Source: https://regulations.justia.com/regulations/fedreg/2010/11/09/2010-28129.html
Timestamp: 2020-08-09 15:43:19
Document Index: 527032030

Matched Legal Cases: ['Application No. 2011', 'ART 1', 'ART 1', 'art 2', 'art002', 'art0020309', 'ART 1', 'ART 1', 'art 73', 'art 50', 'art 73', 'ART 1', 'ART 1', 'ART 1', 'ART 1', 'art 2', 'ART 1', 'ART 1', 'art 73', 'art 50', 'art 73']

Notice; Applications and Amendments to Facility Operating 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, 68831-68840 [2010-28129] :: Nuclear Regulatory Commission :: Agencies And Commissions :: Regulation Tracker :: Justia
Justia Regulation Tracker Agencies And Commissions Nuclear Regulatory Commission Notice; Applications and Amendments to Facility Operating 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, 68831-68840 [2010-28129]
Notice; Applications and Amendments to Facility Operating 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, 68831-68840 [2010-28129]
Download as PDF Federal Register / Vol. 75, No. 216 / Tuesday, November 9, 2010 / Notices Location: Canada Glacier, Lake Fryxell, Taylor Valley (ASPA 131) Dates: February 28, 2011 to February 28, 2016 Permit Application No. 2011–022. 2. Applicant: Adam Kustka, Department of Earth & Environmental Sciences, Rutgers University, 101 Warren Street, Newark, NJ 07102. Activity for Which Permit Is Requested Export from USA, and Introduce Nonindigenous Species into Antarctica. The applicant is investigating the role of modified circumpolar deep water on supplying Fe to the surface ocean and how this Fe supply impacts initial CO2 sequestration and how it impacts the composition of the phytoplankton community assemblage. To trace the fate and recycling of organic carbon and Fe that has been incorporated into phytoplankton, they will use cell lysates labeled with the radioisotopes of C or Fe. In complementary experiments, lysates will also be labeled with the stable isotope 13C. These lysates will be generated in the university lab using cultures of a centric diatom (Thhalassiosira weissflogii) and a temperate haptophyte (Phaeocystic globosa)—species that cannot tolerate seawater temperatures in Antarctica. The lysates will be shipped from the University via New Zealand and used onboard the research vessel, Nathaniel B. Palmer, in the Ross Sea. Once experiments are concluded, the lysates will be placed in the radioactive waste stream and not released to the environment. Location: Ross Sea, Antarctica Dates: January 1, 2011 to March 1, 2011 Nadene G. Kennedy, Permit Officer, Office of Polar Programs. [FR Doc. 2010–28202 Filed 11–8–10; 8:45 am] BILLING CODE 7555–01–P NATIONAL SCIENCE FOUNDATION Notice of Permits Issued Under the Antarctic Conservation Act of 1978 National Science Foundation. Notice of permits issued under the Antarctic Conservation of 1978, Public Law 95–541. AGENCY: wwoods2 on DSK1DXX6B1PROD with NOTICES_PART 1 ACTION: The National Science Foundation (NSF) is required to publish notice of permits issued under the Antarctic Conservation Act of 1978. This is the required notice. FOR FURTHER INFORMATION CONTACT: Nadene G. Kennedy, Permit Office, SUMMARY: VerDate Mar<15>2010 15:18 Nov 08, 2010 Jkt 223001 Office of Polar Programs, Rm. 755, National Science Foundation, 4201 Wilson Boulevard, Arlington, VA 22230. SUPPLEMENTARY INFORMATION: On October 1, 2010 and October 5, 2010, the National Science Foundation published notices in the Federal Register of permit applications received. Permits were issued on November 1, 2010 and November 3, 2010, respectively, to: Robert W. Sanders ... Yu-Ping Chin ............ Permit No. 2011–019. Permit No. 2011–018. Nadene G. Kennedy, Permit Officer. [FR Doc. 2010–28209 Filed 11–8–10; 8:45 am] BILLING CODE 7555–01–P NUCLEAR REGULATORY COMMISSION [NRC–2010–0335] Notice; Applications and Amendments to Facility Operating Licenses Involving Proposed No Significant Hazards Considerations and Containing Sensitive Unclassified NonSafeguards Information and Order Imposing Procedures for Access to Sensitive Unclassified Non-Safeguards Information I. Background Pursuant to section 189a. (2) of the Atomic Energy Act of 1954, as amended (the Act), the U.S. Nuclear Regulatory Commission (the Commission, NRC, 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 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 sensitive unclassified non-safeguards information (SUNSI). Notice of Consideration of Issuance of Amendments to Facility Operating 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. PO 00000 Frm 00084 Fmt 4703 Sfmt 4703 68831 Under the Commission’s regulations in Title 10 of the Code of Federal Regulations (10 CFR), Section 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 60day 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. Written comments may be submitted by mail to the Chief, Rules, Announcements and Directives Branch (RADB), TWB–05–B01M, Division of Administrative Services, Office of Administration, U.S. Nuclear Regulatory Commission, Washington, DC 20555– 0001, and should cite the publication date and page number of this Federal Register notice. Written comments may also be faxed to the RADB at 301–492– 3446. Documents may be examined, and/or copied for a fee, at the NRC’s Public Document Room (PDR), located at One White Flint North, Public File Area O1 F21, 11555 Rockville Pike (first floor), Rockville, Maryland. Within 60 days after the date of publication of this notice, any person(s) E:\FR\FM\09NON1.SGM 09NON1 wwoods2 on DSK1DXX6B1PROD with NOTICES_PART 1 68832 Federal Register / Vol. 75, No. 216 / Tuesday, November 9, 2010 / Notices 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. 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 Commission’s PDR, located at One White Flint North, Public File Area 01F21, 11555 Rockville Pike (first floor), Rockville, Maryland, or at http://www.nrc.gov/reading-rm/doccollections/cfr/part002/part0020309.html. Publicly available records will be accessible from the Agencywide Documents Access and Management System’s (ADAMS) Public Electronic Reading Room on the Internet at the NRC Web site, http://www.nrc.gov/ reading-rm.html. 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 VerDate Mar<15>2010 15:18 Nov 08, 2010 Jkt 223001 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, any hearing held would take place before the issuance of any amendment. All documents filed in NRC adjudicatory proceedings, including a request for hearing, a petition for leave to intervene, any motion or other document filed in the proceeding prior to the submission of a request for hearing or petition to intervene, and documents filed by interested governmental entities participating under 10 CFR 2.315(c), must be filed in accordance with the NRC E-Filing rule (72 FR 49139, August 28, 2007). The E-Filing process requires participants to submit and serve all adjudicatory documents over the Internet, or in some cases to mail copies on electronic storage media. Participants may not submit paper copies of their filings PO 00000 Frm 00085 Fmt 4703 Sfmt 4703 unless they seek an exemption in accordance with the procedures described below. To comply with the procedural requirements of E-Filing, at least ten (10) days prior to the filing deadline, the participant should contact the Office of the Secretary by e-mail 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 NRCissued 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 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 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 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/esubmittals.html. Once a participant has obtained a digital ID certificate and a docket has been created, the participant can then submit a request for hearing or petition for leave to intervene. Submissions should be in Portable Document Format (PDF) in accordance with NRC guidance available on the NRC public Web site at E:\FR\FM\09NON1.SGM 09NON1 wwoods2 on DSK1DXX6B1PROD with NOTICES_PART 1 Federal Register / Vol. 75, No. 216 / Tuesday, November 9, 2010 / Notices http://www.nrc.gov/site-help/esubmittals.