|
---|
Category:Letter
MONTHYEARIR 05000259/20240102024-11-12012 November 2024 Design Basis Assurance Inspection Program Inspection Report 05000259/2024010 and 05000260/2024010 and 05000296/2024010 IR 05000259/20240032024-11-0404 November 2024 Integrated Inspection Report 05000259/2024003 and 05000260/2024003 and 05000296/2024003 CNL-24-043, Application for Subsequent Renewed Operating Licenses, Second Safety Supplement2024-11-0101 November 2024 Application for Subsequent Renewed Operating Licenses, Second Safety Supplement ML24305A1692024-10-31031 October 2024 Site Emergency Plan Implementing Procedure Revision 05000259/LER-2024-003, Valid Specified System Actuation Caused the Automatic Start of Emergency Diesel Generators2024-10-29029 October 2024 Valid Specified System Actuation Caused the Automatic Start of Emergency Diesel Generators 05000259/LER-2024-001-02, Secondary Containment Isolation Valve Inoperable Due to Mechanical Failure2024-10-28028 October 2024 Secondary Containment Isolation Valve Inoperable Due to Mechanical Failure ML24299A2632024-10-25025 October 2024 Response to Apparent Violation in NRC Inspection Report 05000260/2024090, EA-24-075 ML24289A1232024-10-24024 October 2024 Letter to James Barstow Re Environmental Scoping Summary Report for Browns Ferry CNL-24-074, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-10-23023 October 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML24308A0042024-10-16016 October 2024 Ahc 24-1578 Environmental Review of the Browns Ferry Nuclear Plant, Units 1, 2 and 3 Subsequent License Renewal Application Limestone County CNL-24-077, Application for Subsequent Renewed Operating Licenses, Response to Request for Additional Information, Set 12024-10-0909 October 2024 Application for Subsequent Renewed Operating Licenses, Response to Request for Additional Information, Set 1 ML24270A2162024-09-27027 September 2024 Notice of Intentions Regarding Preliminary Finding from NRC Inspection Report 05000260/2024090, EA-24-075 ML24262A1502024-09-24024 September 2024 Requalification Program Inspection - Browns Ferry Nuclear Plant CNL-24-060, Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description2024-09-24024 September 2024 Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description ML24262A0602024-09-23023 September 2024 Summary of August 19, 2024, Meeting with Tennessee Valley Authority Regarding a Proposed Supplement to the Tennessee Valley Authority Nuclear Quality Assurance Plan ML24263A2952024-09-19019 September 2024 Site Emergency Plan Implementing Procedure Revision CNL-24-065, Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-09-18018 September 2024 Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000260/20240902024-09-17017 September 2024 NRC Inspection Report 05000260/2024090 and Preliminary White Finding and Apparent Violation - 1 CNL-24-062, Cycle 16 Reload Analysis Report2024-09-16016 September 2024 Cycle 16 Reload Analysis Report ML24255A8862024-09-10010 September 2024 Core Operating Limits Report for Cycle 16 Operation, Revision 0 IR 05000259/20244042024-09-0303 September 2024 Cyber Security Inspection Report 05000259/2024404 and 05000260-2024404 and 05000296/2024404-Cover Letter ML24239A3332024-09-0303 September 2024 Full Audit Plan IR 05000259/20240052024-08-26026 August 2024 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2024005, 05000260/2024005 and 05000296/2024005 ML24225A1682024-08-16016 August 2024 – Notification of Inspection and Request ML24219A0272024-08-0606 August 2024 Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations IR 05000259/20244022024-08-0606 August 2024 Security Baseline Inspection Report 05000259/2024402 and 05000260/2024402 and 05000296/2024402 IR 05000259/20240022024-08-0202 August 2024 Brown Ferry Nuclear Plant – Integrated Inspection Report05000259/2024002 and 05000260/2024002 and 05000296/2024002 ML24199A0012024-07-22022 July 2024 Clarification and Correction to Exemption from Requirement of 10 CFR 37.11(c)(2) ML24172A1342024-07-15015 July 2024 Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter ML24183A4142024-07-10010 July 2024 – License Renewal Regulatory Limited Scope Audit Regarding the Environmental Review of the License