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Category:Letter type:ND
MONTHYEARND-24-0019, Submittal of Vogtle Electric Generating Plant (Vegp), Unit 4, Combined License (COL) Operational Programs and Other License Conditions Implementation Schedule2024-02-0101 February 2024 Submittal of Vogtle Electric Generating Plant (Vegp), Unit 4, Combined License (COL) Operational Programs and Other License Conditions Implementation Schedule ND-23-0912, Submittal of Vogtle Electric Generating Plant (Vegp), Unit 4, Combined License (COL) Operational Programs and Other License Conditions Implementation Schedule2024-01-0202 January 2024 Submittal of Vogtle Electric Generating Plant (Vegp), Unit 4, Combined License (COL) Operational Programs and Other License Conditions Implementation Schedule ND-23-0881, Submittal of Vogtle Electric Generating Plant (Vegp), Unit 4, Combined License (COL) Operational Programs and Other License Conditions Implementation Schedule2023-12-0404 December 2023 Submittal of Vogtle Electric Generating Plant (Vegp), Unit 4, Combined License (COL) Operational Programs and Other License Conditions Implementation Schedule ND-23-0817, (Vegp), Units 3 and 4 - Report of UFSAR Chapter 14 Changes to the Initial Test Program in Accordance with License Condition 2.D.(7)(a)2023-11-17017 November 2023 (Vegp), Units 3 and 4 - Report of UFSAR Chapter 14 Changes to the Initial Test Program in Accordance with License Condition 2.D.(7)(a) ND-23-0823, Combined License (COL) Operational Programs and Other License Conditions Implementation Schedule2023-11-0303 November 2023 Combined License (COL) Operational Programs and Other License Conditions Implementation Schedule ND-23-0723, (Vegp), Unit 4, Combined License (COL) Operational Programs and Other License Conditions Implementation Schedule2023-10-0404 October 2023 (Vegp), Unit 4, Combined License (COL) Operational Programs and Other License Conditions Implementation Schedule ND-23-0697, (Vegp), Unit 4, Submittal of Combined License (COL) Operational Programs and Other License Conditions Implementation Schedule2023-09-0505 September 2023 (Vegp), Unit 4, Submittal of Combined License (COL) Operational Programs and Other License Conditions Implementation Schedule ND-23-0669, (Vegp), Unit 4, Combined License (COL) Operational Programs and Other License Conditions Implementation Schedule2023-08-0707 August 2023 (Vegp), Unit 4, Combined License (COL) Operational Programs and Other License Conditions Implementation Schedule ND-23-0205, (Vegp), Unit 3 - Combined License (COL) License Condition 2.D.(5)(d) Completion of Power Ascension Tests2023-07-28028 July 2023 (Vegp), Unit 3 - Combined License (COL) License Condition 2.D.(5)(d) Completion of Power Ascension Tests ND-23-0618, Resubmittal of ITAAC Closure Notification on Completion of ITAAC Item 3.3.00.07c.ii.a (Index Number 797)2023-07-20020 July 2023 Resubmittal of ITAAC Closure Notification on Completion of ITAAC Item 3.3.00.07c.ii.a (Index Number 797) ND-23-0609, Notification of Completion of All ITAAC2023-07-20020 July 2023 Notification of Completion of All ITAAC ND-23-0608, ITAAC Closure Notification on Completion of ITAAC 2.1.03.03 (Index Number 72)2023-07-20020 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.1.03.03 (Index Number 72) ND-23-0607, ITAAC Closure Notification on Completion of ITAAC 2.1.02.02a (Index Number 13)2023-07-20020 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.1.02.02a (Index Number 13) ND-22-0796, ITAAC Closure Notification on Completion of ITAAC Item 3.3.00.08 (Index Number 813)2023-07-20020 July 2023 ITAAC Closure Notification on Completion of ITAAC Item 3.3.00.08 (Index Number 813) ND-23-0459, ITAAC Closure Notification on Completion of ITAAC 2.6.01.04d (Index Number 587)2023-07-19019 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.6.01.04d (Index Number 587) ND-23-0162, ITAAC Closure Notification on Completion of ITAAC 2.2.03.05a.i (Index Number 165)2023-07-19019 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.2.03.05a.i (Index Number 165) ND-23-0575, ITAAC Closure Notification on Completion of ITAAC 2.6.01.04e (Index Number 588)2023-07-18018 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.6.01.04e (Index Number 588) ND-23-0439, ITAAC Closure Notification on Completion of ITAAC 2.2.05.07a.i (Index Number 265)2023-07-18018 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.2.05.07a.i (Index Number 265) ND-23-0552, Southern Nuclear Operating Company, Vogtle Electric Generating Plant, Unit 4, ITAAC Closure Notification on Completion of ITAAC Item 2.6.04.02c (Index Number 624)2023-07-18018 July 2023 Southern Nuclear Operating Company, Vogtle Electric Generating Plant, Unit 4, ITAAC Closure Notification on Completion of ITAAC Item 2.6.04.02c (Index Number 624) ND-23-0483, ITAAC Closure Notification on Completion of ITAAC 2.1.01.04 (Index Number 4)2023-07-18018 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.1.01.04 (Index Number 4) ND-23-0586, ITAAC Closure Notice on Completion of ITAAC 2.2.03.02a (Index Number 159)2023-07-17017 July 2023 ITAAC Closure Notice on Completion of ITAAC 2.2.03.02a (Index Number 159) ND-23-0610, ITAAC Closure Notification on Completion of ITAAC Item 2.6.03.04c (Index Number 603)2023-07-17017 July 2023 ITAAC Closure Notification on Completion of ITAAC Item 2.6.03.04c (Index Number 603) ND-23-0573, ITAAC Closure Notification on Completion of 2.4.02.02a (Index Number 497)2023-07-16016 July 2023 ITAAC Closure Notification on Completion of 2.4.02.02a (Index Number 497) ND-23-0406, ITAAC Closure Notification on Completion of ITAAC Item 2.4.02.02b (Index Number 498)2023-07-16016 July 2023 ITAAC Closure Notification on Completion of ITAAC Item 2.4.02.02b (Index Number 498) ND-22-0816, ITAAC Closure Notification of Completion of ITAAC 2.1.02.05a (Index Number 19)2023-07-15015 July 2023 ITAAC Closure Notification of Completion of ITAAC 2.1.02.05a (Index Number 19) ND-23-0603, ITAAC Closure Notification on Completion of ITAAC Item 3.5.00.06 (Index Number 831)2023-07-15015 July 2023 ITAAC Closure Notification on Completion of ITAAC Item 3.5.00.06 (Index Number 831) ND-23-0446, ITAAC Closure Notification on Completion of ITAAC 2.2.04.12a.iii (Index Number 250)2023-07-15015 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.2.04.12a.iii (Index Number 250) ND-23-0594, ITAAC Closure Notification on Completion of ITAAC 2.6.05.02.ii (Index Number 629)2023-07-15015 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.6.05.02.ii (Index Number 629) ND-23-0601, ITAAC Closure Notification on Completion of ITAAC Item 2.7.05.02.i (Index Number 719)2023-07-15015 July 2023 ITAAC Closure Notification on Completion of ITAAC Item 2.7.05.02.i (Index Number 719) ND-23-0606, ITAAC Closure Notification on Completion of ITAAC 2.5.04.02.i (Index Number 557)2023-07-15015 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.5.04.02.i (Index Number 557) ND-23-0476, ITAAC Closure Notification on Completion of ITAAC 2.3.06.02a (Index Number 355)2023-07-15015 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.3.06.02a (Index Number 355) ND-23-0499, ITAAC Closure Notification on Completion of ITAAC 2.7.01.14 (Index Number 700)2023-07-15015 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.7.01.14 (Index Number 700) ND-23-0588, ITAAC Closure Notification on Completion of ITAAC Item 2.1.03.07.i (Index Number 78)2023-07-14014 July 2023 ITAAC Closure Notification on Completion of ITAAC Item 2.1.03.07.i (Index Number 78) ND-23-0121, ITAAC Closure Notification on Completion of ITAAC C.2.6.09.07 (Index Number 667)2023-07-14014 July 2023 ITAAC Closure Notification on Completion of ITAAC C.2.6.09.07 (Index Number 667) ND-23-0122, ITAAC Closure Notification on Completion of ITAAC C.2.6.09.08a (Index Number 668)2023-07-14014 July 2023 ITAAC Closure Notification on Completion of ITAAC C.2.6.09.08a (Index Number 668) ND-23-0597, ITAAC Closure Notification on Completion of ITAAC 2.5.02.06a.ii (Index Number 530)2023-07-14014 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.5.02.06a.ii (Index Number 530) ND-23-0002, ITAAC Closure Notification on Completion of ITAAC 2.2.05.07c (Index Number 270)2023-07-14014 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.2.05.07c (Index Number 270) ND-23-0111, ITAAC Closure Notification on Completion of ITAAC 2.6.09.05c (Index Number 646)2023-07-13013 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.6.09.05c (Index Number 646) ND-22-0980, ITAAC Closure Notification on Completion of ITAAC Item 2.1.03.06.i (Index Number 75)2023-07-13013 July 2023 ITAAC Closure Notification on Completion of ITAAC Item 2.1.03.06.i (Index Number 75) ND-23-0587, ITAAC Closure Notification on Completion of ITAAC 2.6.02.02c (Index Number 595)2023-07-13013 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.6.02.02c (Index Number 595) ND-23-0461, ITAAC Closure Notification on Completion of ITAAC 2.6.09.13a (Index Number 652)2023-07-13013 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.6.09.13a (Index Number 652) ND-23-0543, ITAAC Closure Notification on Completion of ITAAC Item 2.6.04.02a (Index Number 622)2023-07-13013 July 2023 ITAAC Closure Notification on Completion of ITAAC Item 2.6.04.02a (Index Number 622) ND-23-0394, ITAAC Closure Notification on Completion of ITAAC 2.7.02.03a (Index Number 703)2023-07-13013 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.7.02.03a (Index Number 703) ND-23-0592, ITAAC Closure Notification on Completion of 2.7.06.03.i (Index Number 726)2023-07-12012 July 2023 ITAAC Closure Notification on Completion of 2.7.06.03.i (Index Number 726) ND-23-0589, ITAAC Closure Notification on Completion of ITAAC 2.6.03.04a (Index Number 601)2023-07-12012 