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MONTHYEARML15294A2792015-11-19019 November 2015 Issuance of Amendment No. 284, Request to Revise License Condition Related to Cyber Security Plan Milestone 8 Full Implementation Date Project stage: Approval LIC-16-0109, Request for Exemptions from Portions of 10 CFR 50.47 and 10 CFR Part 50, Appendix E (Attachments 1, 2, 4, 5 and 6)2016-12-16016 December 2016 Request for Exemptions from Portions of 10 CFR 50.47 and 10 CFR Part 50, Appendix E (Attachments 1, 2, 4, 5 and 6) Project stage: Request LIC-17-0052, License Amendment Request 17-04; Modification of License Condition 3.C to Delete Requirement for a Commission-Approved Cyber Security Plan2017-06-16016 June 2017 License Amendment Request 17-04; Modification of License Condition 3.C to Delete Requirement for a Commission-Approved Cyber Security Plan Project stage: Request 2016-12-16
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Category:Letter
MONTHYEARIR 05000285/20240032024-10-29029 October 2024 NRC Inspection Report 05000285/2024003 LIC-24-0012, Independent Spent Fuel Storage Installation - Response to Proposed Revision to Decommissioning Quality Assurance Plan (DQAP) - Request for Additional Information2024-10-0707 October 2024 Independent Spent Fuel Storage Installation - Response to Proposed Revision to Decommissioning Quality Assurance Plan (DQAP) - Request for Additional Information LIC-24-0011, Independent Spent Fuel Storage Installation - Response to Application for License Amendment Request to Revise the License Termination Plan - Supplemental Information Needed, EPID L-2024-LLA-00952024-10-0202 October 2024 Independent Spent Fuel Storage Installation - Response to Application for License Amendment Request to Revise the License Termination Plan - Supplemental Information Needed, EPID L-2024-LLA-0095 ML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status ML24243A1042024-09-12012 September 2024 Proposed Revision to the OPPD FCS DQAP - Request for Additional Information (License No. DPR-40, Docket Nos. 50-285, 72-054, and 71-0256) ML24255A0962024-09-12012 September 2024 License Amendment Request to Revise the License Termination Plan - Request Supplemental Information (License No. DPR-40, Docket No. 50-285) IR 05000285/20240022024-08-21021 August 2024 NRC Inspection Report 05000285/2024002 ML24235A0822024-08-10010 August 2024 Response to Fort Calhoun Station, Unit No. 1 - Phase 1 Final Status Survey Report to Support Approved License Termination Plan - Request for Additional Information - Request for Additional Information (EPID L-2024-DFR-0002) July 8, 2024 ML24180A2082024-07-0808 July 2024 Phase 1 Final Status Survey Reports Request for Additional Information Letter ML24183A3222024-07-0808 July 2024 Proposed Revision to the Omaha Public Power District Fort Calhoun Station Decommissioning Quality Assurance Plan - Acceptance Review LIC-24-0007, License Amendment Request (LAR) to Revise License Termination Plan (LTP)2024-06-18018 June 2024 License Amendment Request (LAR) to Revise License Termination Plan (LTP) IR 05000285/20240012024-06-0505 June 2024 NRC Inspection Report 05000285/2024001 ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities LIC-24-0008, Proposed Revision to the Omaha Public Power District (OPPD) Fort Calhoun Station (FCS) Decommissioning Quality Assurance Plan (Dqap), Unit No. 1 and ISFSI2024-05-16016 May 2024 Proposed Revision to the Omaha Public Power District (OPPD) Fort Calhoun Station (FCS) Decommissioning Quality Assurance Plan (Dqap), Unit No. 1 and ISFSI LIC-24-0003, Independent Spent Fuel Storage Installation - Radiological Effluent Release Report and Radiological Environmental Operating Report2024-04-25025 April 2024 Independent Spent Fuel Storage Installation - Radiological Effluent Release Report and Radiological Environmental Operating Report LIC-24-0006, (Fcs), Unit 1, Independent Spent Fuel Storage Installation, Phase 1 Final Status Survey Report to Support Approved License Termination Plan2024-04-17017 April 2024 (Fcs), Unit 1, Independent Spent Fuel Storage Installation, Phase 1 Final Status Survey Report to Support Approved License Termination Plan ML24079A1702024-03-10010 March 2024 ISFSI, Unit 1 - 10 CFR 50.59 Report, Quality Assurance (QA) Program Changes, Technical Specification Basis Changes, 10 CFR 71.106 Quality Assurance Program Approval, Aging Management Review, Commitment Revisions and Revision of Updated Safe LIC-24-0005, Annual Decommissioning Funding / Irradiated Fuel Management Status Report2024-03-0101 March 2024 Annual Decommissioning Funding / Irradiated Fuel Management Status Report LIC-24-0002, Independent Spent Fuel Storage Installation - Submittal of Annual Radioactive Effluent Release Report2024-02-27027 February 2024 Independent Spent Fuel Storage Installation - Submittal of Annual Radioactive Effluent Release Report ML24019A1672024-01-31031 January 2024 Issuance of Amendment to Renewed Facility License to Add License Condition to Include License Termination Plan Requirements IR 05000285/20230062023-12-21021 December 2023 NRC Inspection Report 05000285/2023006 LIC-23-0007, Response to Fort Calhoun, Unit 1 & Independent Spent Fuel Storage Installation Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements – Request for Additional Information2023-12-0606 December 2023 Response to Fort Calhoun, Unit 1 & Independent Spent Fuel Storage Installation Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements – Request for Additional Information IR 05000285/20230052023-11-0202 November 2023 NRC Inspection Room 05000285/2023005 ML23276A0042023-09-28028 September 2023 U.S. EPA Response Letter to NRC Letter on Consultation and Finality on Decommissioning and Decontamination of Contaminated Sites MOU - Fort Calhoun Station, Unit 1 – (License No. DPR-40, Docket No. 50-285) IR 05000285/20230042023-09-13013 September 2023 NRC Inspection Report 05000285/2023-004 LIC-23-0005, Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - 2nd Request for Additional Information (EPID L-2021-LIT-0000) June 2, 20232023-08-24024 