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Category:Letter type:NL
MONTHYEARNL-23-0930, Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program2024-09-11011 September 2024 Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program NL-24-0337, Interim 10 CFR 21.21(a)(2) Report Regarding Operation Technology, Inc., ETAP Software Error in Transient Stability Program2024-09-0909 September 2024 Interim 10 CFR 21.21(a)(2) Report Regarding Operation Technology, Inc., ETAP Software Error in Transient Stability Program NL-24-0334, 0 to the Updated Final Safety Analysis Report, Technical Specifications Bases Changes, Technical Requirements Manual Changes, License Renewal 10 CFR 54 .37(b) Changes, 10 CFR 50.59 Summary Report & Revised Nrc2024-09-0303 September 2024 0 to the Updated Final Safety Analysis Report, Technical Specifications Bases Changes, Technical Requirements Manual Changes, License Renewal 10 CFR 54 .37(b) Changes, 10 CFR 50.59 Summary Report & Revised Nrc NL-24-0313, Application to Revise Technical Specifications Surveillance Requirements to Increase Safety/Relief Valves Setpoint Response to Request for Additional Information2024-08-23023 August 2024 Application to Revise Technical Specifications Surveillance Requirements to Increase Safety/Relief Valves Setpoint Response to Request for Additional Information NL-24-0276, Post-Audit Supplement to License Amendment Request to Revise Renewed Facility Operating Licenses to Adopt an Alternative Seismic Method for Categorization of Structures, Systems, and Components2024-07-26026 July 2024 Post-Audit Supplement to License Amendment Request to Revise Renewed Facility Operating Licenses to Adopt an Alternative Seismic Method for Categorization of Structures, Systems, and Components NL-24-0290, Response to Request for Additional Information Related to Request for Specific Exemption2024-07-26026 July 2024 Response to Request for Additional Information Related to Request for Specific Exemption NL-24-0261, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20232024-07-19019 July 2024 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2023 NL-24-0260, Inservice Inspection Program Owner’S Activity Report (OAR-1) for Refueling Outage 1R312024-07-0909 July 2024 Inservice Inspection Program Owner’S Activity Report (OAR-1) for Refueling Outage 1R31 NL-24-0237, Incorrectly Installed Temporary Modification Results in Multiple Conditions Prohibited by Plant Technical Specifications2024-07-0303 July 2024 Incorrectly Installed Temporary Modification Results in Multiple Conditions Prohibited by Plant Technical Specifications NL-24-0240, Reactor Core Isolation Cooling (RCIC) System Inoperable Due to Mispositioned Link2024-07-0303 July 2024 Reactor Core Isolation Cooling (RCIC) System Inoperable Due to Mispositioned Link NL-24-0143, Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in2024-06-27027 June 2024 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in NL-24-0239, Response to Apparent Violation in NRC Inspection Report 05000321, 366/2024090: EA-23-1392024-06-17017 June 2024 Response to Apparent Violation in NRC Inspection Report 05000321, 366/2024090: EA-23-139 NL-24-0148, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2024-06-0404 June 2024 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis NL-24-0202, SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations2024-05-24024 May 2024 SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations NL-24-0191, Annual Radiological Environmental Operating Reports for 20232024-05-10010 May 2024 Annual Radiological Environmental Operating Reports for 2023 NL-24-0166, Manual Reactor Trip Due to Loss of Feedwater2024-05-0909 May 2024 Manual Reactor Trip Due to Loss of Feedwater NL-24-0195, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times for Residual Heat Removal Service Water.2024-05-0707 May 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times for Residual Heat Removal Service Water. NL-24-0064, Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.52024-05-0303 May 2024 Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.5 NL-24-0165, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20232024-04-25025 April 2024 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2023 NL-24-0157, Incorrectly Installed Temporary Modification Results in a Condition Prohibited by Plant Technical Specifications2024-04-24024 April 2024 Incorrectly Installed Temporary Modification Results in a Condition Prohibited by Plant Technical Specifications NL-24-0026, Application to Revise Technical Specifications Surveillance Requirements to Increase Safety/Relief Valves Setpoint2024-04-19019 April 2024 Application to Revise Technical Specifications Surveillance Requirements to Increase Safety/Relief Valves Setpoint NL-24-0144, Primary Containment Penetration Exceeded Maximum Allowable Primary Containment Leakage Rate (La)2024-04-0909 April 2024 Primary Containment Penetration Exceeded Maximum Allowable Primary Containment Leakage Rate (La) NL-24-0115, Response to Request for Additional Information Exemption Requests for Physical.2024-04-0404 April 2024 Response to Request for Additional Information Exemption Requests for Physical. NL-24-0116, Nuclear Property Insurance Coverage as of April 1, 2024 and Licensee Guarantees of