Letter Sequence Other |
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MONTHYEARML0924004922009-08-22022 August 2009 G20090487/EDATS: OEDO-2009-0517 - Sherwood Martinelli E-mail Formal 2.206 Petition Seeking Enforcement Action Against Entergy and All Other Parties Who Mis-Managed Decommissioning Funds Project stage: Other NL-09-147, Proposed License Amendment Regarding Cyber Security Plan2009-11-19019 November 2009 Proposed License Amendment Regarding Cyber Security Plan Project stage: Other JAFP-09-0128, Entergy Nuclear Operations, Inc. - Request for Approval of the James A. FitzPatrick Cyber Security Plan2009-11-23023 November 2009 Entergy Nuclear Operations, Inc. - Request for Approval of the James A. FitzPatrick Cyber Security Plan Project stage: Request ML1013105132010-05-17017 May 2010 Entergy Nuclear Operations, Inc. Cyber Security Plan - James A. Fitzpatrick Nuclear Power Plant, Indian Point Generating Units 1, 2, and 3, Pilgrim Nuclear Power Station, and Vermont Yankee Nuclear Power Station Project stage: Other NL-10-064, License Amendment Withdrawal and Request - Cyber Security Plan2010-07-0808 July 2010 License Amendment Withdrawal and Request - Cyber Security Plan Project stage: Other ML1019703592010-07-15015 July 2010 Submittal of License Amendment Request, Cyber Security Plan Project stage: Request BVY 10-036, Technical Specifications Proposed Change No. 292, License Amendment Withdrawal and Request - Cyber Security Plan2010-07-16016 July 2010 Technical Specifications Proposed Change No. 292, License Amendment Withdrawal and Request - Cyber Security Plan Project stage: Request ML1021500552010-08-0505 August 2010 Cyber Security Amendment Withdrawal Letter Project stage: Other CNRO-2011-00001, Status of Decommissioning Funding for Plants Operated by Entergy Operations, Inc2011-03-31031 March 2011 Status of Decommissioning Funding for Plants Operated by Entergy Operations, Inc Project stage: Request ML1128705662011-11-0808 November 2011 G20090487/EDATS: OEDO-2009-0517 - Notice of Issuance of Directors Decision Under 10 CFR 2.206 Project stage: Request ML1128705422011-11-0808 November 2011 G20090487/EDATS: OEDO-2009-0517 - FRN: General Notice, Final Director'S Decision Under 10 CFR 2.206 to Sherwood Martinelli Project stage: Request ML1128705332011-11-0808 November 2011 G20090487/EDATS: OEDO-2009-0517 - Letter to Sherwood Martinelli Entergy Decommissioning Funding Project stage: Other 2010-07-15
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Entergy Nuclear Operations, Inc. Cyber Security Plan - James A. Fitzpatrick Nuclear Power Plant, Indian Point Generating Units 1, 2, and 3, Pilgrim Nuclear Power Station, and Vermont Yankee Nuclear Power StationML101310513 |
Person / Time |
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Site: |
Indian Point, Pilgrim, Vermont Yankee, FitzPatrick |
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Issue date: |
05/17/2010 |
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From: |
Pickett D Plant Licensing Branch 1 |
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To: |
Mccann J Entergy Nuclear Operations |
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Pickett D NRR/DORLLPL1-1 415-1364 |
References |
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TAC ME2138, TAC ME2744, TAC ME2745, TAC ME2747, TAC ME2802, TAC ME2743 |
Download: ML101310513 (4) |
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Category:Letter
MONTHYEARBVY 24-028, Pre-Notice of Disbursement from Decommissioning Trust2024-10-31031 October 2024 Pre-Notice of Disbursement from Decommissioning Trust BVY 24-027, Report of Investigation Pursuant to 10 CFR 20, Appendix G2024-10-30030 October 2024 Report of Investigation Pursuant to 10 CFR 20, Appendix G JAFP-24-0055, Response to Request for Additional Information for License Amendment Request to Add Temporary Change to TS 3.3.2.1, Condition C, Control Rod Block Instrumentation2024-10-29029 October 2024 Response to Request for Additional Information for License Amendment Request to Add Temporary Change to TS 3.3.2.1, Condition C, Control Rod Block Instrumentation IR 05000333/20240902024-10-29029 October 2024 Final Significance Determination of a White Finding with Assessment Follow-Up and Notice of Violation; Inspection Report 05000333/2024090 IR 05000333/20244022024-10-28028 October 2024 Material Control and Accounting Program Inspection Report 05000333/2024402 (Cover Letter Only) ML24276A1332024-10-17017 October 2024 Issuance of Amendment No. 357 Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision-4, and Administrative Changes ML24282B0302024-10-11011 October 2024 Project Manager Assignment RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests ML24207A0192024-10-0909 October 2024 SE Addendum Related to the License Amendment No. 338 for Implementation of the Alternative Source Term (DPO-2021-001) ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing JAFP-24-0051, Reply to Preliminary White Finding and Apparent Violation in NRC Inspection Report 05000333/2024011; EA-24-0882024-10-0303 October 2024 Reply to Preliminary White Finding and Apparent Violation in NRC Inspection Report 05000333/2024011; EA-24-088 BVY 24-026, Pre-Notice of Disbursement from Decommissioning Trust2024-10-0202 October 2024 Pre-Notice of Disbursement from Decommissioning Trust ML24270A0742024-09-30030 September 2024 Individual Notice of Consideration of Issuance of Amendments to Renewed Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, & Opportunity for a Hearing (EPID L-2024-LLA-0134) - LTR ML24270A1452024-09-26026 September 2024 Notice of Enforcement Discretion for James A. Fitzpatrick Nuclear Power Plant JAFP-24-0047, License Amendment Request – Temporary Addition to TS 3.3.2.1 Condition C, Control Rod Block Instrumentation to Support Upgrade to Rod Worth Minimizer Software2024-09-25025 September 2024 License Amendment Request – Temporary Addition to TS 3.3.2.1 Condition C, Control Rod Block Instrumentation to Support Upgrade to Rod Worth Minimizer Software JAFP-24-0046, Request for Enforcement Discretion for Technical Specification (TS) 3.3.2.1 Control Rod Block Instrumentation2024-09-25025 September 2024 Request for Enforcement Discretion for Technical Specification (TS) 3.3.2.1 Control Rod Block Instrumentation JAFP-24-0045, Supplemental Information for License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications2024-09-20020 September 2024 Supplemental Information for License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications IR 05000333/20240112024-09-19019 September 2024 Follow-up to Inspection Procedure 71153 Report 05000333/2024011 and Preliminary White Finding and Apparent Violation ML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status JAFP-24-0044, Core Operating Limits Report Cycle 272024-09-16016 September 2024 Core Operating Limits Report Cycle 27 JAFP-24-0043, Revision to Commitment Relating to Resolution of Anchor Darling Double Disc Gate Valve Part 21 Issues2024-09-12012 September 2024 Revision to Commitment Relating to Resolution of Anchor Darling Double Disc Gate Valve Part 21 Issues 05000333/LER-2024-002, Reactor Protection System Electric Power Monitoring System Trip Caused Primary Containment Isolation2024-09-0404 September 2024 Reactor Protection System Electric Power Monitoring System Trip Caused Primary Containment Isolation ML24165A0382024-09-0404 September 2024 Issuance of Amendment No. 356 Update Fuel Handling Accident Analysis IR 05000333/20240052024-08-29029 August 2024 Updated Inspection Plan for James A. Fitzpatrick Nuclear Power Plant (Report 05000333/2024005) 05000333/LER-2024-001-01, EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket2024-08-21021 August 2024 EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket IR 05000293/20240022024-08-21021 August 2024 NRC Inspection Report No. 05000293/2024002 ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition IR 05000333/20240022024-08-0707 August 2024 Integrated Inspection Report 05000333/2024002 IR 05000003/20240022024-08-0606 August 2024 NRC Inspection Report 05000003/2024002, 05000247/2024002, 05000286/2024002 PNP 2024-030, Update Report for Holtec Decommissioning International Fleet Decommissioning Quality Assurance Program Rev. 3 and Palisades Transitioning Quality Assurance Plan, Rev 02024-08-0202 August 2024 Update Report for Holtec Decommissioning International Fleet Decommissioning Quality Assurance Program Rev. 3 and Palisades Transitioning Quality Assurance Plan, Rev 0 JAFP-24-0034, 10 CFR 50.46 Annual Report2024-07-31031 July 2024 10 CFR 50.46 Annual Report ML24208A0492024-07-30030 July 2024 Notice of Consideration of Issuance of Amendments to Facility Operating Licenses and Proposed No Significant Hazards Consideration Determination (Letter) BVY 24-024, Pre-Notice of Disbursement from Decommissioning Trust2024-07-30030 July 2024 Pre-Notice of Disbursement from Decommissioning Trust JAFP-24-0036, Supplement to License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2024-07-29029 July 2024 Supplement to License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis JAFP-24-0033, Response to Request for Information Pertaining to a Licensed Operator Positive Fitness-For-Duty Test2024-07-23023 July 2024 Response to Request for Information Pertaining to a Licensed Operator Positive Fitness-For-Duty Test IR 05000333/20244032024-07-18018 July 2024 Biennial Problem Identification and Resolution Inspection Report 05000333/2024403 (Cover Letter Only) IR 05000333/20244012024-07-15015 July 2024 Security Baseline Inspection 05000333/2024401 RS-24-070, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions2024-07-12012 July 2024 Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions ML24190A1932024-07-0909 July 2024 Correction Letter of Amendment No. 355 Revise Technical Specifications Section 3.4.3.1, Safety Relief