ML23305A092
| ML23305A092 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 12/07/2023 |
| From: | Thomas Wengert Plant Licensing Branch IV |
| To: | Entergy Operations |
| Wengert T | |
| References | |
| EPID L-2022-LLA-0197 | |
| Download: ML23305A092 (1) | |
Text
December 7, 2023 ANO Site Vice President Arkansas Nuclear One Entergy Operations, Inc.
N-TSB-58 1448 S.R. 333 Russellville, AR 72802
SUBJECT:
ARKANSAS NUCLEAR ONE, UNIT 1 -
SUMMARY
OF REGULATORY AUDIT REGARDING THE LICENSE AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATIONS TO ADOPT TSTF-505, REVISION 2, PROVIDE RISK-INFORMED EXTENDED COMPLETION TIMES - RITSTF INITIATIVE 4b (EPID L-2022-LLA-0197)
Dear Sir or Madam:
By letter dated December 22, 2022 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML22356A249), as supplemented by letter dated September 21, 2023 (ML23264A856), Entergy Operations, Inc. (Entergy, the licensee) requested an amendment to the Renewed Facility Operating License for Arkansas Nuclear One, Unit 1, to revise Technical Specifications to adopt risk-informed completion times based on Technical Specifications Task Force (TSTF) Traveler TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF [Risk-Informed TSTF] Initiative 4b.
To support its review, the U.S. Nuclear Regulatory Commission (NRC) staff conducted a virtual regulatory audit from May 17, 2023, through December 5, 2023, to support its review of the license amendment request. During the regulatory audit, the NRC staff reviewed documents and held discussions with the Entergy staff and its representatives. The regulatory audit summary is enclosed with this letter.
If you have any questions, please contact me at 301-415-4037 or by email at Thomas.Wengert@nrc.gov.
Sincerely,
/RA/
Thomas J. Wengert, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-313
Enclosure:
Regulatory Audit Summary cc: Listserv
OFFICE OF NUCLEAR REACTOR REGULATION REGULATORY AUDIT
SUMMARY
IN SUPPORT OF LICENSE AMENDMENT REQUEST TO ADOPT TSTF-505 ENTERGY OPERATIONS, INC.
ARKANSAS NUCLEAR ONE, UNIT 1 DOCKET NO. 50-313
1.0 BACKGROUND
By application dated December 22, 2022 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML22356A249), as supplemented by letter dated September 21, 2023 (ML23264A856) Entergy Operations, Inc. (Entergy, the licensee) submitted a license amendment request (LAR) for Arkansas Nuclear One, Unit 1 (ANO-1). The amendment would revise technical specification (TS) requirements to permit the use of risk-informed completion times for actions to be taken when limiting conditions for operation are not met. The proposed changes are based on Technical Specifications Task Force (TSTF)
Traveler TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF
[Risk-Informed TSTF] Initiative 4b, dated July 2, 2018 (ML18183A493). The U.S. Nuclear Regulatory Commission (NRC) staff issued a final model safety evaluation approving TSTF-505, Revision 2, on November 21, 2018 (Package No. ML18269A041).
Information that the NRC staff relies upon to make the safety determination must be submitted on the docket. However, the NRC staff may review supporting information retained as records under Title 10 of the Code of Federal Regulations (10 CFR) 50.71, Maintenance of records, making of reports, and/or 10 CFR 54.37, Additional records and recordkeeping requirements, which, although not required to be submitted as part of the licensing action, would help the NRC staff better understand the licensees submitted information. To support its review of the LAR, the NRC staff issued a regulatory audit plan on May 10, 2023 (ML23121A301). The purpose of the audit is to review the documentation related to the subject of its application (e.g.,
calculations and reports) that were not submitted on the ANO-1 docket, to acquire additional understanding about the amendment request, and to determine whether additional information is needed to be docketed to complete the NRC staffs safety evaluation.
2.0 AUDIT ACTIVITIES The NRC audit team consisted of NRC staff and NRC contract support from the Pacific Northwest National Laboratory (PNNL). Attachment 1 of this audit summary lists the individuals that took part in or attended the audit. The virtual regulatory audit was conducted from May 17, 2023, through November 20, 2023. Throughout the audit period, the NRC audit team used an internet-based portal provided by the licensee to review primarily non-docketed information related to the application. On June 14, 2023, the NRC staff submitted audit questions to the licensee (ML23166A013). On July 11 and July 12, 2023, formal, virtual audit meetings were held with the licensee to facilitate technical discussions of the audit questions according to the audit plan.
