and during any plant transients or anticipated operational occurrences.
Based on the above, NPPD Nebraska Public Power District concludes that the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
2. Do the proposed changes create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No.
Creation of the possibility of a new or different kind of accident from an accident previously evaluated would require creation of precursors of that accident. New accident precursors may be created by modification of the plant configuration or changes in how the plant is operated. The proposed change does not involve a modification of the plant configuration or in how the plant is operated. The proposed change to the SLMCPR values assures that safety criteria are maintained.
Based on the above, NPPD concludes that the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated.
3. Do the proposed changes involve a significant reduction in a margin of safety?
Response: No.
The values of the proposed SLMCPR provides a margin of safety by ensuring that no more than 0.1% of fuel rods are expected to be in boiling transition if the Minimum Critical Power Ratio limit is not violated. The proposed change will ensure the appropriate level of fuel protection is maintained. Additionally, operational limits are established based on the proposed SLMCPR to ensure that the SLMCPR is not violated during all modes of operation. This will ensure that the fuel design safety criteria are met (i.e., that at least 99.9% of the fuel rods do not experience transition boiling during normal operation as well as anticipated operational occurrences).
Based on the above, NPPD concludes that 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 standards of 10 CFR 50.92(c) are satisfied. Therefore, the NRC staff proposes to determine that the amendment request involves no significant hazards consideration.
Attorney for licensee: Mr. John C. McClure, Nebraska Public Power District, Post Office Box 499, Columbus, NE 68602-0499.
NRC Branch Chief: Michael T. Markley.
Tennessee Valley Authority, Docket Nos. 50-260 and 50-296, Browns Ferry Nuclear Plant (BFN), Units 2 and 3, Limestone County, Alabama
Date of amendment request: July 30, 2012. A publicly available version is in ADAMS under Accession No. ML12215A005.
Description of amendment request: This amendment request contains sensitive unclassified non-safeguards information (SUNSI). The proposed amendments would delete the BFN, Units 2 and 3, Technical Specification (TS) Surveillance Requirement 3.5.1.12, which requires the verification of the capability to automatically transfer the power supply from the normal source to the alternate source for each Low-Pressure Coolant Injection (LPCI) subsystem inboard injection valve and each recirculation pump discharge valve on a 24-month frequency. In addition, the licensee is requesting approval for the use of a modified loss-of-coolant accident (LOCA) methodology that will require revising TS 5.6.5.b to include a reference to the modified LOCA methodology. Also, the request revises TSs 3.3.1.1, 5.6.5.a, and 5.6.5.b to include the modified LOCA methodology for the oscilliation power range monitor upscale function period based detection algorithm setpoint limits.
Basis for proposed no significant hazards consideration determination: As required by 10 CFR 50.91(a), the licensee has provided its analysis of the issue of no significant hazards consideration, which is presented below:
1. Does the proposed Technical Specification change involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No.
The 480V RMOV Reactor Motor-Operational Value Boards D or E, the equipment they power, or the automatic power transfer feature provided for these boards are not precursors to any accident previously evaluated in the Updated Final Safety Analysis Report (UFSAR). Therefore, the probability of an evaluated accident is not increased by modifying this equipment.
The proposed deletion of a surveillance requirement to verify automatic transfer capability for the power supply to the LPCI inboard injection valves, RHR residual heat removal minimum flow valves and recirculation pump discharge valves does not change the number of Emergency Core Cooling System (ECCS) subsystems credited in the BFN licensing basis. The proposed change does not affect the operational characteristics or function of systems, structures, or components (SSCs), the interfaces between credited SSCs and other plant systems, or the reliability of SSCs. The proposed change does not impact the capability of credited SSCs to perform their required safety functions.
The proposed change to the ECCS Evaluation Model meets the requirements of 10 CFR 50.46(a)(1)(ii) and ensures the limits of 10 CFR 50.46(b) are maintained. The proposed changes to TS 5.6.5a, 5.6.5b and 3.3.1.1 are required to implement AREVA Analytical Methodologies.
Therefore, the proposed TS changes will not significantly increase the consequences of an accident previously evaluated.
2. Does the proposed Technical Specification change create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No.
The proposed deletion of a surveillance requirement to verify automatic transfer capability for the power supply to the LPCI inboard injection valves, RHR minimum flow valves and recirculation pump discharge valves does not introduce new equipment, which could create a new or different kind of accident.
The proposed change to the ECCS Evaluation Model meets the requirements of 10 CFR 50.46(a)(1)(ii) and ensures the limits of 10 CFR 50.46(b) are maintained. The proposed changes to TS 5.6.5.a, 5.6.5.b and 3.3.1.1 are required to implement AREVA Analytical Methodologies.
