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MONTHYEARML21048A3242021-02-17017 February 2021 License Amendment Request for Application to Revise Technical Specifications to Adopt TSTF-205 -A Revision of Calibration, Channel Functional Test, and Related Definitions Project stage: Request RA-20-0252, License Amendment Request to Remove Extraneous Content and Requirements from the Operating License and Technical Specifications2021-02-24024 February 2021 License Amendment Request to Remove Extraneous Content and Requirements from the Operating License and Technical Specifications Project stage: Request CNL-21-016, License Amendment Request to Revise Technical Specifications to Change the Steam Generator Secondary Side Water Level to Accommodate the Replacement Steam Generators (WBN-TS-20-05)2021-03-0202 March 2021 License Amendment Request to Revise Technical Specifications to Change the Steam Generator Secondary Side Water Level to Accommodate the Replacement Steam Generators (WBN-TS-20-05) Project stage: Request ML21105A0332021-03-0808 March 2021 ISFSI Emergency Plan License Amendment Request - Public Project stage: Request RA-21-0052, License Amendment Request Regarding Change to Containment Spray Nozzle Test Frequency2021-03-24024 March 2021 License Amendment Request Regarding Change to Containment Spray Nozzle Test Frequency Project stage: Request DCL-21-020, Request for Revision to Technical Specification 3.8.1, AC Sources - Operating to Support Diesel Fuel Oil Transfer System Component Planned Maintenance2021-03-29029 March 2021 Request for Revision to Technical Specification 3.8.1, AC Sources - Operating to Support Diesel Fuel Oil Transfer System Component Planned Maintenance Project stage: Request ML21089A0582021-03-30030 March 2021 NRR E-mail Capture - Acceptance Review - Watts Bar Nuclear Plant, Unit 2 - CNL-21-016 - LAR to Revise TS to Change SG Secondary Side Water Level to Accommodate RSGs (L-2021-LLA-0032) Project stage: Acceptance Review RS-21-007, Application to Address the Issues Identified in Westinghouse Documents NSAL-09-5, Rev.1 and NSAL-15-1, Rev. 02021-04-0707 April 2021 Application to Address the Issues Identified in Westinghouse Documents NSAL-09-5, Rev.1 and NSAL-15-1, Rev. 0 Project stage: Request ML21104A1622021-04-14014 April 2021 NRR E-mail Capture - (External_Sender) Salem Generating Station - Incidental Take Reports: Atlantic Sturgeon 04/13/2021 Project stage: Request WBL-21-020, Annual Non-Radiological Environmental Operating Report - 20202021-04-20020 April 2021 Annual Non-Radiological Environmental Operating Report - 2020 Project stage: Request LR-N21-0036, LR-N21-0036 LAR to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2021-04-28028 April 2021 LR-N21-0036 LAR to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections Project stage: Other ML21119A1412021-04-29029 April 2021 License Amendment Request, Revise Technical Specifications Administrative Controls Section 5.5.7 Regarding the Frequency for Performing Certain Ventilation Filter Testing Project stage: Request ML21144A0742021-05-24024 May 2021 NRR E-mail Capture - Watts Bar Nuclear Plant, Unit 2 - Audit Plan for SG Water Level Change LAR Project stage: Approval ML21217A2222021-08-13013 August 2021 Regulatory Audit Summary Related to Request to Revise Technical Specifications to Change the Steam Generator Water Level Project stage: Other ML21252A0912021-09-0909 September 2021 NRR E-mail Capture - Request for Comments on Proposed Issuance of Amendments to Watts Bar Nuclear Plant, Unit 2 - Revise Steam Generator Secondary Side Water Level Project stage: Approval ML21260A2102021-11-22022 November 2021 Issuance of Amendment No. 57 to Revise Technical Specifications to Change the Steam Generator Secondary Side Water Level Project stage: Approval 2021-03-08
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Category:Audit Report