Enclosure
Technical discussions were focused on the following major areas: probabilistic risk assessment, external hazards, fire protection, TSs, electrical engineering, and instrumentation and controls.
On July 12, 2023, the NRC staff provided a brief conclusion of the formal, virtual audit meeting including audit objectives that were met and details on the path forward. The only deviation from the audit plan was a shortening of the formal audit by 1 day. Non-docketed information provided by the licensee in response to audit questions and the formal meetings is listed in attachment 2 of this audit summary. At the conclusion of the meetings, Entergy committed to issuing a supplement to the application to provide documentation on the docket of certain audit discussion points. Although the formal audit meetings ended on July 12, 2023, NRC staff interactions with the licensee continued until November 20, 2023. In lieu of an exit meeting, the NRCs licensing project managers December 5, 2023, discussion with the licensee regarding the supplement completed the regulatory audit related activities.
3.0 RESULTS OF THE AUDIT By letter dated September 21, 2023 (ML23264A856), the licensee supplemented its application to address certain items discussed during the audit. The NRC staff subsequently reviewed the licensees supplement and determined that no additional information was needed for the staff to complete its review of the LAR.
Attachments:
- 1. List of Participants
- 2. List of Documents Available for Staff Review During the Audit
List of Participants U.S. Nuclear Regulatory Commission (NRC) Audit Team Name, Organization Thomas Wengert, Plant Licensing Branch IV (LPL4)
Thomas Byrd, LPL4 Alexander Schwab, Probabilistic Risk Assessment (PRA) Licensing Branch A (APLA)
Jeff Circle, APLA Keith Tetter, PRA Licensing Branch C (APLC)
Sunwoo Park, APLC Edmund Kleeh, Electrical Engineering Branch (EEEB)
Steve Wyman, EEEB Ming Li, Instrumentation and Controls Branch (EICB)
Norbert Carte, EICB Kaihwa Hsu, Mechanical Engineering and Inservice Testing Branch (EMIB)
Angelo Stubbs, Containment and Plant Systems Branch (SCPB)
Derek Scully, SCPB Fred Forsaty, Nuclear Systems Performance Branch Andrea Russell, Technical Specifications Branch Steve Short, Pacific Northwest National Laboratory Entergy Operations, Inc. (Entergy) Audit Team Name, Organization Mark Reid, Arkansas Nuclear One (ANO) Licensing Phil Couture, Entergy Corporate Licensing Howard Mahan, Entergy Corporate Licensing Jason Hall, ANO PRA Trevor Thompson, ANO PRA Ashton Williams, ANO PRA Andrew Osborn, ANO Project Management Brad Miller, ANO Engineering Andrew Fox, ANO Engineering Sara Newton, ANO Engineering Brian Duesterbeck, ANO Engineering Jeff Schappaugh, Jensen Hughes Joe Renner, Jensen Hughes David Passehl, Jensen Hughes Ed Parsley, Jensen Hughes Leo Shanley, Jensen Hughes Attachment 1
List of Documents Available for Staff Review During the Audit Entergy Operations, Inc. (Entergy, the licensee) provided supporting documentation (e.g.,
analyses, calculations, reports, drawings, and procedures) on the Arkansas Nuclear One, Unit 1 (ANO-1) document portal during the audit period. Below is a listing of the documents provided on the portal for the U.S. Nuclear Regulatory Commission (NRC) audit teams review during the audit.
