ML24017A160
| ML24017A160 | |
| Person / Time | |
|---|---|
| Site: | 07001113 |
| Issue date: | 01/31/2024 |
| From: | Robert Williams NRC/RGN-II/DFFI |
| To: | Huth R Global Nuclear Fuel |
| References | |
| IR 2023004 | |
| Download: ML24017A160 (16) | |
Text
Ryan Huth Facility Manager Global Nuclear Fuel - Americas, LLC P.O. Box 780, Mail Code J20 Wilmington, NC 28402
SUBJECT:
GLOBAL NUCLEAR FUEL - AMERICAS - CORE INSPECTION REPORT 07001113/2023004
Dear Ryan Huth:
On December 31, 2023, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Global Nuclear Fuel - Americas and discussed the results of this inspection with Jonathan Rohner and other members of your staff. The results of this inspection are documented in the enclosed report.
No violations of more than minor significance were identified during this inspection.
This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely, Robert E. Williams, Chief Projects Branch 1 Division of Fuel Facility Inspection Docket No. 07001113 License No. SNM-1097
Enclosure:
As stated cc w/ encl: Distribution via LISTSERVJanuary 26, 2024 Signed by Williams, Robert on 01/26/24
M24017A160 Non-Sensitive Publicly Available SUNSI Review Sensitive Non-Publicly Available
OFFICE RII: DFFI RII: DFFI RII: DFFI RII: DFFI RII: DFFI NAME G. Goff J. Grice J. Rivera T. Vukovinsky R. Williams DATE 1/17/2024 1/23/2024 1/18/2024 1/17/2024 1/26/2024
U.S. NUCLEAR REGULATORY COMMISSION Inspection Report
Docket Number: 07001113
License Number: SNM-1097
Report Number: 07001113/2023004
Enterprise Identifier: I-2023-004-0064
Licensee: Global Nuclear Fuel - Americas, LLC
Facility: Global Nuclear Fuel - Americas
Location: Wilmington, NC
Inspection Dates: October 02, 2023 to December 01, 2023
Inspectors: G. Goff, Fuel Facilities Inspector J. Grice, Fuel Facilities Inspector J. Rivera Ortiz, Sr. Fuel Facility Project Inspector T. Vukovinsky, Sr. Fuel Facility Project Inspector
Approved By: Robert E. Williams, Jr., Chief Projects Branch 1 Division of Fuel Facility Inspection
Enclosure
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a core inspection at Global Nuclear Fuel - Americas, in accordance with the fuel cycle facility inspection program. This is the NRCs program for overseeing the safe operation of licensed fuel cycle facilities. Refer to https://www.nrc.gov/materials/fuel-cycle-fac.html for more information.
List of Violations
No violations of more than minor significance were identified.
Additional Tracking Items
None.
2 INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Inspections were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2600, Fuel Cycle Facility Operational Safety and Safeguards Inspection Program. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
SAFETY OPERATIONS
88020 - Operational Safety
The inspectors evaluated selected aspects of the licensees Operational Safety program to verify compliance with selected portions of 10 CFR 70, including 70.24, 70.61, 70.62, and Chapter 11, Management Measures, of the facilitys license application, and applicable licensee procedures.