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.6.03.04a (Index Number 601) ND-23-0581, ITAAC Closure Notification on Completion of ITAAC 2.2.04.02a (Index Number 220)2023-07-12012 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.2.04.02a (Index Number 220) ND-23-0486, ITAAC Closure Notification on Completion of ITAAC 2.2.01.11a.iv (Index Number 117)2023-07-11011 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.2.01.11a.iv (Index Number 117) ND-23-0559, CFR26.719(c)(1) 30-Day Report for a Blind Sample Analysis Error2023-07-11011 July 2023 CFR26.719(c)(1) 30-Day Report for a Blind Sample Analysis Error ND-23-0443, ITAAC Closure Notification on Completion of ITAAC 2.3.10.07a.ii (Index Number 444)2023-07-0808 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.3.10.07a.ii (Index Number 444) ND-23-0183, ITAAC Closure Notification on Completion of ITAAC Item 2.3.11.03b (Index Number 454)2023-07-0808 July 2023 ITAAC Closure Notification on Completion of ITAAC Item 2.3.11.03b (Index Number 454) 2024-02-01
[Table view] Category:Report
MONTHYEARML23325A2022024-01-16016 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 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 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 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) 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 ML21118A1162021-04-28028 April 2021 Emergency Response Data System (ERDS) Data Point Library for Vogtle Unit 3 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 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 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 ML20274A2582020-09-10010 September 2020 Wp on Uswc for AP1000_Revised, Reactor Oversight Process Whitepaper - Modification of the Description of Unplanned Scrams with Complications Performance Indicator to Reflect AP1000 Design 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) ND-20-0561, Submittal of Turbine Maintenance and Inspection Program in Accordance with Updated Final Safety Analysis Report2020-07-10010 July 2020 Submittal of Turbine Maintenance and Inspection Program in Accordance with Updated Final Safety Analysis Report ML20189A4292020-07-0707 July 2020 Construction Reactor Oversight Process Resources July 2020 ML20136A4562020-04-30030 April 2020 Updated Flex Plan Nuclear Regulatory Commission Order EA-12-049 Strategies for Beyond Design Basis External Events NL-19-0832, EPRI Technical Report 3002014590, Technical Bases for Inspection Requirements for PWR Steam Generator Feedwater and Main Steam Nozzle-to-Shell Welds and Nozzle Inside Radius Sections.2019-12-31031 December 2019 EPRI Technical Report 3002014590, Technical Bases for Inspection Requirements for PWR Steam Generator Feedwater and Main Steam Nozzle-to-Shell Welds and Nozzle Inside Radius Sections. ML19284B3722019-11-15015 November 2019 Attachment - VEGP U3 Amendment 166 (LAR-19-008) 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 2024-01-08
[Table view] Category:Miscellaneous
MONTHYEARNL-23-0926, Correction of Technical Specification Typographical Error2024-01-12012 January 2024 Correction of Technical Specification Typographical Error 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 ML21280A3052021-10-0707 October 2021 Q/2020 Performance Summary ML21280A3042021-10-0707 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) 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) 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-18-0670, 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-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-17-0218, 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 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 ML15106A3102015-04-17017 April 2015 April 22, 2015, Meeting with Southern Nuclear Company, Draft Minimum Shift Staffing Analysis ND-14-2009, 4 - 10 CFR 26.719(c) Report: False Negative Results for a Blind Performance Test Sample2014-12-17017 December 2014 4 - 10 CFR 26.719(c) Report: False Negative Results for a Blind Performance Test Sample NL-14-1899, Vogle, Units 1 and 2 - 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20132014-12-0808 December 2014 Vogle, Units 1 and 2 - 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2013 ML14279A3522014-11-0606 November 2014 Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation ML14169A5992014-06-30030 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 ML14049A3542014-02-24024 February 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 ML13162A5342013-06-10010 June 2013 Initial Exam 2013-301 Final SRO Written Exam NL-13-0173, Southern Nuclear Operating Company'S Overall Integrated Plan in Response to March 12,2012 Commission Order Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation (Order EA-12-051)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 Reliable Spent Fuel