ML23033A350
| ML23033A350 | |
| Person / Time | |
|---|---|
| Site: | 07003103 |
| Issue date: | 02/06/2023 |
| From: | Robert Williams NRC/RGN-II/DFFI/FFB1 |
| To: | Padgett W Louisiana Energy Services, URENCO USA |
| References | |
| 55861, 55932, 56258, EN55861, EN55932, EN56258 IR 2022004 | |
| Download: ML23033A350 (17) | |
Text
February 3, 2023 EN55861 EN55932 EN56258 Wyatt Padgett Compliance Manager Louisiana Energy Services dba Urenco USA (UUSA)
Urenco USA P.O. Box 1789 Eunice, NM 88231
SUBJECT:
URENCO USA - INTEGRATED INSPECTION REPORT 07003103/2022004
Dear Wyatt Padgett:
On December 15, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed inspections at Urenco USA and discussed the results of these inspections with Paul Lorskulsint and other members of your staff. The results of these inspections 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, Jr., Chief Projects Branch 1 Division of Fuel Facility Inspection Docket No. 07003103 License No. SNM-2010
Enclosure:
As stated cc w/ encl: Distribution via LISTSERV Signed by Williams, Robert on 02/03/23
SUNSI Review X
Non-Sensitive
Sensitive X
Publicly Available
Non-Publicly Available OFFICE RII/DFFI RII/DFFI RII/DRP RII/DFFI RII/DFFI RII/DFFI NAME T. Shewmaker L. Cooke M. Ruffin L. Pitts T. Sippel R. Williams DATE 01/12/23 01/05/23 01/09/23 01/06/23 01/12/23 01/3/23
Enclosure U.S. NUCLEAR REGULATORY COMMISSION Inspection Report Docket Number:
07003103 License Number:
SNM-2010 Report Number:
07003103/2022004 Enterprise Identifier:
I-2022-004-0059 Licensee:
Louisiana Energy Services dba Urenco USA (UUSA)
Facility:
Urenco USA Location:
Eunice, NM Inspection Dates:
December 12, 2022 to December 15, 2022 Inspectors:
L. Cooke, Fuel Facility Inspector L. Pitts, Sr. Fuel Facility Projects Inspector M. Ruffin, Project Engineer T. Shewmaker, Fuel Facility Inspector T. Sippel, Sr. Fuel Facility Projects Inspector Approved By:
Robert E. Williams, Jr., Chief Projects Branch 1 Division of Fuel Facility Inspection
2
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Urenco USA, 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 Type Issue Number Title Report Section Status WER 07003103/2022-006-00 Unexpected Contamination Discovered in Autoclave (EN55932) 88015 Closed WER 07003103/2022-010-00 Leak from Slab Tank Berm (EN56258) 88015 Closed WER 07003103/2022-003-00 Unplanned Contamination Event (EN55861) 88015 Open
3 PLANT STATUS The UUSA Facility in Eunice, New Mexico enriches uranium hexafluoride (UF6) using gas centrifuge technology. During the inspection period, normal production activities were ongoing.
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 IP 88015 - Nuclear Criticality Safety The inspectors evaluated selected aspects of the licensees Nuclear Criticality Safety (NCS) program to verify compliance with selected portions of 10 CFR 70, including 70.50, 70.61, 70.62, Chapter 5, Nuclear Criticality Safety, of the facilitys license application, and applicable licensee procedures.