Probabilistic Risk Assessment (PRA) Documents Application-Specific Documents Addendum to PRA Licensing Branch C (APLC) response regarding TORMIS calculations ANO Phoenix Demonstration Slide Presentation EN-DC-401, Revision 0, Risk Informed Completion Time EN-DC-402, Revision 0, Calculation of RMATs [Risk Management Action Times] and RICTs [Risk-Informed Completion Times]
Enclosure 8 Snippet PSA-ANO1-06-4B-EST EC93893, Revision 0, ANO-1 PRA - RICT Estimates for TSTF
[Technical Specifications Task Force]-505 (RICT) Program LAR [License Amendment Request] Submittal, dated February 21, 2023 Full-Scope and Focused-Scope Peer Reviews and Facts and Observations (F&Os) Closure Reviews ANO-1 Internal Flooding PRA Peer Review, Revision 0 ANO-1 Power Plant Probabilistic Risk Assessment Focused-Scope Peer Review (LERF
[Large Early Release Frequency]), Revision 0 ANO-1 Focused Scope Peer Review Fire PRA 5384, Revision 1, November 2012 (Final)
Editorial Comments in ANO 1 Fire HRA [Human Reliability Analysis] Peer Review Report, June 2014 Fire PRA Peer Review Against Fire PRA Standard Supporting Requirements, Westinghouse, January 27, 2010 Locations of LAR References- Fact and Observation and Peer Reviews (spreadsheet)
PSA-ANO-01, Revision 1, ANO-1 PSA [Probabilistic Safety Analysis] - Summary Report for Level-1 Model 6p0 PSA-ANO1-08-FNO-CL-01, Revision 0, ANO-1 PRA Finding Level Fact and Observation Independent Assessment Results of ANO-1 Focused Scope Peer Review, dated May 30, 2012 Key Assumptions and Sources of Uncertainty PSA-ANO1-01-IF-SOU, Revision. 2, ANO-1 Internal Flooding Sources of Uncertainty PSA-ANO1-01-QU-01, Revision 1, ANO-1 PSA Uncertainty and Sensitivity Analysis PSA-ANO1-01-SOU, Revision 2, ANO-1 PRA - Internal Events Sources of Uncertainty PSA-ANO1-01-03-SOU, Revision 1, ANO-1 Fire PRA Sources of Uncertainty PSA-ANO1-03-FQ-01, Revision 0, ANO-1 Fire PRA Uncertainty/Sensitivity Analysis PSA-ANO1-06-4B-EST, Revision 0, ANO-1 PRA RICT Estimates for TSTF-505 PSA-ANO1-06-4B SOU, Revision 0, ANO-1 PRA - Assessment of Key Assumptions and Sources of Uncertainty for TSTF-505 (RICT) Submittal Attachment 2
Modeling of Diverse and Flexible Coping Strategies (FLEX)
PSA-ANO1-01-AS, Revision 2, PRA - Level 1 Accident Sequence Book (Draft)
PSA-ANO1-01-DA, Revision 3, ANO-1 PRA - Data Analytics (Draft)
PSA-ANO1-01-HR, Revision 3, ANO-1 PRA - Human Reliability Analysis (Draft)
PSA-ANO1-01-IE-0, Revision 2, ANO-1 Loss of Offsite Power (Draft)
PSA-ANO1-01-SC, Revision 2, ANO-1 PRA - Level 1 Success Criteria Analysis (Draft)
PSA-ANO1-01-SC-03, ANO-1 PRA MAAP 4.07 OSPR Success Criteria (Draft),
PSA-ANO1-01-SY-03, Revision 2, ANO-1 PRA - Appendix 3 AC [Alternating Current]
Power (AC) (Draft)
PSA-ANO1-01-SY-04, Revision 2, ANO-1 PRA - Appendix 4 DC [Direct Current] Power (Draft)
PSA-ANO1-01-SY-11, Revision 2, ANO-1 PRA - Appendix 11, Emergency/Auxiliary Feedwater (EFW/AFW) (Draft)
PSA-ANO1-01-SY-13, Revision 2, ANO-1 PRA-Appendix 13 - Service Water System (Draft)
PSA-ANO1-01-SY-19, Revision 0, ANO PRA - Appendix 19 Diverse and Flexible Coping Strategies (FLEX) Notebook (Draft)
