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Category:Letter type:NL
MONTHYEARNL-24-0320, License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3,.2024-09-27027 September 2024 License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3,. NL-24-0349, Units 1 and 2 - 10 CFR 26.719(c)(1) 30-Day Report Blind Performance Test Results Inconsistent with Sample Provided2024-09-20020 September 2024 Units 1 and 2 - 10 CFR 26.719(c)(1) 30-Day Report Blind Performance Test Results Inconsistent with Sample Provided NL-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-24-0341, Response to Request for Additional Information Related to the Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency2024-09-10010 September 2024 Response to Request for Additional Information Related to the Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency 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-24-0259, License Amendment Request to Revise Technical Specification 3.4.14, Reactor Coolant System Pressure Isolation Valve Leakage, Surveillance Requirement 3.4.14.3 Acceptance Criteria and Miscellaneous Obsolete Changes2024-09-0404 September 2024 License Amendment Request to Revise Technical Specification 3.4.14, Reactor Coolant System Pressure Isolation Valve Leakage, Surveillance Requirement 3.4.14.3 Acceptance Criteria and Miscellaneous Obsolete Changes NL-24-0340, Unit 1 - Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 1 R322024-09-0404 September 2024 Unit 1 - Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 1 R32 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-24-0321, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Supplemental Information2024-08-16016 August 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Supplemental Information NL-24-0299, Exemption Request: Final Safety Analysis Report Update Schedule, Response to Request for Additional Information2024-08-14014 August 2024 Exemption Request: Final Safety Analysis Report Update Schedule, 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-24-0126, – Units 3 and 4, License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Action a and SR 3.7.6.62024-07-25025 July 2024 – Units 3 and 4, License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Action a and SR 3.7.6.6 NL-24-0282, License Amendment Request and Exemption Request: Remove Tier 1 and Tier 2* Requirements2024-07-25025 July 2024 License Amendment Request and Exemption Request: Remove Tier 1 and Tier 2* Requirements NL-24-0286, Emergency Request to Revise Technical Specification 3.7.9 for a One-Time Change to Support a Unit 1 Nuclear Service Cooling Water Transfer Pump Repair2024-07-20020 July 2024 Emergency Request to Revise Technical Specification 3.7.9 for a One-Time Change to Support a Unit 1 Nuclear Service Cooling Water Transfer Pump Repair 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-24-0281, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions2024-07-18018 July 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions 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-24-0240, 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-24-0237, 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-24-0227, Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2024-07-0303 July 2024 Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) NL-24-0234, Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown2024-06-28028 June 2024 Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown NL-24-0230, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite – Update to TSTF-3602024-06-28028 June 2024 License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite – Update to TSTF-360 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-24-0087, License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Air Storage Tanks2024-06-21021 June 2024 License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Air Storage Tanks NL-24-0235, Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel2024-06-19019 June 2024 Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel NL-24-0201, Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2024-06-18018 June 2024 Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) NL-24-0243, Registration of Spent Fuel Cask Use2024-06-18018 June 2024 Registration of Spent Fuel Cask Use 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-24-0221, Pressurizer Safety Valve Lift Pressure Outside of Technical Specifications Limits Due to Setpoint Drift2024-06-17017 June 2024 Pressurizer Safety Valve Lift Pressure Outside of Technical Specifications Limits Due to Setpoint Drift NL-24-0238, RIPE License Amendment Request to Change Containment Air Temperature Actions, Supplemental Information2024-06-14014 June 2024 RIPE License Amendment Request to Change Containment Air Temperature Actions, Supplemental Information NL-24-0229, Notice of Intent to Pursue Subsequent License Renewal2024-06-0707 