Pool Instrumentation (Order EA-12-051) NL-12-0324, Special Report 2011-001-02, Inoperable Radiation Monitor 1RE-00062012-02-16016 February 2012 Special Report 2011-001-02, Inoperable Radiation Monitor 1RE-0006 NL-11-0626, Special Report 2011-001-00, Inoperable Radiation Monitor 1RE-0062011-03-29029 March 2011 Special Report 2011-001-00, Inoperable Radiation Monitor 1RE-006 NL-10-1536, Special Report 2010-001-00, Inoperable Radiation Monitor 1RE-0062010-08-18018 August 2010 Special Report 2010-001-00, Inoperable Radiation Monitor 1RE-006 ML1015903342010-06-0808 June 2010 Audit of Steam Generator H Amendment Reference Documents ML1019304172010-05-0606 May 2010 Tritium Database Report ML1012704392010-05-0505 May 2010 Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants NL-09-1449, Submittal of Emergency Response Data System (Eros) Data Point Library Modification2009-09-24024 September 2009 Submittal of Emergency Response Data System (Eros) Data Point Library Modification NL-09-1375, Enclosure 2 and 3 to NL-09-1375 - Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification (TS) Sections 5.5.9 and TS 5.6.102009-08-25025 August 2009 Enclosure 2 and 3 to NL-09-1375 - Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification (TS) Sections 5.5.9 and TS 5.6.10 NL-08-1405, Report of Unsatisfactory Performance Testing2008-09-12012 September 2008 Report of Unsatisfactory Performance Testing NL-08-0343, Response to NRC Request for Additional Information Relating to LTR-CDME-08-11 NP-Attachment2008-03-18018 March 2008 Response to NRC Request for Additional Information Relating to LTR-CDME-08-11 NP-Attachment NL-07-1777, Supplemental Response to NRC Generic Letter 2004-022008-02-28028 February 2008 Supplemental Response to NRC Generic Letter 2004-02 NL-08-0275, Response to 01/28/2008 Request for Additional Information2008-02-27027 February 2008 Response to 01/28/2008 Request for Additional Information ML0732405912007-11-0505 November 2007 Land Management Plan ML0732407392007-11-0505 November 2007 Stratigraphy and Depositional Environments of Sediments from Five Cores from Screven and Burke Counties, Georgia ML0732403812007-11-0505 November 2007 10 CFR 50.75(g) Leak/Spill Decommissioning Record, Figure 1, for 1980s and 1990s, NMP-EN-002, Version 1.0 2024-01-12
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Jeffrey T. Gasser Southern Nuclear Executive Vice President Operating Company, Inc.
Operational Readiness &
Site Integration 7825 River Road Plant Vogtle Units 3&4 Waynesboro, GA 30830 Tel 706.437-6700 SOUTHERN Fax 706-826-5796 COMPANY jtgasser@southernco.com December 17, 2014 Docket Nos.: 05-424 52-025 ND-14-2009 05-425 52-026 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtle Electric Generating Plant (VEGP) Units 1 - 4 10 CFR 26.719(c) Report:
False Negative Results for a Blind Performance Test Sample Ladies and Gentlemen:
In accordance with the requirements of 10 CFR 26.719(c), Southern Nuclear Operating Company hereby submits the enclosed Report.
This letter contains no regulatory commitments . If you have any questions, please contact Michael Yox at 706-826-6459.
Respectfully submitted, 1~.LtJ~
Executive Vice President Operational Readiness & Site Integration JTG/MJY/sdc
Enclosure:
10 CFR 26.719(c) Report
U.S. Nuclear Regulatory Commission ND-14-2009 Page 2 of 3 cc:
Southern Nuclear Operating Company I Georgia Power Company Mr. S. E. Kuczynski (w/o enclosures)
Mr. J. A Miller Mr. D. G. Bost (w/o enclosures)
Mr. B. K. Taber (w/o enclosures)
Mr. B. L. lvey Mr. M. D. Meier Mr. M. D. Rauckhorst (w/o enclosures)
Mr. J. T. Gasser (w/o enclosures)
Mr. D. H. Jones (w/o enclosures)
Mr. J. R. Johnson (w/o enclosures)
Mr. D. R. Madison Mr. D. M. Lloyd Mr. B. H. Whitley Mr. C. R. Pierce Mr. D. L. Fulton Mr. M. J. Yox Mr. J. C. Harrelson Mr. W. A Sparkman Mr. J.P. Redd Mr. G. W. Gunn Document Services RTYPE: VND.LI.LOO File AR.01.02.06 Nuclear Regulatory Commission Mr. V. M. McCree (w/o enclosures)
Mr. M. Delligatti (w/o enclosures)
Mr. L. Burkhart (w/o enclosures)
Mr. D. H. Jaffe Mr. C. Patel Ms. D. L. McGovern Mr. B. M. Bavol Ms. R. Reyes Ms. M. A Sutton Mr. M. E. Ernstes Mr. G. Khouri Mr. L. M. Cain Mr. J. D. Fuller Mr. C. B. Abbott Mr. C. Huffman Ms. S. Temple Oglethorpe Power Corporation Mr. M. W. Price Ms. K. T. Haynes Ms. A Whaley
U.S. Nuclear Regulatory Commission ND-14-2009 Page 3 of 3 Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. S. M. Jackson Dalton Utilities Mr. D. Cope CB&I Mr. J. Simmons (w/o enclosures)
Ms. K. Stoner (w/o enclosures)
Mr. C. A. Castell Westinghouse Electric Company, LLC Mr. T. C. Geer (w/o enclosures)
Mr. S. W. Gray (w/o enclosures)
Mr. L. Woodcock Mr. P. A. Russ Mr. G. F. Couture Mr. M. Y. Shaqqo Mr. B. J. Bedford Mr. M. P. Rubin Ms. S. DiTommaso Other Mr. R. W. Prunty, Bechtel Power Corporation Ms. K. K. Patterson, Tetra Tech NUS, Inc.
