Source: https://www.federalregister.gov/documents/2011/04/12/2011-8453/applications-and-amendments-to-facility-operating-licenses-involving-proposed-no-significant-hazards
Timestamp: 2018-04-19 18:45:02
Document Index: 144258836

Matched Legal Cases: ['art 2', 'art002', 'art002', 'art 73', 'art 50', 'art 50', '§\u200973', '§\u200973', '§\u200973', '§\u200973', '§\u200973']

20377-20385 (9 pages)
NRC-2011-0068
NextEra Energy Point Beach, LLC, Docket Nos. 50-266 and 50-301, Point Beach Nuclear Plant (PBNP), Units 1 and 2, Town of Two Creeks, Manitowoc County, Wisconsin
Southern Nuclear Operating Company, Inc. Docket Nos. 50-424 and 50-425, Vogtle Electric Generating Plant, Units 1 and 2, Burke County, Georgia.
https://www.federalregister.gov/d/2011-8453 https://www.federalregister.gov/d/2011-8453
Pursuant to section 189a.(2) of the Atomic Energy Act of 1954, as amended (the Act), the U.S. Nuclear Regulatory Commission (the Commission or NRC) is publishing this notice. The Act requires the Commission to publish notice of any amendments issued, or proposed to be issued and grants the Commission the authority to issue and make immediately effective any amendment to an operating license 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.
The Commission has made a proposed determination that the following amendment requests involve no significant hazards consideration. Under the Commission's regulations in Title 10 of the Code of Federal Regulations (10 CFR), Section 50.92(c), 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; (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.
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. 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 01 F21, 11555 Rockville Pike (first floor), Rockville, Maryland, or at http://www.nrc.gov/​reading-rm/​doc-collections/​cfr/​part002/​part002-0309.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/​adams.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.
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 Start Printed Page 20378contention 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.
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 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 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'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.
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 Start Printed Page 20379excerpts 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.
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 01 F21, 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.
Exelon Generation Company, LLC, et al., Docket No. 50-219, Oyster Creek Nuclear Generating Station, Ocean County, New Jersey Exelon Generation Company, LLC, and PSEG Nuclear LLC, Docket Nos. 50-277 and 50-278, Peach Bottom Atomic Power Station, Units 2 and 3, York and Lancaster Counties, Pennsylvania
Date of amendment request: November 23, 2009, as supplemented by letters dated January 15, July 23, August 18, November 18, September 24 and December 21, 2010.
Description of amendment request: This amendment request contains sensitive unclassified non-safeguards information (SUNSI). This proposed amendment requests approval of the Exelon Cyber Security Plan, provides an Implementation Schedule, and adds a sentence to the existing Facility Operating License (FOL) Physical Protection license condition to require Exelon to fully implement and maintain in effect all provisions of the approved Cyber Security Plan. This proposed amendment is intended to conform to the model application contained in NEI 08-09, Revision 6, “Cyber Security Plan for Nuclear Power Reactors.”
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 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. Any plant modifications or changes resulting from implementation of the Cyber Security Plan will be evaluated per 10 CFR 50.59 to determine if a License Amendment is required. Changes will be evaluated per 10 CFR 50.54(q) to determine if the effectiveness of the site Emergency Plan is reduced. Changes will be evaluated per 10 CFR 50.54(p) to determine if the effectiveness of the site Security Plan is reduced. Prior NRC approval will be obtained if required by these evaluations.
In addition, an editorial change to correct two typographical errors as part of the Braidwood FOL revisions for Unit 1 and Unit 2 is administrative in nature and has no impact on the probability or consequences of an 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 a plan in the FOL 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. In addition, an editorial change to correct two typographical errors as part of the Braidwood FOL revisions for Unit 1 and Unit 2 is administrative in nature and does not create the possibility of a new or different kind of accident.
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. In addition, an editorial change to correct two typographical errors as part of the Braidwood FOL revisions for Unit 1 and Unit 2 is administrative in nature and has no impact on the margin of safety. 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. Start Printed Page 20380
Date of amendment request: July 8, 2010, as supplemented by letters dated September 28, November 12, and November 23, 2010.