June 2024 Notice of Intent to Pursue Subsequent License Renewal 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-24-0194, Revised Request for Relief and Alternative Requirements for Squib Valves First Test Interval (V34-IST-ALT-03-R1)2024-05-0707 May 2024 Revised Request for Relief and Alternative Requirements for Squib Valves First Test Interval (V34-IST-ALT-03-R1) 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-24-0188, Cycle 33 Core Operating Limits Report2024-05-0101 May 2024 Cycle 33 Core Operating Limits Report NL-24-0170, Responses to Second Round NRC Request for Additional Information for Refueling Outage 1 R24 Steam Generator Tube Inspection Report2024-04-25025 April 2024 Responses to Second Round NRC Request for Additional Information for Refueling Outage 1 R24 Steam Generator Tube Inspection Report 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-24-0137, RIPE License Amendment Request to Change Containment Air Temperature Actions2024-04-19019 April 2024 RIPE License Amendment Request to Change Containment Air Temperature Actions NL-24-0154, Preservice Inspection Progam Owners Activity Report2024-04-16016 April 2024 Preservice Inspection Progam Owners Activity Report NL-24-0123, for Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel2024-04-15015 April 2024 for Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel NL-24-0134, Renewed National Pollutant Discharge Elimination System (NPDES) Permit2024-04-12012 April 2024 Renewed National Pollutant Discharge Elimination System (NPDES) Permit 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) 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 NL-24-0238, RIPE License Amendment Request to Change Containment Air Temperature Actions, Supplemental Information2024-06-14014 June 2024 RIPE License Amendment Request to Change Containment Air Temperature Actions, Supplemental Information ML24047A2092024-02-22022 February 2024 Calendar Year 2023 Baseline Inspection Completion ML23325A2022024-01-16016 January 2024 CFR Part 52 Construction Lessons-Learned Report NL-23-0926, Correction of Technical Specification Typographical Error2024-01-12012 January 2024 Correction of Technical Specification Typographical Error ML24004A2192024-01-0808 January 2024 Construction Reactor Oversight Process Performance Metric Report for Calendar Year 2023 ML24005A1142024-01-0505 January 2024 Recommendation for 2023-301 Cr/Sim 3 (Emergency Depress the Reactor Using Main Steam Line Drains) ND-23-0025, Compliance with Order EA-12-0492023-08-21021 August 2023 Compliance with Order EA-12-049 ML22348A0932023-07-28028 July 2023 Finding That the Acceptance Criteria in the Combined License Are Met ML22348A0882023-07-25025 July 2023 VEGP Unit 4 - 103g - Basis Document ML23184A0472023-07-0303 July 2023 Dashboard Report 7-3-2023 ML23156A1882023-06-0505 June 2023 Construction Reactor Oversight Process Resources Report June 5, 2023 ML23121A0392023-05-0101 May 2023 Dashboard Report 5-1-2023 ML23003A0412023-01-0303 January 2023 Construction Reactor Oversight Process Resources Report January 3, 2023 ND-22-0817, Enclosures 1 and 2: Proposed Alternative Inspection Requirements for Steam Generator Nozzle to Reactor Coolant Pump Casing Welds and Alternative for Use of Code Case 648-2 for Inservice Inspection2022-11-0404 November 2022 Enclosures 1 and 2: Proposed Alternative Inspection Requirements for Steam Generator Nozzle to Reactor Coolant Pump Casing Welds and Alternative for Use of Code Case 648-2 for Inservice Inspection ND-22-0831, (Vegp), Units 3 and 4, Comments on AP1000 Standard Technical Specifications (STS) Draft NUREG-2194, Revision 12022-10-31031 October 2022 (Vegp), Units 3 and 4, Comments on AP1000 Standard Technical Specifications (STS) Draft NUREG-2194, Revision 1 ML22278A0382022-10-0505 October 2022 Dashboard Report 10-5-2022 ML22215A0962022-08-0303 August 2022 Construction Reactor Oversight Process Resources Report August 3, 2022 ML22214A0072022-08-0101 August 2022 Archives ML20290A2762022-08-0101 August 2022 10CFR52.103(g) Basis Document 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 ML22179A1462022-06-15015 June 2022 Tier 1, Revision 10, Updated Through 04/22/2022 ML22159A1712022-06-0808 June 2022 Construction Reactor Oversight Process Resources Report June 8, 2022 ML22131A0502022-05-11011 May 2022 Construction Reactor Oversight Process Resources Report May 11, 2022 ML22089A0412022-03-30030 March 2022 Construction Reactor Oversight Process Resources Report March 30 2022 ND-22-0003, Report of 10 CFR 50.59 Changes, Tests, and Experiments and 10 CFR 52 Appendix D Departure Report2022-01-0606 January 2022 Report of 10 CFR 50.59 Changes, Tests, and Experiments and 10 CFR 52 Appendix D Departure Report A000412, National Pollutant Discharge Elimination System (NPDES) Permit Renewal Application2021-12-0202 December 2021 National Pollutant Discharge Elimination System (NPDES) Permit Renewal