MONTHYEARML21217A2222021-08-13013 August 2021 Regulatory Audit Summary Related to Request to Revise Technical Specifications to Change the Steam Generator Water Level ML18115A1382018-07-10010 July 2018 Staff Review of the Seismic Probabilistic Risk Assessment Associated with the Implementation of the Near-Term Task Force Recommendation 2.1: Seismic (CAC Nos. MF9879 and MF9880; EPID L-2017-JLD-0044 ML15345A4242015-12-23023 December 2015 Audit Report Related to License Amendment Request to Revise Technical Specification 4.2.1, Fuel Assemblies ML15334A1252015-12-23023 December 2015 Audit of the Licensee'S Management of Regulatory Commitments ML15294A2032015-10-30030 October 2015 NRC Report for the Audit of Tennessee Valley Authority'S Flood Hazard Reevaluation Report Submittals Relating to the Near-Term Task Force Recommendation 2.1-Flooding for Browns Ferry, Units 1,2 & 3, Sequoyah, Units 1 & 2, and Watts Bar, Uni ML14323A5622014-12-0303 December 2014 Report for the Audit Regarding Implementation of Licensing Preservation Program ML14211A3462014-08-18018 August 2014 Report for the Westinghouse Audit in Support of Reliable Spent Fuel Instrumentation Related to Order EA-12-051 ML14128A1292014-05-15015 May 2014 Report for the Audit Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Instrumentation Related to Orders EA-12-049 and EA-12-051 ML13343A0362013-12-20020 December 2013 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML13022A4012013-02-0707 February 2013 Audit of the Licensee'S Management of Regulatory Commitments ML1110306242011-04-27027 April 2011 Accident Analyses Audit Report Westinghouse Documents Relating to Final Safety Analysis Report Accident Analyses ML1034005992011-01-20020 January 2011 Commercial Grade Dedication of Hardware and Software Used in the Post Accident Monitoring System Audit Report ML0929300102009-10-21021 October 2009 Audit of the Licensee'S Management of Regulatory Commitments ML0621204692006-11-22022 November 2006 Plant Audit Report--Watts Bar Unit 1 Nuclear Plant New Sump Design in Response to Audit Report ML0615900812006-07-0303 July 2006 Letter, Audit of the Licensee'S Management of Regulatory Commitments ML0419101202004-07-0606 July 2004 LTR-04-0425 - Richard Schneider Ltr Final TVA Control Area Readiness Audit 2021-08-13
[Table view] Category:Letter
MONTHYEARML23319A2452024-01-29029 January 2024 Issuance of Amendment Nos. 366 and 360; 164 and 71 Regarding the Adoption of TSTF-567, Revision 1, Add Containment Sump TS to Address GSI-191 Issues ML24008A2462024-01-18018 January 2024 Revision to the Reactor Vessel Material Surveillance Capsule Withdrawal Schedule CNL-24-017, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions2024-01-17017 January 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions CNL-24-016, Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)2024-01-10010 January 2024 Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14) CNL-23-052, Application to Adopt TSTF-427-A, Revision 2, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability2024-01-0909 January 2024 Application to Adopt TSTF-427-A, Revision 2, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability CNL-23-062, Application to Revise the Technical Specifications Section 3.8.2, AC Sources-Shutdown, to Remove Reference to the C-S Diesel Generator (WBN-TS-23-018)2024-01-0808 January 2024 Application to Revise the Technical Specifications Section 3.8.2, AC Sources-Shutdown, to Remove Reference to the C-S Diesel Generator (WBN-TS-23-018) ML23346A1382024-01-0303 January 2024 Regulatory Audit Summary Related to Request to Increase the Number of Tritium Producing Burnable Absorber Rods CNL-23-069, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-21021 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000390/20234412023-12-21021 December 2023 Plantfinal Significance Determination for a Security-Related Greater than Green Finding, Nov, and Assessment Follow-up, 05000390-2023441 and 05000391-2023441-Public CNL-23-036, Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08)2023-12-18018 December 2023 Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08) IR 05000390/20234042023-12-14014 December 2023 Security Baseline Inspection Report 05000390/2023404 and 05000391/2023404 CNL-23-001, Rebaseline of Sections 3.1 and 