Shared or Cross-Tied System Modeling Documents Document No. 11060.016 Change No. 86 - Condensate and Feedwater System Operation E-4 Sheet 2, Revision 1, Common Feedwater System 4.16 kW [kilowatt] SWGR
[Switchgear] A-15 PSA-ANO1-01-1E-01, Revision 2, Loss of Offsite Power PSA-ANO1-01-1E, Revision 1, PSA - Initiating Events Analysis PSA-ANO1-01-IF-FA EC84473, Revision 1, ANO-1 Internal Flooding Accident Sequence Analysis Report PSA-ANO1-01-IF-FA EC79014, Revision 0, ANO-1 Internal Flooding Flood Area Definition Report PSA-ANO1-01-SY-03 EC79014, Revision 1, ANO-1 PRA System Notebook AC Power (AC)
PSA-ANO1-01-SY-04 EC79014, Revision 1, ANO-1 PRA System Notebook DC Power (DC)
PSA-ANO1-01-SY-08, Revision 1, IA EC79014, ANO-1 PRA System Notebook Instrument Air (IA)
PSA-ANO1-01-SY-11, Revision 1, EFW EC79014, ANO-1 PRA System Notebook Emergency Auxiliary Feedwater (EFWAFW)
PSA-ANOC-06-4B-TORMIS, Revision 0, Tornado Missile and Pressure Fragilities for Select ANO SSCs [Structures, Systems, and Components]
Upper Level Document (ULD)-0-SYS-01, Revision 13, Control Room HVAC [H.V.A.C.,
Heating, Ventilation, and Air Conditioning]
ULD-0-SYS-02, Revision 16, Offsite Power System ULD-0-SYS-03, Revision 7, New and Spent Handling System ULD-0-SYS-07, Revision 4, ANO Emergency Lighting System ULD-0-SYS-09, Revision 7, Fire Protection System ULD-0-SYS-19, Revision 13, Alternate AC Generator System
Fire PRA PSA-ANO-03-PP, Revision 2, Plant Partitioning and Fire Ignition Frequency PSA-ANO1-03-ES, Revision 2, ANO1 Component and Cable Report PSA-ANO1-03-FQ-01, Revision 1, ANO-1 Fire PRA Uncertainty/Sensitivity Analysis PSA-ANO1-03-FSS, Revision 1, ANO-1 Fire Scenarios Report PSA-ANO1-03-FSS-01, Revision 0, ANO-1 Multi-Compartment/Hot Gas Layer Analysis Report PSA-ANO1-03-HRA, Revision 2, ANO-1 Fire PRA Human Reliability Analysis Notebook PSA-ANO1-03, Revision 2, ANO-1 Fire PRA (FPRA) Summary Report PSA-ANO1-06-01, Revision 5, EC91529, ANO-1 Phoenix Risk Monitor Work Package PSA-ANO1-06-05, Revision 2, ANO-1 PRA - Time Sensitive Actions (TSA)
PSA-ANO1-06-MP, Revision 0, ANO-1 NFPA [National Fire Protection Association] 805 Monitoring Program Phase 2: Screening Using Risk Criteria and Phase 3: Risk Target Value Determination External Hazards PSA-ANO1-06-4B-TMPF EC93893, Revision 0, ANO-1 Tornado Missile Penalty Factor Calculations for RICT Application Electric Power Research Institute (EPRI) Technical Report 3002003107, High Wind Risk Assessment Guidelines Plant and PRA Configuration Control Procedures EN-DC-151, Revision 9, PRA Maintenance and Update EN-NE-G-007, Revision 3, Data Analysis for PRA Models EN-NE-G-006, Revision 1, Initiating Events Analysis for PSA EN-NE-G-008, Revision 2, Probabilistic Safety Assessment Success Criteria EN-NE-G-009, Revision 1, PSA Accident Sequence Analysis EN-NE-G-010, Revision 2, Probabilistic Risk Analysis System Analysis EN-NE-G-011, Revision 1, Probabilistic Safety Assessment Containment Performance Guidelines EN-NE-G-012, Revision 1, Probabilistic Safety Assessment Internal Flooding Analysis EN-NE-G-013, Revision 4, HRA Guide R004 Human Reliability Analysis for PRA EN-NE-G-014, Revision 1, Probabilistic Safety Assessment Level 1 Quantification EN-NE-G-015, Revision 5, Risk Monitor Model Development and Control EN-NE-G-016, Revision 3, Loss of Offsite Power (LOSP) Analysis EN-NE-G-017, Revision 1, Probabilistic Safety Assessment Uncertainty Analysis EN-NE-G-025, Revision 1, Probabilistic Safety Assessment Documentation EN-NE-G-026, Revision 8, Probabilistic Risk Analysis Applications Guideline EN-NE-G-027, Revision 1, Probabilistic Safety Assessment Terms and Definitions EN-NE-G-035, Revision 1, Fire PRA Maintenance and Use