Description of amendment request: This amendment request contains Sensitive Unclassified Non-Safeguards Information (SUNSI). The proposed amendment includes three parts: The proposed PBNP Cyber Security Plan, an implementation schedule, and a proposed sentence to be added to the Renewed Facility Operating License Physical Protection license condition for NextEra Energy (the licensee) to fully implement and maintain in effect all provisions of the Commission-approved PBNP Cyber Security Plan as required by Title 10 of the Code of Federal Regulations (10 CFR) Section 73.54. The Federal Register notice dated March 27, 2009, 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 Part 50 to submit a Cyber Security Plan that satisfies the requirements of the Rule. The regulation also requires that each submittal include a proposed implementation schedule, and the implementation of the licensee's Cyber Security Program must be consistent with the approved schedule. The background for this application is addressed by the Nuclear Regulatory Commission's (NRC) Notice of Availability published on March 27, 2009 (74 FR 13926).
The proposed amendment incorporates a new requirement in the Renewed 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 Renewed 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.
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 Renewed 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.
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.
Attorney for licensee: William Blair, Senior Attorney, NextEra Energy Point Beach, LLC,. P. O. Box 14000, Juno Beach, FL 33408-0420.
Date of amendment request: August 5, 2010, as supplemented on November 30, 2010.
Description of amendment request: This amendment request contains sensitive unclassified non-safeguards information (SUNSI). The proposed change requests to incorporate a new requirement into the facility operating license (FOL) to implement and maintain a cyber security plan (CSP). The CSP describes how the requirements of Title 10 of the Code of Federal Regulations (10 CFR), Section 73.54 will be implemented in order to protect the health and safety of the public from radiological sabotage as a result of a cyber attack. The plan provides a description of how the requirements of 10 CFR 73.54 will be implemented at VCSNS Unit 1. The CSP establishes the licensing basis for the cyber security program for VCSNS Unit 1. The CSP establishes how to achieve high assurance that nuclear power plant digital computer and communication systems and networks associated with certain systems are adequately protected against cyber attacks up to and including the design basis threat.
The proposed change incorporates a new requirement, in the Operating License, to implement and maintain a cyber security plan as part of the facility's overall program for physical protection. The Cyber Security Plan itself does not require any plant modifications. Rather, the Cyber Security Plan describes how the requirements of 10 CFR 73.54 are implemented in order to identify, evaluate, and mitigate cyber attacks up to and including the design basis threat, thereby achieving high assurance that the facility's digital computer and communications systems and networks are protected from cyber attacks. The proposed change requiring the implementation and maintenance of a Cyber Security Plan does not alter the plant configuration, require new plant equipment to be installed, alter accident analysis assumptions, add any accident initiators, or affect the function of plant systems or the manner in which systems are operated, maintained, modified, tested, or inspected.
Therefore, the inclusion of the Cyber Security Plan as a part of the facility's other physical protection programs specified in the facility's operating license has no impact on the probability or consequences of an accident previously evaluated.
The proposed change incorporates a new requirement, in the Operating License, to implement and maintain a cyber security plan as part of the facility's overall program for physical protection. The creation of the possibility of a new or different kind of accident requires creating one or more new accident precursors. New accident precursors may be created by modifications of the plant's configuration, including changes in the allowable modes of operation. The Cyber Security Plan itself does not require any plant modifications, nor does the Cyber Security Plan affect the control parameters governing unit operation or the response of plant equipment to a transient condition. Because the proposed change does not change or introduce any new equipment, modes of system operation, or failure mechanisms, no new accident precursors are created.
The proposed change incorporates a new requirement, in the Operating License, to implement and maintain a cyber security plan as part of the facility's overall program for physical protection. Plant safety margins are established through limiting Conditions for Operation, Limiting Safety System Settings, and Safety limits specified in the Technical Specifications. Because the Cyber Security Plan itself does not require any plant modifications and does not alter the operation of plant equipment, the proposed change does not change established safety margins.
Southern Nuclear Operating Company, Inc. (SNC), Georgia Power Company, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, City of Dalton, Georgia, Docket Nos. 50-321 and 50-366, Edward I. Hatch Nuclear Plant, Units 1 and 2, Appling County, Georgia;
Southern Nuclear Operating Company, Inc., Docket Nos. 50-348 and 50-364, Joseph M. Farley Nuclear Plant, Units 1 and 2, Houston County, Alabama;
Description of amendment request: This amendment request contains sensitive unclassified non-safeguards information (SUNSI). The license amendment request (LAR) proposes a revision to the Renewed Facility Operating License (FOL) to require the license to fully implement and maintain in effect all provisions of a Nuclear Regulatory Commission (NRC)-approved cyber security plan (CSP). The LAR was submitted pursuant to Section 73.54 of Title 10 of the Code of Federal Regulations (10 CFR) which requires licensees currently licensed to operate a nuclear power plant under 10 CFR Part 50 to submit a CSP for NRC review and approval.