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 e-mail notice confirming receipt of the document. The E-Filing system also distributes an e-mail notice that provides access to the document to the NRC 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 Web site at http:// www.nrc.gov/site-help/ e-submittals.html, by e-mail at MSHD.Resource@nrc.gov, or by a tollfree 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 firstclass mail as of the time of deposit in the mail, or by courier, express mail, or expedited delivery service upon VerDate Mar<15>2010 15:18 Nov 08, 2010 Jkt 223001 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:// ehd.nrc.gov/EHD_Proceeding/home.asp, 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. Nontimely filings will not be entertained absent a determination by the presiding officer that the petition or request should be granted or the contentions should be admitted, based on a balancing of the factors specified in 10 CFR 2.309(c)(1)(i)–(viii). For further details with respect to this amendment action, see the application for amendment which is available for public inspection at the Commission’s PDR, located at One White Flint North, Public File Area 01F21, 11555 Rockville Pike (first floor), Rockville, Maryland. Publicly available records will be accessible electronically from the ADAMS Public Electronic Reading Room on the Internet at the NRC Web site, http://www.nrc.gov/reading-rm/ adams.html. If you do not have access to ADAMS or if there are problems in accessing the documents located in ADAMS, contact the PDR Reference staff at 1–800–397–4209, 301–415–4737, or by e-mail to pdr.resource@nrc.gov. Arizona Public Service Company, et al., Docket Nos. STN 50–528, STN 50–529, and STN 50–530, Palo Verde Nuclear Generating Station, Units 1, 2, and 3, Maricopa County, Arizona Date of amendment request: July 22, 2010. Description of amendment request: This amendment request contains sensitive unclassified non-safeguards PO 00000 Frm 00086 Fmt 4703 Sfmt 4703 68833 information (SUNSI). The amendments would approve the proposed Cyber Security Plan and implementation schedule and would revise the existing Facility Operating License (FOL) Physical Protection License Condition to require the licensee to fully implement and maintain in effect all provisions of the Commission-approved Cyber Security Plan as required by 10 CFR 73.54. 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: Criterion 1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated? Response: No. The proposed amendment incorporates a new requirement in the Facility Operating License (FOL) to implement and maintain a Cyber Security Plan as part of the facility’s overall program for physical protection. Inclusion of the Cyber Security Plan in the FOL itself does not involve any modifications to the safety-related structures, systems, or components (SSCs). Rather, the Cyber Security Plan describes how the requirements of 10 CFR 73.54 are to be implemented to identify, evaluate, and mitigate cyber attacks up to and including the design basis cyber attack threat, thereby achieving high assurance that the facility’s digital computer and communications systems and networks are protected from cyber attacks. The addition of the Cyber Security Plan to the Physical Security Plan will not alter previously evaluated Updated Final Safety Analysis Report (UFSAR) design basis accident analysis assumptions, add any accident initiators, or affect the function of the plant safety-related SSCs as to how they are operated, maintained, modified, tested, or inspected. Therefore, it is concluded that this change does not involve a significant increase in the probability or consequences of an accident previously evaluated. Criterion 2. Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated? Response: No. This proposed amendment provides assurance that safety-related SSCs are protected from cyber attacks. Implementation of 10 CFR 73.54 and the inclusion of a plan in the FOL do not result in the need of any new or different FSAR [Final Safety Analysis Report] design basis accident analysis. It does not introduce new equipment that could create a new or different kind of accident, and no new equipment failure modes are created. As a result, no new accident scenarios, failure mechanisms, or limiting single failures are introduced as a result of this proposed amendment. E:\FR\FM\09NON1.SGM 09NON1 68834 Federal Register / Vol. 75, No. 216 / Tuesday, November 9, 2010 / Notices Therefore, the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated. Criterion 3. Does the proposed amendment involve a significant reduction in a margin of safety? Response: No. The margin of safety is associated with the confidence in the ability of the fission product barriers (i.e., fuel cladding, reactor coolant pressure boundary, and containment structure) to limit the level of radiation to the public. The proposed amendment would not alter the way any safety-related SSC functions and would not alter the way the plant is operated. The amendment provides assurance that safety-related SSCs are protected from cyber attacks. The proposed amendment would not introduce any new uncertainties or change any existing uncertainties associated with any safety limit. The proposed amendment would have no impact on the structural integrity of the fuel cladding, reactor coolant pressure boundary, or containment structure. Based on the above considerations, the proposed amendment would not degrade the confidence in the ability of the fission product barriers to limit the level of radiation to the public. Therefore, the proposed change does not involve a significant reduction in a margin of safety. wwoods2 on DSK1DXX6B1PROD with NOTICES_PART 1 The NRC staff has reviewed the licensee’s analysis and, based on that review, it appears that the three standards of 10 CFR 50.92(c) are satisfied. Therefore, the NRC staff proposes to determine that the request for amendments involves no significant hazards consideration. Attorney for licensee: Michael G. Green, Senior Regulatory Counsel, Pinnacle West Capital Corporation, P.O. Box 52034, Mail Station 8695, Phoenix, Arizona 85072–2034. NRC Branch Chief: Michael T. Markley. Dominion Energy Kewaunee, Inc., Docket No. 50–305, Kewaunee Power Station (KPS), Kewaunee County, Wisconsin Date of amendment request: July 12, 2010, as supplemented by a letter dated August 5, 2010. Description of amendment request: This amendment request contains sensitive unclassified non-safeguards information (SUNSI). The licensee proposed an amendment to the Facility Operating License for KPS. In the same amendment request letter, sent under Dominion Resources Services, Inc. letterhead, Millstone Power Station Units 2 and 3; North Anna Power Station Units 1 and 2; and Surry Power Station Units 1 and 2 submitted amendment requests pertaining to their Cyber Security Plans. This notice only VerDate Mar<15>2010 15:18 Nov 08, 2010 Jkt 223001 addresses the application as it pertains to KPS. The licensee requested NRC approval of the KPS Cyber Security Plan, provided a proposed implementation schedule, and proposed to add a sentence to License Condition 2.C.(4), ‘‘Physical Protection,’’ of KPS Facility Operating License (FOL) DPR– 43 that would affirm when the licensee would fully implement and maintain in effect all provisions of the Cyber Security Plan. 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. The NRC staff reviewed the licensee’s NHSC analysis and has prepared its own as follows: Criterion 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated? Response: No. The Plan establishes the licensing basis for the Cyber Security Program for the Sites. The Plan establishes how to achieve high assurance that specified nuclear power plant digital computer and communication systems, networks and functions are adequately protected against cyber attacks up to and including the design basis threat. Part one of the proposed changes is designed to achieve high assurance that the systems are protected from cyber attacks. The Plan describes how plant modifications that involve digital computer systems are reviewed to provide high assurance of adequate protection against cyber attacks, up to and including the design basis threat. The proposed change does not alter accident analysis assumptions, add any initiators, or affect the function of plant systems or the manner in which systems are operated, maintained, modified, tested, or inspected. The first part of the proposed change is designed to achieve high assurance that the systems within the scope of the requirement are protected from cyber attacks and has no