The proposed change does not alter the manner in which equipment operation is initiated, nor will the functional demands on credited equipment be changed. The capability of credited SSCs to perform their required function will not be affected by the proposed change. In addition, the proposed change does not affect the interaction of plant SSCs with other plant SSCs whose failure or malfunction can initiate an accident or transient. As such, no new failure modes are being introduced. No new external threats, release pathways, or equipment failure modes are created. Therefore, the proposed deletion of a surveillance requirement to verify automatic transfer capability for the power supply to the LPCI inboard injection valves, RHR minimum flow valves and recirculation pump discharge valves will not create a possibility for an accident of a new or different type than those previously evaluated.
3. Does the proposed Technical Specification change involve a significant reduction in a margin of safety?
Response: No.
The proposed change to the ECCS Evaluation Model and the deletion of a surveillance requirement to verify automatic transfer capability for the power supply to the LPCI inboard injection valves, RHR minimum flow valves and recirculation pump discharge valves does not change the conditions, operating configurations, or minimum amount of operating equipment credited in the safety analyses for accident or transient mitigation.
The proposed change does not alter the assumptions contained in the safety analyses. The proposed change does not alter the manner in which safety limits, limiting safety system settings or limiting conditions for operation are determined.
The proposed change does not impact the safety analysis-credited redundancy or
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availability of SSCs required for accident or transient mitigation, or the ability of the plant to cope with design basis events as assumed in safety analyses. In addition, no changes are proposed in the manner in which the credited SSCs provide plant protection or which create new modes of plant operation. The requirements of 10 CFR 50.46 and Appendix K continue to be met. Therefore, the proposed change does not involve a significant reduction in the margin of safety.
The proposed changes to TS 5.6.5a, 5.6.5b, and 3.3.1.1 are required to implement AREVA Analytical Methodologies.
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: General Counsel, Tennessee Valley Authority, 400 West Summit Hill Drive, 6A West Tower, Knoxville, Tennessee 37902.
NRC Acting Branch Chief: Jessie F. Quichocho.
Order Imposing Procedures for Access to Sensitive Unclassified Non-
Safeguards Information for Contention Preparation
Exelon Generation Company, LLC, Docket No. 50-374, LaSalle County Station, Unit 2, LaSalle County, Illinois
Nebraska Public Power District, Docket No. 50-298, Cooper Nuclear Station, Nemaha County, Nebraska
Tennessee Valley Authority, Docket Nos. 50-260 and 50-296, Browns Ferry Nuclear Plant, Units 2 and 3, Limestone County, Alabama
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This Order contains instructions regarding how potential parties to this proceeding may request access to documents containing Sensitive Unclassified Non-Safeguards Information (SUNSI).
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Within 10 days after publication of this notice of hearing and opportunity to petition for leave to intervene, any potential party who believes access to SUNSI is necessary to respond to this notice may request such access. A ``potential party'' is any person who intends to participate as a party by demonstrating standing and filing an admissible contention under 10 CFR 2.309. Requests for access to SUNSI submitted later than 10 days after publication will not be considered absent a showing of good cause for the late filing, addressing why the request could not have been filed earlier.
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The requestor shall submit a letter requesting permission to access SUNSI to the Office of the Secretary, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, Attention: Rulemakings and Adjudications Staff, and provide a copy to the Associate General Counsel for Hearings, Enforcement and Administration, Office of the General Counsel, Washington, DC 20555-0001. The expedited delivery or courier mail address for both offices is: U.S. Nuclear Regulatory Commission, 11555 Rockville Pike, Rockville, Maryland 20852. The email address for the Office of the Secretary and the Office of the General Counsel are Hearing.Docket@nrc.gov and OGCmailcenter@nrc.gov, respectively.\1\ The request must include the following information:
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\1\ While a request for hearing or petition to intervene in this proceeding must comply with the filing requirements of the NRC's ``E-Filing Rule,'' the initial request to access SUNSI under these procedures should be submitted as described in this paragraph.
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(1) A description of the licensing action with a citation to this Federal Register notice;
(2) The name and address of the potential party and a description of the potential party's particularized interest that could be harmed by the action identified in C.(1); and
(3) The identity of the individual or entity requesting access to SUNSI and the 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.
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Based on an evaluation of the information submitted under paragraph C.(3) the NRC staff will determine within 10 days of receipt of the request whether:
(1) There is a reasonable basis to believe the petitioner is likely to establish standing to participate in this NRC proceeding; and
(2) The requestor has established a legitimate need for access to SUNSI.
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If the NRC staff determines that the requestor satisfies both D.(1) and D.(2) above, the NRC staff will notify the requestor in writing that access to SUNSI has been granted. The written notification will contain instructions on how the requestor may obtain copies of the requested documents, and any other conditions that may apply to access to those documents. These conditions may include, but are not limited to, the signing of a Non-Disclosure Agreement or Affidavit, or Protective Order \2\ setting forth terms and conditions to prevent the unauthorized or inadvertent disclosure of SUNSI by each individual who will be granted access to SUNSI.
