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MONTHYEARML1001506442010-01-14014 January 2010 Supplement to License Amendment Request (LAR) for Approval of the Northern States Power Company - Minnesota (NSPM) Cyber Security Plan Project stage: Supplement ML1011708792010-05-21021 May 2010 Letter Request the Licensee to Revise the Applications for Cyber Security Amendment Project stage: Other ML1011605352010-05-21021 May 2010 Request for Dominion to Revise the Application Re. Cyber Security Amendment Project stage: Other ML1013802062010-06-0303 June 2010 License Amendment Request for Approval of the Cyber Security Plan Project stage: Other ML1020201642010-07-20020 July 2010 License Amendment Request for Approval of the Northern States Power Company - Minnesota Cyber Security Plan Project stage: Request ML1021405702010-08-0909 August 2010 Acknowledge Withdrawal of 11/23/09 Application for Proposed Cyber Security Amendment Project stage: Withdrawal 2010-06-03
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Category:Letter
MONTHYEARML24298A0552024-10-30030 October 2024 Response to Alternative RR-10, Auxiliary Feedwater Valve Testing ML24283A1192024-10-28028 October 2024 Letter to Shawn Hafen, Re Monticello Subsequent License Renewal Schedule Change IR 05000282/20244032024-10-25025 October 2024 – Security Baseline Inspection Report 05000282/2024403 and 05000306/2024403 05000282/LER-2024-001-01, Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies2024-10-22022 October 2024 Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies L-PI-24-044, Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program2024-10-21021 October 2024 Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program L-MT-24-038, Subsequent License Renewal Application Response to Request for Additional Information - 3rd Round RAI2024-10-15015 October 2024 Subsequent License Renewal Application Response to Request for Additional Information - 3rd Round RAI ML24277A0202024-10-0303 October 2024 Operator Licensing Examination Approval Monticello Nuclear Generating Plant, October 2024 ML24277A1012024-10-0303 October 2024 Closure of Interim Report of a Potential Deviation or Failure to Comply Associated with Bentley Systems Incorporated Autopipe Software ML24199A1752024-10-0101 October 2024 Issuance of Amendment No. 212 Revise Technical Specification 3.8.6, Battery Parameters, Surveillance Requirement 3.8.6.6 IR 05000263/20240112024-10-0101 October 2024 Biennial Problem Identification and Resolution Inspection Report 05000263/2024011 ML24221A3622024-09-27027 September 2024 Issuance of Amendment Nos. 245 and 233 Revise Technical Specification 3.8.1, AC Sources-Operating, Surveillance Requirement 3.8.1.2, Note 3 L-MT-24-025, Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements2024-09-26026 September 2024 Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements ML24241A1682024-09-23023 September 2024 Transmittal Letter Amendment No. 13 to Materials License No. Special Nuclear Material-2506 for the Prairie Island Independent Spent Fuel Storage Installation 05000282/LER-2024-001, Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies2024-09-16016 September 2024 Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies IR 05000282/20243012024-09-13013 September 2024 NRC Initial License Examination Report 05000282/2024301 and 05000306/2024301 L-MT-24-029, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information-Supplement to Set 1 Part 2 and Response to 2ci Round RAI2024-09-13013 September 2024 Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information-Supplement to Set 1 Part 2 and Response to 2ci Round RAI IR 05000263/20240052024-08-30030 August 2024 Updated Inspection Plan and Follow-Up Letter for Monticello Nuclear Generating Plant, Unit 1 (Report 05000263/2024005) L-MT-24-028, Response to RCI for RR-017 ISI Impracticality2024-08-28028 August 2024 Response to RCI for RR-017 ISI Impracticality IR 05000282/20240052024-08-28028 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2024005 and 05000306/2024005) ML24222A1822024-08-27027 August 2024 – Proposed Alternative Request VR-09 to the Inservice Testing Requirements of the ASME OM Code for Main Steam Safety Relief Valves 05000263/LER-2024-002, Low Pressure Coolant Injection Inoperable Due to Motor Valve Failure2024-08-27027 August 2024 Low Pressure Coolant Injection Inoperable Due to Motor Valve Failure L-PI-24-040, Post-Submittal Package Letter2024-08-23023 August 2024 Post-Submittal Package Letter IR 05000263/20244202024-08-21021 August 2024 Security Baseline