August 2023 Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - 2nd Request for Additional Information (EPID L-2021-LIT-0000) June 2, 2023 ML23234A2412023-08-18018 August 2023 Email - Letter to M Porath Re Ft Calhoun Unit 1 LTP EA Section 7 Informal Consultation Request ML23234A2392023-08-18018 August 2023 Letter to B Harisis Re Ft Calhoun Unit 1 LTP EA State of Nebraska Comment Request.Pdf IR 05000285/20230032023-07-10010 July 2023 – NRC Inspection Report 05000285/2023003 ML23082A2202023-06-26026 June 2023 Consultation on the Decommissioning of the Fort Calhoun Station Unit 1 Pressurized Water Reactor in Fort Calhoun, Nebraska ML23151A0032023-06-0505 June 2023 – Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements – 2nd Request for Additional Information (EPID L-2021-LIT-0000) June 2, 2023 IR 05000285/20230022023-06-0505 June 2023 NRC Inspection Report 05000285/2023002 LIC-23-0004, (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report2023-04-20020 April 2023 (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report LIC-23-0003, Annual Decommissioning Funding / Irradiated Fuel Management Status Report2023-03-15015 March 2023 Annual Decommissioning Funding / Irradiated Fuel Management Status Report LIC-23-0001, Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - Request for Additional Information2023-02-27027 February 2023 Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - Request for Additional Information ML22361A1022023-02-24024 February 2023 Reactor Decommissioning Branch Project Management Changes for Some Decommissioning Facilities and Establishment of Backup Project Manager for All Decommissioning Facilities IR 05000285/20230012023-02-24024 February 2023 NRC Inspection Report 05000285/2023001 LIC-23-0002, Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report2023-02-20020 February 2023 Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report ML23020A0462023-01-19019 January 2023 Threatened and Endangered Species List: Nebraska Ecological Services Field Office IR 05000285/20220062023-01-0505 January 2023 NRC Inspection Report 05000285/2022-006 ML22357A0662022-12-30030 December 2022 Technical RAI Submittal Letter on License Amendment Request for Approval of License Termination Plan IR 05000285/20220052022-10-26026 October 2022 NRC Inspection Report 05000285/2022-005 ML22276A1052022-09-30030 September 2022 Conclusion of Consultation Under Section 106 NHPA for Ft. Calhoun Station LTP ML22258A2732022-09-29029 September 2022 Letter to John Swigart, SHPO; Re., Conclusion of Consultation Under Section 106 Hnpa Fort Calhoun Station Unit 1 ML22265A0262022-09-26026 September 2022 U.S. Nuclear Regulatory Commissions Analysis of Omaha Public Power Districts Decommissioning Status Report (License No. DPR-40, Docket No. 50-285) IR 05000285/20220042022-09-14014 September 2022 NRC Inspection Report 05000285/2022004 ML22138A1252022-08-0303 August 2022 Letter to Mr. Timothy Rhodd, Chairperson, Iowa Tribe of Kansas and Nebraska, Re., Ft Calhoun LTP Section 106 ML22138A1222022-08-0303 August 2022 Letter to Mr. John Shotton, Chairman, Otoe-Missouria Tribe of Indians, Oklahoma, Re., Ft Calhoun LTP Section 106 ML22138A1302022-08-0303 August 2022 Letter to Justin Wood, Principal Chief, Sac and Fox Nation, Oklahoma, Re., Ft Calhoun LTP Section 106 ML22214A0922022-08-0303 August 2022 Letter to Stacy Laravie, Thpo, Ponca Tribe of Nebraska, Re., Ft Calhoun LTP Section 106 2024-09-18
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML24019A1672024-01-31031 January 2024 Issuance of Amendment to Renewed Facility License to Add License Condition to Include License Termination Plan Requirements ML20071E1042020-03-25025 March 2020 Issuance of Amendment to Change the Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan to Reflect an ISFSI-Only Configuration ML19297D6772019-12-11011 December 2019 Issuance of Amendment to Revise the Permanently Defueled Technical Specifications to Align to the Requirements for Permanent Removal of Spent Fuel from the Spent Fuel Pool ML18047A6612018-03-28028 March 2018 Issuance of Amendment No. 298, Request to Modify License Condition 3.C to Delete Requirement for Commission-Approved Cyber Security Plan (CAC No. MF9850; EPID L-2017-LLA-0236) ML18068A1652018-03-0909 March 2018 Correction to Page 1 of Attachment to Enclosure 1 for Amendment No. 297, Request for Technical Specification Changes to Align to Those Requirements for Decommissioning (CAC No. MF9567; EPID L-2017-LLA-0192) ML18010A0872018-03-0606 March 2018 Issuance of Amendment No. 297, Request for Technical Specification Changes to Align to Those Requirements for Decommissioning (CAC No. MF9567; EPID L-2017-LLA-0192) ML17338A1722018-01-19019 January 2018 Issuance of Amendment No. 296, Revise Technical Specifications (TS) to Delete Dry Spent Fuel Cask Loading Limits from TS 3.8.3(6), Figure 2-11, Table 3-4, Table 3-5, and TS 4.3.1.3 (CAC No. MF9831; EPID L-2017-LLA-0235) ML17276B2862017-12-12012 December 2017 Issuance of Amendment No. 295, Revise the Emergency Plan and Emergency Action Level Scheme for the Permanently Defueled Condition (CAC No. MF8951; EPID L-2016-LLA-0036) ML17289A0602017-11-22022 November 2017 Issuance of Amendment No. 294, Revise Cyber Security Plan Implementation Schedule for Milestone 8 and Associated License Condition (CAC No. MF9559; EPID L-2017-LLA-0184) ML17278A6072017-11-17017 November 2017 Issuance of Amendment No. 293, Request to Revise Current Licensing Basis for the Auxiliary Building to Use American Concrete Institute Ultimate Strength Requirements (CAC No. MF8525; EPID L-2016-LLA-0013) ML17165A4652017-07-28028 July 2017 Fort Calhoun Station, Unit 1 - Issuance of Amendment No. 292, Revise Technical Specifications to Align Staffing Requirements to Those Required for Decommissioning (CAC No. MF8437) ML17123A3482017-07-27027 July 2017 Issuance of Amendment No. 291, Revise the Radiological Emergency Response Plan for Permanently Defueled Condition ML17179A1782017-06-29029 June 2017 Correction to Technical Specification Definitions - Page 7 for Amendment No. 