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\2\ Any motion for Protective Order or draft Non-Disclosure Affidavit or Agreement for SUNSI must be filed with the presiding officer or the Chief Administrative Judge if the presiding officer has not yet been designated, within 30 days of the deadline for the receipt of the written access request.
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Filing of Contentions. Any contentions in these proceedings that are based upon the information received as a result of the request made for SUNSI must be filed by the requestor no later than 25 days after the requestor is granted access to that information. However, if more than 25 days remain between the date the petitioner is granted access to the information and the deadline for filing all other contentions (as established in the notice of hearing or opportunity for hearing), the petitioner may file its SUNSI contentions by that later deadline.
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Review of Denials of Access.
(1) If the request for access to SUNSI is denied by the NRC staff after a determination on standing and need for access, the NRC staff shall immediately notify the requestor in writing, briefly stating the reason or reasons for the denial.
(2) The requestor may challenge the NRC staff's adverse determination by filing a challenge within 5 days of receipt of that determination with: (a) The presiding officer designated in this proceeding; (b) if no presiding officer has been appointed, the Chief Administrative Judge, or if he or she is unavailable, another administrative judge, or an administrative law judge with jurisdiction pursuant to 10 CFR 2.318(a); or (c) if another officer has been designated to rule on information access issues, with that officer.
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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 with the Chief Administrative Judge within 5 days of the notification by the NRC staff of its grant of access.
If challenges to the NRC staff determinations are filed, these procedures give way to the normal process for litigating disputes concerning access to information. The availability of interlocutory review by the Commission of orders ruling on such NRC staff determinations (whether granting or denying access) is governed by 10 CFR 2.311.\3\
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\3\ Requestors should note that the filing requirements of the NRC's E-Filing Rule (72 FR 49139; August 28, 2007) apply to appeals of NRC staff determinations (because they must be served on a presiding officer or the Commission, as applicable), but not to the initial SUNSI request submitted to the NRC staff under these procedures.
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The Commission expects that the NRC staff and presiding officers (and any other reviewing officers) will consider and resolve requests for access to SUNSI, and motions for protective orders, in a timely fashion in order to minimize any unnecessary delays in identifying those petitioners who have standing and who have propounded contentions meeting the specificity and basis requirements in 10 CFR Part 2. Attachment 1 to this Order summarizes the general target schedule for processing and resolving requests under these procedures.
It is so ordered.
Dated at Rockville, Maryland, this 25th day of October 2012.
For the Nuclear Regulatory Commission.
Annette L. Vietti-Cook,
Secretary of the Commission.
Attachment 1--General Target Schedule for Processing and Resolving
Requests for Access to Sensitive Unclassified Non-Safeguards Information
in This Proceeding
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Day Event/activity
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0............................. Publication of Federal Register notice
of hearing and opportunity to petition
for leave to intervene, including order
with instructions for access requests.
10............................ Deadline for submitting requests for
access to Sensitive Unclassified Non-
Safeguards Information (SUNSI) with
information: Supporting the standing of
a potential party identified by name
and address; describing the need for
the information in order for the
potential party to participate
meaningfully in an adjudicatory
proceeding.
60............................ Deadline for submitting petition for
intervention containing: (i)
Demonstration of standing; (ii) all
contentions whose formulation does not
require access to SUNSI (+25 Answers to
petition for intervention; +7 requestor/
petitioner reply).
20............................ 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 need for
SUNSI. (NRC staff also informs any
party to the proceeding whose interest
independent of the proceeding would be
harmed by the release of the
information.) If NRC staff makes the
finding of need for SUNSI and
likelihood of standing, NRC staff
begins document processing (preparation
of redactions or review of redacted
documents).
25............................ If NRC staff finds no ``need'' or no
likelihood of standing, the deadline
for 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.
A............................. If access granted: Issuance of presiding
officer or other designated officer
decision on motion for protective order
for access to sensitive information
(including schedule for providing
access and submission of contentions)
or decision reversing a final adverse
determination by the NRC staff.
A + 3......................... Deadline for filing executed Non-
Disclosure Affidavits. Access provided
to SUNSI consistent with decision
issuing the protective order.
A + 28........................ Deadline for submission of contentions
whose development depends upon access
to SUNSI. However, if more than 25 days
remain between the petitioner's receipt
of (or access to) the information and
the deadline for filing all other
contentions (as established in the
notice of hearing or opportunity for
hearing), the petitioner may file its
SUNSI contentions by that later
deadline.
A + 53........................ (Contention receipt +25) Answers to
contentions whose development depends
upon access to SUNSI.
A + 60........................ (Answer receipt +7) Petitioner/
Intervenor reply to answers.
>A + 60....................... Decision on contention admission.
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FR Doc. 2012-26762 Filed 11-2-12; 8:45 am
BILLING CODE 7590-01-P