3.2 of the Technical Specifications (WBN-TS-23-01)2023-12-13013 December 2023 Rebaseline of Sections 3.1 and 3.2 of the Technical Specifications (WBN-TS-23-01) ML23293A0572023-12-0606 December 2023 Issuance of Amendment Nos. 163 and 70 Regarding Adoption of TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control IR 05000390/20230102023-11-30030 November 2023 RE-Issue Watts Bar Nuclear Plant - Biennial Problem Identification and Resolution Inspection Report 050000390/2023010 and 05000391/2023010 and Apparent Violation CNL-23-067, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-11-27027 November 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000390/20230032023-11-13013 November 2023 Integrated Inspection Report 05000390/2023003 and 05000391/2023003 and Apparent Violation ML23312A1432023-11-0808 November 2023 Submittal of Dual Unit Updated Final Safety Analysis Report (UFSAR) Amendment 5 CNL-23-059, Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-2023-09-20020 September 2023 Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 CNL-23-061, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-09-20020 September 2023 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision ML23251A2002023-09-11011 September 2023 Request for Withholding Information from Public Disclosure for Watts Bar Nuclear Plant, Units 1 and 2 CNL-23-057, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 642023-09-0505 September 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 64 IR 05000390/20230052023-08-30030 August 2023 Updated Inspection Plan for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390/2023005 and 05000391/2023005 ML23233A0042023-08-28028 August 2023 Proposed Alternative to the Requirements of the ASME Boiler and Pressure Vessel Code for Upper Head Injection Dissimilar Metal Butt Welds IR 05000390/20230022023-08-16016 August 2023 Reissue - Watts Bar Nuclear Plant - Integrated Inspection Report 05000390/2023002 and 05000391/2023002 ML23220A1582023-08-0909 August 2023 Integrated Inspection Report 05000390/2023002 and 05000391/2023002 CNL-23-045, License Amendment Request to Revise Technical Specification Table 1.1-1 Regarding the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts (WBN-TS-23-010)2023-08-0707 August 2023 License Amendment Request to Revise Technical Specification Table 1.1-1 Regarding the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts (WBN-TS-23-010) CNL-23-028, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 and WBN-TS-23-06)2023-08-0202 August 2023 Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 and WBN-TS-23-06) ML23192A4472023-07-31031 July 2023 Staff Assessment of Updated Seismic Hazards at TVA Sites Following the NRC Process for the Ongoing Assessment of Natural Hazards Information CNL-23-055, Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills2023-07-25025 July 2023 Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills IR 05000390/20230112023-07-24024 July 2023 Quadrennial Focused Engineering Inspection (FEI) Commercial Grade Dedication Report 05000390 2023011 and 05000391 2023011 CNL-23-053, Tennessee Valley Authority - Radiological Emergency Plan Revisions2023-07-18018 July 2023 Tennessee Valley Authority - Radiological Emergency Plan Revisions CNL-23-020, Application to Revise Technical Specifications to Adopt TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control (WBN-TS-22-06)2023-06-28028 June 2023 Application to Revise Technical Specifications to Adopt TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control (WBN-TS-22-06) CNL-23-049, Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan .2023-06-26026 June 2023 Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan . ML23122A2322023-06-0707 June 2023 Issuance of Amendment Nos. 162 and 69 Regarding Change to Date in Footnotes for Technical Specification 3.7.11, Control Room Emergency Air Temperature Control System (Creatcs) CNL-23-044, Transmittal of Revision 3 to WCAP-18774-P and WCAP-18774-NP, Addendum to the Rotterdam Dockyard Company Final Stress Report for 173 P.W.R. Vessels TVA III & IV (Report