Renewal Application (EPID Number: L-2024-SLE-0000) (Docket Numbers: 50-259, 50-260, and 50-296) 05000296/LER-2024-003, Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints2024-07-0808 July 2024 Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints 05000259/LER-2024-001-01, Inoperability of Unit 3 Diesel Generator Due to Relay Failure2024-07-0303 July 2024 Inoperability of Unit 3 Diesel Generator Due to Relay Failure ML24184A1142024-07-0202 July 2024 Site Emergency Plan Implementing Procedure Revision ML24183A3842024-07-0101 July 2024 Registration of Use of Cask to Store Spent Fuel (MPC-364, -365) ML24179A0282024-06-26026 June 2024 Evaluation of Effects of Out-of-Limits Condition as Described in IWB-3720(a) 05000259/LER-2024-002, Reactor Scram Due to Generator Step-Up Transformer Failure2024-06-24024 June 2024 Reactor Scram Due to Generator Step-Up Transformer Failure ML24175A0042024-06-23023 June 2024 Interim Report of a Deviation or Failure to Comply Associated with a Valve in the Unit 3 High Pressure Coolant Injection System ML24176A1132024-06-23023 June 2024 American Society of Mechanical Engineers, Section XI, Fourth 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owner’S Activity Report Cycle 21 Oper ML24089A1152024-06-21021 June 2024 Transmittal Letter, Environmental Assessments and Findings of No Significant Impact Related to Exemption Requests from 10 CFR 37.11(c)(2) ML24155A0042024-06-18018 June 2024 Proposed Alternative to the Requirements of the ASME Code (Revised Alternative Request 0-ISI-47) ML24158A5312024-06-0606 June 2024 Registration of Use of Cask to Store Spent Fuel (MPC-361, -362, -363) ML24071A0292024-06-0505 June 2024 Subsequent License Renewal Application Enclosure 3 - Proprietary Determination Letter ML24068A2612024-06-0505 June 2024 SLRA Fluence Methodology Report - Proprietary Determination Letter ML24151A6322024-05-30030 May 2024 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report IR 05000259/20244032024-05-22022 May 2024 – Security Baseline Report 05000259/2024403 and 05000260/2024403 and 05000296/2024403 05000260/LER-2024-002, High Pressure Coolant Injection Inoperable Due to Rupture Disc Failure and Resulting System Isolation2024-05-20020 May 2024 High Pressure Coolant Injection Inoperable Due to Rupture Disc Failure and Resulting System Isolation ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24136A0702024-05-15015 May 2024 2023 Annual Radiological Environmental Operating Report IR 05000259/20240012024-05-14014 May 2024 Integrated Inspection Report 05000259/2024001, 05000260/2024001, and 05000296/2024001 CNL-24-040, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-05-0808 May 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions 2024-09-03
[Table view] |
Text
UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555*0001 June 7, 2010 Mr. R. M. Krich Vice President, Nuclear Licensing Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2, AND 3 -LICENSE AMENDMENT REQUEST FOR APPROVAL OF THE CYBER SECURITY PLAN (TAC NOS. ME2707, ME2708, AND ME2709)
Dear Mr. Krich:
By letter dated November 27,2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML093290183), as supplemented by letter dated December 18, 2009 (ADAMS Accession No. ML093570094), Tennessee Valley Authority (the licensee) submitted a license amendment request (LAR) for Browns Ferry Nuclear Plant (BFN), Units 1, 2, and 3. The LAR includes the proposed cyber security plan, proposed changes to Renewed Facility Operating License Nos. DPR-33, DPR-52, and DPR-68 for BFN Units 1, 2, and 3, respectively, and a proposed cyber security plan implementation schedule.
The proposed cyber security plan was submitted in accordance with Title 10 of the Code of Federal Regulations (10 CFR), Section 73.54. The purpose of this letter is to inform you that the U.S. Nuclear Regulatory Commission (NRC) staff has completed an initial review of this LAR. In accordance with Office of Nuclear Reactor Regulation Office Instruction L1C-109, "Acceptance Review Procedures" (ADAMS Accession No. ML09181 0088), Section 3.1.3, the NRC staff has decided to forgo the traditional acceptance review due to the complexity and "first-of-a-kind" nature of this application.