Criticality Analysis (IP Section 02.01)
The inspectors interviewed licensee staff and reviewed criticality safety analyses (CSAs),
and associated documentation and calculations, to verify compliance with 10 CFR 70 and applicable sections of the license application, including portions of 5.1.2, 5.2.1.2, 5.2.1.3, 5.2.1.4, and 5.2.1.6. Specifically, the inspectors interviewed licensee staff and reviewed the following CSAs and supporting documents:
ISA-HAZ-0009, "Gaseous Effluent Vent Systems (GEVS) HAZOP and Risk Determination Analysis," Revision (Rev.) 0, Attachment C, "SEQUENCE OF EVENTS FOR A CRITICALITY IN DIFFERENT GEVS UNITS," which documents the licensee's determination that the sequence of events needed for a criticality in GEVS units is incredible
ISA-MEM-0048, "ISA Team Meeting Minutes for Gaseous Effluent Vent Systems (GEVS)," Rev. 9; which was reviewed because it contains the what-if analysis, and description of normal, credible abnormal, and non-credible accident sequences for the GEVS
NCS-CSA-007, "Nuclear Criticality Safety Analysis of GEVS Units in the SBM," Rev. 5, which was reviewed because it contained a variety of calculations and information supporting the licensee's evaluation of criticality in GEVS
NCS-CSA-025, "Criticality Safety Analysis of UUSA Process Gas Pipework (All Assays)," Rev. 3
4
NCS-CSA-030, "Nuclear Criticality Safety Analysis of Storage Cabinets,"
Rev. 3
The inspectors also reviewed recently completed nuclear safety releases (NSRs) and safe-by-design attribute verification (SBDV) forms, including:
NSR-2022-003, "WS251 Pump 31002473123," dated November 22, 2022; and SBDV-2022-0016, "WS501 Product Pump Measurements," dated August 30, 2022 Criticality Implementation (IP Section 02.02)
The inspectors selected engineered and administrative controls from the licensees integrated safety analysis (ISA) summary to verify proper implementation through a review of process and system descriptions, and plant walkdowns to verify compliance with 10 CFR 70 and applicable sections of the license application, including portions of section 5.1.1 and 5.1.2. Specifically, the inspectors interviewed licensee staff and reviewed the following controls and items relied on for safety (IROFS) associated with the GEVS:
Passive engineered safe-by-design attributes (e.g., spacing, geometry) associated with the SBM-1001 GEVS
Passive engineered safe-by-design attributes (e.g., volume) associated with pumps
Administrative control on spacing of uranium bearing components Criticality Operational Oversight (IP Section 02.03)
The inspectors assessed the NCS staffs oversight of plant operators, procedures, and operations of systems involving special nuclear material to verify compliance with 10 CFR 70 and applicable sections of the license application, including portions of sections 5.1.1, 5.1.5, and 11.3.3.1.1. Specifically, the inspectors performed the following activities:
reviewed NCS training material provided to operators and logistics personnel, including: "2021 Nuclear Safety Worker Continuing Training;" and GXNSWLP00I00ILT, "Nuclear Safety Worker," Rev. 13
interviewed licensee engineers concerning criticality hazards and control methods in GEVS units, including monitoring for long-term accumulations on the filters
observed a licensee NCS engineer conduct a weekly walkdown in the SBM-1001 and SBM-1001X process service corridor (PSC)
reviewed a sample of recent records of walkdowns, including: NCSI-22-0033, NCSI-22-0034, and NCSI-22-0035 Criticality Programmatic Oversight (IP Section 02.04)
The inspectors reviewed NCS program procedures, audits, and NCS staff qualifications records to verify compliance with 10 CFR 70 and applicable sections of the license application, including, 5.1.1, 5.1.5, 11.5. Specifically, the inspectors interviewed licensee NCS staff and reviewed the following documents:
three qualification records for licensee NCS staff who have recently completed a qualification
5
the 2022 self-assessment of the licensee's NCS program: SA-2022-001, "Nuclear Criticality Safety Programmatic Assessment (SAR) NCS IROFS Training," dated April 10, 2022
the most recent revision to licensee procedures: EG-3-3200-02, "Nuclear Criticality Safety Analysis/Evaluation," and CR-2-1000-01, "Nuclear Criticality Safety Program Description" Criticality Incident Response and Corrective Action (IP Section 02.05)
The inspectors reviewed the licensees corrective action program (CAP) to verify compliance with 10 CFR 70. Additionally, the inspectors followed-up on open items related to contamination events. Specifically, the inspectors observed activities, reviewed documents, and/or interviewed licensee staff concerning the following:
reviewed the following NCS-related CAP entries: EV 151170, EV 158403, EV 151820, EV 152997, EV 156479, EV 156490
reviewed the following contamination or spill related CAP entries, including:
EV 111023, EV 112921, EV 113877, EV 116283, EV 117238, EV 136211, EV 148894, EV 151253
walked down the liquid effluent collections and transfer system (LECTS) room FACILITY SUPPORT IP 88072 - Plant Modifications (Triennial)
The inspectors conducted an extensive review into the licensees configuration management system for plant modifications to ensure that safety-related systems and components (i.e.,
IROFS or credited safety controls) could adequately perform their intended safety function and that system changes had not adversely impacted plant safety and operability. The inspectors review focused on verifying compliance with the applicable requirements in 10 CFR 70 and ISA Summary section 3.1.8.3, Management Measures - Configuration Management.