Payment of Deferred.2024-03-29029 March 2024 Nuclear Property Insurance Coverage as of April 1, 2024 and Licensee Guarantees of Payment of Deferred. NL-24-0062, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2024-03-12012 March 2024 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis NL-24-0089, Correction of Technical Specification Omission2024-03-0909 March 2024 Correction of Technical Specification Omission NL-24-0061, Cycle 32 Core Operating Limits Report Version 12024-03-0101 March 2024 Cycle 32 Core Operating Limits Report Version 1 NL-24-0067, 10 CFR 72.48(d)(2) Biennial Report2024-02-26026 February 2024 10 CFR 72.48(d)(2) Biennial Report NL-24-0051, License Amendment Request to Revise Renewed Facility Operating Licenses to Adopt an Alternative Seismic Method for Categorization of Structures, Systems, and Components2024-02-20020 February 2024 License Amendment Request to Revise Renewed Facility Operating Licenses to Adopt an Alternative Seismic Method for Categorization of Structures, Systems, and Components NL-24-0042, Response to Request for Additional Information Exemption Requests for Physical Barriers2024-02-13013 February 2024 Response to Request for Additional Information Exemption Requests for Physical Barriers NL-24-0033, Response to Question for Withholding Information from Public Disclosure Exemption Requests for Physical Barriers2024-02-0505 February 2024 Response to Question for Withholding Information from Public Disclosure Exemption Requests for Physical Barriers NL-24-0014, Revised Response to Request for Additional Information Regarding License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical.2024-01-30030 January 2024 Revised Response to Request for Additional Information Regarding License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical. NL-23-0889, Units 1 and 2 - License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times for Residual Heat Removal Service Water (RHRSW) and Plant Service Water (Psw) Systems2023-12-0606 December 2023 Units 1 and 2 - License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times for Residual Heat Removal Service Water (RHRSW) and Plant Service Water (Psw) Systems NL-23-0879, Request for Exemption from Security Event Notification Implementation2023-11-29029 November 2023 Request for Exemption from Security Event Notification Implementation NL-23-0841, Update to Notice of Intent to Pursue Subsequent License Renewal2023-11-20020 November 2023 Update to Notice of Intent to Pursue Subsequent License Renewal NL-23-0658, Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal2023-08-11011 August 2023 Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal NL-23-0542, CFR 50.46 ECCS Evaluation Model Annual Report for 20222023-08-0909 August 2023 CFR 50.46 ECCS Evaluation Model Annual Report for 2022 NL-23-0624, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2023-08-0404 August 2023 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis NL-23-0566, ISFSI and Edwin I. Hatch Nuclear Plant ISFSI - Registration of Spent Fuel Cask Use2023-07-13013 July 2023 ISFSI and Edwin I. Hatch Nuclear Plant ISFSI - Registration of Spent Fuel Cask Use NL-23-0555, Request for Exemption from Physical Barrier Requirement2023-07-0707 July 2023 Request for Exemption from Physical Barrier Requirement NL-23-0444, Quality Assurance Topical Report Submittal2023-06-15015 June 2023 Quality Assurance Topical Report Submittal NL-23-0457, ISFSI, and Edwin I. Hatch Nuclear Plant, ISFSI - Registration of Spent Fuel Cask Use2023-06-12012 June 2023 ISFSI, and Edwin I. Hatch Nuclear Plant, ISFSI - Registration of Spent Fuel Cask Use NL-23-0422, Inservice Inspection Program Owner'S Activity Report for Refueling Outage 2R272023-05-30030 May 2023 Inservice Inspection Program Owner'S Activity Report for Refueling Outage 2R27 NL-23-0383, SNC Response to Regulatory Issue Summary 2023-01:Preparation And.2023-05-19019 May 2023 SNC Response to Regulatory Issue Summary 2023-01:Preparation And. NL-23-0372, Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 20222023-05-10010 May 2023 Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 2022 NL-23-0310, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20222023-04-25025 April 2023 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2022 NL-23-0019, GEN-ISI-ALT-2023-01, Request to Use Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2023-04-12012 April 2023 GEN-ISI-ALT-2023-01, Request to Use Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI NL-23-0263, Southern Nuclear Company Submittal of Drug and Alcohol Testing Errors Identified 10 CFR 26.719(c) 30-Day Report2023-04-0505 April 2023 Southern Nuclear Company Submittal of Drug and Alcohol Testing Errors Identified 10 CFR 26.719(c) 30-Day Report NL-23-0208, Independent Spent Fuel Storage Installation ISFSI, Decommissioning Funding Plan Triennial Update2023-03-29029 March 2023 Independent Spent Fuel Storage Installation ISFSI, Decommissioning Funding Plan Triennial Update NL-23-0014, Southern Nuclear Operating Co Submittal of Report on Status of Decommissioning Funding2023-03-29029 March 2023 Southern Nuclear Operating Co Submittal of Report on Status of Decommissioning Funding 2024-09-09
[Table view] Category:Report