impact on the probability or consequences of an accident previously evaluated. The proposed change implements a Cyber Security Plan as a requirement not previously formally addressed. As such, the proposed Plan provides a significant enhancement to cyber security where no requirement existed before. The second part of the proposed changes adds a sentence to the existing facility license conditions for Physical Protection. These changes are administrative and have no impact on the probability or consequences of an accident previously evaluated. Therefore, it is concluded that these changes do not involve a significant increase in the probability or consequences of an accident previously evaluated. Criterion 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated? Response: No. PO 00000 Frm 00087 Fmt 4703 Sfmt 4703 This proposed amendment provides assurance that safety-related structures, systems and components (SSCs) are protected from cyber attacks. Implementation of 10 CFR 73.54 and the inclusion of a plan in the FOL do not result in the need of any new or different design basis accident analysis. It does not introduce new equipment that could create a new or different kind of accident, and no new equipment failure modes are created. As a result, no new accident scenarios, failure mechanisms, or limiting single failures are introduced as a result of this proposed amendment. Therefore, the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated. Criterion 3. Does the proposed change involve a significant reduction in a margin of safety? Response: No. The margin of safety is associated with the confidence in the ability of the fission product barriers (i.e., fuel cladding, reactor coolant pressure boundary, and containment structure) to limit the level of radiation to the public. The proposed amendment would not alter the way any safety-related SSC functions and would not alter the way the plant is operated. The amendment provides assurance that safety-related SSCs are protected from cyber attacks. The proposed amendment would not introduce any new uncertainties or change any existing uncertainties associated with any safety limit. The proposed amendment would have no impact on the structural integrity of the fuel cladding, reactor coolant pressure boundary, or containment structure. Based on the above considerations, the proposed amendment would not degrade the confidence in the ability of the fission product barriers to limit the level of radiation to the public. Therefore, the proposed change does not involve a significant reduction in a margin of safety. 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 proposed amendment involves no significant hazards consideration. Attorney for licensee: Lillian M. Cuoco, Senior Counsel, Dominion Resources Services, Inc., Counsel for Dominion Energy Kewaunee, Inc., 120 Tredegar Street, Richmond, VA 23219. NRC Branch Chief: Robert J. Pascarelli. FirstEnergy Nuclear Operating Company, et al., Docket No. 50–440, Perry Nuclear Power Plant, Unit No. 1, Lake County, Ohio Date of amendment request: July 22, 2010. Description of amendment request: This amendment request contains sensitive unclassified non-safeguards information (SUNSI). The proposed E:\FR\FM\09NON1.SGM 09NON1 Federal Register / Vol. 75, No. 216 / Tuesday, November 9, 2010 / Notices amendment to the Facility operating License (FOL) includes: (1) The proposed Perry Nuclear Power Plant (PNPP) Unit No. 1 Cyber Security Plan, (2) an implementation schedule, and (3) a proposed sentence to be added to the existing FOL Physical Protection license condition 2.E to require the FirstEnergy Nuclear Operating Company (FENOC, the licensee) to fully implement and maintain in effect all provisions of the Commission approved cyber plan as required by 10 CFR 73.54. Federal Register notice issued the final rule that amended 10 CFR Part 73. The regulations in 10 CFR 73.54, ‘‘Protection of digital computer and communication systems and networks,’’ establish the requirements for a cyber security program. This regulation specifically requires each licensee currently licensed to operate a nuclear power plant under 10 CFR Part 50 to submit a cyber security plan that satisfies the requirements of the rule. Each submittal must include a proposed implementation schedule and implementation of the licensee’s cyber security program must be consistent with the approved schedule. The background for this application is addressed by the NRC’s Notice of Availability, Federal Register Notice, Final Rule 10 CFR Part 73, Power Reactor Security Requirements, published on March 27, 2009 (74 FR 13926). 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: wwoods2 on DSK1DXX6B1PROD with NOTICES_PART 1 Criterion 1: The proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated The proposed change is required by 10 CFR 73.54 and includes three parts. The first part is the submittal of the Plan for NRC review and approval. The Plan provides a description of how the requirements of the rule will be implemented at the PNPP. The Plan establishes the licensing basis for the FENOC cyber security program for the PNPP. The Plan establishes how to achieve high assurance that nuclear power plant digital computer and communication systems and networks associated with the following are adequately protected against cyber attacks up to and including the design basis threat: 1. Safety-related and important-to-safety functions, 2. Security functions, 3. Emergency preparedness functions including offsite communications, and 4. Support systems and equipment which if compromised, would adversely impact VerDate Mar<15>2010 15:18 Nov 08, 2010 Jkt 223001 safety, security, or emergency preparedness functions. Part one of the proposed change is designed to achieve high assurance that the systems within the scope of the rule are protected from cyber attacks. The Plan itself does not require any plant modifications. However, the Plan does describe how plant modifications which involve digital computer systems are reviewed to provide high assurance of adequate protection against cyber attacks, up to and including the design basis threat as defined in the rule. The proposed change does not alter the plant configuration, require new plant equipment to be installed, alter accident analysis assumptions, add any initiators, affect the function of plant systems, or affect the manner in which systems are operated. The first part of the proposed change is designed to achieve high assurance that the systems within the scope of the rule are protected from cyber attacks and has no impact on the probability or consequences of an accident previously evaluated. The second part of the proposed change is an implementation schedule. The third part adds a sentence to the existing FOL license condition 2.E for Physical Protection. Both of these changes are administrative and have no impact on the probability or consequences of an accident previously evaluated. Therefore, it is concluded that this change does not involve a significant increase in the probability or consequences of an accident previously evaluated. Criterion 2: The proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated The proposed change is required by 10 CFR 73.54 and includes three parts. The first part is the submittal of the Plan for NRC review and approval. The Plan provides a description of how the requirements of the rule will be implemented at the PNPP. The Plan establishes the licensing basis for the FENOC cyber security program for the PNPP. The Plan establishes how to achieve high assurance that nuclear power plant digital computer and communication systems and networks associated with the following are adequately protected against cyber attacks up to and including the design basis threat: 1. Safety-related and important-to-safety functions, 2. Security functions, 3. Emergency preparedness functions including offsite communications, and 4. Support systems and equipment which if compromised, would adversely impact safety, security, or emergency preparedness functions. Part one of the proposed change is designed to achieve high assurance that the systems within the scope of the rule are protected from cyber attacks. The Plan itself does not require any plant modifications. However, the Plan does describe how plant modifications which involve digital computer systems are reviewed to provide