286, Administrative Changes to the Technical Specifications to Update Titles, Delete Obsolete Actions in Appendix B, and ... LIC-17-0047, Final Request for Additional Information Concerning License Amendment Request 16-07: Revise the Emergency Plan to the Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme2017-05-15015 May 2017 Final Request for Additional Information Concerning License Amendment Request 16-07: Revise the Emergency Plan to the Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme ML17053A0992017-04-0707 April 2017 Issuance of Amendment No. 290, Request to Delete License Condition 3.D., Fire Protection Program, No Longer Needed for Permanently Shutdown and Defueled Condition ML16182A3632016-08-19019 August 2016 Issuance of Amendment No. 289, Request to Adopt Technical Specification Task Force (TSTF)-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control ML16139A8042016-06-0808 June 2016 Issuance of Amendment No. 288, Request to Adopt Technical Specifications Task Force (TSTF)-426, Revision 5, Revise or Add Actions to Preclude Entry Into LCO 3.0.3 - RITSTF Initiative 6b & 6c ML16084A7552016-04-0505 April 2016 Issuance of Amendment No. 287, Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours/Month, Using CLIIP ML15307A0132016-02-23023 February 2016 Issuance of Amendment No. 286, Request to Make Administrative Changes to the Technical Specifications to Update Titles, Delete Obsolete Actions in Appendix B, and Relocate a Definition ML15288A0052015-12-15015 December 2015 Issuance of Amendment No. 285, Adopt Emergency Action Level Scheme Pursuant to Nuclear Energy Institute (NEI) 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors ML15294A2792015-11-19019 November 2015 Issuance of Amendment No. 284, Request to Revise License Condition Related to Cyber Security Plan Milestone 8 Full Implementation Date ML15209A8022015-08-10010 August 2015 Issuance of Amendment No. 283, Revise Updated Safety Analysis Report to Allow Pipe Stress Analysis to Be Performed in Accordance with ASME Code Section III ML15111A3992015-06-30030 June 2015 Issuance of Amendment No. 282, Revise Updated Safety Analysis Report for Controlling Raw Water Pump Operation and Safety Classification of Components During a Flood ML15035A2032015-03-27027 March 2015 Issuance of Amendment No. 281, Revise Technical Specification 3.1, Table 3-3 to Correct Administrative Error in Surveillance Method for Containment Wide Range Radiation Monitors ML15015A4132015-02-20020 February 2015 Issuance of Amendment No. 280, Revise Technical Specification 3.2, Table 3-5 to Add New Surveillance Requirement ML14356A0122014-12-29029 December 2014 Issuance of Amendment No. 279, Revise Technical Specification Surveillance Requirements for One-Time Extension from Refueling Frequency of Once Per 18 Months to Maximum of 28 Months ML14328A8142014-12-22022 December 2014 Issuance of Amendment No. 278, Revise Technical Specification 2.5, Auxiliary Feedwater (AFW) System to Allow 7-Day Completion Time for Turbine-Driven AFW Pump Based on TSTF-340, Revision 3 ML14279A2752014-11-0606 November 2014 Issuance of Amendment No. 277, Revise Technical Specification Surveillance Requirement 3.2, Table 3-5, Item 3, for One-Time Extension of Frequency to Maximum of 28 Months ML14209A0272014-08-0707 August 2014 Issuance of Amendment No. 276, Request to Revise Updated Safety Analysis Report for Westinghouse Plant-Specific Leak-Before-Break Analysis ML14098A0922014-06-16016 June 2014 Issuance of Amendment No. 275, Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants (2001 Edition) ML14003A0032014-01-28028 January 2014 Issuance of Amendment No. 274, Revise Technical Specification 2.16, River Level, and Establish EAL Classification Criteria for External Flooding Events Under Radiological Emergency Response Plan ML13296A5842013-10-25025 October 2013 Issuance of Amendment No. 273, Revise Current Licensing Basis of Pipe Break Criteria for High Energy Line Breaks (Exigent Circumstances) ML13203A0702013-07-26026 July 2013 Issuance of Amendment No. 272 - Revise Current Licensing Basis to Adopt Revised Design Basis/Methodology for Addressing Design-Basis Tornado/Tornado Missile Impact (Exigent Circumstances) ML13070A0422013-03-29029 March 2013 Issuance of Amendment No. 271, Relocate Technical Specification LCO 2.17, Miscellaneous Radioactive Material Sources, and Surveillance Requirement 3.13 to Updated Safety Analysis Report ML13043A6612013-02-28028 February 2013 Issuance of Amendment No. 270 to Revise Technical Specification 2.15 to Establish Limiting Condition for Operation Requirements for Reactor Protective System Actuation Circuits ML1126204022011-09-30030 September 2011 Issuance of Amendment No. 268, Revise Updated Safety Analysis Report to Relocate Acoustic Position and Tail Pipe Temperature Indication Surveillance Requirements from Technical Specifications ML1118615712011-08-31031 August 2011 Issuance of Amendment No. 267, Revise Technical Specification (TS) 2.15 and TS 3.1 Related to Operability of Secondary Control Element Assembly Position Indication System Channels; Correction to TS 2.10.2(7)c ML1118010942011-07-27027 July 2011 Issuance of Amendment No. 266, Revise License Condition and Approve Cyber Security Plan and Associated Implementation Schedule ML1015202962010-06-0202 June 2010 License Amendment, Issuance of Amendment No. 265, Revise Technical Specification 2.15, Table 2-5, Note C for Safety Valve Acoustic Position Indication (Emergency Circumstances) ML1009100772010-05-14014 May 2010 License Amendment, 264, Revision of Tech Spec Sections 2.0.1 and 2.7 for Inoperable System, Subsystem, or Component Due to Inoperable Power Source and Deletion of Diesel Generator Surveillance Requirement 3.7(1)e ML0925405912009-10-0909 October 2009 License Amendment, Issuance of Amendment No. 263 Modify Technical Specifications to Add Operability and Testing Requirements for Steam Generator Blowdown Isolation on a Reactor Trip ML0919005692009-07-24024 July 2009 Unit No.1 - Issuance of Amendment No. 261, Modify Transformer Allowed Outage Time in Technical