MONTHYEARNL-24-0334, 0 to the Updated Final Safety Analysis Report, Technical Specifications Bases Changes, Technical Requirements Manual Changes, License Renewal 10 CFR 54 .37(b) Changes, 10 CFR 50.59 Summary Report & Revised Nrc2024-09-0303 September 2024 0 to the Updated Final Safety Analysis Report, Technical Specifications Bases Changes, Technical Requirements Manual Changes, License Renewal 10 CFR 54 .37(b) Changes, 10 CFR 50.59 Summary Report & Revised Nrc ML24047A2092024-02-22022 February 2024 Calendar Year 2023 Baseline Inspection Completion ML24005A1142024-01-0505 January 2024 Recommendation for 2023-301 Cr/Sim 3 (Emergency Depress the Reactor Using Main Steam Line Drains) NL-22-0510, Plants Units 1 and 2, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20212022-07-14014 July 2022 Plants Units 1 and 2, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2021 A000412, National Pollutant Discharge Elimination System (NPDES) Permit Renewal Application2021-12-0202 December 2021 National Pollutant Discharge Elimination System (NPDES) Permit Renewal Application NL-20-1295, 10 CFR 71.95 Report on Non-Compliance Involving Radwaste Cask 3-60B2020-12-14014 December 2020 10 CFR 71.95 Report on Non-Compliance Involving Radwaste Cask 3-60B ML20309A5052020-11-0303 November 2020 Inspector Notes Cover Sheet ML20303A1782020-09-29029 September 2020 Submittal of Revision 38 to Updated Final Safety Analysis Report NL-19-0674, Proposed Alternative to Use ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 12019-09-30030 September 2019 Proposed Alternative to Use ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 1 NL-18-0863, CFR 50.55a Request for Alternative HNP-ISI-ALT-05-04 Implementation of BWRVIP Documents in Lieu of Certain 8-N-1 and 8-N-2 Examinations2018-06-21021 June 2018 CFR 50.55a Request for Alternative HNP-ISI-ALT-05-04 Implementation of BWRVIP Documents in Lieu of Certain 8-N-1 and 8-N-2 Examinations NL-18-0506, Failure to Observe the Certificate of Compliance Condition of the 8-120B Cask Pre-Shipment Leak Test2018-04-16016 April 2018 Failure to Observe the Certificate of Compliance Condition of the 8-120B Cask Pre-Shipment Leak Test NL-17-1713, Proposed Alternative GEN-ISI-ALT-2017-03, and HNP-ISI-ALT-05-07, Version 1.0 Service Water Evaluation for Code Case N-513-4 for Moderate Pressure, and for Higher Pressure2018-04-0606 April 2018 Proposed Alternative GEN-ISI-ALT-2017-03, and HNP-ISI-ALT-05-07, Version 1.0 Service Water Evaluation for Code Case N-513-4 for Moderate Pressure, and for Higher Pressure NL-18-0282, Enclosure 1: NFPA 805 LAR Transition Report for Edwin I. Hatch2018-04-0404 April 2018 Enclosure 1: NFPA 805 LAR Transition Report for Edwin I. Hatch NL-17-1916, Pressure and Temperature Limits Report2017-11-27027 November 2017 Pressure and Temperature Limits Report ML18012A0582017-10-31031 October 2017 NEDO-33884, Revision 0, Gnf Fecrai ATF Lead Test Assembly for Edwin I. Hatch Nuclear Plant, Unit 1. NL-18-0026, NEDO-33884, Revision 0, Gnf Fecrai ATF Lead Test Assembly for Edwin I. Hatch Nuclear Plant, Unit 1.2017-10-31031 October 2017 NEDO-33884, Revision 0, Gnf Fecrai ATF Lead Test Assembly for Edwin I. Hatch Nuclear Plant, Unit 1. NL-18-0026, NEDO-33884, Revision 0, Gnf Fecrai Atf Lead Test Assembly for Edwin I. Hatch Nuclear Plant, Unit 1.2017-10-31031 October 2017 NEDO-33884, Revision 0, Gnf Fecrai Atf Lead Test Assembly for Edwin I. Hatch Nuclear Plant, Unit 1. NL-18-0026, NEDO-33883, Revision 0, Gnf Armor Lead Test Assembly for Edwin I. Hatch Nuclear Plant, Unit 1.2017-09-30030 September 2017 NEDO-33883, Revision 0, Gnf Armor Lead Test Assembly for Edwin I. Hatch Nuclear Plant, Unit 1. NL-17-1255, Fukushima Near-Term Task Force Recommendation 2.1 Seismic Limited-Scope High Frequency Confirmation Evaluation2017-08-22022 August 2017 Fukushima Near-Term Task Force Recommendation 2.1 Seismic Limited-Scope High Frequency Confirmation Evaluation NL-17-0955, Alternatives HNP-ISI-ALT-05-05 and HNP-ISI-ALT-05-062017-06-0505 June 2017 Alternatives HNP-ISI-ALT-05-05 and HNP-ISI-ALT-05-06 ML17069A2402017-04-13013 April 2017 Mitigating Strategies Assessment (CAC Nos. MF7932 and MF7933) - Redacted ML16356A0172016-12-16016 December 2016 Information Report for Lead Use Assemblies NL-16-2466, Fukushima Near-Term Task Force Recommendation 2.1 Expedited Seismic Evaluation Process Report Completion2016-12-15015 December 2016 Fukushima Near-Term Task Force Recommendation 2.1 Expedited Seismic Evaluation Process Report Completion NL-16-1136, Fukushima Near-Term Task Force Recommendation 2.1 Seismic Limited-Scope Low Frequency Evaluation2016-08-10010 August 2016 Fukushima Near-Term Task Force Recommendation 2.1 Seismic Limited-Scope Low Frequency Evaluation NL-16-0463, Submittal of 10 CFR 50.46 ECCS Evaluation Model, Annual Report for 2015 and Significant Change/Error Report2016-04-0101 April 2016 Submittal of 10 CFR 50.46 ECCS Evaluation Model, Annual Report for 2015 and Significant Change/Error Report ML16028A2952016-01-29029 January 2016 10 CFR 71.95 Notification Associated with the Failure to Observe Certificate of Compliance Condition of the 8-120B Secondary Lid Test Port Configuration PLA-7414, Redacted - Susquehanna, Units 1 and 2 - Submittal of 10 CFR 71.95 Report Regarding Energy Solutions 8-120B Cask Certificate of Compliance 91682015-11-19019 November 2015 Redacted - Susquehanna, Units 