Application ND-21-1003, Request for Exemption: Applicability of 10 CFR 26.3. Scope, Until Initial Fuel Load - Supplement2021-11-12012 November 2021 Request for Exemption: Applicability of 10 CFR 26.3. Scope, Until Initial Fuel Load - Supplement ND-21-0991, Exemption Request: Applicability of 10 CFR 26.3, Scope, Until Initial Fuel Load2021-11-0505 November 2021 Exemption Request: Applicability of 10 CFR 26.3, Scope, Until Initial Fuel Load ML21280A3052021-10-0707 October 2021 Q/2020 Performance Summary ML21280A3042021-10-0707 October 2021 Q 2020 Performance Summary ML21277A0762021-10-0404 October 2021 Vog 4 Dashboard 10-4-2021 ND-21-0848, Enclosure - Unit 4 Operator Candidates Requesting Credit for Unit 3 Written Examination and Operating Test (Revised)2021-10-0101 October 2021 Enclosure - Unit 4 Operator Candidates Requesting Credit for Unit 3 Written Examination and Operating Test (Revised) IR 05000424/20210052021-08-25025 August 2021 Updated Inspection Plan for Vogtle Electric Generating Plant, Units 1 and 2 (Report 05000424/2021005 and 05000425/2021005) ML21214A3182021-08-0202 August 2021 301 Comments ND-21-0603, Electrical Construction and Measuring & Test Equipment Control2021-06-25025 June 2021 Electrical Construction and Measuring & Test Equipment Control ML21179A0972021-06-15015 June 2021 to Tier 1 ML21132A0482021-05-12012 May 2021 Construction Reactor Oversight Process Resources Report May 2021 ND-21-0342, Emergency Response Data System (ERDS) Data Point Library for Vogtie Unit 42021-04-28028 April 2021 Emergency Response Data System (ERDS) Data Point Library for Vogtie Unit 4 ML21118A1162021-04-28028 April 2021 Emergency Response Data System (ERDS) Data Point Library for Vogtle Unit 3 ML21090A2092021-03-31031 March 2021 Construction Reactor Oversight Process Resources Report March 2021 ML21040A1672021-02-0909 February 2021 (Vegp), Units 3 and 4, Revision to Westinghouse Non-Proprietary Technical Description of the Flaw Tolerance Evaluation Conducted on the Subject Weldolet Branch Connections ML20358A1822020-12-31031 December 2020 LTR-SDA-20-096-NP, Revision 1, Flaw Tolerance Evaluation to Assess Lack of Inspection Coverage of AP1000 14 X 4 Stainless Steel Weldolets to Pipe Welds 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 ML20343A0672020-12-0202 December 2020 Dashboard Report 12-2-2020 ML20314A0492020-11-0909 November 2020 Construction Reactor Oversight Process Resources November 2020 ND-20-1220, Report of Changes Incorporated Into Revision 6 to the Security Plan, Training and Qualification Plan, and Safeguards Contingencv Plan2020-10-21021 October 2020 Report of Changes Incorporated Into Revision 6 to the Security Plan, Training and Qualification Plan, and Safeguards Contingencv Plan ML20287A1862020-10-13013 October 2020 Construction Reactor Oversight Process Resources October 2020 ML20303A1782020-09-29029 September 2020 Submittal of Revision 38 to Updated Final Safety Analysis Report NL-20-0713, Request for One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Pandemic2020-09-21021 September 2020 Request for One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Pandemic 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 NL-24-0238, RIPE License Amendment Request to Change Containment Air Temperature Actions, Supplemental Information2024-06-14014 June 2024 RIPE License Amendment Request to Change Containment Air Temperature Actions, Supplemental Information ML24047A2092024-02-22022 February 2024 Calendar Year 2023 Baseline Inspection Completion NL-23-0926, Correction of Technical Specification Typographical Error2024-01-12012 January 2024 Correction of Technical Specification Typographical Error ML24005A1142024-01-0505 January 2024 Recommendation for 2023-301 Cr/Sim 3 (Emergency Depress the Reactor Using Main Steam Line Drains) ML22348A0932023-07-28028 July 2023 Finding That the Acceptance Criteria in the Combined License Are Met ML23184A0472023-07-0303 July 2023 Dashboard Report 7-3-2023 ND-22-0831, (Vegp), Units 3 and 4, Comments on AP1000 Standard Technical Specifications (STS) Draft NUREG-2194, Revision 12022-10-31031 October 2022 (Vegp), Units 3 and 4, Comments on AP1000 Standard Technical Specifications (STS) Draft NUREG-2194, Revision 1 ML22215A0962022-08-0303 August 2022 Construction Reactor Oversight Process Resources Report August 3, 2022 ML22214A0072022-08-0101 August 2022 Archives ML22131A0502022-05-11011 May 2022 Construction Reactor Oversight Process Resources Report May 11, 2022 ND-21-1003, Request for Exemption: Applicability of 10 CFR 26.3. Scope, Until Initial Fuel Load - Supplement2021-11-12012 November 2021 Request for Exemption: Applicability of 10 CFR 26.3. Scope, Until Initial Fuel Load - Supplement ND-21-0991, Exemption Request: Applicability of 10 CFR 26.3, Scope, Until Initial Fuel Load2021-11-0505 November 2021 Exemption Request: Applicability of 10 CFR 26.3, Scope, Until Initial Fuel Load