Selection of Modifications (IP Section 02.01)
The inspectors reviewed licensing documents and discussed plant modifications in risk-significant areas/processes with the licensee. The inspectors selected the following processes for an in-depth review of historical modifications identified as Plant Modifications:
Cylinder Receipt & Dispatch Building (CRDB) GEVS
Mod-17-0073, "Autoclave GEVS IROFS10 1001-471-2A7," dated March 2017
Mod-18-0038, "Revise LES-1100-M-PID-666-001-01 to correct the volume flow in the GEVS Exhaust Stack," dated September 2018
Mod-18-0048, "Addition of Harting Connectors to the GEVS Velocity Transmitters," dated December 2018
Mod-19-0017, "CRDB 666 GEVS, Site 664 LXGEVS Prefilter Efficiency Requirements," dated June 2019
Mod-19-0054, "CRDB (1100) GEVS and HVAC Penetration Seal Design,"
dated October 2019
6
Mod-21-0034, "Abandon GEVS Smoke Detector in Place," dated November 2021 Pump Extract GEVS
Mod-16-0121, "7 Bar Test Facility Phase 2," dated November 2016
Mod-19-0031, "Ventilated Room Pump Extract GEVS Station Clarification,"
dated May 2019
Mod-19-0040, "Add Oil Filter on HF Monitor," dated August 2019
Mod-19-0049, "Remove the Bag In, Bag Out Requirements for filters from the GEVS Site Specifications," dated October 2019
Mod-20-0008, "Alpha & HF Override Switch Relocation," dated December 2020 Local Extract GEVS
Mod-16-0122, "Abandon in Place GEVS 664 Valve," dated October 2016
Mod-17-0153, "GEVS 1005-664 Camfil Carbon Filter Testing results Clarification," dated June 2017
Mod-19-0044, "Chemistry Lab Complex Additional Local Extract GEVS drop,"
dated November 2019
Mod-19-0049A, "Remove the Bag In, Bag Out Requirements for filters from the GEVS Site Specifications," dated March 2020 Design Process Review (IP Section 02.02)
For the selected modifications listed above, the inspectors reviewed the design process to verify the licensee followed the applicable configuration management requirements in the license application and 10 CFR 70. Specifically, the inspectors conducted the inspection activities listed below:
Interviewed licensee staff, performed walkdowns, and reviewed configuration management packages and supporting documentation to verify that plant modifications were developed, reviewed, classified, approved, and implemented in accordance with 10 CFR 70.72, Facility Changes and Change Process, and 70.62(d), Management Measures
Interviewed licensee staff, performed walkdowns, and reviewed the ISA, ISA Summary, and safety program information impacted by the modifications to verify compliance with 10 CFR 70.62, 10 CFR 70.72, and the baseline design criteria of 10 CFR 70.64, as applicable
Interviewed licensee staff, performed walkdowns, and reviewed configuration management packages and supporting documentation to verify that safety systems and components impacted by the modification, including interactions with other systems, would perform their intended safety function as described in the ISA and safety program documentation
Interviewed licensee staff, performed walkdowns, and reviewed design information for the selected modifications to verify that design assumptions, including Natural Phenomena Hazards (NPH) analysis and set points for instrumentation and control equipment, were supported by adequate technical basis consistent with the design bases and licensing bases of the facility
7
Interviewed licensee staff, and reviewed corrective action documents for plant modification issues, including configuration management audits, to verify compliance with the corrective action program activities
Interviewed licensee staff to verify that system/responsible engineers had an adequate understanding of their assigned systems and the impact of selected modifications on the systems function System Condition and Capability Review (IP Section 02.03)
For the selected modifications, the inspectors reviewed the system condition and tested capability to verify they were consistent with the applicable design requirements and licensing basis. Specifically, the inspectors conducted the inspection activities listed below:
interviewed engineering and chemistry staff, reviewed records, and performed system walkdowns to verify whether the modifications were adequately implemented consistent with the configuration management packages
interviewed engineering staff, reviewed records, and performed system walkdowns to verify assumptions in the ISA or safety basis applicable to the modification were valid based on the actual configuration and operation of the modified processes
interviewed operations and engineering staff, reviewed records, and performed system walkdowns to verify that administrative controls that involve operator action could be accomplished as assumed in the licensees ISA Post-Modification Testing (IP Section 02.04)
For the selected modifications, the inspectors interviewed licensee staff and reviewed post-modification testing records to determine whether the plant was in a safe configuration during post-modification testing. The inspectors reviewed the following post-modification tests to determine whether post-modification testing ensured adequate implementation of the design and safety system functionality.