Dr. W. R. Jacobs, Jr., Ph.D., GDS Associates, Inc.
Mr. S. Roetger, Georgia Public Service Commission Ms. S. W. Kernizan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. S. Blanton, Balch Bingham Mr. R. Grumbir, APOG
Southern Nuclear Operating Company ND-14-2009 Enclosure Vogtle Electric Generating Plant (VEGP) Units 1 - 4 10 CFR 26.719(c) Report:
False Negative Results for a Blind Performance Test Sample
U.S. Nuclear Regulatory Commission ND-14-2009 Enclosure Vogtle Electric Generating Plant HHS Laboratory Blind Performance Error
==
Introduction:==
10 CFR 26.719(c)(1), "Drug and alcohol testing errors", describes the requirements for reporting Fitness for Duty (FFD) drug testing errors or unsatisfactory performance discovered at any Health and Human Services (HHS) certified laboratory or licensee testing facility. Any identified errors involving false negative test results must be reported to the NRC within 30 days of completing an investigation in accordance with 10 CFR 26.719(c). Southern Nuclear Operating Company (SNC) performs on-site analysis of urine specimens at each of its nuclear plant sites.
Laboratory Corporation of America (LabCorp) is utilized for analysis of urine specimens collected at SNC Corporate headquarters and to perform confirmation testing for initial positive drug tests when analyzed on-site by SNC FFD personnel.
On September 28, 2014, the Medical Services Supervisor at Plant Vogtle performed on-site analysis of a blind performance specimen and verified the initial positive results for phencyclidine (PCP). The specimen was prepared for shipment and was received for testing at LabCorp on September 30, 2014. Specimen ID 011150869 was assigned by LabCorp and testing was completed on October 2, 2014. LabCorp released the specimen to SNC with a negative result. SNC's Medical Services Supervisor contacted the laboratory on October 2, 2014 to inform the laboratory that the specimen was a blind performance specimen for PCP with a target concentration of 37.5 ng/mL and the expected result was not reported. The Laboratory initiated an investigation into the incident.
Investigation Summary:
On September 28, 2014, the Medical Services Supervisor selected a blind specimen to analyze in accordance with SNC procedures. The specimen was analyzed and confirmed as an initial positive for phencyclidine. This specimen was prepared for shipment to the HHS certified laboratory, LabCorp, for further confirmation. The specimen was received at LabCorp on September 30, 2014 and assigned Specimen ID 0111550869. The initial test of the specimen was positive at LabCorp for phencyclidine and negative for all other drugs on immunoassay.
The specimen was scheduled for GC/MS (Gas Chromatography-Mass Spectrometry) confirmation testing on September 30, 2014. The specimen was aliquoted, extracted and analyzed on October 1, 2014. The specimen was tested in PCP batch 199636 and received a confirmation result of 14 ng/mL which is below the cutoff of 25 ng/mL and was reported as negative on October 2, 2014.
The Vogtle Medical Services Supervisor contacted the laboratory on October 2, 2014 and notified the laboratory responsible person that the specimen was a blind performance specimen and the expected results were not obtained. Use of LabCorp was immediately suspended pending the outcome of the investigation. The laboratory initiated an investigation into the incident on October 2, 2014. The laboratory had not discarded the original specimens. As part of the investigation, the samples from this PCP batch were re-injected on two different GC/MS instruments. The data from the two additional GC/MS runs was analyzed and all parameters were found acceptable, including calibration, and quality control specimens. The batch contained four (4) specimens, three of which contained no drug and matched the data from the original GC/MS run. However, Specimen ID 0111550869 was quantitated at 36 ng/mL and
U.S. Nuclear Regulatory Commission ND-14-2009 Enclosure 30ng/ml on the additional GC/MS instruments. The specimen was not re-injected on the original GC/MS instrument as it was out of service for maintenance.