high assurance of adequate protection against cyber attacks, up to and including the design basis threat defined in the rule. The proposed change does not alter the plant configuration, require new plant equipment to be installed, PO 00000 Frm 00088 Fmt 4703 Sfmt 4703 68835 alter accident analysis assumptions, add any initiators, affect the function of plant systems, or affect the manner in which systems are operated. The first part of the proposed change is designed to achieve high assurance that the systems within the scope of the rule are protected from cyber attacks and does not create the possibility of a new or different kind of accident from any previously evaluated. The second part of the proposed change is an implementation schedule. The third part adds a sentence to the existing FOL license condition 2.E for Physical Protection. Both of these changes are administrative and do not create the possibility of a new or different kind of accident from any previously evaluated. Therefore, the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated. Criterion 3: The proposed change does not involve a significant reduction in a margin of safety The proposed change is required by 10 CFR 73.54 and includes three parts. The first part is the submittal of the Plan for NRC review and approval. The Plan provides a description of how the requirements of the rule will be implemented at the PNPP. The Plan establishes the licensing basis for the FENOC cyber security program for the PNPP. The Plan establishes how to achieve high assurance that nuclear power plant digital computer and communication systems and networks associated with the following are adequately protected against cyber attacks up to and including the design basis threat: 1. Safety-related and important-to-safety functions, 2. Security functions, 3. Emergency preparedness functions including offsite communications, and 4. Support systems and equipment which if compromised, would adversely impact safety, security, or emergency preparedness functions. Part one of the proposed change is designed to achieve high assurance that the systems within the scope of the rule are protected from cyber attacks. Plant safety margins are established through Limiting Conditions for Operation, Limiting Safety System Settings and Safety limits specified in the Technical Specifications, methods of evaluation that establish design basis or change Updated Final Safety Analysis. Because there is no change to these established safety margins, the proposed change does not involve a significant reduction in a margin of safety. The second part of the proposed change is an implementation schedule. The third part adds a sentence to the existing FOL license condition 2.E for Physical Protection. Both of these changes are administrative and do 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 E:\FR\FM\09NON1.SGM 09NON1 68836 Federal Register / Vol. 75, No. 216 / Tuesday, November 9, 2010 / Notices 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: David W. Jenkins, FirstEnergy Nuclear Operating Company, FirstEnergy Corporation, 76 South Main Street, Akron, OH 44308. NRC Branch Chief: Robert D. Carlson. wwoods2 on DSK1DXX6B1PROD with NOTICES_PART 1 NextEra Energy Duane Arnold, LLC, Docket No. 50–331, Duane Arnold Energy Center, Linn County, Iowa Date of amendment request: July 14, 2010. Description of amendment request: This amendment request contains sensitive unclassified non-safeguards information (SUNSI). The licensee proposes an amendment to the Facility Operating License for the Duane Arnold Energy Center. The licensee requests NRC approval of the NextEra Energy Duane Arnold Cyber Security Plan, provides an implementation schedule, and adds a sentence to the existing Operation License Physical Protection license condition to require NextEra Energy Duane Arnold to fully implement and maintain in effect all provisions of the Commission-approved Cyber Security Plan. 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 (NSHC). The licensee’s NSHC analysis, addressing each issue described above, is reproduced below: Criterion 1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated? Response: No. The proposed amendment incorporates a new requirement in the Facility Operating License to implement and maintain a Cyber Security Plan as part of the facility’s overall program for physical protection. Inclusion of the Cyber Security Plan in the Facility Operating License itself does not involve any modifications to the safety-related structures, systems or components (SSCs). Rather, the Cyber Security Plan describes how the requirements of 10 CFR 73.54 are to be implemented to identify, evaluate, and mitigate cyber attacks up to and including the design basis cyber attack threat, thereby achieving high assurance that the facility’s digital computer and communications systems and networks are protected from cyber attacks. The Cyber Security Plan will not alter previously evaluated Final Safety Analysis Report (FSAR) design basis accident analysis assumptions, add any accident initiators, or affect the function of the plant safety-related SSCs as to how they are operated, maintained, modified, tested, or inspected. Therefore, the proposed VerDate Mar<15>2010 15:18 Nov 08, 2010 Jkt 223001 amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated. Criterion 2. Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated? Response: No. The proposed amendment provides assurance that safety-related SSCs are protected from cyber attacks. Implementation of 10 CFR 73.54 and the inclusion of a plan in the Facility Operating License do not result in the need for any new or different FSAR design basis accident analysis. It does not introduce new equipment that could create a new or different kind of accident, and no new equipment failure modes are created. As a result, no new accident scenarios, failure mechanisms, or limiting single failures are introduced as a result of this proposed amendment. Therefore, the proposed amendment does not create a possibility for an accident of a new or different type than those previously evaluated. Criterion 3. Does the proposed amendment involve a significant reduction in a margin of safety? Response: No. The margin of safety is associated with the confidence in the ability of the fission product barriers (i.e., fuel cladding, reactor coolant pressure boundary, and containment structure) to limit the level of radiation to the public. The proposed amendment would not alter the way any safety-related SSC functions and would not alter the way the plant is operated. The amendment provides assurance that safety-related SSCs are protected from cyber attacks. The proposed amendment would not introduce any new uncertainties or change any existing uncertainties associated with any safety limit. The proposed amendment would have no impact on the structural integrity of the fuel cladding, reactor coolant pressure boundary, or containment structure. Based on the above considerations, the proposed amendment would not degrade the confidence in the ability of the fission product barriers to limit the level of radiation to the public. 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: Mr. R.E. Helfrich, Florida Power & Light Company, P. O. Box 14000, Juno Beach, FL 33408–0420. NRC Branch Chief: Robert J. Pascarelli. PO 00000 Frm 00089 Fmt 4703 Sfmt 4703 Southern California Edison Company, et al., Docket Nos. 50–361 and 50–362, San Onofre Nuclear Generating Station, Units 2 and 3, San Diego County, California Date of amendment request: July 22, 2010. Description of amendment request: This amendment request contains sensitive unclassified non-safeguards information (SUNSI). The amendments would approve the proposed Cyber Security Plan and implementation schedule and would revise the existing Facility Operating License Physical Protection License Condition to require the licensee to fully implement and maintain in effect all provisions of the Commission-approved Cyber Security Plan as required by 10 CFR 73.54. 