Mod-19-0040, "Add Oil Filter on HF Monitor"
WO 1000436164, "1M: SBM1 HF Mon Maint," dated May 6, 2020
WO 1000436165, "1M: SBM3 HF Mon Maint," dated May 13, 2020
WO 1000436437, "1M: SBM1 HF Mon Maint," dated June 6, 2020
WO 1000436438, "1M: SBM3 HF Mon Maint," dated June 13, 2020
WO 1000436482, "1M: SBM5 HF Mon Maint," dated June 28, 2020
EN-3-3020-02, "MacGiver HF-2 Calibration," Rev. 3 Documentation Review (IP Section 02.05)
The inspectors reviewed a sample of plant documents impacted by the modifications selected for review to verify the licensee had either updated or was in the process of updating such documents to reflect the modifications in accordance with the license application requirements and 10 CFR 70.72. The inspection sample included:
CH-3-1050-01, "Chemistry Surveillance," Rev. 4, 5, and 6
EG-3-4100-02, "Plant Modifications," Rev. 24
ISA Summary, "Integrated Safety Analysis Summary," Rev. 33b
8
OP-3-0660-01, "Gaseous Effluent Vent System," Rev. 24
QAPD, "Quality Assurance Program Description," Rev. 44
RW-3-4000-02, "Startup, Operation and Shutdown of the Multi-Functional Decontamination Train," Rev. 17, 18, and 19
RW-3-5000-03, "Emptying of Chemical and NaF Traps," Rev. 7, 8, and 9
RW-3-5000-04, "Heeled, Cleaned, or Partially Filled 30B and 48Y Cylinder Component Replacement and Testing," Rev. 7, 8, and 9
SAR, "Safety Analysis Report," Rev. 49c
NEF-BD-23b, "Personal Respiratory Use for Handling Designated Uranic Material in the CRDB," Rev. 4
NEF-BD-24a, "Establishment of Airflow Away From the Worker for Handling Designated Uranic Material in the CRDB," Rev. 4
NEF-BD-24b, "Establish GEVS Flow for Sample Handling or Transfer," Rev. 4
NEF-BD-24c, "Administrative Establishment of Airflow Away from the Worker,"
Rev. 2
NEF-BD-24d, "Establish GEVS Flow for Handling of Uranic Materials in URENCO Technology Center," Rev. 1
ORM-23b-24a, "Personal Respiratory Use and Establishment of Airflow Away From the Worker for Handling Designated Uranic Material in the CRDB,"
Rev. 1
ORM-24b-46, "Chemical Lab Hood Sample Operations," Rev. 2
ORM-24c, "Administratively Control Establishment of Airflow Away from the Worker in MFDT," Rev. 2
ORM-24d-39c, "URENCO Technology Center (UTC) Fume Hood and Glovebox Operations," Rev. 1 INSPECTION RESULTS WER (Closed)
Unexpected Contamination Discovered in Autoclave (EN55932)
WER 07003103/2022-006-00 88015
==
Description:==
On June 8, 2022, the licensee reported in Event Number55932 to the NRC, that on June 7, 2022, while performing a disconnect on the 3LS1 autoclave, an operator noticed contamination on the cylinder and in the autoclave. The autoclave was posted as a contamination area and decontamination efforts continued throughout the day.
The area remained posted as a contamination area for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />; therefore, the licensee reported the event under 10 CFR 70.50(b)(1). Decontamination efforts continued until the cylinder and autoclave were clean.
The inspectors walked down the 3LS1 autoclave, interviewed licensee radiation protection (RP) staff about the event and decontamination efforts, reviewed EV151830 and the licensee's 30-Day Report, dated July 7, 2022 (Agencywide Documents Access and Management System (ADAMS) Accession Number ML22208A107), to verify that the licensee reported conservatively or as required by the regulation based on the information available at the time of the report, that RP barriers were established and decontamination activities were performed.