1 and 2 - Submittal of 10 CFR 71.95 Report Regarding Energy Solutions 8-120B Cask Certificate of Compliance 9168 ML15321A4542015-11-13013 November 2015 Submittal of 10 CFR 71.95 Report on the 8-120B Cask JAFP-15-0129, Submittal of 10 CFR 71.95 Report Involving 8-120B Cask2015-11-0606 November 2015 Submittal of 10 CFR 71.95 Report Involving 8-120B Cask NL-15-2010, E.I. Hatch - Submits 10 CFR 71.95 Report on Non-Conformance Involving Radwaste Cask 8-120B2015-11-0202 November 2015 E.I. Hatch - Submits 10 CFR 71.95 Report on Non-Conformance Involving Radwaste Cask 8-120B NLS2015128, Submittal of 10 CFR 71.95 Report Involving Energysolutions Certificate of Compliance No. 91682015-10-29029 October 2015 Submittal of 10 CFR 71.95 Report Involving Energysolutions Certificate of Compliance No. 9168 ZS-2015-0156, Zionsolutions, LLC - Submittal of 10 CFR 71.95 Report on the 8-120B Cask2015-10-26026 October 2015 Zionsolutions, LLC - Submittal of 10 CFR 71.95 Report on the 8-120B Cask ML15313A1642015-10-0808 October 2015 Submittal of 10 CFR 71.95 Report on the 8-120B Cask DCL-15-102, 10 CFR 71.95 Report Regarding Energy Solutions' Model 8-120B Shipping Cask2015-08-24024 August 2015 10 CFR 71.95 Report Regarding Energy Solutions' Model 8-120B Shipping Cask ML15259A3422015-08-24024 August 2015 10 CFR 71.95 Report Evaluation Form; Submitted by Fenok, Erwin Resin Solutions, North Anna Power Stations, Et Al NL-15-1461, Submittal of 10 CFR 71.95 Report on Potential Issues Involving Radwaste Cask 8-120B2015-08-21021 August 2015 Submittal of 10 CFR 71.95 Report on Potential Issues Involving Radwaste Cask 8-120B PLA-7374, Submittal of 10 CFR71.95 Report Regarding Energy Solutions 8-120B Cask Certificate of Compliance 91682015-08-20020 August 2015 Submittal of 10 CFR71.95 Report Regarding Energy Solutions 8-120B Cask Certificate of Compliance 9168 NRC-15-0085, Submittal of 10 CFR 71.95 Report on the 8-120B Shipping Cask2015-08-19019 August 2015 Submittal of 10 CFR 71.95 Report on the 8-120B Shipping Cask ZS-2015-0131, Zionsolutions, LLC - Submittal of10 CFR 71.95 Report on the 8-120B Cask2015-08-18018 August 2015 Zionsolutions, LLC - Submittal of10 CFR 71.95 Report on the 8-120B Cask ML15246A1452015-08-11011 August 2015 Submittal of 10 CFR 71.95 Report on the 8-120B Cask NLS2015091, 10 CFR 71.95 Report Involving Energysolutions Certificate of Compliance No. 91682015-07-28028 July 2015 10 CFR 71.95 Report Involving Energysolutions Certificate of Compliance No. 9168 ML15097A4242015-04-27027 April 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Reevaluations Relating to Recommendation 2.1 of the NTTF Review ML15106A3102015-04-17017 April 2015 April 22, 2015, Meeting with Southern Nuclear Company, Draft Minimum Shift Staffing Analysis ML14335A1372015-03-25025 March 2015 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-13-109 (Severe Accident Capable Hardened Vents) NL-14-1989, Expedited Seismic Evaluation Process Report - Fukushima Near-Term Task Force Recommendation 2.12014-12-30030 December 2014 Expedited Seismic Evaluation Process Report - Fukushima Near-Term Task Force Recommendation 2.1 NL-14-1876, Proposed Lnservice Inspection Alternative HNP-ISI-ALT-HDPE-01, Version 2.0, Conceptual Design Information Package2014-11-24024 November 2014 Proposed Lnservice Inspection Alternative HNP-ISI-ALT-HDPE-01, Version 2.0, Conceptual Design Information Package NL-14-1245, 10 CFR 26.719(c) Report: False Negative Results for a Blind Performance Test Sample2014-08-22022 August 2014 10 CFR 26.719(c) Report: False Negative Results for a Blind Performance Test Sample ZS-2014-0271, Zionsolutions' 10 CFR 71.95 Report of Non-Compliance with Certificate of Compliance No. 9168, Revision No. 20 - Cask 8-120B2014-08-18018 August 2014 Zionsolutions' 10 CFR 71.95 Report of Non-Compliance with Certificate of Compliance No. 9168, Revision No. 20 - Cask 8-120B ML14223A7942014-07-31031 July 2014 Enclosure 2 - Non-Proprietary Gnf Report GNF-001N6296-R1-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR, Hatch 2 Cycle 24 ML14155A4052014-06-30030 June 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident (TAC MF0234-35) 2024-09-03
[Table view] Category:Miscellaneous
MONTHYEARNL-24-0334, 0 to the Updated Final Safety Analysis Report, Technical Specifications Bases Changes, Technical Requirements Manual Changes, License Renewal 10 CFR 54 .37(b) Changes, 10 CFR 50.59 Summary Report & Revised Nrc2024-09-0303 September 2024 0 to the Updated Final Safety Analysis Report, Technical Specifications Bases Changes, Technical Requirements Manual Changes, License Renewal 10 CFR 54 .37(b) Changes, 10 CFR 50.59 Summary Report & Revised Nrc ML24047A2092024-02-22022 February 2024 Calendar Year 2023 Baseline Inspection Completion ML24005A1142024-01-0505 January 2024 Recommendation for 2023-301 Cr/Sim 3 (Emergency Depress the Reactor Using Main Steam Line Drains) NL-18-0863, CFR 50.55a Request for Alternative HNP-ISI-ALT-05-04 Implementation of BWRVIP Documents in Lieu of Certain 8-N-1 and 8-N-2 Examinations2018-06-21021 June 2018 CFR 50.55a Request for Alternative HNP-ISI-ALT-05-04 Implementation of BWRVIP Documents in Lieu of Certain 8-N-1 and 8-N-2 Examinations NL-18-0506, Failure to Observe the Certificate of Compliance Condition of the 8-120B Cask Pre-Shipment Leak