Identification of Safety Controls and Related Programs (IP Section 02.01)
The inspectors selected specific process areas for inspection based on the safety basis information of the facility, the risk/safety significance of the process areas, the description of plant changes submitted to the NRC, and past plant performance documentation. For the process areas of interest, the inspectors selected a sample of accident sequences in nuclear criticality safety, radiation safety, fire safety, and/or chemical safety based on the information provided in the integrated safety analysis (ISA) summary. The inspectors conducted a general plant tour of each major plant operating area. The process areas (or nodes) and accident sequences selected for review are listed below:
- ISA 5.1 (Node 101), UF6 Cylinder Handling o 3.4.1 UF6 Cylinder Rupture Due to Fire near Cylinder Receipt Area o 3.4.2 UF6 Cylinder Rupture Due to Fire on/near the Cylinder Storage Pads o 3.4.3 UF6 Cylinder Rupture Due to Fire near the Dry Conversion Process (DCP) Staging Pad o 3.4.4 UF6 Cylinder Rupture Due to Fire near DCP Cylinder Hallway
- ISA 5.15 (Node 601), Bundle Assembly o 3.2.1 Moderator from External Sources Spills onto Bundle Assembly Processing
- ISA 5.20 (Node 705), Scrap Pack Facility (SPF) o 3.2.1 Spill of Greater than a Safe Mass from a Container o 3.2.2 Cans are Improperly Stored in SPF Incinerator Scrap Storage Area o 3.2.3 Excessive Mass Placed in Scrap Pack Hood o 3.2.4 Excessive Mass Placed into Rework Hood o 3.2.5 Poly Bottles on Conveyor Loop are Overweight o 3.2.6 Conveyor Loop is Filled with Unapproved Containers
3 o 3.2.7 Overweight Poly Bottles are Stored in New Powder Containers (NPCs)
- ISA 5.27 (Node 806), Shipping o 3.2.1 Moderator Release onto Rod Storage Tube Rack o 3.4.1 Fire Occurs near the Rod Storage Tube Rack
Review of Safety Controls and Related Programs (IP Section 02.02)
The inspectors reviewed information related to administrative, augmented administrative, engineered, and passive items relied on for safety (IROFS) for the accident sequences selected in Section 02.01, above, including the identification of the licensees assumptions and bounding cases as they apply to each of the selected accident sequences and IROFS. This review was performed to verify that the IROFS were available and reliable to perform their intended safety functions and that the design basis assumptions were reflected in the actual conditions in the field. The specific IROFS selected for review are listed below:
- IROFS 101-08, Combustible Controls
- IROFS 601-03, Passive Rod Scan Equipment
- IROFS 601-04, Passive Rod Scan Equipment
- IROFS 601-05, Active Rod Scan Equipment
- IROFS 601-06, Active Rod Scan Equipment
- IROFS 601-07, Bundle Accumulation Equipment
- IROFS 601-08, Bundle Accumulation Equipment
- IROFS 705-01, Feed Hopper Overfill Interlock
- IROFS 705-02, Scrap Pack Combustible Control Program
- IROFS 705-06, Scrap Pack Hood
- IROFS 705-08, Rework Hood
- IROFS 705-09, Conveyor Loop
- IROFS 705-10, NPC Inner Containment Canister Assembly
- IROFS 705-11, Poly Bottle in Place Interlock
- IROFS 705-12, Poly Bottle Process Scale Interlock
- IROFS 806-01, Process Equipment Barrier (Rod Storage Tube)
- IROFS 806-02, Tube Loading and Storage Requirements
- IROFS 806-03, Rod Storage Combustible Control Program
Implementation of Safety Controls (IP Section 02.03)
For the selected safety controls listed above, the inspectors reviewed management measures to verify proper implementation in accordance with 10 CFR 70 and applicable sections of the license application. This review was performed to verify that selected safety
4 controls or IROFS were present, available, and reliable to perform their safety function and that the design basis assumptions were reflected in the actual conditions in the field. The inspectors conducted the activities described below to verify the implementation of selected safety controls. The specific documents reviewed are listed in the "Documents Reviewed" section of this inspection report.