ML21280A3042021-10-0707 October 2021 Q 2020 Performance Summary ML21280A3052021-10-0707 October 2021 Q/2020 Performance Summary IR 05000424/20210052021-08-25025 August 2021 Updated Inspection Plan for Vogtle Electric Generating Plant, Units 1 and 2 (Report 05000424/2021005 and 05000425/2021005) ML21214A3182021-08-0202 August 2021 301 Comments ND-21-0603, Electrical Construction and Measuring & Test Equipment Control2021-06-25025 June 2021 Electrical Construction and Measuring & Test Equipment Control ML20343A0672020-12-0202 December 2020 Dashboard Report 12-2-2020 ML20314A0492020-11-0909 November 2020 Construction Reactor Oversight Process Resources November 2020 ML20287A1862020-10-13013 October 2020 Construction Reactor Oversight Process Resources October 2020 ML20191A3832020-08-14014 August 2020 Transition to Reactor Oversight Process for Vogtle Electric Generating Plant, Units 3 and 4 ND-20-0907, Revision to Proposed Alternative Requirements for Preservice Inspection Acceptance of Volumetric Examinations, in Accordance with 10 CFR 50.551(z)(1),(VEGP 3&4-PSI/ISI-ALT-14R1)2020-07-28028 July 2020 Revision to Proposed Alternative Requirements for Preservice Inspection Acceptance of Volumetric Examinations, in Accordance with 10 CFR 50.551(z)(1),(VEGP 3&4-PSI/ISI-ALT-14R1) NL-20-0034, Inservice Inspection Program Owner'S Activity Report for Outage 1R292020-01-17017 January 2020 Inservice Inspection Program Owner'S Activity Report for Outage 1R29 ML19284B3722019-11-15015 November 2019 Attachment - VEGP U3 Amendment 166 (LAR-19-008) ND-18-1500, CFR 50.46 Thirty Day Report2018-12-18018 December 2018 CFR 50.46 Thirty Day Report ML18152B7852018-10-12012 October 2018 Summary of Nuclear Regulatory Commission Vendor Inspections Affecting Inspections, Tests, Analyses, and Acceptance Criteria ND-18-1047, Enclosure 2 - Redacted COL Operational Programs and Other License Conditions Implementation Schedule2018-08-0808 August 2018 Enclosure 2 - Redacted COL Operational Programs and Other License Conditions Implementation Schedule 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-18-0670, Third 10-Year Interval Inservice Inspection Program ISI Program Update: Notification of Impractical ASME Code Requirements2018-05-24024 May 2018 Third 10-Year Interval Inservice Inspection Program ISI Program Update: Notification of Impractical ASME Code Requirements 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-17-2061, Special Report 2017-002-00, Nonfunctional Radiation Monitor R-60B2017-12-14014 December 2017 Special Report 2017-002-00, Nonfunctional Radiation Monitor R-60B NL-17-1889, NEI 12-06, Appendix H, Revision 4, H.4.5 Path 5: GMRS Greater than 2 X SSE, Mitigating Strategies Assessment (MSA) Report for the New Seismic Hazard Information2017-12-0505 December 2017 NEI 12-06, Appendix H, Revision 4, H.4.5 Path 5: GMRS Greater than 2 X SSE, Mitigating Strategies Assessment (MSA) Report for the New Seismic Hazard Information NL-17-0777, Flooding Focused Evaluation Summary Report2017-06-30030 June 2017 Flooding Focused Evaluation Summary Report 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 NL-17-0218, Fukushima Near-Term Task Force Recommendation 2.1: Seismic Probabilistic Risk Assessment2017-03-27027 March 2017 Fukushima Near-Term Task Force Recommendation 2.1: Seismic Probabilistic Risk Assessment ML16356A0172016-12-16016 December 2016 Information Report for Lead Use Assemblies NL-16-2541, Notification of 10 CFR 26.719(c) 30-Day Report for False Positive Drug Test Results2016-11-29029 November 2016 Notification of 10 CFR 26.719(c) 30-Day Report for False Positive Drug Test Results NL-16-0810, Submittal of Post Accident Monitoring Report2016-06-0909 June 2016 Submittal of Post Accident Monitoring Report NL-16-0683, Special Report No. 2016-002-00, Alternate AC Source Out of Service2016-06-0202 June 2016 Special Report No. 2016-002-00, Alternate AC Source Out of Service NL-16-0751, Special Report 2016-001-00, Nonfunctional Radiation Monitor R-60B and R-60C2016-05-23023 May 2016 Special Report 2016-001-00, Nonfunctional Radiation Monitor R-60B and R-60C 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 ML15253A4102016-03-11011 March 2016 Enclosure 2 Screening Analysis Report NL-15-2276, Submittal of 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20142015-12-23023 December 2015 Submittal of 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2014 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 NL-15-1489, 10 CFR 71.95 Report on Potential Issues Involving Radwaste Cask 8-12082015-08-17017 August 2015 10 CFR 71.95 Report on Potential Issues Involving Radwaste Cask 8-1208 ML15182A1752015-06-26026 June 2015 Completion of Required Action by NRC Order EA-12-051 Reliable Spent Fuel Pool Level Instrumentation 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 2024-09-03
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Southern Nuclear Operating Company, Inc.