Test2018-04-16016 April 2018 Failure to Observe the Certificate of Compliance Condition of the 8-120B Cask Pre-Shipment Leak Test NL-17-1713, Proposed Alternative GEN-ISI-ALT-2017-03, and HNP-ISI-ALT-05-07, Version 1.0 Service Water Evaluation for Code Case N-513-4 for Moderate Pressure, and for Higher Pressure2018-04-0606 April 2018 Proposed Alternative GEN-ISI-ALT-2017-03, and HNP-ISI-ALT-05-07, Version 1.0 Service Water Evaluation for Code Case N-513-4 for Moderate Pressure, and for Higher Pressure NL-17-0955, Alternatives HNP-ISI-ALT-05-05 and HNP-ISI-ALT-05-062017-06-0505 June 2017 Alternatives HNP-ISI-ALT-05-05 and HNP-ISI-ALT-05-06 ML17069A2402017-04-13013 April 2017 Mitigating Strategies Assessment (CAC Nos. MF7932 and MF7933) - Redacted ML16356A0172016-12-16016 December 2016 Information Report for Lead Use Assemblies NL-16-0463, Submittal of 10 CFR 50.46 ECCS Evaluation Model, Annual Report for 2015 and Significant Change/Error Report2016-04-0101 April 2016 Submittal of 10 CFR 50.46 ECCS Evaluation Model, Annual Report for 2015 and Significant Change/Error Report ML16028A2952016-01-29029 January 2016 10 CFR 71.95 Notification Associated with the Failure to Observe Certificate of Compliance Condition of the 8-120B Secondary Lid Test Port Configuration PLA-7414, Redacted - Susquehanna, Units 1 and 2 - Submittal of 10 CFR 71.95 Report Regarding Energy Solutions 8-120B Cask Certificate of Compliance 91682015-11-19019 November 2015 Redacted - Susquehanna, Units 1 and 2 - Submittal of 10 CFR 71.95 Report Regarding Energy Solutions 8-120B Cask Certificate of Compliance 9168 ML15321A4542015-11-13013 November 2015 Submittal of 10 CFR 71.95 Report on the 8-120B Cask JAFP-15-0129, Submittal of 10 CFR 71.95 Report Involving 8-120B Cask2015-11-0606 November 2015 Submittal of 10 CFR 71.95 Report Involving 8-120B Cask NLS2015128, Submittal of 10 CFR 71.95 Report Involving Energysolutions Certificate of Compliance No. 91682015-10-29029 October 2015 Submittal of 10 CFR 71.95 Report Involving Energysolutions Certificate of Compliance No. 9168 ZS-2015-0156, Zionsolutions, LLC - Submittal of 10 CFR 71.95 Report on the 8-120B Cask2015-10-26026 October 2015 Zionsolutions, LLC - Submittal of 10 CFR 71.95 Report on the 8-120B Cask ML15313A1642015-10-0808 October 2015 Submittal of 10 CFR 71.95 Report on the 8-120B Cask ML15259A3422015-08-24024 August 2015 10 CFR 71.95 Report Evaluation Form; Submitted by Fenok, Erwin Resin Solutions, North Anna Power Stations, Et Al DCL-15-102, 10 CFR 71.95 Report Regarding Energy Solutions' Model 8-120B Shipping Cask2015-08-24024 August 2015 10 CFR 71.95 Report Regarding Energy Solutions' Model 8-120B Shipping Cask NL-15-1461, Submittal of 10 CFR 71.95 Report on Potential Issues Involving Radwaste Cask 8-120B2015-08-21021 August 2015 Submittal of 10 CFR 71.95 Report on Potential Issues Involving Radwaste Cask 8-120B PLA-7374, Submittal of 10 CFR71.95 Report Regarding Energy Solutions 8-120B Cask Certificate of Compliance 91682015-08-20020 August 2015 Submittal of 10 CFR71.95 Report Regarding Energy Solutions 8-120B Cask Certificate of Compliance 9168 NRC-15-0085, Submittal of 10 CFR 71.95 Report on the 8-120B Shipping Cask2015-08-19019 August 2015 Submittal of 10 CFR 71.95 Report on the 8-120B Shipping Cask ZS-2015-0131, Zionsolutions, LLC - Submittal of10 CFR 71.95 Report on the 8-120B Cask2015-08-18018 August 2015 Zionsolutions, LLC - Submittal of10 CFR 71.95 Report on the 8-120B Cask ML15246A1452015-08-11011 August 2015 Submittal of 10 CFR 71.95 Report on the 8-120B Cask ML15097A4242015-04-27027 April 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Reevaluations Relating to Recommendation 2.1 of the NTTF Review ML15106A3102015-04-17017 April 2015 April 22, 2015, Meeting with Southern Nuclear Company, Draft Minimum Shift Staffing Analysis ML14335A1372015-03-25025 March 2015 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-13-109 (Severe Accident Capable Hardened Vents) NL-14-1989, Expedited Seismic Evaluation Process Report - Fukushima Near-Term Task Force Recommendation 2.12014-12-30030 December 2014 Expedited Seismic Evaluation Process Report - Fukushima Near-Term Task Force Recommendation 2.1 NL-14-1245, 10 CFR 26.719(c) Report: False Negative Results for a Blind Performance Test Sample2014-08-22022 August 2014 10 CFR 26.719(c) Report: False Negative Results for a Blind Performance Test Sample ZS-2014-0271, Zionsolutions' 10 CFR 71.95 Report of Non-Compliance with Certificate of Compliance No. 9168, Revision No. 20 - Cask 8-120B2014-08-18018 August 2014 Zionsolutions' 10 CFR 71.95 Report of Non-Compliance with Certificate of Compliance No. 9168, Revision No. 20 - Cask 8-120B ML14155A4052014-06-30030 June 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident (TAC MF0234-35) ML14155A3612014-06-0606 June 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident NL-14-0326, Units 1 and 2, Recommendation 2.1 Flood Hazard Reevaluation Report, Requested by NRC Letter Dated March 12, 20122014-03-0606 March 2014 Units 1 and 2, Recommendation 2.1 Flood Hazard Reevaluation Report, Requested by NRC Letter Dated March 12, 2012 NL-13-133, 10 CFR 71.95 Report on Failure to Observe Certificate of Compliance Conditions for Radwaste Model 8-120B Cask Vent Port Leak Test Hold Time2013-10-0202 October 2013 10 CFR 71.95 