- performed walkdowns of the rod and bundle assembly area shipping warehouse annex to observe IROFS 601-03 through 601-08 and IROFS 806-01 through 806-03
- performed walkdowns of the Cylinder Receipt, Cylinder Storage Pads 2 & 6B, DCP Staging Pad, DCP Queuing Area and Cylinder Hallway, and SPF to assess the licensee's control of transient combustibles for IROFS 101-08 and 705-02
- performed walkdowns of the SPF to assess the implementation of IROFS 705-01 through 705-03, and IROFS 705-05 through 705-12
- reviewed quantitative risk assessments (QRAs) to assess the licensee's likelihood evaluation of accident sequences in the selected processes
- reviewed criticality safety assessments (CSAs) to identify the criticality accident scenarios evaluated for the selected processes
- reviewed the process hazard analysis for Node 101 to identify the type of accidents considered for the QRAs and ISA
- reviewed calculations supporting QRA-101 related to the likelihood of a UF6 cylinder breach in a fire
- reviewed operating procedures implementing administrative IROFS 101-01, 101-05, 101-08, 705-02, and 705-03
- reviewed functional testing records for active engineered IROFS 705-01, 705-05, 705-07, 705-11, and 705-12
- reviewed calibration records for equipment relied on for IROFS 101-01, 705-07, 705-11, and 705-12
- reviewed surveillance records for passive IROFS 705-06, 705-08, 705-09, and 705-10
- interviewed operators on the implementation of functional test instructions (FTIs) and IROFS for IROFS 705-01, 705-05, 705-07, 705-11, and 705-12
- reviewed the operating procedures implementing administrative IROFS 806-03
- reviewed functional testing records for administrative IROFS 806-02
Safety Control Support Programs (IP Section 02.04)
The inspectors assessed additional management measures that support the availability and reliability of the selected IROFS to verify these were implemented in accordance with 10 CFR 70 and applicable sections of the license application. Specifically, the inspectors conducted the following:
- reviewed the following condition reports (CRs) entered in the corrective action program (CAP) for IROFS-related issues:
o CR 41451, 01/18/2023
5 o UIR FAB-0604, 01/24/2006 o CR 44365, 11/29/2023 o CR 44361, 11/29/2023
- reviewed quarterly combustible control audits of Node 806
- reviewed training material and training completion records for a sample of operators assigned to Nodes 101, 601, 705, and 806 to verify their IROFS qualifications were up to date
- reviewed a sample of audits associated with the licensee's safety program to verify these were completed in accordance with Chapter 11 of the license application and that audit findings, if any, were entered in the CAP for resolution
- reviewed staffing changes, if any, in organizational groups responsible for operational safety activities to verify compliance with the position-specific requirements in the license application
FACILITY SUPPORT
88051 - Evaluation of Exercises and Drills
The inspectors observed and evaluated the licensees graded biennial exercise conducted on October 4, 2023, as well as briefings and critiques involving both on-site and off-site participants, to verify compliance with 10 CFR 70.32(i) and the Global Nuclear Fuel Radiological Contingency and Emergency Plan. The scenario included a simulated vehicle accident involving a full 30B UF6 cylinder. The simulated accident resulted in a fire engulfing the UF6 cylinder, requiring activation of the emergency response organization (ERO), an emergency declaration, and off-site response.
Exercise Planning (IP Section 02.01)
The inspectors reviewed the emergency exercise scenario, discussed the exercise objectives with licensee personnel, observed controller meetings, and walked down the plant areas before the exercise to verify compliance with the Radiological Contingency and Emergency Plan, Emergency Plan Implementing Procedures, and 10 CFR 70.32(i). The inspectors reviewed or observed the following:
- the frequency of exercises conducted by the licensee
- the scenario as it related to testing all elements of the Emergency Plan
- pre-staging of equipment in preparation for the exercise
- duties and responsibilities for exercise personnel including controllers, evaluators, and observers
- licensee's measures to maintain confidentiality of the scenario and objectives
- the controllers' meeting for the emergency exercise
- the objectives of the exercise and the expectations from responders
- the post-drill critiques for the exercise
Exercise Execution and Emergency Plan Implementation (IP Section 02.02)
The inspectors observed the initiation of the emergency exercise, the activation of the emergency organizations, classification of the event, notification of off-site response organizations, establishment of the incident command post, implementation of field response teams, and reviewed on-site and off-site communications, press releases and
6 notifications to verify compliance with the Radiological Contingency and Emergency Plan, Emergency Plan Implementing Procedures and 10 CFR 70.32(i). The inspectors reviewed the following:
- the Emergency Director's command and control of the EO organization
- the licensees analysis of plant conditions including assessment and classification of the accident scenario
- protective action recommendations implemented by the ECC organization
- drafting of off-site notifications including a review of content and time of issuance
- on-site communication to occupational workers as it related to protective action recommendations
- press release approval and issuance
- dose assessor use of applicable Radiological Assessment System for Consequence Analysis software and use of the dose assessment, radiation survey results, environmental monitoring results during assessment of the accident scenario
- staffing of the ERO positions at the Incident Command Post
- the Incident Commander's control of the emergency response team and coordination of actions with off-site emergency responders
- occupational workers participation in evacuation and shelter-in-place protective actions and the process to conduct personnel accountability
- members of the licensees emergency response team assembly at designated assembly areas and the arrival of off-site emergency responders including fire and Emergency Medical Technicians (EMTs)
- emergency response teams actions including search and rescue activities for injured victims and assessment of the affected area
- response to emerging situations to address the exercise scenario and meet the exercise objectives
- response coordinators recommendations regarding conditions for terminating the event and restarting normal operations
- recovery and re-entry recommendations implemented by the ECC organization
Critiques, Exercise Control, and Identification and Resolution of Problems (IP Section 02.03)
The inspectors observed the staff critiques of the emergency exercise and reviewed the licensees related corrective action program entries to verify compliance with the Emergency Plan, Emergency Plan Implementing Procedures and 10 CFR 70.32(i). The inspectors reviewed or observed the following:
- critique meetings conducted by licensee's participants
- critique meetings conducted by licensee's exercise controllers to determine whether the exercise's objectives were met
- documented deficiencies identified during critiques including items planned for entry into the licensees corrective action program
7 INSPECTION RESULTS
No issues were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On October 6, 2023, the inspectors presented the biennial emergency drill observation (IP 88051) inspection results to Jonathan Rohner and other members of the licensee staff.