The laboratory used a separate aliquot and repeated the extraction and analysis of PCP for Specimen ID 0111550869 (Batch 27501) on all three GC/MS instruments, including the original instrument post maintenance. The confirmation results were all consistent between the three instruments and ranged from 34-37 ng/ml. All calibration, quality control, recovery, and documentation were found acceptable. The instrument log for the original GC/MS instrument showed that the instrument was taken out of service shortly after PCP batch 199636 was completed and prior to analysis of any other batch. The GC/MS technologist was unable to achieve the daily auto-tune of the instrument and upon further investigation revealed a crack in the GC/MS column which caused leaking at the interface between the Gas Chromatograph and the Mass Spectrometer. As part of the corrective action, the GC/MS source was cleaned and a new column was installed on the instrument.
Based on the laboratory investigation which was released on October 14, 2014, the corrective actions initiated were the replacement of the GC/MS column and the implementation of a quality control specimen injection at the end of each batch to ensure acceptable instrument performance throughout the analysis of each batch.
SNC contracted with an independent Forensic Toxicologist, to oversee the investigation and to review the investigation results released by LabCorp. The results of the initial investigation were rejected by the independent reviewer and SNC due to the lack of depth and broadness review. This decision was based on the fact that the laboratory had an earlier PCP blind performance issue at Plant Hatch on July 4, 2014 in which an extraction technician inadvertently failed to utilize the correct amount during the extraction of the specimen. This in turn led to the incorrect result being reported to SNC. SNC requested LabCorp conduct a more thorough investigation to include a broadness review of the PCP analysis at the laboratory. This was communicated to the laboratory on October 31, 2014.
LabCorp immediately initiated a new investigation into the PCP issues at its facility. The second investigation report was released to SNC on November 20, 2014. This investigation report was reviewed by the independent Forensic Toxicologist and SNC and was found to be acceptable on December 1, 2014.
Corrective Actions:
- 1. Addition of a quality control specimen injected as the last sample of each confirmation batch.
- 2. Extractors will be required to complete a Visual Verification of Volumes sheet for each batch.
- 3. NRC sample numbers will be manually identified either when the batch is created or prior to certification and reporting.
- 4. Internal Standard Abundance criteria will be applied to NRC samples, i.e. any NRC sample with internal standard that is not within 50-200% of the calibrator and quality controls will be repeated in accordance with HHS/DOT guidelines.
- 5. An up-front dilution of 1:5 has been added to the SOP for PCP when the initial test result is equal to or greater than 100. This was instituted because samples with high
U.S. Nuclear Regulatory Commission ND-14-2009 Enclosure concentrations of PCP must be re-extracted due to column overloading. This dilution based on initial results is currently in place for THC and Cocaine confirmation assays.
- 6. NRC samples initially testing positive for THC, Cocaine, and PCP that confirm negative will be repeated and the entire batch held until the repeat is complete and still negative.
If the repeat does not correlate with the extraction, the whole batch will be repeated. In accordance with HHS/DOT guidelines, this is currently done for THC and Cocaine.
- 7. Vogtle FFD will increase the number of blind performance specimens submitted to the HHS lab from one percent (1 %) of all specimens sent to the HHS lab, to two percent (2%) for 30 days and review the results to verify that the laboratory corrective actions were effective.
==
Conclusions:==
Recently, SNC has identified blind performance testing errors with PCP at LabCorp. SNC Letter NL-14-1245 was previously submitted documenting a July 2014 lab error on a Hatch blind specimen. The second error, as outlined in this 30-day report, involved a failure of an instrument at the HHS laboratory. An independent investigation documented that LabCorp has instituted policies and procedures to address Corrective Actions 1-6 above. SNC has initiated actions (Corrective Action 7) increasing the number of blind samples sent to the HHS lab to verify that the laboratory corrective actions were effective. The investigation and corrective actions adequately address the false negative result and have strengthened the testing process.
These measures are deemed adequate to prevent recurrence of this type of problem.
Jeffrey T. Gasser Southern Nuclear Executive Vice President Operating Company, Inc.
Operational Readiness &
Site Integration 7825 River Road Plant Vogtle Units 3&4 Waynesboro, GA 30830 Tel 706.437-6700 SOUTHERN Fax 706-826-5796 COMPANY jtgasser@southernco.com December 17, 2014 Docket Nos.: 05-424 52-025 ND-14-2009 05-425 52-026 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtle Electric Generating Plant (VEGP) Units 1 - 4 10 CFR 26.719(c) Report:
False Negative Results for a Blind Performance Test Sample Ladies and Gentlemen:
In accordance with the requirements of 10 CFR 26.719(c), Southern Nuclear Operating Company hereby submits the enclosed Report.
This letter contains no regulatory commitments . If you have any questions, please contact Michael Yox at 706-826-6459.