While the NRC staff has docketed your application, we are not rendering a judgment as to the acceptability of the submittal within the context of an acceptance review. The cyber security plan submittal prepared for BFN is based on an earlier version of Nuclear Energy Institute (NEI) guidance.
The NRC staff had significant generic concerns with this guidance.
As a result of NRC staff discussions with NEI and the Executive Task Force of the industry Nuclear Security Working Group (NSWG), NEI and NSWG committed to represent operating power reactor licensees in resolving these concerns.
Through numerous interactions, the NRC staff has communicated its generic concerns with the NEI guidance.
The security-related nature of the information required that these interactions be conducted in closed meetings not open to the public. A publicly available list of the specific issues discussed with NEI and NSWG was communicated to the licensees via e-mail dated March 9, 2010 (ADAMS Accession No. ML 100680284).
R. M. Krich -2 By letter dated April 28, 2010 (ADAMS Accession No. ML 101180434), NEI submitted Revision 6 to NEI 08-09, "Cyber Security Plan for Nuclear Power Reactors" (ADAMS Accession No. ML 101180437), which contains changes that address the NRC staff concerns associated with previous versions.
Based on a technical review of the document, the Office of Nuclear Security and Incident Response, in its letter dated May 5, 2010 (ADAMS Accession No. ML 101190371), concluded that submission of a cyber security plan using the template provided in NEI 08-09, Revision 6, dated April 2010, would be acceptable for use by licensees to comply with the requirements of 10 CFR 73.54, with the exception of the definition of "cyber attack." Therefore, to resolve the NRC staff's concerns with the previously submitted LAR, the licensee is requested to review the list of generic issues provided via e-mail dated March 9, 2010, and provide a revised submittal.
The licensee is also requested to provide justification for any generic issues that will not be addressed in the revised submittal.
For any changes to the Cyber Security Plan proposed in the LAR, the licensee is requested to indicate that the revised submittal supersedes, in its entirety, the previous submittal or indicate what portions are superseded.
As an alternative to addressing the individual generic issues, the licensee may submit a revised Cyber Security Plan consistent with NRC Regulatory Guide (RG) 5.71* or submit a revised Cyber Security Plan consistent with NEI 08-09, Revision 6. However, if this option is exercised, the NRC staff expects that the existing application will be withdrawn and the revised application resubmitted at the same time. The NRC staff requests that the licensee's response or revised application be submitted within 60 days of the date of this letter. Please contact me if circumstances result in the need to revise the requested response date. Following receipt and review of the licensee's response, you will be advised by separate correspondence if any further information is needed to support the NRC staff's detailed technical review.
This guidance provides an approach that the NRC staff deems acceptable for complying with the Commission's regulations regarding the protection of digital computers, communications systems, and networks from a cyber security attack.
R. M. Krich -3 If you have any questions regarding this matter, I may be reached at (301) 415-1321.
Sincerely, Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-259, 50-260, and 50-296 cc: Distribution via ListServ R. M. Krich -If you have any questions regarding this matter, I may be reached at (301) 415-1321.
Sincerely, IRA! Stewart Bailey, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-259, 50-260, and 50-296 cc: Distribution via ListServ DISTRIBUTION:
PUBLIC RidsNrrDorlDpr Resource RidsNrrDirsltsb Resource LPL2-2 Reading RidsAcrsAcnw_MailCTR Resource RidsNrrDorlLpl2-2 Resource RidsNrrLABClaytonResource
RidsNrrPMBrownsF erry Resource RidsNsirDsp Resource RidsRgn2MailCenter Resource C. Erlanger, NSIRlDSP/lSCPB P. Pederson, NSIRIDSP/ISCPB RidsOgcRp Resource ADAMS Accession No ML101450225 OFFICE NRRlLPL2-2/PM NRRlLPL2-2/LA NRRlLPL2-2/BC NAME SBailey BClayton DBroaddus (EBrown for) DATE OS/26/10 OS/25/10 06/07/10 OFFICIAL RECORD COPY