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: Criterion 1. Do the proposed amendments involve a significant increase in the probability or consequences of an accident previously evaluated? Response: No. The proposed amendment incorporates a new requirement in the Facility Operating License to implement and maintain the Cyber Security Plan as part of the facility’s overall program for physical protection. Inclusion of the Cyber Security Plan in the Facility Operating License itself does not involve any modifications to the safety-related structures, systems, or components (SSCs). Rather, the Cyber Security Plan describes how the requirements of 10 CFR 73.54 are to be implemented to identify, evaluate, and mitigate cyber attacks up to and including the design basis cyber attack threat, thereby achieving high assurance that the facility’s digital computer and communications systems and networks are protected from cyber attacks. The implementation and incorporation of the Cyber Security Plan into the Facility Operating License will not alter previously evaluated Updated Final Safety Analysis Report (UFSAR) design basis accident analysis assumptions, add any accident initiators, or affect the function of the plant safety-related SSCs as to how they are operated, maintained, modified, tested, or inspected. Therefore, the proposed amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated. Criterion 2. Do the proposed amendments create the possibility of a new or different kind of accident from any accident previously evaluated? Response: No. This proposed amendment provides assurance that safety-related SSCs are protected from cyber attacks. Implementation E:\FR\FM\09NON1.SGM 09NON1 Federal Register / Vol. 75, No. 216 / Tuesday, November 9, 2010 / Notices of 10 CFR 73.54 and the inclusion of the Cyber Security Plan in the Facility Operating License do not result in the need of any new or different UFSAR design basis accident analysis. It does not introduce new equipment that could create a new or different kind of accident, and no new equipment failure modes are created. As a result, no new accident scenarios, failure mechanisms, or limiting single failures are introduced as a result of this proposed amendment. Therefore, the proposed amendment does not create the possibility of a new or different kind of accident from any previously evaluated. Criterion 3. Do the proposed amendments involve a significant reduction in a margin of safety? Response: No. The margin of safety is associated with the confidence in the ability of the fission product barriers (i.e., fuel cladding, reactor coolant pressure boundary, and containment structure) to limit the level of radiation to the public. The proposed amendment would not alter the way any safety-related SSC functions and would not alter the way the plant is operated. The amendment provides assurance that safety-related SSCs are protected from cyber attacks. The proposed amendment would not introduce any new uncertainties or change any existing uncertainties associated with any safety limit. The proposed amendment would have no impact on the structural integrity of the fuel cladding, reactor coolant pressure boundary, or containment structure. Based on the above considerations, the proposed amendment would not degrade the confidence in the ability of the fission product barriers to limit the level of radiation to the public. Therefore, the proposed amendment does not involve a significant reduction in a margin of safety. wwoods2 on DSK1DXX6B1PROD with NOTICES_PART 1 The NRC staff has reviewed the licensee’s analysis and, based on that review, it appears that the three standards of 10 CFR 50.92(c) are satisfied. Therefore, the NRC staff proposes to determine that the request for amendments involves no significant hazards consideration. Attorney for licensee: Douglas K. Porter, Esquire, Southern California Edison Company, 2244 Walnut Grove Avenue, Rosemead, California 91770. NRC Branch Chief: Michael T. Markley. STP Nuclear Operating Company, Docket Nos. 50–498 and 50–499, South Texas Project, Units 1 and 2, Matagorda County, Texas Date of amendment request: July 27, 2010. Description of amendment request: This amendments request contains sensitive unclassified non-safeguards information (SUNSI). The amendments would approve the STP Nuclear VerDate Mar<15>2010 15:18 Nov 08, 2010 Jkt 223001 Operating Company’s request for approval of South Texas Project, Units 1 and 2 Cyber Security Plan in accordance with 10 CFR 73.54. The amendments would also revise Section 2.F of the Facility Operating Licenses (FOLs) numbered NPF–76 and NPF–80 to incorporate the requirement to fully implement and maintain in effect all provisions of the Commission-approved cyber security plan. The requirements of 10 CFR 73.54, ‘‘Protection of digital computer and communication systems and networks,’’ establish the requirements for a cyber security program. 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: Criterion 1. Do the proposed changes involve a significant increase in the probability or consequences of an accident previously evaluated? Response: No. The proposed change incorporates a new requirement in the FOL to implement and maintain the Cyber Security Plan as part of the facility’s overall program for physical protection. Inclusion of the Cyber Security Plan in the FOL itself does not involve any modifications to the safety related structures, systems or components (SSCs). Rather, the Cyber Security Plan describes how the requirements of 10 CFR 73.54 are to be implemented to identify, evaluate, and mitigate cyber attacks up to and including the design basis cyber attack threat, thereby achieving high assurance that the facility’s digital computer and communications systems and networks are protected from cyber attacks. The implementation and incorporation of the Cyber Security Plan into the FOL will not alter previously evaluated Updated Final Safety Analysis Report (UFSAR) design basis accident analysis assumptions, add any accident initiators, or affect the function of the plant safety related SSCs as to how they are operated, maintained, modified, tested, or inspected. Therefore, the proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated. Criterion 2. Do the proposed changes create the possibility of a new or different kind of accident from any accident previously evaluated? Response: No. This proposed amendment provides assurance that safety related SSCs are protected from cyber attacks. Implementation of 10 CFR 73.54 and the inclusion of the Cyber Security Plan in the FOL do not result in the need of any new or different UFSAR design basis accident analysis. It does not introduce new equipment that could create a new or different kind of accident, and no new equipment failure modes are created. As PO 00000 Frm 00090 Fmt 4703 Sfmt 4703 68837 a result, no new accident scenarios, failure mechanisms, or limiting single failures are introduced as a result of this proposed amendment. Therefore, the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated. Criterion 3. Do the proposed changes involve a significant reduction in a margin of safety? Response: No. The margin of safety is associated with the confidence in the ability of the fission product barriers (i.e., fuel cladding, reactor coolant pressure boundary, and containment structure) to limit the level of radiation to the public. The proposed amendment would not alter the way any safety related SSC functions and would not alter the way the plant is operated. The amendment provides assurance that safety related SSCs are protected from cyber attacks. The proposed amendment would not introduce any new uncertainties or change any existing uncertainties associated with any safety limit. The proposed amendment would have no impact on the structural integrity of the fuel cladding, reactor coolant pressure boundary, or containment structure. Based on the above considerations, the proposed amendment would not degrade the confidence in the ability of the fission product barriers to limit the level of radiation to the public. Therefore the proposed change does not involve a 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: A.H. Gutterman, Esq., Morgan, Lewis & Bockius, 1111 Pennsylvania Avenue, NW., Washington, DC 20004. NRC Branch Chief: Michael T. Markley. Union Electric Company, Docket No. 50–483, Callaway Plant, Unit 1, Callaway County, Missouri Date of amendment request: August 12, 2010. Description of amendment request: The amendment request contains sensitive unclassified non-safeguards information (SUNSI). The amendment would approve the Union Electric Company’s request for approval of the Callaway Plant, Unit 1 Cyber Security Plan in accordance with 10 CFR 73.54. The amendments would also revise Section 2.E of the Facility Operating License (FOL) numbered NPF–30 to incorporate the provisions to implement and maintain in effect all provisions of the Commission-approved cyber security plan. The requirements of 10 E:\FR\FM\09NON1.SGM 09NON1 68838 Federal Register / Vol. 75, No. 216 / Tuesday, November 9, 2010 / Notices CFR 73.54, ‘‘Protection of digital computer and communication systems and networks,’’ establish the requirements for a cyber security program. 