Respectfully submitted, 1~.LtJ~
Executive Vice President Operational Readiness & Site Integration JTG/MJY/sdc
Enclosure:
10 CFR 26.719(c) Report
U.S. Nuclear Regulatory Commission ND-14-2009 Page 2 of 3 cc:
Southern Nuclear Operating Company I Georgia Power Company Mr. S. E. Kuczynski (w/o enclosures)
Mr. J. A Miller Mr. D. G. Bost (w/o enclosures)
Mr. B. K. Taber (w/o enclosures)
Mr. B. L. lvey Mr. M. D. Meier Mr. M. D. Rauckhorst (w/o enclosures)
Mr. J. T. Gasser (w/o enclosures)
Mr. D. H. Jones (w/o enclosures)
Mr. J. R. Johnson (w/o enclosures)
Mr. D. R. Madison Mr. D. M. Lloyd Mr. B. H. Whitley Mr. C. R. Pierce Mr. D. L. Fulton Mr. M. J. Yox Mr. J. C. Harrelson Mr. W. A Sparkman Mr. J.P. Redd Mr. G. W. Gunn Document Services RTYPE: VND.LI.LOO File AR.01.02.06 Nuclear Regulatory Commission Mr. V. M. McCree (w/o enclosures)
Mr. M. Delligatti (w/o enclosures)
Mr. L. Burkhart (w/o enclosures)
Mr. D. H. Jaffe Mr. C. Patel Ms. D. L. McGovern Mr. B. M. Bavol Ms. R. Reyes Ms. M. A Sutton Mr. M. E. Ernstes Mr. G. Khouri Mr. L. M. Cain Mr. J. D. Fuller Mr. C. B. Abbott Mr. C. Huffman Ms. S. Temple Oglethorpe Power Corporation Mr. M. W. Price Ms. K. T. Haynes Ms. A Whaley
U.S. Nuclear Regulatory Commission ND-14-2009 Page 3 of 3 Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. S. M. Jackson Dalton Utilities Mr. D. Cope CB&I Mr. J. Simmons (w/o enclosures)
Ms. K. Stoner (w/o enclosures)
Mr. C. A. Castell Westinghouse Electric Company, LLC Mr. T. C. Geer (w/o enclosures)
Mr. S. W. Gray (w/o enclosures)
Mr. L. Woodcock Mr. P. A. Russ Mr. G. F. Couture Mr. M. Y. Shaqqo Mr. B. J. Bedford Mr. M. P. Rubin Ms. S. DiTommaso Other Mr. R. W. Prunty, Bechtel Power Corporation Ms. K. K. Patterson, Tetra Tech NUS, Inc.
Dr. W. R. Jacobs, Jr., Ph.D., GDS Associates, Inc.
Mr. S. Roetger, Georgia Public Service Commission Ms. S. W. Kernizan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. S. Blanton, Balch Bingham Mr. R. Grumbir, APOG
Southern Nuclear Operating Company ND-14-2009 Enclosure Vogtle Electric Generating Plant (VEGP) Units 1 - 4 10 CFR 26.719(c) Report:
False Negative Results for a Blind Performance Test Sample
U.S. Nuclear Regulatory Commission ND-14-2009 Enclosure Vogtle Electric Generating Plant HHS Laboratory Blind Performance Error
==
Introduction:==
10 CFR 26.719(c)(1), "Drug and alcohol testing errors", describes the requirements for reporting Fitness for Duty (FFD) drug testing errors or unsatisfactory performance discovered at any Health and Human Services (HHS) certified laboratory or licensee testing facility. Any identified errors involving false negative test results must be reported to the NRC within 30 days of completing an investigation in accordance with 10 CFR 26.719(c). Southern Nuclear Operating Company (SNC) performs on-site analysis of urine specimens at each of its nuclear plant sites.
Laboratory Corporation of America (LabCorp) is utilized for analysis of urine specimens collected at SNC Corporate headquarters and to perform confirmation testing for initial positive drug tests when analyzed on-site by SNC FFD personnel.
On September 28, 2014, the Medical Services Supervisor at Plant Vogtle performed on-site analysis of a blind performance specimen and verified the initial positive results for phencyclidine (PCP). The specimen was prepared for shipment and was received for testing at LabCorp on September 30, 2014. Specimen ID 011150869 was assigned by LabCorp and testing was completed on October 2, 2014. LabCorp released the specimen to SNC with a negative result. SNC's Medical Services Supervisor contacted the laboratory on October 2, 2014 to inform the laboratory that the specimen was a blind performance specimen for PCP with a target concentration of 37.5 ng/mL and the expected result was not reported. The Laboratory initiated an investigation into the incident.
Investigation Summary:
On September 28, 2014, the Medical Services Supervisor selected a blind specimen to analyze in accordance with SNC procedures. The specimen was analyzed and confirmed as an initial positive for phencyclidine. This specimen was prepared for shipment to the HHS certified laboratory, LabCorp, for further confirmation. The specimen was received at LabCorp on September 30, 2014 and assigned Specimen ID 0111550869. The initial test of the specimen was positive at LabCorp for phencyclidine and negative for all other drugs on immunoassay.
The specimen was scheduled for GC/MS (Gas Chromatography-Mass Spectrometry) confirmation testing on September 30, 2014. The specimen was aliquoted, extracted and analyzed on October 1, 2014. The specimen was tested in PCP batch 199636 and received a confirmation result of 14 ng/mL which is below the cutoff of 25 ng/mL and was reported as negative on October 2, 2014.