Electrical Engineering Documents Load List for Each Safety-Related Bus ANO-1 4160V [Volt] Safety Bus Load Lists: ANO-1 EDG [Emergency Diesel Generator]
Load List (K4A/B), Calculation No. 86-E-0002-01, Attachment 1 ANO-1 480V Safety Bus Load Lists: Calculation No. 95-E-0001-02 (extract), pages 24 through 31 ANO-1 Battery D06 and D07 Load Lists: CALC-92-E-0021-01, Emergency Duty Cycle and Battery Sizing Calc, Attachment 1 Plant Procedures Related to the Risk Management Action for the Electrical Power Systems ANO COPD-024, Revision 75, Risk Assessment Guidelines Waterford Administrative Procedure OI-037-000, Revision 321, WF3 [Waterford 3]
Operations Risk Assessment Guideline Waterford 3 Administrative Procedure OP-100-010, Revision 330, Equipment Out of Service Single Line Diagrams E-1 Sheet 1, Revision 63, Station Single Line Diagram E-4 Sheet 1, Revision 33, 4160V System Main Supply E-4 Sheet 2, Revision 1, Common Feedwater 4160V SWGR Bus A-15 E-4 Sheet 3, Revision 1, Common Feedwater 4.160 kV SWGR Bus A-19 E-5 Sheet 1, Revision 28, 4160 Volt System, Engineered Safeguard E-8 Sheet 1, Revision 32, 480V Load Centers Engineered Safeguard and Main Supply E-17 Sheet 1A, Revision 20, Green Train Vital AC and 120 Volt DC E-17 Sheet 1, Revision 55, Red Train D Vital AC and 120 Volt DC Piping and Instrumentation Diagrams M-202 Sheet 1, Revision 103, Main Steam and H.P. [High Pressure] Turbine M-204 Sheet 3, Revision 37, Emergency Feedwater M-204 Sheet 5, Revision 18, Emergency Feedwater Storage M-204 Sheet 6, Revision 23, Emergency Feedwater Pump Turbine M-206 Sheet 1, Revision 133, Steam Generator Secondary System M-206 Sheet 2, Revision 24, Main Steam Isolation Valve Operator Controls M-209 Sheet 1, Revision 116, Circulating Water, Service Water and Fire Water Intake Structure Equipment M-210 Sheet 1, Revision 155, Service Water M-213 Sheet, Revision 61, Dirty Radioactive Waste Drainage and Filtration M-213 Sheet 2, Revision 33, Laundry Waste and Containment and Auxiliary Building Sump Drainage M-231 Sheet 1, Revision 116, Makeup and Purification System M-231 Sheet 2, Revision 52, Makeup and Purification System M-231 Sheet 3, Revision 11, Makeup and Purification System M-232 Sheet 1, Revision 111, Decay Heat Removal System M-233 Sheet 1, Revision 80, Chemical Addition System M-234 Sheet 1, Revision 98, Intermediate Cooling Water
M-234 Sheet 2, Revision 46, Intermediate Cooling Water M-236 Sheet 1, Revision 97, Reactor Building Spray and Core Flooding Systems M-261 Sheet 1, Revision 60, Reactor Building H.V.A.C.
M-261 Sheet 2, Revision 46, Reactor Building H.V.A.C.
M-261 Sheet 3, Revision 35, Reactor Building H.V.A.C.
M-261 Sheet 5, Revision 0, Reactor Building H.V.A.C.