Specification 2.7(2) and Delete Associated 2.7(2) Special Reporting Requirements in TS 5.9.3j ML0916205692009-07-24024 July 2009 Issuance of Amendment 262, Modify Technical Specifications to Adopt TSTF-511, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26 ML0912801022009-07-22022 July 2009 Issuance of Amendment No. 260, Modification of Surveillance Requirements in TS 3.6(3), Containment Recirculating Air Cooling and Filtering System & Removal of License Conditions ML0832606972009-05-12012 May 2009 Issuance of Amendment No. 259, Revise Technical Specifications to Correct Typographical Errors and Make Administrative Clarifications ML0907108912009-03-27027 March 2009 License Amendment, Issuance of Amendment No. 258, Revise Limiting Condition for Operation 2.7(2)j in TS 2.7, Electrical Systems, to Clarify Allowed Outage Time for Emergency Diesel Generators ML0730903612007-12-17017 December 2007 Issuance of Amendment No. 251, Modify Technical Specification Requirements to Support Addition of Safety-Related Swing Inverters to 120 Volt AC Buses ML0720400972007-07-26026 July 2007 Conforming License Amendment to Incorporate the Mitigation Strategies of Commission Order EA-02-026 (Tac No. MD4534) ML0720402832007-07-26026 July 2007 Revised Pages of Facility Operating License DPR-40 to Incorporate the Mitigation Strategies Required by Section B.5.b. of Commission Order EA-02-026 ML0706102692007-06-0606 June 2007 Issuance of Amendment No. 250 Adoption of TSTF-447 to Delete Requirements for Hydrogen Purge System - CLIIP 2024-01-31
[Table view] Category:Safety Evaluation
MONTHYEARML24019A1682024-01-31031 January 2024 Safety Evaluation Report for Approval of License Termination Plan ML21271A5992021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 8, 12, Omaha Public Power District, FCS-SAF-103, FCS Deconstruction Health and Safety Plan CAC2 ML20056E4872020-02-26026 February 2020 Staff Review of Fort Calhoun Independent Spent Fuel Storage Installation Physical Security Plan, Security Training and Qualification Plan, and Safeguard Contingency Plan, Revision 0 and the Verification of Additional Security Measures (ASM) ML19297D6742019-12-0909 December 2019 FCS ISFSI Only Tech Specs SER ML18017B0052018-03-30030 March 2018 Review of the Irradiated Fuel Management Plan (CAC No. MF9553; EPID L-2017-LLL-0009) ML18047A6612018-03-28028 March 2018 Issuance of Amendment No. 298, Request to Modify License Condition 3.C to Delete Requirement for Commission-Approved Cyber Security Plan (CAC No. MF9850; EPID L-2017-LLA-0236) ML18010A0872018-03-0606 March 2018 Issuance of Amendment No. 297, Request for Technical Specification Changes to Align to Those Requirements for Decommissioning (CAC No. MF9567; EPID L-2017-LLA-0192) ML17338A1722018-01-19019 January 2018 Issuance of Amendment No. 296, Revise Technical Specifications (TS) to Delete Dry Spent Fuel Cask Loading Limits from TS 3.8.3(6), Figure 2-11, Table 3-4, Table 3-5, and TS 4.3.1.3 (CAC No. MF9831; EPID L-2017-LLA-0235) ML17276B2862017-12-12012 December 2017 Issuance of Amendment No. 295, Revise the Emergency Plan and Emergency Action Level Scheme for the Permanently Defueled Condition (CAC No. MF8951; EPID L-2016-LLA-0036) ML17263B1982017-12-11011 December 2017 Letter and Safety Evaluation, Request for Exemption from 10 CFR 50.47 and 10 CFR 50 Appendix E to Reduce Emergency Planning Requirements for Permanently Defueled Condition (CAC MF9067; EPID L-2016-LLE-0003) ML17289A0602017-11-22022 November 2017 Issuance of Amendment No. 294, Revise Cyber Security Plan Implementation Schedule for Milestone 8 and Associated License Condition (CAC No. MF9559; EPID L-2017-LLA-0184) ML17275A2642017-11-21021 November 2017 Safety Evaluation Input on Fort Calhoun Station Request for Approval of Permanently Defueled Emergency Plan and Emergency Action Level Scheme, Docket No. 50-285 ML17278A6072017-11-17017 November 2017 Issuance of Amendment No. 293, Request to Revise Current Licensing Basis for the Auxiliary Building to Use American Concrete Institute Ultimate Strength Requirements (CAC No. MF8525; EPID L-2016-LLA-0013) ML17165A4652017-07-28028 July 2017 Fort Calhoun Station, Unit 1 - Issuance of Amendment No. 292, Revise Technical Specifications to Align Staffing Requirements to Those Required for Decommissioning (CAC No. MF8437) ML17123A3482017-07-27027 July 2017 Issuance of Amendment No. 291, Revise the Radiological Emergency Response Plan for Permanently Defueled Condition ML17144A2462017-06-21021 June 2017 Approval of Certified Fuel Handler Training and Retraining Program to Facilitate Activities Associated with Decommissioning and Irradiated Fuel Handling Management ML17053A0992017-04-0707 April 2017 Issuance of Amendment No. 290, Request to Delete License Condition 3.D., Fire Protection Program, No Longer Needed for Permanently Shutdown and Defueled Condition ML16141A7392016-05-27027 May 2016 Safety Evaluation, Review of Aging Management Program of Reactor Vessel Internals Based on MRP-227-A, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines ML16104A0742016-04-15015 April 2016 Relief Request, Request to Use a Portion of a Later Edition of the ASME B&PV Code, Section XI, Fourth 10-Year Inservice Inspection Interval ML16084A7552016-04-0505 April 2016 Issuance of Amendment No. 287, Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours/Month, Using CLIIP ML15307A0132016-02-23023 February 2016 Issuance of Amendment No. 286, Request to Make Administrative Changes to the Technical Specifications to Update Titles, Delete Obsolete Actions in Appendix B, and Relocate a Definition ML16041A3082016-02-19019 February 2016 Relief Requests P-1 - LPSI and CS Pumps; P-2 - Adjusting Hydraulic Parameters Consistent W/Code Case OMN-21; G-1 - Test Frequency Consistent W/Code Case OMN-20, Fifth 10-Year Inservice Testing Interval ML15288A0052015-12-15015 December 2015 Issuance of Amendment No. 285, Adopt Emergency Action Level Scheme Pursuant to Nuclear Energy Institute (NEI) 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors ML15294A2792015-11-19019 November 2015 Issuance