Post Office Box 1295 Birmingham, Alabama 35201-1295 Tel 205,992.5000 SOUT¶HERN ZIý*
COMPANY TM September 12, 2008 Energy to Serve Your World" Docket Nos.: 50-321 50-348 50-424 NL-08-1405 50-366 50-364 50-425 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Edwin I. Hatch Nuclear Plant Joseph M. Farley Nuclear Plant Vogtle Electric Generating Plant Report of Unsatisfactory Performance Testingq Ladies and Gentlemen:
Southern Nuclear Operating Company (SNC) operates the Joseph M. Farley Nuclear Plant, the Edwin I. Hatch Nuclear Plant, and the Vogtle Electric Generating Plant. The requirements of 10 CFR Part 26, Appendix A, Paragraph 2.8, include submittal of blind performance test specimens to a Department of Health and Human Services (HHS) certified laboratory for testing. Specimen 54282327 was provided to Kroll Laboratory Specialists (Kroll) located in Gretna, Louisiana on August 12, 2007. Specimen 54282327 was prepared and certified by ElSohly Laboratories, Incorporated (ElSohly) as a blind performance test specimen spiked with amphetamine at limits of detection (LOD).
The requirements of 10 CFR Part 26, Appendix A, Paragraph 2.8(e)(4) requires reporting of unsatisfactory performance testing incidents within 30 days. There were two separate and distinct unsatisfactory performance testing incidents associated with specimen 54282327 summarized as follows:
- 1. Kroll originally performed testing on specimen 54282327 at NRC cutoff levels. The SNC-required cutoffs for this specimen were at LOD. As a result, the blind performance specimen was initially reported out negative.
- 2. ElSohly provided blind performance specimen 54282327 to SNC certified to contain amphetamine only. Based on the test results from Kroll and subsequent verification testing, the specimen was determined to be positive for both amphetamine and methamphetamine.
Kroll performed an investigation of the events that led to the unsatisfactory performance testing incident described in item 1 above. The findings of this investigation are provided in Enclosure 1.
U. S. Nuclear Regulatory Commission NL-08-1405 Page 2 Similarly, ElSohly performed an investigation of the events that led to the unsatisfactory performance testing incident described in item 2 above. The findings of this investigation are provided in Enclosure 2.
In addition to the investigations performed by Kroll and ElSohly, SNC requested an independent review of the incident and the corresponding corrective action by Dr. Larry A. Broussard, Toxicology Consultant. Dr. Broussard's findings are provided in Enclosure 3. In summary, Dr. Broussard's investigation determined corrective actions taken by both Kroll and ElSohly are appropriate and, when fully implemented, will preclude recurrence of similar incidents.
This letter contains no NRC commitments. If you have any questions, please advise.
Sincerely, M. J. Ajluni Manager, Nuclear Licensing MJA/TWS/daj
Enclosures:
- 1. Kroll Laboratories - Investigation of Unsatisfactory Testing Results
- 2. ElSohly Laboratories - Investigation of Unsatisfactory Testing Results
- 3. Dr. Larry A. Broussard - Investigation of Unsatisfactory Testing Results cc: Southern Nuclear Operating Company Mr. J. T. Gasser, Executive Vice President Mr. J. R. Johnson, Vice President - Farley Mr. D. R. Madison, Vice President - Hatch Mr. T. E. Tynan, Vice President - Vogtle Mr. D. H. Jones, Vice President - Engineering RType: CFA04.054; CHA02.004; CVC7000; LC# 14835 U. S. Nuclear Regulatory Commission Mr. L. A. Reyes, Regional Administrator Mr. K. D. Feintuch, NRR Project Manager - Farley Mr. R. E. Martin, NRR Project Manager - HatchL.7 Mr. R. A. Jervey, NRR Project Manager - Vogtle Mr. E. L. Crowe, Senior Resident Inspector - Farley Mr. J. A. Hickey, Senior Resident Inspector - Hatch Mr. G. J. McCoy, Senior Resident Inspector - Vogtle
Edwin I. Hatch Nuclear Plant Joseph M. Farley Nuclear Plant Vogtle Electric Generating Plant Report of Unsatisfactory Performance Testing Enclosure I Kroll Laboratories - Investigation of Unsatisfactory Testing Results
KROLL 1111 Newton Street Gretna, LA 70053 504 361 8989 X237 Fax 504 361 8235 www.kroll.com Memo To: April Nai Brockson Date: 7 September 2008 From: David Green, Ph.D., DABCC, FACB
Subject:
Results of investigation regarding specimen ID 54282327 Specimen ID 54282327 was received on August 12, 2008 and screened positive for amphetamines.