- On November 30, 2023, the inspectors presented the operational safety (IP 88020) inspection results to Jonathan Rohner and other members of the licensee staff.
8 DOCUMENTS REVIEWED
Inspection Type Designation Description or Title Revision Procedure (Rev.) or Date 88020 Calculations CALC-101-00-7 Likelihood Evaluation of Fire That Leads to UF6 Cylinder Rev. 1, Rupture October 2019 Corrective Action Condition Report 01/18/2023 Documents 41451 Condition Report 11/07/2023 44166 UIR FAB-0604 01/24/2006 Drawings 0042E18 TPC Loose Long Rod Storage Assembly & Details Rev. 2 Engineering CSA-806.02.100 Criticality Safety Assessment - TPC Fuel Rods Storage Rev. 1 Evaluations CSA-101.00.100 Criticality Safety Assessment - UF6 Cylinder Handling Rev. 0 CSA-407.00.100 Criticality Safety Assessment - Rod Processing Rev. 7 CSA-407.00.200 Criticality Safety Assessment - Rod Processing Appendix September 2023 CSA-705.00.100 Criticality Safety Assessment - FMO Scrap Pack Facility Rev. 6 PHA Item Process Hazard Analysis - Improper storage or arrangement September
- 4070.11 of rod trays occur 2023 PHA Item Process Hazard Analysis - External moderator spills on rod September
- 4070.16 load process equipment 2023 PHA Item Process Hazard Analysis - Rods are improperly stacked on September
- 4070.6 rod load ramps 2023 PHA Item Process Hazard Analysis - External moderator spilled or September
- 6011.5 leaks onto MAPS process equipment 2023 PHA-101 Process Hazard Analysis - Likelihood Evaluation of Fire That Rev. 6 Leads to UF6 Cylinder Rupture PHA-601 Process Hazard Analysis - ISA Reference Report for the Rev. 13 Fabrication - Bundle Assembly Node Group PHA-806 Process Hazard Analysis - ISA Reference Report for the 806 Rev. 3 Node Group QRA-101 Quantitative Risk Assessment - UF6 Cylinder Handling Rev. 12 QRA-705 Quantitative Risk Assessment - FMOX Scrap Pack Facility Rev. 12
9 Inspection Type Designation Description or Title Revision Procedure (Rev.) or Date Fire Plans FHA-BOP-01 Fire Hazard Analysis - 4.12 Balance of Plant - Shipping - Rev. 5 Node 806 Miscellaneous ISA Summary Rev. 26 Audit NRC License SNM-1097, Triennial Independent Audit-2022 12/02/2022 Audit Triennial External Nuclear Criticality Safety Audit 12/11/2022 FTI - Test # F1 Functional Test Instruction - Scrap material can mass and Rev. 4 hood mass control at the entrance gate and exit gate of Scrap Can Transfer Hood EN1100 FTI - Test # F5 Functional Test Instruction - Scrap Material can mas, hood Rev. 6 mass, and can count controls at the entrance and exit gates of rework hood EN1400 FTI - Test # F6 Functional Test Instruction - Scrap Pack Hood - Product Rev. 0 discharge valve PLCs must close discharge valve FTI 2100.00F1 Functional Testing of IROFS 705-05 Rev. 5 (Test Conducted on 12/28/22)
FTI 2100.00F5 Functional Testing of IROFS 705-07 Rev. 6 (Test Conducted on 6/21/2023)
FTI 2100.11F6 Functional Testing of IROFS 705-01/705-11/705-12 Rev. 0 (Test Conducted on 9/27/22)
FTI A for IROFS TPC Bundle Disassembly - Tube Storage Control 04/27/2021 806-02 FTI B for IROFS TPC Bundle Disassembly - Tube Storage Control 04/27/2021 806-02 NQS-2022-36 2022 GNF-A Fire and Explosion Triennial Audit 12/30/2022 QRA-601 Quantitative Risk Assessment - Fabrication - Bundle Rev. 18 Assembly QRA-806 Quantitative Risk Assessment - Shipping Rev. 4 SNMR051 Fuel Tube Storage Records October 2021