No. 30749-B-030, Rev. 3) - Evaluation of One Closure Stud Out2023-06-0101 June 2023 Transmittal of Revision 3 to WCAP-18774-P and WCAP-18774-NP, Addendum to the Rotterdam Dockyard Company Final Stress Report for 173 P.W.R. Vessels TVA III & IV (Report No. 30749-B-030, Rev. 3) - Evaluation of One Closure Stud Out IR 05000390/20234032023-05-30030 May 2023 Cyber Security Inspection Report 05000390/2023403 and 05000391/2023403 ML23131A1812023-05-23023 May 2023 Correction to Amendment No. 161 to Facility Operating License No. NPF-90 CNL-23-042, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-05-16016 May 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000390/20220032023-05-0909 May 2023 Reissue Watts Bar Nuclear Plant - Integrated Inspection Report 05000390/2022003 and 05000391/2022003 ML23125A2202023-05-0505 May 2023 Issuance of Amendment No. 161 Regarding a Change to Footnotes for Technical Specification Table 1.1-1 Modes (Emergency Circumstances) IR 05000390/20230012023-05-0404 May 2023 Integrated Inspection Report 05000390/2023001 and 05000391/2023001 CNL-23-043, Emergency License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical Specification Table 1.1-1, Modes (WBN-TS-23-09)2023-05-0404 May 2023 Emergency License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical Specification Table 1.1-1, Modes (WBN-TS-23-09) CNL-23-032, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 412023-04-27027 April 2023 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 41 CNL-23-030, Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update2023-04-27027 April 2023 Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-23-033, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-04-24024 April 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision CNL-23-029, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-04-11011 April 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML23072A0652023-04-0505 April 2023 Units 1 and 2 Issuance of Amendment Nos. 364 and 358; 160 and 68 Regarding a Revision to Technical Specification 3.4.12 ML23073A2762023-04-0303 April 2023 Individual Notice of Consideration of Issuance of Amendments to Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing (EPID L-2023-LLA-0029) (Letter) CNL-23-023, Annual Insurance Status Report2023-03-30030 March 2023 Annual Insurance Status Report CNL-23-024, TVA Guarantee of Payment of Deferred Premiums - 2022 Annual Report2023-03-29029 March 2023 TVA Guarantee of Payment of Deferred Premiums - 2022 Annual Report 2024-01-09
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August 13, 2021 Mr. James Barstow Vice President, Nuclear Regulatory Affairs and Support Services Tennessee Valley Authority 1101 Market Street, LP 4A-C Chattanooga, TN 37402-2801
SUBJECT:
WATTS BAR NUCLEAR PLANT, UNIT 2 - REGULATORY AUDIT
SUMMARY
RELATED TO REQUEST TO REVISE TECHNICAL SPECIFICATIONS TO CHANGE THE STEAM GENERATOR WATER LEVEL (EPID L-2021-LLA-0032)
Dear Mr. Barstow:
By letter to the U.S. Nuclear Regulatory Commission (NRC) dated March 2, 2021, Tennessee Valley Authority (TVA) submitted a license amendment request that would amend the Watts Bar, Unit 2 Technical Specifications (TS) to change the steam generator (SG) water level requirement in Watts Bar, Unit 2 TS Limiting Condition for Operation (LCO) 3.4.7.b, RCS Loops
- MODE 5, Loops Filled, and Surveillance Requirements (SR) 3.4.5.2, RCS Loops - MODE 3, SR 3.4.6.3, RCS Loops - MODE 4, and SR 3.4.7.2 from greater than or equal to () 6 percent
(%) to 32%. The proposed change is needed to support the Watts Bar, Unit 2 Replacement SG (RSG) project.
To enhance the review of TVAs request, the NRC staff conducted an audit of supporting documents on June 3, 2021. The staff audited the requested documents to confirm certain information relied upon in the license amendment request. A summary of the regulatory audit is enclosed.
The NRC staff did not identify any significant issues during the audit. The staff also identified there is no additional information needed to complete the review of the subject license amendment request.