The Vogtle Medical Services Supervisor contacted the laboratory on October 2, 2014 and notified the laboratory responsible person that the specimen was a blind performance specimen and the expected results were not obtained. Use of LabCorp was immediately suspended pending the outcome of the investigation. The laboratory initiated an investigation into the incident on October 2, 2014. The laboratory had not discarded the original specimens. As part of the investigation, the samples from this PCP batch were re-injected on two different GC/MS instruments. The data from the two additional GC/MS runs was analyzed and all parameters were found acceptable, including calibration, and quality control specimens. The batch contained four (4) specimens, three of which contained no drug and matched the data from the original GC/MS run. However, Specimen ID 0111550869 was quantitated at 36 ng/mL and
U.S. Nuclear Regulatory Commission ND-14-2009 Enclosure 30ng/ml on the additional GC/MS instruments. The specimen was not re-injected on the original GC/MS instrument as it was out of service for maintenance.
The laboratory used a separate aliquot and repeated the extraction and analysis of PCP for Specimen ID 0111550869 (Batch 27501) on all three GC/MS instruments, including the original instrument post maintenance. The confirmation results were all consistent between the three instruments and ranged from 34-37 ng/ml. All calibration, quality control, recovery, and documentation were found acceptable. The instrument log for the original GC/MS instrument showed that the instrument was taken out of service shortly after PCP batch 199636 was completed and prior to analysis of any other batch. The GC/MS technologist was unable to achieve the daily auto-tune of the instrument and upon further investigation revealed a crack in the GC/MS column which caused leaking at the interface between the Gas Chromatograph and the Mass Spectrometer. As part of the corrective action, the GC/MS source was cleaned and a new column was installed on the instrument.
Based on the laboratory investigation which was released on October 14, 2014, the corrective actions initiated were the replacement of the GC/MS column and the implementation of a quality control specimen injection at the end of each batch to ensure acceptable instrument performance throughout the analysis of each batch.
SNC contracted with an independent Forensic Toxicologist, to oversee the investigation and to review the investigation results released by LabCorp. The results of the initial investigation were rejected by the independent reviewer and SNC due to the lack of depth and broadness review. This decision was based on the fact that the laboratory had an earlier PCP blind performance issue at Plant Hatch on July 4, 2014 in which an extraction technician inadvertently failed to utilize the correct amount during the extraction of the specimen. This in turn led to the incorrect result being reported to SNC. SNC requested LabCorp conduct a more thorough investigation to include a broadness review of the PCP analysis at the laboratory. This was communicated to the laboratory on October 31, 2014.
LabCorp immediately initiated a new investigation into the PCP issues at its facility. The second investigation report was released to SNC on November 20, 2014. This investigation report was reviewed by the independent Forensic Toxicologist and SNC and was found to be acceptable on December 1, 2014.
Corrective Actions:
- 1. Addition of a quality control specimen injected as the last sample of each confirmation batch.
- 2. Extractors will be required to complete a Visual Verification of Volumes sheet for each batch.
- 3. NRC sample numbers will be manually identified either when the batch is created or prior to certification and reporting.
- 4. Internal Standard Abundance criteria will be applied to NRC samples, i.e. any NRC sample with internal standard that is not within 50-200% of the calibrator and quality controls will be repeated in accordance with HHS/DOT guidelines.
- 5. An up-front dilution of 1:5 has been added to the SOP for PCP when the initial test result is equal to or greater than 100. This was instituted because samples with high
U.S. Nuclear Regulatory Commission ND-14-2009 Enclosure concentrations of PCP must be re-extracted due to column overloading. This dilution based on initial results is currently in place for THC and Cocaine confirmation assays.
- 6. NRC samples initially testing positive for THC, Cocaine, and PCP that confirm negative will be repeated and the entire batch held until the repeat is complete and still negative.
If the repeat does not correlate with the extraction, the whole batch will be repeated. In accordance with HHS/DOT guidelines, this is currently done for THC and Cocaine.
- 7. Vogtle FFD will increase the number of blind performance specimens submitted to the HHS lab from one percent (1 %) of all specimens sent to the HHS lab, to two percent (2%) for 30 days and review the results to verify that the laboratory corrective actions were effective.
==
Conclusions:==
Recently, SNC has identified blind performance testing errors with PCP at LabCorp. SNC Letter NL-14-1245 was previously submitted documenting a July 2014 lab error on a Hatch blind specimen. The second error, as outlined in this 30-day report, involved a failure of an instrument at the HHS laboratory. An independent investigation documented that LabCorp has instituted policies and procedures to address Corrective Actions 1-6 above. SNC has initiated actions (Corrective Action 7) increasing the number of blind samples sent to the HHS lab to verify that the laboratory corrective actions were effective. The investigation and corrective actions adequately address the false negative result and have strengthened the testing process.
These measures are deemed adequate to prevent recurrence of this type of problem.