Report on Failure to Observe Certificate of Compliance Conditions for Radwaste Model 8-120B Cask Vent Port Leak Test Hold Time DCL-13-094, and Humboldt Bay Power Plant, 10 CFR 71.95 Reports Regarding Energysolutions' Model 8-120B Shipping Cask2013-09-30030 September 2013 and Humboldt Bay Power Plant, 10 CFR 71.95 Reports Regarding Energysolutions' Model 8-120B Shipping Cask L-2013-258, 10 CFR 71.95 - Cask 8-120B - 60 Day Report2013-09-16016 September 2013 10 CFR 71.95 - Cask 8-120B - 60 Day Report NRC-13-0052, CFR 71.95 Report - Failure to Observe Certificate of Compliance Conditions for the 8-120B Vent Port Leak Test Hold Time2013-09-0909 September 2013 CFR 71.95 Report - Failure to Observe Certificate of Compliance Conditions for the 8-120B Vent Port Leak Test Hold Time NL-13-1898, 10 CFR 71.95 Report on Potential Issues Involving Radwaste Cask 8-120B2013-08-30030 August 2013 10 CFR 71.95 Report on Potential Issues Involving Radwaste Cask 8-120B ML13273A6912013-08-20020 August 2013 Redacted - Letter from R. Dale Roberts 10 CFR 71.95 Report on the 8-120B Cask ML13247A0362013-08-20020 August 2013 Letter from R. Dale Roberts 10 CFR 71.95 Report on the 8-120B Cask ML13193A3662013-08-0707 August 2013 Request for Concurrence on the Effects of the Edwin I. Hatch Nuclear Plant, Units 1 and 2 on the Federally-Listed Endangered Species Altamaha Spinymussel NL-13-0172, Southern Nuclear Operating Company'S Overall Integrated Plan in Response to 3/12/2012 Commission Order Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation (EA-12-051)2013-02-27027 February 2013 Southern Nuclear Operating Company'S Overall Integrated Plan in Response to 3/12/2012 Commission Order Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation (EA-12-051) NL-13-0214, Southern Nuclear Operating Company'S Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events..2013-02-27027 February 2013 Southern Nuclear Operating Company'S Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events.. ML12356A4102012-11-26026 November 2012 SNCH082-RPT-02, Ver. 1.0, Edwin I. Hatch, Unit 2 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Part 9 of 11 ML12356A4092012-11-26026 November 2012 SNCH082-RPT-02, Ver. 1.0, Edwin I. Hatch, Unit 2 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Part 11 of 11 ML12356A4082012-11-26026 November 2012 SNCH082-RPT-02, Ver. 1.0, Edwin I. Hatch, Unit 2 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Part 10 of 11 ML12355A6662012-11-26026 November 2012 SNCH082-RPT-02, Ver. 1.0, Edwin I. Hatch, Unit 2 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Part 7 of 11 NL-12-2269, SNCH082-RPT-02, Ver. 1.0, Edwin I. Hatch, Unit 2, Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Part 6 of 112012-11-26026 November 2012 SNCH082-RPT-02, Ver. 1.0, Edwin I. Hatch, Unit 2, Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Part 6 of 11 ML12355A6622012-11-26026 November 2012 SNCH082-RPT-02, Ver. 1.0, Edwin I. Hatch, Unit 2 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Part 8 of 11 ML12355A6372012-11-26026 November 2012 SNCH082-RPT-02, Ver. 1.0, Edwin I. Hatch Unit 2 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Part 1 of 11 2024-09-03
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Text
Charles R. Pierce Southern Nuclear Regulatory Affai rs Director Operating Company. Inc.
40 Inverne ss Center Parkway Pos t Offi ce Box 1295 Bi rm ingham. Alabama 35201 Tel 205.992.7872 Fax 205.992.7601 SOUTH RN'\
COMPANY August 30, 2013 Docket Nos.: 50-321 NL-13-1898 50-366 Mr. Mark Lombard, Director Division of Spent Fuel Storage and Transportation Office of Nuclear Material Safety and Safeguards U. S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, D. C. 20555-0001 Edwin I. Hatch Nuclear Plant 10 CFR 71.95 Report on Potential Issues Involving Radwaste Cask 8-120B
Dear Mr. Lombard:
Southern Nuclear Operating Company (SI\lC) hereby submits this report pursuant to 10 CFR 71 .95(a)(3) regarding potential instances in which the conditions of approval in Certificate of Compliance (CoC) #9168 for the EnergySolutions model 8-120B cask may not have been observed in making shipments from Edwin I.
Hatch Nuclear Plant (Hatch). This report is based on our discovery of the potential condition on July 2, 2013, when EnergySolutions (the certificate holder) notified SNC of this potential condition. The potential condition involves a discrepancy in the vent port seal air pressure drop test hold time between EnergySolutions test procedure TR-TP-002 and the Safety Analysis Report (SAR) for the 8-120B cask (20 minute hold time per the test procedure, versus 60 minutes required by the SAR supporting the CoC).
The enclosed notification report from EnergySolutions provides the information related to the condition , as required by 10 CFR 71.95(a)(3), and is applicable to the use of the 8-120B cask at Hatch. Due to the approximately 12-year time frame over which the discrepancy between the procedure and the SAR has existed, SNC cannot definitively state that shipments have not occurred in which a previous cask user may have opened and subsequently incorrectly tested the subject vent port seal on a cask that was later used at Hatch. Air pressure drop leak tests of the vent port seals were performed by SNC, but used the incorrect 20 minute hold time criterion.