of Amendment No. 284, Request to Revise License Condition Related to Cyber Security Plan Milestone 8 Full Implementation Date ML15232A0032015-08-21021 August 2015 Relief Request RR-14, Relief from ASME Code Case N-729-1 Requirements for Reactor Vessel Head Penetration Nozzle Welds, Fourth 10-Year Inservice Inspection Interval ML15209A8022015-08-10010 August 2015 Issuance of Amendment No. 283, Revise Updated Safety Analysis Report to Allow Pipe Stress Analysis to Be Performed in Accordance with ASME Code Section III ML15111A3992015-06-30030 June 2015 Issuance of Amendment No. 282, Revise Updated Safety Analysis Report for Controlling Raw Water Pump Operation and Safety Classification of Components During a Flood ML15035A2032015-03-27027 March 2015 Issuance of Amendment No. 281, Revise Technical Specification 3.1, Table 3-3 to Correct Administrative Error in Surveillance Method for Containment Wide Range Radiation Monitors ML15015A4132015-02-20020 February 2015 Issuance of Amendment No. 280, Revise Technical Specification 3.2, Table 3-5 to Add New Surveillance Requirement ML14356A0122014-12-29029 December 2014 Issuance of Amendment No. 279, Revise Technical Specification Surveillance Requirements for One-Time Extension from Refueling Frequency of Once Per 18 Months to Maximum of 28 Months ML14328A8142014-12-22022 December 2014 Issuance of Amendment No. 278, Revise Technical Specification 2.5, Auxiliary Feedwater (AFW) System to Allow 7-Day Completion Time for Turbine-Driven AFW Pump Based on TSTF-340, Revision 3 ML14323A5992014-12-0202 December 2014 Relief Request RR-13, Relief from Inservice Testing Requirements to Perform Testing of 4 Valves During the April 2015 Refueling Outage ML14316A1672014-11-19019 November 2014 Relief Request RR-14, Proposed Alternative for Temporary Acceptance of a Pin Hole Leak in Raw Water System 20-Inch Elbow Located in Room 19 of Auxiliary Building ML14279A2752014-11-0606 November 2014 Issuance of Amendment No. 277, Revise Technical Specification Surveillance Requirement 3.2, Table 3-5, Item 3, for One-Time Extension of Frequency to Maximum of 28 Months ML14209A0272014-08-0707 August 2014 Issuance of Amendment No. 276, Request to Revise Updated Safety Analysis Report for Westinghouse Plant-Specific Leak-Before-Break Analysis ML14098A0922014-06-16016 June 2014 Issuance of Amendment No. 275, Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants (2001 Edition) ML14003A0032014-01-28028 January 2014 Issuance of Amendment No. 274, Revise Technical Specification 2.16, River Level, and Establish EAL Classification Criteria for External Flooding Events Under Radiological Emergency Response Plan ML13296A5842013-10-25025 October 2013 Issuance of Amendment No. 273, Revise Current Licensing Basis of Pipe Break Criteria for High Energy Line Breaks (Exigent Circumstances) ML13203A0702013-07-26026 July 2013 Issuance of Amendment No. 272 - Revise Current Licensing Basis to Adopt Revised Design Basis/Methodology for Addressing Design-Basis Tornado/Tornado Missile Impact (Exigent Circumstances) ML13141A6082013-06-25025 June 2013 Safety Assessment in Response to Request for Information Pursuant to 10 CFR 50.54(f) - Recommendation 9.3 Communications Assessment ML13070A0422013-03-29029 March 2013 Issuance of Amendment No. 271, Relocate Technical Specification LCO 2.17, Miscellaneous Radioactive Material Sources, and Surveillance Requirement 3.13 to Updated Safety Analysis Report ML13043A6612013-02-28028 February 2013 Issuance of Amendment No. 270 to Revise Technical Specification 2.15 to Establish Limiting Condition for Operation Requirements for Reactor Protective System Actuation Circuits ML13017A4672013-01-31031 January 2013 Approval of Request for Change to the Reactor Vessel Surveillance Capsule Removal Schedule ML12333A1192012-12-31031 December 2012 Issuance of Amendment No. 269, Incorporate New Radial Peaking Factor Definition and Clarify Limiting Condition for Operation (LCO) 2.10.2(6) ML1126204022011-09-30030 September 2011 Issuance of Amendment No. 268, Revise Updated Safety Analysis Report to Relocate Acoustic Position and Tail Pipe Temperature Indication Surveillance Requirements from Technical Specifications ML1118615712011-08-31031 August 2011 Issuance of Amendment No. 267, Revise Technical Specification (TS) 2.15 and TS 3.1 Related to Operability of Secondary Control Element Assembly Position Indication System Channels; Correction to TS 2.10.2(7)c ML1122702902011-08-18018 August 2011 Relief Request RR-12 from Code Case N-722, Additional Examinations for PWR Pressure Retaining Welds in Class 1 Components Fabricated with Alloy 600/82/182 Materials, Fourth 10-Year Inservice Inspection Interval ML1118010942011-07-27027 July 2011 Issuance of Amendment No. 266, Revise License Condition and Approve Cyber Security Plan and Associated Implementation Schedule ML1022101332010-08-20020 August 2010 Request for Use of Alternative to Depth-Sizing Qualification for Volumetric Examinations of Reactor Pressure Vessel Welds for 4th 10-year Inservice Inspection Interval ML1009100772010-05-14014 May 2010 License Amendment, 264, Revision of Tech Spec Sections 2.0.1 and 2.7 for Inoperable System, Subsystem, or Component Due to Inoperable Power Source and Deletion of Diesel Generator Surveillance Requirement 3.7(1)e 2024-01-31
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 19, 2015 Mr. Louis P. Cortopassi Site Vice President and Chief Nuclear Officer Omaha Public Power District Fort Calhoun Station 9610 Power Lane, Mail Stop FC-2-4 Blair, NE 68008
SUBJECT:
FORT CALHOUN STATION, UNIT NO. 1 - ISSUANCE OF AMENDMENT RE:
REVISION TO CYBER SECURITY PLAN IMPLEMENTATION SCHEDULE COMPLETION DATE (CAC NO. MF5854)
Dear Mr. Cortopassi:
The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendmi:rnt No. 284 to Renewed Facility Operating License No. DPR-40 for the Fort Calhoun Station, Unit No. 1. The amendment consists of changes to the operating license in response to your application dated November 25, 2014. You provided a redacted version of your application by letter dated April 20, 2015.
