Source: https://www.federalregister.gov/documents/2010/08/20/2010-20692/notice-applications-and-amendments-to-facility-operating-licenses-involving-proposed-no-significant
Timestamp: 2017-09-22 15:42:02
Document Index: 308469654

Matched Legal Cases: ['art 73', 'art 50', 'art 73', 'art 73', 'art 50', 'art 73', 'art 73', 'art 50', 'art 73']

51490-51498 (9 pages)
NRC-2010-0279
Tennessee Valley Authority, Docket Nos. 50-390, Watts Bar Nuclear Plant (WBN), Unit 1, Rhea County, Tennessee
Criterion 1: The Proposed Amendment Does Not Involve a Significant Increase in the Probability or Consequences of an Accident Previously Evaluated
Criterion 2: The Proposed Amendment Does Not Create the Possibility of a New or Different Kind of Accident From Any Accident Previously Evaluated
Criterion 3: The Proposed Amendment Does Not Involve a Significant Reduction in a Margin of Safety
https://www.federalregister.gov/d/2010-20692 https://www.federalregister.gov/d/2010-20692
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 51491contention will not be permitted to participate as a party.
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 Start Printed Page 51492information. 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.
The proposed amendment incorporates a new requirement in the FOL [facility operating license] to implement and maintain a Cyber Security Plan as part of Energy Northwest's overall program for physical protection of CGS [Columbia Generating Station]. Inclusion of the CGS Cyber Security Plan in the FOL itself does not involve any modifications to any safety-related structures, systems or components (SSCs). Rather, the CGS 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 CGS's digital computer and communications systems and networks are protected from cyber attacks. The CGS 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.
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 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.
Description of amendment request: This amendment request contains sensitive unclassified non-safeguards information (SUNSI). The proposed amendment to the Renewed Facility Operating License (FOL) includes: (1) The proposed JAF Cyber Security Plan, (2) an implementation schedule, and (3) a proposed sentence to be added to the existing renewed FOL Physical Protection license condition for JAFNPP requiring Entergy to fully implement and maintain in effect all provisions of the Commission-approved JAFNPP Cyber Security Plan as required by 10 CFR 73.54. 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 of this chapter 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 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 Start Printed Page 51493consideration, which is presented below:
As required by 10 CFR 73.54 Entergy is submitting a cyber security plan for NRC review and approval for JAF. The JAF Cyber Security Plan 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 JAF Cyber Security Plan does not require any plant modifications which affect the performance capability of the, structures, systems, and components relied upon to mitigate the consequences of postulated accidents. The JAF Cyber Security Plan is designed to achieve high assurance that the systems within the scope of 10 CFR 73.54 are protected from cyber attacks and has no impact on the probability or consequences of an accident previously evaluated.
As required by 10 CFR 73.54 Entergy is submitting a cyber security plan for NRC review and approval for JAF. The JAF Cyber Security Plan 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 JAF Cyber Security Plan does not require any plant modifications which affect the performance capability of the structures, systems, and components relied upon to mitigate the consequences of postulated accidents. The JAF Cyber Security Plan is designed to achieve high assurance that the systems within the scope of the 10 CFR 73.54 Rule are protected from cyber attacks and does not create the possibility of a new or different kind of accident from any accident previously evaluated.
As required by 10 CFR 73.54 Entergy is submitting a cyber security plan for NRC review and approval for JAF. 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 as [a] result of the implementation of the JAF Cyber Security Plan, the proposed change does not involve a significant reduction in a margin of safety.
Description of amendment request: This amendment request contains sensitive unclassified non-safeguards information (SUNSI). The proposed amendment to the Facility Operating License (FOL) includes: (1) The proposed Pilgrim Nuclear Power Station (PNPS) Cyber Security Plan, (2) an implementation schedule, and (3) a proposed sentence to be added to the existing FOL Physical Protection license condition for PNPS requiring Entergy to fully implement and maintain in effect all provisions of the Commission-approved PNPS Cyber Security Plan as required by 10 CFR 73.54. 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 of this chapter 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 Notice of Availability, Federal Register Notice, Final Rule 10 CFR part 73, Power Reactor Security Requirements, published on March 27, 2009, 74 FR 13926.
As required by 10 CFR 73.54 Entergy has submitted a cyber security plan for NRC review and approval for Pilgrim Nuclear Power Station (PNPS). The PNPS Cyber Security Plan does not require any plant modifications which affect the performance capability of the, structures, systems, and components relied upon to mitigate the consequences of postulated accidents. The PNPS Cyber Security Plan 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 PNPS Cyber Security Plan is designed to achieve high assurance that the systems within the scope of the 10 CFR 73.54 Rule are protected from cyber attacks and has no impact on the probability or consequences of an accident previously evaluated.
As required by 10 CFR 73.54 Entergy has submitted a cyber security plan for NRC review and approval for PNPS. The PNPS Cyber Security Plan does not require any plant modifications which affect the performance capability of the structures, systems, and components relied upon to mitigate the consequences of postulated accidents. The PNPS Cyber Security Plan Start Printed Page 51494does 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 PNPS Cyber Security Plan is designed to achieve high assurance that the systems within the scope of the 10 CFR 73.54 Rule are protected from cyber attacks and does not create the possibility of a new or different kind of accident from any accident previously evaluated.