The inspectors did not identify any violations, therefore WER 07003103/2022-006-00, "Unexpected Contamination Discovered in Autoclave (EN55932)" is closed.
9 WER (Closed)
Leak from Slab Tank Berm (EN56258)
WER 07003103/2022-010-00 88015
==
Description:==
In EN56258 the licensee reported to the NRC, that on December 4, 2022, licensee staff discovered a spill of contaminated water on the floor of the LECTS room. A pump's seals had failed resulting in about 170 L of contaminated water from the south Slab Tank collecting in its berm. The pump was stopped and the leak was isolated when a licensee technician arrived. Some of the water, about 7 L, had leaked out of the berm into the normally non-contaminated room area.
Access to the spill area was restricted by roping the area off and posting it as a contaminated area. The area remained posted and roped off as a contaminated area for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Therefore, the spill was reported under 10 CFR 70.50(b)(1).
The inspectors reviewed EV 158739 and the licensee's 30-day follow-up report (ML22355A635), interviewed licensee staff concerning the spill, cleanup activities, and reviewed the calculations and measurements used to determine if reporting criteria were met.
The inspectors also walked down the LECTS room where the spill occurred to observed RP barriers, the status of cleanup measures and the location of the spill.
The inspectors did not identify any violations, therefore WER 07003103/2022-010-00, "Leak from Slab Tank Berm (EN56258)" is closed.
WER (Discussed)
Unplanned Contamination Event (EN55861)
WER 07003103/2022-003-00 88015
==
Description:==
In EN55861, the licensee reported the unplanned contaminated event discussed in Non-Cited Violation (NCV) 7003103/2022001-01, Failure to make a required report. (See NRC Inspection Report 07003103/2022001, dated April 29, 2022 (ML22119A057)). On May 17, 2022, the licensee updated the report to include the results of an extent of condition review that the licensee performed. This extent of condition revealed nine historical examples of unplanned contamination events that resulted in expansions of Contaminated Areas that were not previously reported under 10 CFR 70.50(b)(1).
The licensee identified that these had occurred on March 3, 2016 (as documented in CAP entry EV 111023), April 14, 2016 (EV 112921), August 4, 2016 (EV 113877), December 7, 2016 (EV 116283), February 23, 2017 (EV 117238), November 24, 2019 (EV 136211),
November 29, 2021 (EV 148894), February 28, 2022 (EV 149668), and April 14, 2022 (EV 151253). The licensee additionally reported that these events had been corrected around the time that they were identified.
During this inspection the inspectors reviewed the above CAP entries, the licensees 30-day follow-up report (ML22145A138), interviewed licensee RP staff concerning the cleanup of these events, and walked down selected areas where the events had occurred.
However, in letters dated June 13, 2022 (ML22172A014), and August 3, 2022 (ML22221A004), the licensee denied that Violation NCV 7003103/2022001-01 occurred as stated, and provided additional information concerning the basis for the dispute, respectively.
WER 07003103/2022-003-00, Unplanned Contamination Event (EN55861), will remain open pending resolution of the disputed violation.
10 EXIT MEETINGS AND DEBRIEFS The inspectors verified no proprietary information was retained or documented in this report.
On December 15, 2022, the inspectors presented the nuclear criticality safety and plant modifications (triennial) inspection results to Paul Lorskulsint, Chief Nuclear Officer and other members of the licensee staff.
11 DOCUMENTS REVIEWED Inspection Procedure Type Designation Description or Title Revision or Date 88015 Corrective Action Documents EV 111023, EV 112921, EV 113877, EV 116283, EV 117238, EV 136211, EV 148894, EV 151253 EVs related to past spills and contamination events...