The SNC Cyber Security Plan generally conforms to the template provided in [Nuclear Energy Institute] NEI 08-09, Revision 6, and provides a description of how the requirements of § 73.54 will be implemented at Hatch, Farley, and Vogtle. [ * * *]. Accordingly, the SNC Cyber Security Plan establishes the licensing basis for the cyber security program for Hatch, Farley, and Vogtle sites. The SNC Cyber Security Plan provides 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 communications; and
4. Support systems and equipment which, if compromised, would adversely impact safety, security, or emergency preparedness functions. These systems include, in part, all non-safety related balance of plant equipment which if compromised, could result in a reactor scram or actuation of a safety-related system and therefore, impact reactivity.
The SNC Cyber Security Plan itself does not require any plant modifications. However, the plan describes appropriate configuration management requirements to assure plant modifications involving digital computer systems are reviewed to provide adequate protection against cyber attacks, up to and including the design basis threat as defined in § 73.1. The proposed change does not alter the plant configuration, involve the installation of new plant equipment, alter accident analysis assumptions, add any new initiators, or affect the function of plant systems or the manner in which systems are operated, maintained, modified, tested, or inspected. The SNC Cyber Security Plan is designed to provide high assurance that the systems within the scope of § 73.54 are protected from cyber attacks and does not impact the probability or consequences of an accident previously evaluated.
In addition, the proposed change modifies the existing FOL for each SNC-operated facility to incorporate the SNC Cyber Security Plan into the existing condition for physical protection. This change is administrative in nature and does not impact the probability or consequences of an accident previously evaluated.
The SNC Cyber Security Plan generally conforms to the template provided in NEI 08-09, Revision 6. [ * * * ]. Accordingly, the SNC Cyber Security Plan provides high assurance that digital computer and communication systems and networks associated with the following are adequately Start Printed Page 20382protected against cyber attacks up to and including the design basis threat:
3. Emergency preparedness functions, including offsite communications; and,
The proposed SNC Cyber Security Plan does not alter plant configuration, install new plant equipment, alter accident analysis assumptions, add any initiators, or affect the function of plant systems or the manner in which systems are operated, maintained, tested, or inspected. The proposed SNC Cyber Security Plan includes appropriate configuration management controls to assure modifications do not introduce vulnerability to cyber attacks. The SNC Cyber Security Plan provides high assurance that the systems within the scope of § 73.54 are adequately protected from cyber attacks. Accordingly, the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated.
In addition, the proposed change modifies the existing FOL for each SNC-operated facility to incorporate the SNC Cyber Security Plan by reference. This change is administrative in nature and does not create the possibility of a new or different kind of accident previously evaluated.
The SNC Cyber Security Plan generally conforms to the template provided by NEI 08-09, Revision 6, and provides a description of how the requirements of § 73.54 will be implemented at Hatch, Farley, and Vogtle. [ * * * ]. Accordingly, the SNC Cyber Security Plan establishes the licensing basis for the cyber security program for Hatch, Farley, and Vogtle sites. The SNC Cyber Security Plan provides 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:
The proposed SNC Cyber Security Plan does not alter plant configuration, install new plant equipment, alter accident analysis assumptions, add any initiators, or affect the function of plant systems or the manner in which systems are operated, maintained, tested, or inspected. Plant safety margins are established through Limiting Conditions for Operation, Limiting Safety System Settings and Safety Limits specified in the Technical Specifications. Because there is no change to these established safety margins, the proposed change does not involve a reduction in a margin of safety.
In addition, the proposed change modifies the existing FOL for each SNC-operated facility to incorporate the SNC Cyber Security Plan by reference. This change is administrative in nature and does not involve a reduction in margin of safety.
Attorney for licensee: Arthur H. Domby, Troutman Sanders Nations Bank Plaza, Suite 5200, 600 Peachtree Street, NE., Atlanta, Georgia 30308-2216.
Exelon Generation Company, LLC, Docket Nos. STN 50-456 and STN 50-457, Braidwood Station, Will County, Illinois
South Carolina Electric & Gas Company, Docket No. 50-395, South Carolina Public Service Authority, Virgil C. Summer Nuclear Station (VCSNS), Unit 1, Fairfield County, South Carolina
Southern Nuclear Operating Company, Inc. (SNC), Georgia Power Company, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, City of Dalton, Georgia, Docket Nos. 50-321 and 50-366, Edward I. Hatch Nuclear Plant, Units 1 and 2, Appling County, Georgia
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: Start Printed Page 20383Rulemakings 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 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:
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