As required by 10 CFR 73.54 Entergy has submitted a cyber security plan for NRC review and approval for PNPS. 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 as [a] result of the implementation of the PNPS Cyber Security Plan, 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 Grand Gulf Nuclear Station, Unit 1 (GGNS) Cyber Security Plan (Plan) for NRC review and approval. The Plan 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 Plan does not require any plant modifications which affect the performance capability of the structures, systems, and components relied upon to mitigate the consequences of postulated accidents. The Plan is designed to achieve high assurance that the systems within the scope of the 10 CFR 73.54 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, and the third part adds a sentence to the existing Facility Operating License (FOL) license condition for Physical Protection. Both of these changes are administrative and have no impact on 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 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 Plan does not require any plant modifications which affect the performance capability of the structures, systems, and components relied upon to mitigate the consequences of postulated accidents. The Plan is designed to achieve high assurance that the systems within the scope of the 10 CFR 73.54 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, and the third part adds a sentence to the existing FOL license condition 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.
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. 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 as a result of the implementation of the Plan, 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, and the third part adds a sentence to the existing FOL license condition for Physical Protection. Both of these changes are administrative and do not involve a significant reduction in a margin of safety.
Description of amendment request: This amendment request contains sensitive unclassified non-safeguards information (SUNSI). The proposed amendment to the Facility Operating License (FOL) includes: (1) The proposed Vermont Yankee Nuclear Start Printed Page 51495Power Station (VY) Cyber Security Plan, (2) an implementation schedule, and (3) a proposed sentence to be added to the existing FOL Physical Protection license condition for VY requiring Entergy to fully implement and maintain in effect all provisions of the Commission-approved VY Cyber Security Plan as required by 10 CFR 73.54. 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 of this chapter 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 Notice of Availability, Federal Register Notice, Final Rule 10 CFR part 73, Power Reactor Security Requirements, published on March 27, 2009, 74 FR 13926.
As required by 10 CFR 73.54 Entergy has submitted a cyber security plan for NRC review and approval for Vermont Yankee Nuclear Power Station (VY). The VY Cyber Security Plan does not require any plant modifications which affect the performance capability of the, structures, systems, and components relied upon to mitigate the consequences of postulated accidents. The VY Cyber Security Plan 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 VY Cyber Security Plan is designed to achieve high assurance that the systems within the scope of 10 CFR 73.54 Rule are protected from cyber attacks and has no impact on the probability or consequences of an accident previously evaluated.
As required by 10 CFR 73.54 Entergy has submitted a cyber security plan for NRC review and approval for VY. The VY Cyber Security Plan does not require any plant modifications which affect the performance capability of the structures, systems, and components relied upon to mitigate the consequences of postulated accidents. The VY Cyber Security Plan 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 VY Cyber Security Plan is designed to achieve high assurance that the systems within the scope of the 10 CFR 73.54 Rule are protected from cyber attacks and does not create the possibility of a new or different kind of accident from any accident previously evaluated.
As required by 10 CFR 73.54 Entergy has submitted a cyber security plan for NRC review and approval for VY. 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 as [a] result of the implementation of the VY Cyber Security Plan, the proposed change does not involve a significant reduction in a margin of safety.
Date of amendment request: November 23, 2009, as supplemented December 18, 2009, and July 23, 2010.
Description of amendment request: This amendment request contains sensitive unclassified non-safeguards information (SUNSI). The proposed amendment would establish a Cyber Security Plan in conformance with the model Cyber Security Plan contained in Appendix A of Nuclear Energy Institute (NEI) document NEI-08-09, “Cyber Security Plan for Nuclear Power Reactors,” Revision 6, dated April 2010, with one deviation regarding the definition of a Cyber Attack as described in the licensee's letter. The proposed amendment requests NRC approval of the Watts Bar Nuclear Plant Cyber Security Plan, provides an Implementation Schedule, and adds a sentence to the existing Unit 1 Operating License's Physical Protection license condition to require WBN Unit 1 to fully implement and maintain in effect all provisions of the Commission approved Cyber Security Plan, as required by 10 CFR 73.54, “Protection of digital computer and communication systems and networks.”
Neither the proposed additional license condition nor the Cyber Security Plan directly impacts the physical configuration or function of plant structures, systems, or components (SSCs). Likewise, they do not change the manner in which SSCs are operated, maintained, modified, tested, or inspected. Neither the proposed additional license condition nor the Cyber Security Plan introduces any initiator of any accident previously evaluated. Any modifications to the physical configuration or function of SSCs or the manner in which SSCs are operated, maintained, modified, tested, or inspected that might result from the implementation of the Cyber Security Plan will be fully evaluated by existing regulatory processes (e.g., 10 CFR 50.59) prior to their implementation to ensure that they do not Start Printed Page 51496result in any increase in the probability or consequence of an accident previously evaluated.
Therefore, it is concluded that this proposed amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated.
Based on the above, the TVA concludes that the proposed amendment presents no significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and accordingly, a finding of no significant hazards consideration is justified.
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 Start Printed Page 51497later 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.
It is so ordered. Dated at Rockville, Maryland, this 16th day of August 2010.
Start Printed Page 51498 End Preamble
[FR Doc. 2010-20692 Filed 8-19-10; 8:45 am]