Schematic Diagrams E-99 Sheet 1, Revision 22, Engineered Safeguards 4160 V Bus A3 Lockout and Undervoltage Relays E-99 Sheet 1A, Revision 6, Engineered Safeguards 4160 V Bus A3 Lockout and Undervoltage Relays E-181 Sheet 1, Revision 7, Decay Heat Removal Pump 34A, Revision 28 E-181 Sheet 1A, Decay Heat Removal Pump 34B E-211 Sheet 1, Revision 24, Primary Makeup Pump P36A E-211 Sheet 1A, Revision 12, Primary Makeup Pump P36C E-241 Sheet 1, Revision 20, Reactor Building Spray Pump P35A E-241 Sheet 1A, Revision 7, Reactor Building Spray Pump P35B E-256 Sheet 5, Revision 2, Reactor Control Rod Drive Power Supply Control E-256 Sheet 6, Revision 2, Reactor Control Rod Drive Power to AC Breaker A E-256 Sheet 7, Revision 3, Reactor Control Rod Drive Breaker Trip E-275 Sheet 1, Revision 33, Service Water Pump A E-275 Sheet 1A, Revision 16, Service Water Pump C E-276 Sheet 1A, Revision 16, Service Water Pump B E-294 Sheet 1, Revision 20, Emergency Feedwater Pump P78 E-361 Sheet 1, Revision 13, Reactor Building Cooler Fan VSF1A E-361 Sheet 1A, Revision 5, Reactor Building Cooler Fan VSF1B E-361 Sheet 1B, Revision 6, Reactor Building Cooler Fan VSF1C E-361 Sheet 1C, Revision 4, Reactor Building Cooler Fan VSF1D E-373 Sheet 1, Revision 10, Control Room Chiller E-373 Sheet 1A, Revision 2, Control Room Chiller Piping Isometric Drawings 5-BS-1 Sheet 1, Revision 14, Reactor Building Spray 5-BS-4 Sheet 1, Revision 0, P-35A Discharge to Containment and Return to BWST 5-BS-5 Sheet 1, Revision 11, Reactor Building Spray 7-DH-12 Sheet 1, Revision 21, Engineered Safeguards Pump Suction Header 7-DH-12 Sheet 2, Revision 7, Engineered Safeguards Pump Suction Header 7-DH-13 Sheet 1, Revision 13, Decay Heat Pump Suction Header 7-DH-16 Sheet 1, Revision 17, Decay Heat Pump Suction from Reactor Building Sump 7-DH-17 Sheet 1, Revision 8, Decay Heat Pump Suction from Reactor Building 7-DH-102 Sheet 1, Revision 11, Borated Water Storage Tank Piping 7-DH-102 Sheet 2, Revision 1, Borated Water Storage Tank Piping 7-DH-102 Sheet 3, Revision 0, FLEX Decay Heat Removal Tie-in 12-CON-129 Sheet 1, Revision 13, Borated Water Storage Tank (BWST) Piping 21-LW-39 Sheet 1, Revision 11, Reactor Building Sump Drain Penetration Piping 28-CA-102 Sheet 1, Revision 15, Sodium Hydroxide Addition Piping
CA-202 Sheet 1, Revision 8, P29 Suction and Sample from T10 Sodium Hydroxide Addition Piping Miscellaneous Upper Level Documents (ULDs) 0-SYS-02, Revision 16, Offsite Power System 0-TOP-11, Revision 9, Degraded Grid Voltage EC No. 77190 1-SYS-07, Revision 4, Core Flood System 1-SYS-08, Revision 7, Emergency Feedwater Initiation and Control (EFIC) System 1-SYS-09, Revision 3, Engineered Safeguards Actuation System (ESAS) 1-SYS-10, Revision 17, Service Water System 1-SYS-12, Revision 10, Emergency Feedwater System 1-SYS-15, Revision 6, Reactor Protection System Plant Arrangement Drawings M-5 Sheet 1, Revision 45, Equipment Location - Ground Floor Plan M-46, Revision 15, Piping Area Drawing, Area 4 and 6, Reactor Auxiliary Building Plan Below Elevation 335 - 0" [inches]
M-47 Sheet 1, Revision 12, Piping Area Drawing, Area 4 Reactor Auxiliary Building Section A - A M-48 Sheet 1, Revision 13, Piping Area Drawing, Area 4 Reactor Auxiliary Building Section B - B M-64 Sheet 1, Revision 13, Piping Area Drawing, Area 6 Reactor Auxiliary Building Plan Below Grade M-66 Sheet 1, Revision 12, Piping Area Drawing, Area 6 Reactor Auxiliary Building, Section A - A M-67 Sheet 1, Revision 10, Piping Area Drawing, Area 6 Reactor Auxiliary Building Sections M-106 Sheet 1, Revision 9, Drainage - Auxiliary Building Areas 4 and 6 Plan at Elevation 317 - 0"
ML23305A092 *by email OFFICE NRR/DORL/LPL4/PM NRR/DORL/LPL4/LA* NRR/DRA/APLA/BC* NRR/DRA/APLC/BC*
NAME TWengert PBlechman RPascarelli SVasavada DATE 12/5/2023 11/2/2023 12/5/2023 12/5/2023 OFFICE NRR/DSS/STSB/BC(A)* NRR/DEX/EEEB/BC* NRR/DEX/EICB/BC(A)* NRR/DORL/LPL4/BC*
NAME SMehta WMorton MLi JRankin DATE 12/5/2023 12/6/2023 12/5/2023 12/6/2023 OFFICE NRR/DORL/LPL4/PM*
NAME TWengert DATE 12/7/2023