Confirmation testing revealed the presence of amphetamine and methamphetamine. Due to a technical issue the sample was retested essentially producing identical amphetamine and methamphetamine results.
However, the certifying scientist committed an administrative error by comparing the results to the standard FFD cut-off levels and reported the sample as Negative on August 14, 2008.
On August 15, 2008 April Brockson contacted Kroll client services to letme know this sample was a double blind and was reported in error. Upon review of the data it was noted that the sample though below the standard cut-off levels, contained significant amounts of both amphetamine and methamphetamine. The report was corrected and both the MRO and April Brockson were notified.
On August 18 we were notified that the sample should only contain amphetamine, further April Brockson was able to provide additional material for our investigation. The sample was retested and again revealed the presence of both amphetamine and methamphetamine. A small portion of the sample was submitted to an independent SAMHSA certified laboratory which corroborated the reported results. The remainder of the sample was forwarded to Dr. ElSohly's laboratory as directedby April Brockson.
The Kroll certifying scientist was counselled to carefully compare the GCMS result to the client requested panel and not to assume the standard FFD cut-off to be correct. Further, Kroll intends to launch our new reporting system prior to 2009 which will automatically perform the result value to cut-off level comparison which will avoid future errors.
Edwin I. Hatch Nuclear Plant Joseph M. Farley Nuclear Plant Vogtle Electric Generating Plant Report of Unsatisfactory Performance Testing Enclosure 2 ElSohly Laboratories - Investigation of Unsatisfactory Testing Results
ElSohly Laboratories, Incorporated 5 Industrial Park Drive e I Oxford, MS 38655 TEL 662-236-2609 FAX 662-234-0253 www.elsohly.com AMENDED REPORT Report on the investigation of the composition of blind QC specimen with ID SSN 574-80-4291 (Gabriel T. Irvin)
The above referenced specimen was submitted to the Southern Nuclear as being part of amphetamines batch A-2481 which contains amphetamine only at approximately 450 ng/mL.
The specimen was submitted to Kroll and Kroll reported both amphetamine and methamphetamine at approximately 300 and 425 ng/mL respectively.
At the request of Southern Nuclear Kroll repeated the analysis and got the same result.
The split was later sent to Kroll and upon analysis Kroll again found both amphetamine and methamphetamine. A portion of the split was submitted by Kroll to another laboratory where again it was found to contain amphetamine and methamphetamine. A second portion of the split was submitted to our laboratory for analysis.
Here is what we did at ELI:
- 1. We checked the records for batch A-2481 and the raw analytical data and verified that it actually contained amphetamine only.
- 2. We reanalyzed the reference sample we have in house from A-2481 and found it to contain amphetamine only, at the level of initial certification.
- 3. We requested an aliquot from the sample in question to analyze in-house.
- 4. Kroll sent an aliquot form the split sample to our laboratory for analysis.
- 5. In the meantime we started investigating any possibility of the sample in question being submitted from a different amphetamines batch than A-2481.
- 6. We found out that we do have a newer batch (A-3219) that is prepared as an LOD batch which contains both amphetamine and methamphetamine at levels comparable to those reported by Kroll for the specimen in question.
- 7. We decided to analyze a sample from A-3219 in parallel with the aliquot received from Kroll for SVT values to see if the matrix matches for these two samples and also against the reference sample from A-2481.
- 8. The results were as follows:
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The data shows that the specimen in question actually matches very well with A-3219 and quite different from A-2481.
- 9. We then investigated how was it possible for a specimen to be labeled as part of A-2481 when in actuality it was from A-3219. We found out that, the two amphetamine batches were stored side by side in the refrigerator (in bulk) and therefore there is a possibility that at the time of preparing the specimen in question for shipping, the laboratory technician pulled A-3219 and aliquoted from it instead of A-2481.
Although, we have no real evidence that this is what happened, it appears that, that possibility is certainly conceivable.