U. S. Nuclear Regulatory Commission I\lL-13-1898 Page 2 No future shipments are planned by SNC using the current 8-120B lid configuration. When the new cask lids are deployed on September 1, 2013, new procedures will be used consistent with the test requirements for those lids.
This letter contains no NRC commitments. If you have any questions, please contact Ken McElroy at (205) 992-7369.
Respectfully submitted, C.R. Pierce Regulatory Affairs Director CRP/DWD/lac
Enclosure:
10 CFR 71.95 Report on 8-120B Cask to NRC by EnergySolutions cc: Southern Nuclear Operating Company Mr. S. E. Kuczynski, Chairman, President & CEO Mr. D. G. Bost, Executive Vice President & Chief Nuclear Officer Mr. D. R. Madison, Vice President - Hatch Mr. B. L. Ivey, Vice President - Regulatory Affairs Mr. B. J. Adams, Vice President - Fleet Operations Mr. G. L. Johnson, Regulatory Affairs Manager - Hatch Mr. S. B. Tipps, Licensing Supervisor - Hatch RTYPE: CHA02.004 U. S. Nuclear Regulatorv Commission Mr. V. M. McCree, Regional Administrator Mr. R. E. Martin, NRR Senior Project Manager - Hatch Mr. E. D. Morris, Senior Resident Inspector - Hatch
Edwin I. Hatch Nuclear Plant 10 CFR 71.95 Report on Potential Issues Involving Radwaste Cask 8-120B Enclosure 10 CFR 71.95 Report on 8-1208 Cask to NRC by EnergySolutions
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~====~~== ENERGYSOLVTIONS==============
August 14,2013 CD13-0232 Mark Lombard, Director Division of Spent Fuel Storage and Transportation Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Washington DC 20555-0001 ATTN: Document Control Desk SUbject: 10 CFR 71.95 Report on the 8-120B Cask
Dear Mr. Lombard:
EnergySolutions hereby submits the attached report providing the infonnation required by 10 CFR 71.95(a)(3) for instances in which the conditions of approval in the Certificate of Compliance for the 8-120B Cask (Certificate of Compliance #9168) may not have been observed in making certain shipments. The circumstances described in this report are applicable to all licensed users of the cask.
If you have any questions regarding this submittal, please contact me at 801-649-2109.
In4fo~
Daniel B. Shrum Senior Vice President, Regulatory Affairs EnergySolutions
Attachment:
Failure to Observe Certificate of Compliance Conditions for the 8-120B Vent Port Leak Test Hold Time cc: Michele Sampson, Chief Thennal and Containment Branch Pierre M. Saverot Licensing Branch 423 West 300 South, Suite 200* Sail Lake City. UT 84101 WHW.energysolulions.com
.y ...
EN ERGVSOLUTIONS Failure to Observe Certificate of Compliance Conditions for the 8-120B Vent Port Leak Test Hold Time August 14, 2013
- 1) Abstract This report provides the infonnation required by 10 CFR 71 .95(a)(3) for instances in which the conditions of approval in the Certificate of Compliance for the 8-120B Cask (Certificate of Compliance #9168) may not have been observed in making certain shipments. The circumstances described in this report are applicable to all licensed users of the cask.
EnergySolutions' air pressure drop test procedure TR-TP-002 describes a 20-minute hold time for the pre-shipment leak test of the cask vent port. The 8-120B Safety Analysis Report (SAR), however, specifies a hold time of 60 minutes for the leak test of the vent port; therefore the conditions of approval in the Certificate of Compliance may not necessarily have been observed in making shipments. TR-TP-002 is the basis for leak: tests on all EnergySolutions shipments, as well as the suggested procedure content for most shipments by our authorized users. I The 8-120B CoC requires the package to be prepared for shipment and operated in accordance with Chapter 7 of the SAR, and tested and maintained in accordance with Chapter 8 of the SAR. TR-TP-002 captures the applicable SAR requirements and provides further detail for the development of a shipper's operating procedure. Recently, an 8-] 20B cask user identified the hold time discrepancy between TR-TP-002 and the SAR (i.e., 20 versus 60 minutes). Based on a review of past revisions of CoCs, SARs, and cask handling procedures, it appears that this discrepancy has existed for approximately 12 years, spanning approximately 88 cask users and approximately 1,400 shipments. .
Upon notification and after confinnation of the discrepancy, EnergySolutions revised TR-TP-002 to incorporate the SAR required 60-minute vent port leak test. This change to TR-TP-002 was communicated to all EnergySolutions registered cask users on June 13, 2013. The SAR requires pre-shipment leak testing of the vent port onl y when the port has been opened since the preceding vent port leak test. EnergySolutions issued a notice to registered cask users on July 2,2013 to clarify this issue. Operation of a package vent port is infrequent. However some vent ports may have been opened during the past 12 years; and therefore the pre-shipment leak testing would have been required.
The licensing basis for the pre-shipment leak tests for all three of the 8-120B lid containment seals is a pressure drop calculation for the largest ofthe three seals (the primary lid seal).
The required hold time is therefore conservative for the two seals with smaller test volumes.
Because of the small size of the vent port seal test volume, EnergySolutions has determined that the 20-minute hold time meets the same criterion by which the 60-minute hold time was derived for the larger primary lid seal. In fact, in the case of the vent port leak test, the 20 minute hold time provides substantial margin for detecting any leakage from the vent port. It therefore follows that there is no safety significance associated with the condition.
) Since registered users of the 8-120B package are licensees, these licensees would normally prepare and issue an approved procedure to control their pre-shipment activities.