Inspection Report 05000263/2024420 - Cover Letter IR 05000263/20240022024-08-14014 August 2024 Integrated Inspection Report 05000263/2024002 ML24218A2282024-08-0505 August 2024 Request for Confirmation of Information for Relief Request RR-017, Inservice Inspection Impracticality During the Fifth Ten-Year Interval IR 05000282/20245012024-08-0505 August 2024 Emergency Preparedness Inspection Report 05000282/2024501 and 05000306/2024501 ML24213A1592024-07-31031 July 2024 Operator Licensing Examination Approval - Prairie Island Nuclear Generating Plant IR 05000282/20240022024-07-30030 July 2024 Integrated Inspection Report 05000282/2024002 and 05000306/2024002 ML24208A1502024-07-26026 July 2024 Independent Spent Fuel Storage Installation - Submittal of Quality Assurance Topical Report (NSPM-1) ML24215A2992024-07-23023 July 2024 Minnesota State Historic Preservation Office Comments on Monticello SLR Draft EIS ML24198A2372024-07-18018 July 2024 Information Request to Support Upcoming Biennial Problem Identification and Resolution (Pi&R) Inspection at Monticello Nuclear Generating Plant ML24197A2012024-07-15015 July 2024 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000282/2024004 L-MT-24-022, – Preparation and Scheduling of Operator Licensing Examinations2024-07-0909 July 2024 – Preparation and Scheduling of Operator Licensing Examinations L-PI-24-036, – Preparation and Scheduling of Operator Licensing Examinations2024-06-28028 June 2024 – Preparation and Scheduling of Operator Licensing Examinations IR 05000282/20240102024-06-28028 June 2024 Comprehensive Engineering Team Inspection Report 05000282/2024010 and 05000306/2024010 L-MT-24-019, Submittal of ASME Section XI, Section IWB-3720 Analytical Evaluation in Accordance with 10 CFR 50.55a(b)(2)(xliii)2024-06-10010 June 2024 Submittal of ASME Section XI, Section IWB-3720 Analytical Evaluation in Accordance with 10 CFR 50.55a(b)(2)(xliii) ML24164A2402024-06-10010 June 2024 Minnesota State Historic Preservation Office- Comments on Draft Monticello SLR Draft EIS ML24158A5912024-06-0606 June 2024 CFR 50.46 LOCA Annual Report L-PI-24-031, Independent Spent Fuel Storage Installation, Supplement to License Amendment Request to Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2)2024-06-0505 June 2024 Independent Spent Fuel Storage Installation, Supplement to License Amendment Request to Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2) L-MT-24-017, Response to Request for Additional Information Regarding License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.6 (EPID-L-2023-LLA-01602024-06-0404 June 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.6 (EPID-L-2023-LLA-0160 ML24137A2792024-06-0303 June 2024 Audit Summary for License Amendment Request to Revise Technical Specification 3.8.6, Battery Parameters, Surveillance Requirement 3.8.6.6 L-PI-24-014, License Amendment Request to Revise the Technical Specification Definition of Reactor Trip System (RTS) Response Time and Apply Response Time Testing to RTS Trip Functions with Time Delay Assumption2024-06-0303 June 2024 License Amendment Request to Revise the Technical Specification Definition of Reactor Trip System (RTS) Response Time and Apply Response Time Testing to RTS Trip Functions with Time Delay Assumption 05000306/LER-2024-001-01, Reactor Trip and Auto-Start Actuation of Auxiliary Feedwater Due to Loss of Suction to the 22 Main Feedwater Pump2024-05-31031 May 2024 Reactor Trip and Auto-Start Actuation of Auxiliary Feedwater Due to Loss of Suction to the 22 Main Feedwater Pump ML24155A1922024-05-31031 May 2024 Refueling Outage Unit 2 R33 Owners Activity Report for Class 1, 2, 3 and Mc Inservice Inspections ML24262A1992024-05-29029 May 2024 L-PI-24-018 PINGP 75 Day Letter ML24149A3712024-05-29029 May 2024 (Ping) - Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection L-PI-24-030, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.12024-05-22022 May 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.1 ML24141A1292024-05-22022 May 2024 Northern States Power Company - Use of Encryption Software for Electronic Transmission of Safeguards Information ML24141A1782024-05-20020 May 2024 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML24141A0452024-05-20020 May 2024 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection 2024-09-27
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~1-~ ¥00*' May21,2010 Mr. Gabor Salamon, Director Nuclear Licensing and Emergency Preparedness Northern States Power Company - Minnesota 414 Nicollet Mall - MP4 Minnesota, MN 55401
SUBJECT:
MONTICELLO NUCLEAR GENERATING PLANT AND PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 - LICENSE AMENDMENT REQUEST FOR APPROVAL OF THE CYBER SECURITY PLAN (TAC NOS. ME2702, ME2773, AND ME2774)
Dear Mr. Salamon:
By letter dated November 23, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML093280030), Northern States Power Company - Minnesota (NSPM), submitted license amendment requests (LARs) for NSPM plants listed above. The proposed LARs include the cyber security plan, proposed changes to appropriate paragraphs of the Facility Operating License or Renewed Facility Operating License, as appropriate, and a proposed Cyber Security Plan Implementation Schedule. The proposed cyber security plan has been 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 Nuclear Regulatory Commission (NRC) staff has completed an initial review of these LARs. In accordance with the Office of Nuclear Reactor Regulation Office Instruction L1C-109, "Acceptance Review Procedures," (ADAMS Accession No. ML091810088), 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, the NRC staff is 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 the above-listed facilities 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 representing 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 these interactions to 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. ML100680284).
By letter dated April 28, 2010 (ADAMS Accession Nos. ML101180434 and ML101180437), NEI submitted Revision 6 to NEI 08-09, "Cyber Security Plan for Nuclear Power Reactors," 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. ML101190371, concluded
G. Salamon -2 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 requested LAR, NSPM is requested to review the list of generic issues provided to the industry cyber security writing team and forwarded to all licensees via e-mail dated March 9, 2010, and provide a revised submittal. For those generic issues that will not be addressed in the revised submittal, please provide additional information or justification in the revised submittal.
For any changes to the Cyber Security Plan proposed in the LAR, NSPM 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, and a potentially less resource-intensive method than addressing the individual issues, NSPM may submit a revised Cyber Security Plan consistent with Regulatory Guide (RG) 5.71 1 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 NSPM 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 your response, you will be advised by separate correspondence if any further information is needed to support the NRC staff's detailed technical review.
If you have any questions regarding this matter, I may be reached at (301) 415-1451.
Sincerely,
~1{;Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-263, 50-282, and 50-306 cc: Distribution via ListServ 1 In January 2010, the NRC staff issued RG 5.71, "Cyber Security Programs for Nuclear Facilities" (ADAMS Accession No. ML090340159). 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.
G. Salamon -2 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 requested LAR, NSPM is requested to review the list of generic issues provided to the industry cyber security writing team and forwarded to all licensees via e-mail dated March 9, 2010, and provide a revised submittal. For those generic issues that will not be addressed in the revised submittal, please provide additional information or justification in the revised submittal.
For any changes to the Cyber Security Plan proposed in the LAR, NSPM 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, and a potentially less resource-intensive method than addressing the individual issues, NSPM may submit a revised Cyber Security Plan consistent with Regulatory Guide (RG) 5.71 2 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 NSPM 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 your response, you will be advised by separate correspondence if any further Information is needed to support the NRC staff's detailed technical review.
If you have any questions regarding this matter, I may be reached at (301) 415-1451.
Sincerely, IRAJ Peter S. Tam, Senior Project Manager Plant Licensing Branch 111*1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50*263, 50-282, and 50*306 cc: Distribution via ListServ 1 In January 2010, the NRC staff issued RG 5.71, "Cyber Security Programs for Nuclear Facilities" (ADAMS Accession No. ML090340159). 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.
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