The amendment revises the Cyber Security Plan (CSP) Implementation Milestone 8 completion -
date and the physical protection license condition, by extending the CSP Milestone 8 full implementation date from December 31, 2015, to December 31, 2017.
A copy of the related Safety Evaluation is enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.
Sincerely, Carl F. Lyoh, Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclyar ~eactor Regulation Docket No. 50-285
Enclosures:
- 1. Amendment No. 284 to DPR-40
- 2. Safety Evaluation cc w/encl:s: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 OMAHA PUBLIC POWER DISTRICT DOCKET NO. 50-285 FORT CALHOUN STATION, UNIT NO. 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 284 Renewed License No. DPR-40
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by the Omaha Public Power District (the licensee), dated November 25, 2014, with a redacted version of the application provided by letter dated April 20, 2015, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
Enclosure 1
- 2. Accordingly, the license is amended by changes to paragraphs 3.8. and 3.C. of R1~newed Facility Operating License No. DPR-40.
Paragraph 3. B. is hereby amended to read as follows:
B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 284, are hereby incorporated in the license. Omaha Public Power District shall operate the facility in accordance with.the Technical Specifications.
Paragraph 3.C. is hereby amended to read as follows:
C. Security and Safeguards Contingency Plans The Omaha Public Power District shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions ofthe Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: "Fort Calhoun Station Security Plan, Training and Qualification Plan, Safeguards Contingency Plan," submitted by letter dated May 19, 2006.
OPPD shall fully implement and maintain in effect all provisions of the Commission-approved Cyber Security Plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The OPPD CSP was approved by License Amendment No. 266 and modified by License Amendment No. 284.
- 3. Ttle license amendment is effective as of its date of issuance and shall be implemented within 60 days of the date of issuance. The implementation of the CSP, including the ke!y intermediate milestone dates and the full implementation date, shall be in accordance with the implementation schedule submitted by the licensee on November 25, 2014, and approved by the NRC staff with this license amendment. All subsequent changes to the NRC-approved CSP implementation schedule will require prior NRC approval pursuant to 10 CFR 50.90.
FOR THE NUCLEAR REGULATORY COMMISSION Robert J. Pascarelli, Chief Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Renewed Facility Operating License No. DPR-40 Date of Issuance: r;Jovember *; 1J 9, 2O1 5
ATTACHMENT TO LICENSE AMENDMENT NO. 285 RENEWED FACILITY OPERATING LICENSE NO. DPR-40 DOCKET NO. 50-285 Replace the following page of the Renewed Facility Operating License No. DPR-40 with the attached revised page. The revised page is identified by amendment number and contains vertical lines indicating the areas of change.
,~License Page REMOVE INSERT (4) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source, or special nuclear material without restriction to chemical or physical form for sample analysis or instrument calibration or when associated with radioactive apparatus or components; (5) Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials. as may be produced by operation of the facility.
- 3. This renewed license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Section 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; and is, subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
A. Maximum Power Level Omaha Public Power District is authorized to operate the Fort Calhoun Station, Unit 1, at steady state reactor core power levels not in excess of 1500 megawatts thermal (rate power).
B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 284 are hereby incorporated in the license. Omaha Public Power District shall operate the facility in accordance with the Technical Specifications.
C. Security and Safeguards Contingency Plans The Omaha Public Power District shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: "Fort Calhoun Station Security Plan, Training and Qualification Plan, Safeguards Contingency Plan," submitted by letter dated May 19, 2006.
OPPD shall fully implement and maintain in effect all provisions of the Commission-approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The OPPD CSP was approved by License Amendment No. 266 and modified by License Amendment No. 284.
Renewed Operating License No. DPR-40 Amendment No. 284
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 284 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-40 OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION. UNIT NO. 1 DOCKET NO. 50-285
1.0 INTRODUCTION
By application dated November 25, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15070A007), Omaha Public Power District (OPPD or the licensee) requested a change to the renewed facility operating license for the Fort Calhoun Station (FCS). The proposed change would revise the date of Cyber Security Plan (CSP)
Implementation Schedule Milestone 8, and the existing license conditions in the facility operating licenses. Milestone 8 of the CSP implementation schedule concerns the full implementation of the CSP.
Portions of the letter dated November 25, 2014, contain sensitive unclassified non-safeguards information and, are withheld from public disclosure in accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390(d)(1 ). OPPD provided a redacted version of the application by letter dated April 20, 2015 (ADAMS Accession No. ML 1511 OA420).
2.0 REGULATORY EVALUATION
The U.S. Nuclear Regulatory Commission (NRC or the Commission) staff reviewed and approved the licensee's existing CSP implementation schedule by FCS License Amendment No. 266 dated July 27, 2011 (ADAMS Accession No. ML111801094), concurrent with the incorporation of the CSP into the facility's current licensing basis. The NRC staff considered the following regulatory requirements and guidance in its review of the current license amendment request (LAR) to modify the existing CSP implementation schedule:
- Title 1O of the Code of Federal Regulations (10 CFR) 73.54, "Protection of digital computer and communication systems and networks," states, in part, that: "Each
[CSP] submittal must include a proposed implementation schedule.
Implementation of the licensee's cyber security program must be consistent with the approved schedule."
Enclosure 2
- The licensee's facility operating license includes a license condition that requires the licensee to fully implement and maintain in effect all provisions of the Commission-approved CSP.
In a publicly-available NRC memorandum dated October 24, 2013 (ADAMS Accession No. ML13295A467), the NRC staff listed criteria to consider during evaluations of licensees' requests to postpone their cyber security program implementation date (commonly known as Milestone 8).
The NRC staff does not regard the CSP milestone implementation dates as regulatory commitm13nts that can be changed unilaterally by the licensee, particularly in light of the regulatory requirement at 10 CFR 73.54, that "[i]mplementation of the licensee's cyber security program must be consistent with the approved schedule." As the NRC staff explained in its letter to all operating reactor licensees dated May 9, 2011 (ADAMS Accession No. ML110980538), the implementation of the plan, including the key intermediate milestone dates and the full implementation date shall be in accordance with the implementation schedule submitted by the licensee and approved by the NRC. All subsequent changes to the NRG-approved CSP implementation schedule, thus, will require prior NRC approval as required by 10 CFR 50.90.