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: Criterion 1: The proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated The proposed change incorporates a new requirement in the Facility Operating License to implement and maintain the Cyber Security Plan as part of the facility’s overall program for physical protection. Inclusion of the Cyber Security Plan in the Facility Operating License itself does not involve any modifications to the safety-related structures, systems or components (SSCs). Rather, the Cyber Security Plan describes how the requirements of 10 CFR 73.54 are to be implemented to identify, evaluate, and mitigate cyber attacks up to and including the design basis cyber attack threat, thereby achieving high assurance that the facility’s digital computer and communications systems and networks are protected from cyber attacks. The implementation and incorporation of the Cyber Security Plan into the Facility Operating License will not alter previously evaluated Final Safety Analysis Report (FSAR) design basis accident analysis assumptions, add any accident initiators, or affect the function of the plant safety-related SSCs as to how they are operated, maintained, modified, tested, or inspected. Therefore, it is concluded that this change does not involve a significant increase in the probability or consequences of an accident previously evaluated. Criterion 3: The proposed change does not involve a significant reduction in a margin of safety The margin of safety is associated with the confidence in the ability of the fission product barriers (i.e., fuel cladding, reactor coolant pressure boundary, and containment structure) to limit the level of radiation to the public. The proposed amendment would not alter the way any safety-related SSC functions and would not alter the way the plant is operated. The amendment provides assurance that safety-related SSCs are protected from cyber attacks. The proposed amendment would not introduce any new uncertainties or change any existing uncertainties associated with any safety limit. The proposed amendment would have no impact on the structural integrity of the fuel cladding, reactor coolant pressure boundary, or containment structure. Based on the above considerations, the proposed amendment would not degrade the confidence in the ability of the fission product barriers to limit the level of radiation to the public. 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: John O’Neill, Esq., Pillsbury Winthrop Shaw Pittman LLP, 2300 N Street, NW., Washington, DC 20037. NRC Branch Chief: Michael T. Markley. wwoods2 on DSK1DXX6B1PROD with NOTICES_PART 1 Criterion 2: The proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated This proposed amendment provides assurance that safety-related SSCs are protected from cyber attacks. Implementation of 10 CFR 73.54 and the inclusion of the Cyber Security Plan in the Facility Operating License do not result in the need of any new or different FSAR design basis accident analysis. It does not introduce new equipment that could create a new or different kind of accident, and no new equipment failure modes are created. As a result, no new accident scenarios, failure mechanisms, or limiting single failures are introduced as a result of this proposed amendment. Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated. VerDate Mar<15>2010 15:18 Nov 08, 2010 Jkt 223001 PO 00000 Frm 00091 Fmt 4703 Sfmt 4703 Order Imposing Procedures for Access to Sensitive Unclassified NonSafeguards Information for Contention Preparation Arizona Public Service Company, et al., Docket Nos. STN 50–528, STN 50–529, and STN 50–530, Palo Verde Nuclear Generating Station, Units 1, 2, and 3, Maricopa County, Arizona Dominion Energy Kewaunee, Inc., Docket No. 50–305, Kewaunee Power Station, Kewaunee County, Wisconsin FirstEnergy Nuclear Operating Company, et al., Docket No. 50–440, Perry Nuclear Power Plant, Unit 1, Lake County, Ohio NextEra Energy Duane Arnold, LLC, Docket No. 50–331, Duane Arnold Energy Center, Linn County, Iowa Southern California Edison Company, et al., Docket Nos. 50–361 and 50–362, San Onofre Nuclear Generating Station, Units 2 and 3, San Diego County, California STP Nuclear Operating Company, Docket Nos. 50–498 and 50–499, South Texas Project, Units 1 and 2, Matagorda County, Texas Union Electric Company, Docket No. 50–483, Callaway Plant, Unit 1, Callaway County, Missouri A. This Order contains instructions regarding how potential parties to this proceeding may request access to documents containing Sensitive Unclassified Non-Safeguards Information (SUNSI). B. Within 10 days after publication of this notice of hearing and opportunity to petition for leave to intervene, any potential party who believes access to SUNSI is necessary to respond to this notice may request 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. C. 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: E:\FR\FM\09NON1.SGM 09NON1 Federal Register / Vol. 75, No. 216 / Tuesday, November 9, 2010 / Notices U.S. Nuclear Regulatory Commission, 11555 Rockville Pike, Rockville, Maryland 20852. The e-mail 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: (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) 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; D. Based on an evaluation of the information submitted under paragraph C.(3) the NRC staff will determine within 10 days of receipt of the request whether: (1) There is a reasonable basis to believe the petitioner is likely to establish standing to participate in this NRC proceeding; and (2) The requestor has established a legitimate need for access to SUNSI. E. If the NRC staff determines that the requestor satisfies both D.(1) and D.(2) above, the NRC staff will notify the requestor in writing that access to SUNSI has been granted. The written notification will contain instructions on how the requestor may obtain copies of the requested documents, and any other conditions that may apply to access 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. F. Filing of Contentions. Any contentions in these proceedings that are based upon the information received as a result of the request made for SUNSI must be filed by the requestor no later than 25 days after the requestor is 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. G. Review of Denials of Access. (1) If the request for access to SUNSI is denied by the NRC staff either after a determination on standing and need for access, 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) 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 68839 2.318(a); or (c) if another officer has been designated to rule on information access issues, with that officer. H. 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 I. The Commission expects that the NRC staff and presiding officers (and any other reviewing officers) will consider and resolve requests for access to SUNSI, and motions for protective orders, in a timely fashion in order to minimize any unnecessary delays in identifying those petitioners who have standing and who have propounded contentions meeting the specificity and basis requirements in 10 CFR Part 2. Attachment 1 to this Order summarizes the general target schedule for processing and resolving requests under these procedures. It is so ordered. Dated at Rockville, Maryland, this 1st day of November 2010. For the Commission. Annette L. Vietti-Cook, Secretary of the Commission. ATTACHMENT 1—GENERAL TARGET SCHEDULE FOR PROCESSING AND RESOLVING REQUESTS FOR ACCESS TO SENSITIVE UNCLASSIFIED NON-SAFEGUARDS INFORMATION IN THIS PROCEEDING Day Event/activity 0 ................................. Publication of Federal Register notice of hearing and opportunity to petition for leave to intervene, including order with instructions for access requests. 