Sincerely,
/RA/
Michael Mahoney, Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-391
Enclosure:
Regulatory Audit Summary cc: Listserv
REGULATORY AUDIT
SUMMARY
RELATED TO LICENSE AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATIONS TO CHANGE THE STEAM GENERATOR WATER LEVEL TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT, UNIT 2 DOCKET NO. 50-391
1.0 BACKGROUND
A regulatory audit is a planned license or regulation-related activity that includes the examination and evaluation of docketed and non-docketed information. The audit was conducted with the intent to gain understanding, to verify information, and to identify information that will require docketing to support the basis of a licensing or regulatory decision.
By letter dated March 2, 2021, Tennessee Valley Authority (TVA) submitted a license amendment request that would amend the Watts Bar, Unit 2 Technical Specifications (TS) to change the steam generator (SG) water level requirement in Watts Bar, Unit 2 TS Limiting Condition for Operation (LCO) 3.4.7.b, RCS [Reactor Coolant System] Loops - MODE 5, Loops Filled and Surveillance Requirements (SR) 3.4.5.2, RCS Loops - MODE 3, SR 3.4.6.3, RCS Loops - MODE 4, and SR 3.4.7.2, RCS Loops - MODE 5, Loops Filled, from greater than or equal to () 6 percent (%) to 32%. The proposed change is needed to support the Watts Bar, Unit 2 Replacement SG (RSG) project.
The U.S. Nuclear Regulatory Commission (NRC) staff performed a preliminary review of the licensing amendment request (LAR) and determined that a regulatory audit would assist in the timely completion of the review. The regulatory audit was performed consistent with NRC Office of Nuclear Reactor Regulation Office Instruction LIC-111, Revision 1, Regulatory Audits, dated October 31, 2019 (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML19226A274).
2.0 AUDIT ACTIVITIES AND RESULTS The NRC staff conducted a regulatory audit that consisted of a remote audit on June 3, 2021.
The audit plan was provided to TVA on May 24, 2021 (ADAMS Accession No. ML21144A074).
The list of documents uploaded by the licensee in response to the NRC staffs request and examined by the audit team is provided in Section 4.0 below.
The remote audit was conducted using an online portal and teleconferencing capabilities. The purpose of the audit was to (1) examine several analyses or documents referenced in the LAR but not provided as part of the LAR, and (2) identify any information that would be required from Enclosure
the licensee to be provided on the docket for the NRC to render a staff finding to support the safety evaluation.
The NRC staff examined the documents identified in Section 4.0 below and held an audit call with members of TVA on June 3, 2021, regarding the LAR under review.
At the conclusion of the audit, the NRC staff determined that additional information would not be needed in order for the staff to complete the review of the LAR.
3.0 AUDIT PARTICIPANTS NRC R. Beaton N. Carte M. Mahoney TVA R. Wells G. Williams 4.0 DOCUMENTS PROVIDED IN ELECTRONIC READING ROOM Westinghouse Calculation CN-SCS-16-12, Revision 2, Watts Bar Unit 2 RSG [Replacement Steam Generator] Narrow Range Level Uncertainty for EOP [Emergency Operating Procedure]
Applications and Technical Specifications Level Surveillances.
Westinghouse LTR-SCS-21-42, Revision 0, Attachment 1, Watts Bar Unit 2: Bases for the Technical Specification Surveillance Limit for Steam Generator Level, May 28, 2021, Attachment to WAT-D-12773.
TVA Drawing 20010E01, Sheet 1 of 3, Revision 2, General Arrangement TVA - Watts Bar 2 RSG.
ML21217A222 OFFICE NRR/DORL/LPL2-2/PM NRR/DORL/LPL2-2/LA NRR/DSS/SNSB/BC NAME MMahoney RButler SKrepel DATE 08/10/2021 08/09/2021 08/10/2021 OFFICE NRR/DORL/LPL2-2/BC NRR/DORL/LPL2-2/PM NAME DWrona MMahoney DATE 08/10/2021 08/13/2021