3.0 TECHNICAL EVALUATION
Amendment No. 266 to Renewed Facility Operating License (FOL) DPR-40 for FCS was issued on July 27, 2011. The NRC staff also approved the licensee's CSP implementation schedule, as discussed in the safety evaluation issued with the amendment. The implementation schedule had been submitted by the licensee based on a template prepared by the Nuclear Energy Institute (NEI) (ADAMS Accession No. ML110600218), which the NRC staff found acceptable for licensees to use to develop their CSP implementation schedules (ADAMS Accession No. ML110070348). The licensee's proposed implementation schedule for the CSP identified completion dates and bases for the following eight milestones:
a) Establish the Cyber Security Assessment Team (CSAT);
b) Identify Critical Systems (CSs) and Critical Digital Assets (CDAs);
c) Install a deterministic one-way device between lower level devices and higher level devices; d) Implement the security control "Access Control for Portable and Mobile Devices";
e) Implement observation and identification of obvious cyber related tampering to existing insider mitigation rounds by ir:icorporating the appropriate elements; f) Identify, document, and implement technical cyber security controls in
- accordance with "Mitigation of Vulnerabilities and Application of Cyber Security Controls" for CDAs that could adversely impact the design function of physical security target set equipment;
g) Commence ongoing monitoring and assessment activities for those target set CDAs whose security controls have been implemented; and
3.1 Licensee's Proposed Change Currently, Milestone 8 of the FCS CSP requires the licensee to fully implement the CSP by Decembe*r 31, 2015. In its November 25, 2014, application, OPPD proposed to change the Milestone 8 completion date to December 31, 2017.
- 3.2 NRC Staff Evaluation The cyber security implementation schedule demonstrates the licensee's ongoing implementation of its CSP prior to full implementation. For OPPD, the date for full implementation is specified by Milestone 8. CSP implementation activities include establishing a CSAT, identifying CSs and CDAs, installing deterministic one-way devices between defensive levels, implementing access control for portable and mobile. devices, implementing methods to observe and identify obvious cyber related tampering, and conducting ongoing monitoring and assessment activities for target set CDAs. In their aggregate, the interim milestones demonstrate ongoing implementation of the CSP.
The importance of ongoing implementation is reflected in the NRC staff's October 24, 2013, guidance for considering requests to postpone the CSP full implementation date. The criteria in the guidance are:
- 1) Identification of the specific requirement or requirements of the cyber security plan that the licensee needs additional time to implement.
- 2) Detailed justification that describes the reason the licensee requires additional time to implement the specific requirement or requirements identified.
- 3) A proposed completion date for Milestone 8 consistent with the remaining scope of work to be conducted and the resources available.
- 4) An evaluation of the impact that the additional time to implement the requirements will have on the effectiveness of ttie licensee's overall cyber security program in the context of milestones already completed.
- 5) A description of the licensee's methodology for prioritizing completion of work for critical digital assets associated with significant safety consequences and with reactivity effects in the balance of plant.
- 6) A discussion of the licensee's cyber security program performance up to the date of the license amendment request.
- 7) A discussion of cyber security issues pending in the licensee's corrective action program.
- 8) A discussion of modifications completed to support the cyber security program and a discussion of pending cyber security modifications.
- The licensee submitted its application on November 25, 2014, after the NRC staff issued the guidance. The licensee's application addressed each of the criteria in the guidance. The NRC staff has evaluated the licensee's application addressing the above criteria in its submittal dated November 25, 2014. The NRC staff's evaluation is below, numbered to match the criteria above.
- 1) Identification of the specific requirement or requirements of the cyber security plan that the licensee needs additional time to implement.
The licensee stated that it needs additional time to implement CSP Section 3.1.6, "Mitigation of Vulnerabilities and Application of Cyber Security Controls." The licensee identified the challenges to completing implementation of the CSP requirE!ment.
- 2) Detailed justification that describes the reason the licensee requires additional time to implement the specific requirement or requirements identified.
The licensee noted that there are ongoing issues that need resolution prior to completing implementation of CSP Section 3.1.6. These include CDA assessment; remediation activities; change management; and training on new processes, procedures, and programs. The licensee stated it is experiencing significant challenges with full implementation of Milestone 8. The large number of CDAs within the FCS I OPPD program, in concert with the deterministic process required by CSP Section 3.1.6 has resulted in a much larger volume of assessment work than originally anticipated. In aggregate, the changes in the assessment and remediation process since 2010 have necessit~ted significant changes to the FCS CDA assessment methodology, changes to approved procedures, and the introduction of new methods not previously considered. These changes have required substantial resources to implement and re-performance of completed assessment activities. Although the precise scope of modifications cannot be conclusively articulated until the assessment process is complete and full program implementation is expected to require technically complex modifications. In most cases, the modifications would require refueling outages for safe implementation and must be coordinated with outa!~e schedules and tested thoroughly prior to installation to confirm proper operation.
The NRC staff acknowledges implementation issues with large numbers of CDAs and the need to address many controls for each. Based on the information provided by the licensee in its application, the NRC staff believes that FCS would not be able to fully implement its CSP by December 31, 2015. The NRC staff recognizes that CDA assessment work is resource-iritensive and that the licensee has a large number of CDAs. The NRC staff agrees remediation activities must be carefully considered and that working with security controls is a new experience for the licensee staff and suppliers, and that security modifications must be implemented to not impact safety and operations. The NRC staff understands that cyber
security program implementation has created change management challenges as it has impacted many aspects of the licensee's plant processes. In conclusion, the NRC staff finds the licensee's explanation of the need for additional time compelling, given the unanticipated complexity and scope of the work required to come into full compliance with its CSP.
- 3) A proposed completion date for Milestone 8 consistent with the remaining scope of work to be conducted and the resources available.
The licensee proposed a Milestone 8 completion date of December 31, 2017, and stated the revised Milestone 8 date will encompass an additional refueling outage, which will provide more time to plan and schedule the implementation of design changes identified as a result of the CDA assessments.
Based on the licensee's application, the NRC staff concludes that delaying final implementation of the cyber security program will provide an opportunity to complete the work safely during the outage.