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. 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). 10 ............................... wwoods2 on DSK1DXX6B1PROD with NOTICES_PART 1 60 ............................... 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. VerDate Mar<15>2010 15:18 Nov 08, 2010 Jkt 223001 2 Any motion for Protective Order or draft NonDisclosure 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. PO 00000 Frm 00092 Fmt 4703 Sfmt 4703 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. E:\FR\FM\09NON1.SGM 09NON1 68840 Federal Register / Vol. 75, No. 216 / Tuesday, November 9, 2010 / Notices ATTACHMENT 1—GENERAL TARGET SCHEDULE FOR PROCESSING AND RESOLVING REQUESTS FOR ACCESS TO SENSITIVE UNCLASSIFIED NON-SAFEGUARDS INFORMATION IN THIS PROCEEDING—Continued Day Event/activity 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). 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. Deadline for NRC staff reply to motions to reverse NRC staff determination(s). (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. 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. Deadline for filing executed Non-Disclosure Affidavits. Access provided to SUNSI consistent with decision issuing the protective order. 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. (Contention receipt +25) Answers to contentions whose development depends upon access to SUNSI. (Answer receipt +7) Petitioner/Intervenor reply to answers. Decision on contention admission. 25 ............................... 30 ............................... 40 ............................... A ................................ A + 3 .......................... A + 28 ........................ A + 53 ........................ A + 60 ........................ > A + 60 .................... [FR Doc. 2010–28129 Filed 11–8–10; 8:45 am] Week of December 6, 2010—Tentative BILLING CODE 7590–01–P There are no meetings scheduled for the week of December 6, 2010. NUCLEAR REGULATORY COMMISSION Week of December 13, 2010—Tentative [NRC–2010–0002] 2 p.m. Briefing on Construction Reactor Oversight Program (cROP) (Public Meeting). (Contact: Aida Rivera-Varona, 301–415–4001). This meeting will be Webcast live at the Web address—http://www.nrc.gov. * * * * * * The schedule for Commission meetings is subject to change on short notice. To verify the status of meetings, call (recording)—(301) 415–1292. Contact person for more information: Rochelle Bavol, (301) 415–1651. * * * * * The NRC Commission Meeting Schedule can be found on the Internet at: http://www.nrc.gov/about-nrc/policymaking/schedule.html. * * * * * The NRC provides reasonable accommodation to individuals with disabilities where appropriate. If you need a reasonable accommodation to participate in these public meetings, or need this meeting notice or the transcript or other information from the public meetings in another format (e.g. braille, large print), please notify Angela Bolduc, Chief, Employee/Labor Relations and Work Life Branch, at 301– Thursday, December 16, 2010. Sunshine Federal Register Notice Nuclear Regulatory Commission. DATES: Weeks of November 8, 15, 22, 29, December 6, 13, 2010. PLACE: Commissioners’ Conference Room, 11555 Rockville Pike, Rockville, Maryland. STATUS: Public and Closed. AGENCY HOLDING THE MEETINGS: Week of November 8, 2010 There are no meetings scheduled for the week of November 8, 2010. wwoods2 on DSK1DXX6B1PROD with NOTICES_PART 1 Week of November 15, 2010—Tentative There are no meetings scheduled for the week of November 15, 2010. Week of November 22, 2010—Tentative There are no meetings scheduled for the week of November 22, 2010. Week of November 29, 2010—Tentative Tuesday, November 30, 2010 1 p.m. Briefing on Security Issues (Closed—Ex. 1). VerDate Mar<15>2010 15:18 Nov 08, 2010 Jkt 223001 PO 00000 Frm 00093 Fmt 4703 Sfmt 4703 492–2230, TDD: 301–415–2100, or by e-mail at angela.bolduc@nrc.gov. Determinations on requests for reasonable accommodation will be made on a case-by-case basis. * * * * * This notice is distributed electronically to subscribers. If you no longer wish to receive it, or would like to be added to the distribution, please contact the Office of the Secretary, Washington, DC 20555 (301–415–1969), or send an e-mail to darlene.wright@nrc.gov. Dated: November 4, 2010. Rochelle C. Bavol, Policy Coordinator, Office of the Secretary. [FR Doc. 2010–28393 Filed 11–5–10; 4:15 pm] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION Request for a License To Import Radioactive Waste Pursuant to 10 CFR 110.70 (b) ‘‘Public Notice of Receipt of an Application,’’ please take notice that the Nuclear Regulatory Commission (NRC) has received the following request for an import license. Copies of the request are available electronically through ADAMS and can be accessed through the Public Electronic Reading Room (PERR) link E:\FR\FM\09NON1.SGM 09NON1
[Pages 68831-68840]
[FR Doc No: 2010-28129]
[NRC-2010-0335]
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. Requests for a
01F21, 11555 Rockville Pike (first floor), Rockville, Maryland, or at
(1) a digital identification (ID) certificate, which allows the
available on the NRC public Web site at
the document and sends the submitter an e-mail notice confirming
receipt of the document. The E-Filing system also distributes an e-mail
amendments would approve the proposed Cyber Security Plan and
implementation schedule and would revise the existing Facility
Operating License (FOL) Physical Protection License Condition to
require the licensee to fully implement and maintain in effect all
provisions of the Commission-approved Cyber Security Plan as required
by 10 CFR 73.54.
Criterion 1. Does the proposed amendment involve a significant increase
in the probability or consequences of an accident previously evaluated?
systems, or components (SSCs). Rather, the Cyber Security Plan
attacks. The addition of the Cyber Security Plan to the Physical
Security Plan will not alter previously evaluated Updated Final
Safety Analysis Report (UFSAR) design basis accident analysis
Criterion 2. Does the proposed amendment create the possibility of a
need of any new or different FSAR [Final Safety Analysis Report]
Criterion 3. Does the proposed amendment involve a significant
Dominion Energy Kewaunee, Inc., Docket No. 50-305, Kewaunee Power
proposed an amendment to the Facility Operating License for KPS. In the
same amendment request letter, sent under Dominion Resources Services,
Inc. letterhead, Millstone Power Station Units 2 and 3; North Anna
Power Station Units 1 and 2; and Surry Power Station Units 1 and 2
This notice only addresses the application as it pertains to KPS. The
licensee requested NRC approval of the KPS Cyber Security Plan,
provided a proposed implementation schedule, and proposed to add a
sentence to License Condition 2.C.(4), ``Physical Protection,'' of KPS
Facility Operating License (FOL) DPR-43 that would affirm when the
licensee would fully implement and maintain in effect all provisions of
consideration. The NRC staff reviewed the licensee's NHSC analysis and
has prepared its own as follows:
Criterion 1. Does the proposed change involve a significant increase in
Criterion 2. Does the proposed change create the possibility of a new
Criterion 3. Does the proposed change involve a significant reduction
amendment to the Facility operating License (FOL) includes: (1) The
proposed Perry Nuclear Power Plant (PNPP) Unit No. 1 Cyber Security
Plan, (2) an implementation schedule, and (3) a proposed sentence to be
added to the existing FOL Physical Protection license condition 2.E to
require the FirstEnergy Nuclear Operating Company (FENOC, the licensee)
to fully implement and maintain in effect all provisions of the
Commission approved cyber plan as required by 10 CFR 73.54. Federal
Register notice issued the final rule that amended 10 CFR Part 73. The
licensee currently licensed to operate a nuclear power plant under 10
CFR Part 50 to submit a cyber security plan that satisfies the
requirements of the rule. Each submittal must include a proposed
implementation schedule and implementation of the licensee's cyber
security program must be consistent with the approved schedule. The
background for this application is addressed by the NRC's Notice of
Availability, Federal Register Notice, Final Rule 10 CFR Part 73, Power
Reactor Security Requirements, published on March 27, 2009 (74 FR
13926).