This is the first occurrence of bottling from the wrong container ever happening in our laboratory.
1O.We have therefore implemented the following procedure to be followed by the laboratory personnel in filling blind QC orders.
- 1. No two batches of the same drug class be stored in the same refrigerator housing bulk materials for bottling.
- 2. Implement a second check of the batch number on the container used in preparing positive specimens against the paperwork by another laboratory person.
- 3. Ascertain that the data base has no records for additional specimens when a particular batch is actually exhausted.
With these measures in place we believe that similar incidences would not occur in the future.
Submitted by:
Ma oud A. EISt*Iy, Ph.D., BCFE, BCFM President Laboratory Director September 5, 2008 E2 - 2
Edwin I. Hatch Nuclear Plant Joseph M. Farley Nuclear Plant Vogtle Electric Generating Plant Report of Unsatisfactory Performance Testing Enclosure 3 Dr. Larry A. Broussard - Investigation of Unsatisfactory Testing Results
Larry A. Broussard, Ph.D.
Toxicology Consultant 8 Melrose Dr. Destrehan, LA 70047 September 10, 2008 Mr. Paul Bizjak and Ms. April Brockson Medical Services Coordinator Southern Nuclear Operating Company Safety & Health Department P.O. Box 1295 Birmingham, AL 35201 Re: Investigation of drug testing incident involving Specimen 9522639 (Donor ID C080453) at Kroll Laboratory.
Dear Mr. Bizjak and Ms. Brockson:
Upon your request I have investigated the following incident concerning a specimen submitted to Kroll Laboratory:
Reporting of Positive results for amphetamine (314 ng/mL) and methamphietamine (424 ng/mL) on a blind LOD sample (Batch 2481;' -supplied by ElSohly Laboratories with a certificate of analysis verifying that the sample-containled amphetamine at a concentration of 43.9 ng/mL and no methamphetamine.
My preliminary and onsite investigation at Kroll included the following actions:
- 1. Review of email correspondence concerning the incident and subsequent telephone conversations with Ms. Brockson during which it was decided that I would investigate the incident as soon as possible and in the meantime the LOD sample program would be suspended and other samples would be sent to LabCorp instead of Kroll.
- 2. Site visit of Kroll Laboratory Specialists on August 26, 2008 (described below) and completion of this report.
Discussion of site visit to laboratory on August 26, 2008:
I visited the lab and met with Dr. Green, the laboratory director. During this visit I reviewed the following paperwork:
" SOP procedure for amphetamine/methamphetamine confirmation to verify that the laboratory's method is not one of the methods which have the potential for generating methamphetamine in the presence of large amounts of pseudoephedrine
" SAMHSA PT sample results for amphetamine and methamphetamine for the past 4 cycles to verify that the laboratory has not experienced any problems with amphetamine and/or methamphetamine testing of these specimens (which are known to contain potential interfering compounds)
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" Chain of custody, screening data and electronic reports for previously submitted samples from the same pool (see Table 1 for further information on these specimens)
- All of the data for the testing of the specimen in question
" Data for re-analysis of remainder of sample that was sent to Kroll when there was none of the original sample remaining
" E-mail from Baptist Hospital in Little Rock (a SAMHSA-certified laboratory) reporting results of testing of the aliquot of the sample sent to Kroll when there was none of the original sample remaining
" Proof that remainder of aliquot would be sent to Dr. ElSohly's lab which should arrive by 8/27/08.
Table of Results of Samples tested at Kroll and Baptist (1 sample only)
Sample Date Amphet Methamp Screening Creat pH Reported GCMS GCMS value 53316074 2/6/08 488 818 45.6 7.3 H080835 54087180 3/27/08 452 842 44.7 7.1 V080689 54580267 7/7/08 468 815 41.6 7.4 F080893 54282327 8/14/08 314 424 1225 41.1 6.7 C080453 corrected Remaining aliquot 344 420 1339 41.9 6.8 from corporate C080453 reanalyzed At Kroll Remaining aliquot 8/26/08 293 419 from corporate C080453 reanalyzed At Baptist Comments:
Variance in creatinine values is not sufficient to determine that the samples came from the same or different performance testing pool.
Variance in pH may not be sufficient evidence that sample 54282327 is different from the previous 3 samples.
The most compelling arguments for sample 54282327 being different from the previous 3 samples are the screening and GCMS data but if methamphetamine had been added to this sample it would also explain these results.
Second visit to lab:
After our telephone conversation following my initial visit I revisited the lab the following morning (8/27/08) to review the screening and accessioning data for the sample in question and other samples either having been received or analyzed with the sample in question.