~ :
ENERGYSOLUTIONS Furthermore, there is no continuing safety concern as new lids are required to be used after August 31, 2013 with different testing procedures.
Due to the long timeframe over which this condition has existed, the large number of 8-120B cask users, the many shipments that have occurred, the difficulty of determining which if any shipments may have been out of compliance, and the finding of no significant safety impact, EnergySolutions hereby submits this notification to summarize the issue as it applies to all 8-120B users. Because of the imminent rollout of new Jids and related test procedures, no further corrective actions by certificate users are necessary to address this leak test procedure.
- 2) Narrative Description of the Event a) Status of Components All 8-120B components are operating normally.
b) Dates of Occurrences February 2001 to present.
c) Cause of Error Discrepancy between EnergySolutions air pressure drop test procedure TR-TP-002 and Chapter 8 of the 8-120B SAR.
d) Failure Mode, Mechanism, and Effects Not applicable; no 8-120B packaging components have failed.
e) Systems or Secondary Functions Affected Not applicable.
f) Method of Discovery of the Error The condi tion was identi fied by an 8-120B cask user.
- 3) Assessment of Safety Consequences There is no safety consequence of performing the pre-shipment leak test of the 8-120B cask vent port using a 20-minute hold time versus the 60-minute hold time that is required by the 8-l20B CoCo The required hold time varies in proportion to the test volume if the test pressure and acceptance criterion remain unchanged. Larger test volumes require longer hold times. The test volume includes the free volume of the space to be tested and the volume of the test manifold. For the original subject 8-120B lids, Section 4.4 of the July 2012 SAR Addendum shows the calculation basis for a 60-minute hold time. Only one calculation was presented for the large primary lid containment seal. Since the other seals have smaller test volumes, a 60-minute hold time was conservatively specified for all seals, including the vent port.
,.,~ _..
.ENERG)SOLUTIONS The SAR test volume for the primary containment seal was] 03.2 ce. For the pre-shipment vent port leak test, there is no safety impact from a 20-minute hold time provided that the test volume is less than or equal to the 20/60 times the primary containment seal test chamber volume, or (20/60)* 103.2 = 34.4 cc. The vent port test volume is equal to the combined volume of the test manifold (10 cc) plus a very small residual volume inside the vent port, which is less than 34.4 cc. Therefore, pre-shipment leak tests of the vent port perfonned using a 20-minute hold time are adequate to demonstrate compliance with maximum leak rate acceptance criteria, and there is no safety consequence from testing vent ports for 20 minutes instead of 60 minutes.
- 4) Planned Corrective Actions As noted above, upon notification and after confinnation of the discrepancy, EnergySolutions revised TR-TP-002 to incorporate the SAR required 60-minute vent port leak test and notified registered cask users of the change.
Beginning September 1,20] 3, the 8-120B fleet will ship with a new lid design, authorized in the latest revision of the CoC? Thereafter, the 8-120B cask may no longer be used with the old seals that were authorized in Revision No. ] 7 of the 8-120B CoCo Shipments with the new lids will be required to use the seals authorized in Revision 19 of the Coc. The EnergySolutions air pressure drop test procedure TR-TP-002 is being revised and reissued based on the requirements of Revision 19 of the 8-120B Coc. These revisions are reviewed and approved by the EnergySolutions Cask Licensing Manager to assure that they are compliant with the requirements of the Coc.
EnergySolutions also has initiated a 1ifecycle procedure for managing Type B casks to assure that CoC requirements flow through the design, fabrication, and operational phases. This is a new procedure that also would identify existing inconsistencies and prevent future inconsistencies between the SAR and operating procedures. The procedure will be effective August 19, 2013.
The error in incorporating the revised 60-minute vent port leak rate criteria into TR-TP-002 raises a question as to whether there are other similar errors involving the flow-down of requirements into operating procedures. Accordingly, EnergySolutions plans to conduct a review of the 8-120B and other EnergySolutions Type B packagings to verify that coc and SAR requirements have been accurately translated into the prescribed operating procedures.
If any such discrepancies are found, EnergySolutions will expand the scope of these reviews as necessary.
- 5) Previous Similar Events Involving the 8-120B No previous similar events have been identified.
2 No shipments have been made using the new lids to date.
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EN ERGYSOLUIIONS
- 6) Contact for Additional Information Dan Shrum EnergySolutions Senior Vice President, Regulatory Affairs (801) 649-2109
- 7) Extent of Exposure of Individuals to Radiation or Radioactive Materials None.
Comment and Impact Form NMP-AP-001-F04 SNC Version 2.1 I Unit S Page 1 of 1 I
Note Refer to NMP-AP-001 Attachment 4 when completing this form.
I Document
Title:
Notice of Enforcement Discretion I Sheet of Document Number: NMP-AD-040 I Revision:
I Reviewers Site/Organization I Type of Review I Due Date Hatch / LicensinQ I Initial L Item Page Numberl Number Section Number Comments Response or Resolution 1 See attached email Other Procedures I NMPs I Instructions I Guidelines Impacted by the change Document Number Document Title Comment I Reason None Change Management: Describe proposed change management needed to support the implementation of the NMP.
lIE provided, review and evaluate the proposed change management plan for effectiveness. By determining whether additional I elements are needed or whether chanQes are needed to the sequence of the elements.
None Training - Describe required training needed to support the implementation of the NMP. Include how and/or if training is to be documented and if required prior to making the NMP effective. Determine if any changes are needed to training material such as JPRs or JPMs. (Needed Training is to be tracked using the CAP program.)
I Reviewed By: Liz Williford I I "Print Name I Signature Date Comment Resolution:
Writer: Liz Williford I "Print Name I Signature Date
- Electronic Signature is located in DMS "Attributes" then "Acknowledgments".
Pnnted August 30, 2013 at 13.23