The proposed change is required by 10 CFR 73.54 and includes
three parts. The first part is the submittal of the Plan for NRC
review and approval. The Plan provides a description of how the
requirements of the rule will be implemented at the PNPP. The Plan
establishes the licensing basis for the FENOC cyber security program
for the PNPP. The Plan establishes how to achieve high assurance
that nuclear power plant digital computer and communication systems
and networks associated with the following are adequately protected
against cyber attacks up to and including the design basis threat:
3. Emergency preparedness functions including offsite
4. Support systems and equipment which if compromised, would
Part one of the proposed change is designed to achieve high
assurance that the systems within the scope of the rule are
protected from cyber attacks. The Plan itself does not require any
plant modifications. However, the Plan does describe how plant
modifications which involve digital computer systems are reviewed to
provide high assurance of adequate protection against cyber attacks,
up to and including the design basis threat as defined in the rule.
The proposed change does not alter the plant configuration, require
new plant equipment to be installed, alter accident analysis
assumptions, add any initiators, affect the function of plant
systems, or affect the manner in which systems are operated. The
first part of the proposed change is designed to achieve high
protected from cyber attacks and has no impact on the probability or
schedule. The third part adds a sentence to the existing FOL license
condition 2.E for Physical Protection. Both of these changes are
administrative and have no impact on the probability or consequences
up to and including the design basis threat defined in the rule. The
proposed change does not alter the plant configuration, require new
plant equipment to be installed, alter accident analysis
protected from cyber attacks and does not create the possibility of
administrative and do not create the possibility of a new or
protected from cyber attacks. Plant safety margins are established
through Limiting Conditions for Operation, Limiting Safety System
Settings and Safety limits specified in the Technical
Specifications, methods of evaluation that establish design basis or
change Updated Final Safety Analysis. Because there is no change to
these established safety margins, the proposed change does not
administrative and do not involve a significant reduction in a
proposes an amendment to the Facility Operating License for the Duane
Arnold Energy Center. The licensee requests NRC approval of the NextEra
Energy Duane Arnold Cyber Security Plan, provides an implementation
schedule, and adds a sentence to the existing Operation License
Physical Protection license condition to require NextEra Energy Duane
Arnold to fully implement and maintain in effect all provisions of the
Commission-approved Cyber Security Plan.
consideration (NSHC). The licensee's NSHC analysis, addressing each
issue described above, is reproduced below:
result of this proposed amendment. Therefore, the proposed amendment
does not create a possibility for an accident of a new or different
type than those previously evaluated.
the public. Therefore, the proposed change does not involve a
Attorney for licensee: Mr. R.E. Helfrich, Florida Power & Light
Operating License Physical Protection License Condition to require the
licensee to fully implement and maintain in effect all provisions of
the Commission-approved Cyber Security Plan as required by 10 CFR
Criterion 1. Do the proposed amendments involve a significant increase
Facility Operating License to implement and maintain the Cyber
safety-related structures, systems, or components (SSCs). Rather,
Security Plan into the Facility Operating License will not alter
initiators, or affect the function of the plant safety-related SSCs
as to how they are operated, maintained, modified, tested, or
Criterion 2. Do the proposed amendments create the possibility of a new
SSCs are protected from cyber attacks. Implementation
of 10 CFR 73.54 and the inclusion of the Cyber Security Plan in the
different UFSAR design basis accident analysis. It does not
accident, and no new equipment failure modes are created. As a
result, no new accident scenarios, failure mechanisms, or limiting
Criterion 3. Do the proposed amendments involve a significant reduction
not alter the way the plant is operated.
The amendment provides assurance that safety-related SSCs are
protected from cyber attacks. The proposed amendment would not
Description of amendment request: This amendments request contains
amendments would approve the STP Nuclear Operating Company's request
for approval of South Texas Project, Units 1 and 2 Cyber Security Plan
in accordance with 10 CFR 73.54. The amendments would also revise
Section 2.F of the Facility Operating Licenses (FOLs) numbered NPF-76
and NPF-80 to incorporate the requirement to fully implement and
maintain in effect all provisions of the Commission-approved cyber
security plan. The requirements of 10 CFR 73.54, ``Protection of
digital computer and communication systems and networks,'' establish
the requirements for a cyber security program.
Criterion 1. Do the proposed changes involve a significant increase in
The proposed change incorporates a new requirement in the FOL to
implement and maintain the Cyber Security Plan as part of the
facility's overall program for physical protection. Inclusion of the
Cyber Security Plan in the FOL itself does not involve any
modifications to the safety related structures, systems or
components (SSCs). Rather, the Cyber Security Plan describes how the
requirements of 10 CFR 73.54 are to be implemented to identify,
basis cyber attack threat, thereby achieving high assurance that the
facility's digital computer and communications systems and networks
are protected from cyber attacks. The implementation and
incorporation of the Cyber Security Plan into the FOL will not alter
initiators, or affect the function of the plant safety related SSCs
Criterion 2. Do the proposed changes create the possibility of a new or
This proposed amendment provides assurance that safety related
73.54 and the inclusion of the Cyber Security Plan in the FOL do not
result in the need of any new or different UFSAR design basis
Criterion 3. Do the proposed changes involve a significant reduction in
would not alter the way any safety related SSC functions and would
amendment would approve the Union Electric Company's request for
approval of the Callaway Plant, Unit 1 Cyber Security Plan in
accordance with 10 CFR 73.54. The amendments would also revise Section
2.E of the Facility Operating License (FOL) numbered NPF-30 to
incorporate the provisions to implement and maintain in effect all
provisions of the Commission-approved cyber security plan. The
requirements of 10
CFR 73.54, ``Protection of digital computer and communication systems
and networks,'' establish the requirements for a cyber security
The proposed change incorporates a new requirement in the
previously evaluated Final Safety Analysis Report (FSAR) design
basis accident analysis assumptions, add any accident initiators, or
affect the function of the plant safety-related SSCs as to how they
73.54 and the inclusion of the Cyber Security Plan in the Facility
Operating License do not result in the need of any new or different
FSAR design basis accident analysis. It does not introduce new
no new equipment failure modes are created. As a result, no new
courier mail address for both offices is:
fashion in order to minimize an