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Dr. ElSohly's investigation:
I discussed the incident both before and after Dr. ElSohly investigated his process of preparing and shipping the blind performance samples. He presented a possible scenario which seems to be the most probable explanation of Kroll receiving a sample containing methamphetamine and amphetamine. His explanation was that the sample received at Kroll matched the composition of a sample prepared in his laboratory and that it was possible that his personnel mislabeled the specimen sent to the corporate office.
Although there is not 100% proof that this occurred it certainly seems to be the most logical explanation.
I have reviewed his final report including the action listed below taken to prevent occurrence of the scenario which seems to have caused this incident:
- 1. No two batches of the same drug class be stored in the same refrigerator housing bulk materials for bottling.
- 2. Implement a second check of the batch number on the container used in preparing positive specimens against the paper work by another laboratory person.
- 3. Ascertain that the data base has no records for additional specimens when a particular batch is actually exhausted Initial Reporting Problem by Kroll:
I investigated the fact that the sample was originally reported as negative with LOD cutoffs listed on the report. This happened as a result of the following set of circumstances:
- The sample originally appeared on a computer generated worklist with the correct LOD cutoff level.
" Due to a technical issue with the batch it had to be rerun.
" Rerun batches at Kroll are hand written and not generated by the computer and the cutoff level must be handwritten on this rerun batch.
- The Certifying Scientist for the failed batch committed an error and wrote the standard cutoff for this specimen.
" The Certifying Scientist who released the rerun batch used the handwritten cutoff of 500 and not the LOD cutoff. This is why it was released as a negative originally.
I have reviewed Dr. Green's report which includes a summary, explanation of the incident (as described above) and the following corrective action taken:
- 1. The Kroll certifying scientist was counseled to carefully compare the GCMS result to the client requested panel and not to assume the standard FFD cut-off to be correct.
- 2. Kroll intends to launch our new reporting system prior to 2009 which will automatically perform the result value to cut-off level comparison which will avoid future errors.
Conclusions During my visits, I reviewed all of the laboratory documentation of this incident including testing data and reports issued. I have summarized some of this documentation in the table on page 1 of this report. I have also reviewed all of the ongoing and final reports from Dr. El Sohly and Dr. Green, ConcerningDr. El Sohly's investigationand corrective action implemented Ifeel that the corrective action is appropriateand will prevent this type of errorfrom happening in the future.
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All representatives and employees of Kroll that I talked to were helpful, candid, and forthcoming with any information I requested. Combined with Dr. ElSohly's investigation and probable explanation it is safe to assume that the testing performed at Kroll on the specimen in question was accurate and that the specimen contained amphetamine and methamphetamine.
Unfortunately although the investigation validates the accuracy of the analytical testing process it reveals the failure of the testing process to detect all possible clerical/administrative errors. The original error of reporting the specimen as negative was due to failure by Certifying Scientists (CS) at 2 steps in the process. The original CS committed the error of recording the incorrect cutoff on the handwritten worklist but the CS who signed the report and released the result electronically should have performed checks to insure that the cutoffs were appropriate. The correct procedure should include cross-checks such as checking the electronic report and CCF to verify that LOD cutoffs were to be applied to this sample. As part of their corrective action the certifying scientist was counseled which is a generally accepted part of any appropriate corrective action plan involving a clerical error.
The most significant part of Kroll's corrective action plan is "to launch the new reporting system prior to 2009 which will automatically perform the result value to cut-off level comparison." In my opinion this corrective action is appropriateand would preventfuture errors of the kind causing this incident. Of course there will be a delay before this system is implemented and the diligence of the testing personnel in following procedure to compare the result to the requested panel will be the primary means of preventing the error until the system is implemented.
To summarize my conclusions I agree that the corrective actions implemented by ElSohly Laboratories, Inc and Kroll are appropriate. I do not have any other suggested recommended action other than to stress that the implementation of the new reporting system by Kroll is the essential element to theirplan and the corrective action will not be complete until the system is implemented. Until that time the current system is the same as that in place when the error occurred. Finally even though this incident revealed problems involving the supplier of the blind performance specimens and the laboratoryperforming the testing it did validate the purpose and value in the blindperformance program-i.e. to detect potential problems in the entire process. It caused all parties involved to critically evaluate theirprocesses and resulted in implementation of plans which will strengthen the drug testingprogram.
I hope that this report sheds further light on this incident and helps you when making decisions about the company's drug-testing program. I look forward to the continuation of our relationship even though we all wish incidents such as this one would never happen. Please feel free to call me if you have any questions about this report.
Sincerely, Larry A. Broussard, Ph.D., DABCC E3 - 4