- 4) An evaluation of the impact that the additional time to implement the requirements will have on the effectiveness of the licensee's overall cyber security program in the context of milestones already completed.
- The licensee indicated it was secure based on the cyber security implementation activities already completed. It then detailed the activities completed in each of the Milestones 1 through 7. The activities address significant cyber-attack vectors and applied controls to the most significant CDAs. Additionally, it is important to note that the delay of Milestone 8 does not affect the effectiveness of the completed activities.
The NRC staff concludes that the licensee's site is much more secure because the controls the licensee put in place mitigate the most significant cyber-attack vectors for the most significant CDAs.
- 5) A description of the licensee's methodology for prioritizing completion of work for critical di!~ital assets associated with significant safety consequences and with reactivity effects in the balance of plant.
The licensee stated that its methodology for prioritizing Milestone 8 activities is predicated on completing CDA assessments and determining where vulnerabilities may exist. Prioritization of CDA assessments will be made on significant safety, security, or emergency preparedness consequences and equipment important to safety. Any resulting remedial modifications are then prioritized through the significance level and work control process. The FCS cyber-related activities are prioritized to first complete priority CDA assessments and then to identify and implement modifications required for remediation activities.
The NRC staff finds that based on the large number of digital assets described above, and the limited resources to perform these activities, the licensee's methodology for prioritizing work on CDAs is logical, conservative, and appropriate.
- 6) A discussion of the licensee's cyber security program performance up to the date of the license amendment request.
The licensee stated that a Nuclear Oversight audit of CSP Milestones 1 through 7 and on-going Quality Assurance surveillances under the physical security surveillance program have concluded that OPPD has an effective program at FCS. Issues identified during the audit were entered into the Corrective Actions Program (CAP) and addressed for improvement of the cyber security program. Also, OPPD has completed a comprehensive peer-assessment for Milestones 1 through 7 to ensure completeness and effectiveness of the implemented actions.
Issues identified during the peer-assessment were entered into the CAP *and addressed for improvement of the cyber security program. The NRC completed a cyber-security inspection at FCS, which resulted in three findings of very low significance (NRC Inspection Report 05000285/2014405, dated June 25, 2014, security-related information withheld. from public availability in accordance with 10 CFR 2.390(d)(1); ADAMS Accession No. ML141768202).
Two of the identified findings have been remediated and the thi.rd finding is scheduled for remediation; these findings and their remediation are appropriately documented in the licensee's corrective action program. The independent Nuclear Safety Review Board comprised of senior managers and industry experts periodically reviews the FCS/OPPD CSP. In addition, ongoing monitoring and time-based periodic actions provide continuing program performance monitoring.
- The NRC staff finds that the licensee's completion of Milestones 1 through 7 provides significant protection against cyber attacks. NRC staff concludes that the licensee is using the quality tools at its disposal to verify the effectiveness of the cyber security program and addressing issues in its corrective action program.
- 7) A discussion of cyber security issues pending in the licensee's corrective action program.
The licensee stated that the OPPD CAP is used to document all cyber security issues in order to trend, correct, and improve the FCS/OPPD CSP. The CAP database documents and tracks all cyber security required actions from Condition Report (CR) initiation to CR closure, including issues identified during ongoing program assessment activities. Adverse trends are monitored for CSP improvement and are addressed via the CAP proce~s. The licensee listed examples of CSP issues and activities pending in the CAP.
The NRC staff finds that the examples reflect the evolution .and implementation of the cyber security program and reinforce the licensee discussions above. The NRC staff concludes that the licensee is using the quality tools at its disposal to verify the effectiveness of the cyber security program and is addressing issues in its corrective action program.
- 8) A discussion of modifications completed to support the CSP and a discussion of pending cyber security modifications.
The licensee provided a discussion of completed modifications and pending modifications.
These are consistent with the discussions provided above and the licensee's CSP.
3.3 Revision to License Condition By letter dated November 25, 2014, the licensee proposed to modify paragraph 3.C. of Renewed FOL No. DPR-40 for FCS that provides a license condition to require the licensee to fully implement and maintain in effect all provisions of the NRG-approved CSP.
Accordingly, the license condition in paragraph 3.C. of Renewed FOL No. DPR-:40 for FCS is revised as follows:
C. Security and Safeguards Contingency Plans The Omaha Public Power District shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: "Fort Calhoun Station Security Plan, Training and Qualification Plan, Safeguards Contingency Plan," submitted by letter dated May 19, 2006.
OPPD shall fully implement and maintain in effect all provisions of the Commission-approved Cyber Security Plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).
The OPPD CSP was approved by License Amendment No. 266 and modified by License Amendment No. 284.
3.4 NRC Staff Conclusion
Based on its review of the licensee's submissions, the NRC staff concludes that implementation of Milestones 1 through 7 provides significant protection against cyber-attacks; that the licensee's explanation of the need for additional time is compelling, an*d that it is acceptable for FCS to complete Milestone 8 (full implementation of the CSP) by December 31, 2017. The NRC has reasonable assurance that the full implementation of the CSP by December 31, 2017, will provide adequate protection of the public health and safety of the common defense and security. The NRC staff also concludes that, upon full implementation of the licensee's cyber security program, the requirements of the licensee's CSP and 10 CFR 73.54 will be met.
Therefore, the NRC staff finds the proposed change acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the appropriate Nebraska State official, Ms. J. Schmitt, was notified on October 23, 2015, of the proposed issuance of the amendment.
The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
This is an amendment to a 10 CFR Part 50 license that relates solely to safeguard matters and does not involve any significant construction impacts. This amendment is an administrative change to extend the date by which the licensee must have its CSP fully implemented.
Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(12)(ii). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: J. Rycyna, NSIR/CSD Date: November 1 9 , 2O1 5
ML15294A279 *email dated OFFICE NRR/DORULPL4-1/PM ..................................................................................... NRR/DORULPL4-1 /LA NSIR/CSD/DD*
NAME .... ~~Y?r.:! ...... JBurkhardt RFelts DATE 11/18/15 10/22/15 10/5/15 OFFICE OGG* NRR/DORULPL4-1/BC NRR/DORULPL4-1/PM NAME LLondon NLO.................................
......................................................... w/edits.. RPascarelli ........................................... ***************** ................ ~.~.Y.?.r.:1. . . .
DATE 11/18/15 11/19/15 11/19/15