10 Inspection Type Designation Description or Title Revision Procedure (Rev.) or Date Surveillance - TPC Tube Storage Arrangement and Equipment Barriers 12/31/2022 IROFS 806-01 &
806-02 Surveillance - Rod Storage Combustible Control Program 03/29/2023 IROFS 806-03 TD 101-01 Training Document - UF6 Cylinder Skin Temperature Rev. 0 TD 101-02 Training Document - UF6 Cylinder, UF6 Cylinder Rev. 0 TD 101-05 Training Document - Visual Inspection of UF6 Cylinders Rev. 0 Following an Off-Normal Event TD 101-05 Training Document - Visual Inspection of UF6 Cylinders Rev. 0 Following an Off-Normal Event TD 101-05 Training Document - Visual Inspection of UF6 Cylinders Rev. 0 Following an Off-Normal Event TD 101-08 Training Document - UF6 Cylinder Handling Combustible Rev. 2 Control Program TD 601-03 Training Document - Passive Rod Scan Equipment - Free Rev. 0 Draining TD 601-04 Training Document - Passive Rod Scan Equipment - Safe Rev. 1 Geometry TD 601-05 Training Document - Active Rod Scan Equipment - Free Rev. 2 Draining TD 601-06 Training Document - Active Rod Scan Equipment Rev. 2 TD 601-07 Training Document - Bundle Accumulation Equipment - Free Rev. 0 Draining TD 601-08 Training Document - Bundle Accumulation Equipment - Safe Rev. 1 Geometry TD 705-01 Training Document - Feed Hopper Overfill Interlock Rev. 0 TD 705-02 Training Document - Scrap Pack Combustible Control Rev. 0 Program TD 705-03 Training Document - Incinerator Scrap Storage Area - Safe Rev. 01 Geometry TD 705-05 Training Document - FBS Control on Mass of Uranium - Rev. 0 Scrap Pack Hood
11 Inspection Type Designation Description or Title Revision Procedure (Rev.) or Date TD 705-06 Training Document - Scrap Pack Hood - Safe Geometry Rev. 0 TD 705-07 Training Document - FBS Control on Mass of Uranium - Rev. 0 Rework Hood TD 705-08 Training Document - Rework Hood - Safe Geometry Rev. 0 TD 705-09 Training Document - Conveyor Loop - Safe Geometry Rev. 0 TD 705-10 Training Document - NPC ICCA - Safe Geometry/Absorber Rev. 0 Control TD 705-11 Training Document - Poly Bottle In Place Interlock Rev. 0 TD 705-12 Training Document - Poly Bottle Process Scale Interlock Rev. 0 TD 806-01 Training Document - Process Equipment Barrier Rod Rev. 0 Storage Tube TD 806-02 Training Document - Tube Loading and Storage Rev. 1 Requirements NDE Reports TD 806-03 Training Document - Rod Storage Combustible Control Rev. 0 Program Procedures CP-06-216 Functional Test Instructions Rev. 2.1 CP-27-108 Combustible Control Program Rev. 7 OP 1050.10.100 Fuel Bundle Accumulation - General Information Rev. 2 OP 1050.72 TPC Bundle Disassembly and Rod Storage Rev. 6 OP 1080.12.000 Outside Pad Storage Rev. 0 OP 1080.12.100 Outside Pad Storage - General Information Rev. 3 OP 1080.70.202 UF6 Cylinder Dock - Abnormal Operations Rev. 4 OP 1080.70.300 UF6 Cylinder Dock - Process Information Rev. 11 OP 1338.00.100 DCP Material Handling - General Information Rev. 16 OP 1338.00.205 DCP Material Handling - UF6 Cylinder Movement Rev. 7 OP 201.00.206 DCP Vaporization - Autoclave Unloading Rev. 7 OP 2100.00.100 Scrap Pack - General Information Rev. 05 OP 2100.00.100 Scrap Pack - General Information Rev. 5 OP 2100.00.202 Scrap Pack - Scrap Pack Hood Operations Rev. 4 OP 2100.00.202 Scrap Pack Hood Operations Rev. 04 OP 2100.00.203 Scrap Pack - Rework Hood Operations Rev. 07 OP 2100.00.203 Scrap Pack - Rework Hood Operations Rev. 7