Valves Setpoint Lower Tolerance IR 05000333/20240102024-07-0808 July 2024 Commercial Grade Dedication Inspection Report 05000333/2024010 ML24184A1662024-07-0303 July 2024 Senior Reactor and Reactor Operator Initial License Examinations BVY 24-023, Pre-Notice of Disbursement from Decommissioning Trust2024-07-0202 July 2024 Pre-Notice of Disbursement from Decommissioning Trust IR 05000271/20240012024-06-28028 June 2024 NRC Inspection Report No. 05000271/2024001, Northstar Nuclear Decommissioning Company, LLC, Vermont Yankee Nuclear Power Station, Vernon, Vermont ML24136A1162024-06-26026 June 2024 Issuance of Amendment No. 355 Revise Technical Specifications Section 3.4.3.1, Safety Relief Valves Setpoint Lower Tolerance 05000333/LER-2024-001, EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket2024-06-24024 June 2024 EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket ML24176A2412024-06-24024 June 2024 Licensed Operator Positive Fitness-for-Duty Test JAFP-24-0027, EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket2024-06-24024 June 2024 EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket ML24171A0122024-06-18018 June 2024 Reply to a Notice of Violation EA-24-037 RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations JAFP-24-0026, Supplement to License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (Srvs) Setpoint Lower Tolerance2024-06-12012 June 2024 Supplement to License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (Srvs) Setpoint Lower Tolerance 2024-09-04
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Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 17, 2010 Mr. John F. McCann, Vice President Nuclear Safety, Emergency Planning and Licensing Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, New York 10601
SUBJECT:
ENTERGY NUCLEAR OPERATIONS, INC. CYBER SECURITY PLAN JAMES A. FITZPATRICK NUCLEAR POWER PLANT, INDIAN POINT GENERATING UNIT NOS. 1,2, AND 3, PILGRIM NUCLEAR POWER STATION, AND VERMONT YANKEE NUCLEAR POWER STATION (TAC NOS. ME2802, ME2743, ME2744, ME2745, ME2747, AND ME2138)
Dear Mr. McCann:
By letters dated November 19, 22, and 23, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML093340070, ML093410280, ML093280951, and ML093310410), Entergy Nuclear Operations, Inc. (ENO), the licensee, submitted license amendment requests (LARs) for the Facility Operating Licenses for the James A. FitzPatrick Nuclear Power Plant, Indian Point Generating Unit Nos. 1, 2, and 3, Pilgrim Nuclear Power Station, and Vermont Yankee Nuclear Power Station. The proposed LARs include the cyber security plans, proposed changes to Section 2 of the Facility Operating Licenses, and proposed Cyber Security Plan Implementation Schedules. The proposed cyber security plans have 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 U.S. Nuclear Regulatory Commission (NRC) staff has completed an initial review of the 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, 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 the ENO sites is based on an earlier version of Nuclear Energy Institute (I'JEI) 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 generic concerns.
Through numerous interactions, the NRC staff has communicated their 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).
J. McCann -2 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 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 LARs, ENO 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 LARs, ENO 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, ENO 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 exlstinq application will be withdrawn and the revised application resubmitted at the same time.
The NRC staff requests that ENO'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 your response, you will be advised by separate correspondence if any further information is needed to support the NRC staff's detailed technical review.
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.
J. McCann -3 If you have any questions regarding this matter, please contact me at (301) 415-1364.
Sincerely, Douglas V. Pickett, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos.50-003, 50-247, 50-286, 50-271, 50-293, and 50-333 cc: Distribution via Listserv
J. McCann -3 If you have any questions regarding this matter, please contact me at (301) 415-1364.
Sincerely, IraJ Douglas V. Pickett, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos.50-003, 50-247, 50-286, 50-271, 50-293, and 50-333 cc: Distribution via Listserv Distribution:
PUBLIC LPL 1-1 rtf RidsNrrDorlLpL 1-1 RidsNrrPMREGinna RidsOgcMailCenter RidsNrrPMFitzPatrick RidsNrrLAS Little RidsAcrsAcnwMailCenter RidsRegion1 MailCenter CErlanger, NSIR PPederson, NSIR RidsNrrDirsltsb RidsN rrDorl DprResourcer ADAMS Accession No. IVIL 101310513 OFFICE LPL1-1/PM LPL 1-1/LA LPL1-1/PM LPL 1-1/PM LPL 1-1/BC NAME DPickett SLittie JBoska JKim NSalgado DATE 05/13/10 05/ 13/ 10 05/13/10 05/13/10 05/17/10