12 Inspection Type Designation Description or Title Revision Procedure (Rev.) or Date WI-06-100-22 CAA Operating Procedures Rev. 1.0 WI-06-100-26 CAA Temporary Operations Rev. 4.0 WI-16-106-02 Configuration Management Program - Nuclear Rev. 19.0 Manufacturing Operations Self-Assessments 1st Quarter Fire Safety Audit - 2023 03/31/2023 2nd Quarter Fire Safety Audit -2023 06/29/2023 3rd Quarter Fire Safety Audit - 2023 09/26/2023 NQS-2022-36 2022 GNF-A Fire and Explosion Triennial Audit 12/30/2022 Work Orders Task 3057022 IROFS 705-02 Surveillance DCP/Powder Combustible Conducted Control Program on 3/27/2023 Task 3120167 IROFS 705-06, 705-08, 705-09, 705-10 Surveillance SPF Conducted Geometry on 9/18/2023 WO 5243915 Calibration Inspection; Acc-Scale FMOX Scrap Pack Completed on 1/31/2023 WO 5243916 Annual Calibration; Calibration Inspection Acc-Scale Can Completed Hood on 1/31/2023 WO 5243917 Annual Calibration; Acc-Scale Port 1 FMOX Scrap Pack Completed on 1/31/2023 WO 5249109 Annual Calibration; Calibration Inspection; FMOX Scrap Completed Pack Non-Accountability on 2/27/2023 WO 5249347 Annual Calibration; Verification for Current Trip, Lince 2A Completed Autoclave on 6/17/2023 WO 5249348 Annual Calibration; Verification for Current Trip, Lince 2B Completed Autoclave on 6/17/2023 WO 5264049 Annual Calibration; Verification for Current Trip, VaporizationCompleted on 4/5/2023 WO 5264050 Annual Calibration; Verification for Current Trip, Line 1A Completed Autoclave on 4/5/2023 WO 5264096 Annual Calibration; Verification for Current Trip, Line 3A Completed Autoclave on 4/5/2023 WO 5264097 Annual Calibration; Verification for Current Trip, Line 3B Completed Autoclave on 4/5/2023 WO 5284104 Calibration Inspection; Acc-Scale FMOX Scrap Pack (Scale Completed
13 Inspection Type Designation Description or Title Revision Procedure (Rev.) or Date 1A) on 7/27/2023 88051 Corrective Action CR 44282 Evaluation of 2023 Biennial Exercise - Objective 5 11/13/2023 Documents CR 44283 Evaluation of 2023 Biennial Exercise - Opportunities for 11/13/2023 Improvement CR 44284 Evaluation of 2023 Biennial Exercise - Opportunities for 11/13/2023 Improvement Miscellaneous NRC Evaluated Exercise Report - Exercise Date: October 4, 11/20/2023 2023 2023 Biennial Evaluated Exercise Scenario Package 09/28/2023 Radiological Contingency and Emergency Plan (RC&EP) for 31 Global Nuclear Fuel - Americas, LLC at Wilmington, NC Procedures CP-28-114 Wilmington Site Emergency Planning 3.1 CP-28-116 Emergency Preparedness Drills and Exercises 0.3 WI-28-114-01 Emergency Director 1.1 WI-28-114-10 Emergency Response Organization (ERO) Operations 2 WI-28-114-14 Protective Actions 2.2 WI-28-114-15 Emergency Organization Activation 5.1 WI-28-114-16 Emergency Classification and Notification 4.1 WI-28-114-17 Hazard Assessment 2.3
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