Various 88015 Corrective Action Documents EV 151170, EV 158403, EV 151820, EV 152997, EV 156479, EV 156490 NCS-related corrective action program entries Various 88015 Corrective Action Documents Resulting from Inspection EV 158866 88015 Engineering Evaluations ISA-HAZ-0009 GEVS HAZOP and Risk Determination Analysis ATTACHMENT C - SEQUENCE OF EVENTS FOR A CRITICALITY IN DIFFERENT GEVS UNITS Rev. 0 88015 Engineering Evaluations ISA-MEM-0048 ISA Team Meeting Minutes for Gaseous Effluent Vent Systems (GEVS)
Rev. 9 88015 Engineering Evaluations NCS-CSA-007 Nuclear Criticality Safety Analysis of GEVS Units in the SBM Rev. 5 88015 Engineering Evaluations NCS-CSA-025 Criticality Safety Analysis of UUSA Process Gas Pipework (All Assays)
Rev. 3 88015 Engineering Evaluations NCS-CSA-030 Nuclear Criticality Safety Analysis of Storage Cabinets Rev. 3 88015 Engineering Evaluations NSR-2022-001 IMU-200 On-Line Mass Spectrometers (System 429) 07/15/2022 88015 Engineering Evaluations NSR-2022-003 WS251 Pump 31002473123 11/22/2022 88015 Engineering SBDV-2022-0013 WS251 Product Pump Measurements 08/30/2022
12 Inspection Procedure Type Designation Description or Title Revision or Date Evaluations 88015 Engineering Evaluations SBDV-2022-0014 WS251 Product Pump Measurements in-situ 08/30/2022 88015 Engineering Evaluations SBDV-2022-0016 WS501 Product Pump Measurements 08/30/2022 88015 Miscellaneous 2021 Nuclear Safety Worker Continuing Training Final Slides 09/13/2021 88015 Miscellaneous E-NCS-QG Nuclear Criticality Safety (NCS) Engineer Qualification Guide for James B.
Completed 09/22/2022 88015 Miscellaneous E-NCS-SS-QG Nuclear Criticality Safety (NCS) Support Staff Qualification Guide for James B.
Completed 06/28/2022 88015 Miscellaneous E-NCS-SS-QG Nuclear Criticality Safety (NCS) Support Staff Qualification Guide for Josh O.
12/08/2022 88015 Miscellaneous GET CBT URENCO USA General Employee Training 08/24/2022 88015 Miscellaneous GXNSWLP00I00ILT Nuclear Safety Worker Rev. 13 88015 Procedures CR-2-1000-01 Nuclear Criticality Safety Program Description Rev. 11, 08/17/2022 88015 Procedures EG-3-3200-02 Nuclear Criticality Safety Analysis/Evaluation Rev. 15, 08/18/2022 88015 Procedures EG-4-2100-05 Seismic Design Reference Manual Rev. 6 88015 Self-Assessments NCSI-22-0030 SBM1001 - PSC 08/04/2022 88015 Self-Assessments NCSI-22-0033 LECTS Room 08/23/2022 88015 Self-Assessments NCSI-22-0034 SBM1005 - PSC 08/30/2022 88015 Self-Assessments NCSI-22-0035 Chemistry Lab Complex 09/02/2022 88015 Self-Assessments SA-2022-001 Nuclear Criticality Safety Programmatic Assessment (SAR)
NCS IROFS Training 04/10/2022 88072 Corrective Action Documents
- EV156313, EV137576,
- EV156393, EV156431, EVs related to GEVS issues Various
13 Inspection Procedure Type Designation Description or Title Revision or Date
- EV158273, EV158514, 88072 Corrective Action Documents Resulting from Inspection EV 158871, EV 158872, EV 158893 88072 Drawings LES-1001-P-PID-662-001-01 Separation Building Module Piping and Instrument Diagram Gaseous Effluent Vent System (GEVS) Pump Extract Rev. 4 88072 Drawings LES-1001-P-PID-662-001-03-4 Piping and Instrumentation Diagram Seperations Building Module GEVS Pumped Extract Safe by Design Sheet 3 Rev. 4 88072 Drawings LES-1003-P-PID-662-001-06 Piping and Instrumentation Diagram Separations Building Module 1003 GEVS Distribution Pumped Extract GEVS Sheet 6 Rev. 2 88072 Drawings LES-1100-M-PID-66-001-01-7 Piping & Instrument Diagram Cylinder Receipt & Dispatch Building Gaseous Effluent Ventilation System Fume Hood Rev. 7 88072 Drawings LES-1100-P-P-001-01-1 Piping Cylinder Receipt & Dispatch Building First Floor Plan Rev. 1 88072 Drawings LES-1100-P-PID-626-001-01-0 Piping and Instrument Diagram Cylinder Receipt &
Dispatch Building 7 Bar Test Rig 0
88072 Drawings LES-1100-P-PID-662-001-03-0 Piping and Instrumentation Diagram Cylinder Receipt and Dispatch Building 7 Bar Test Facility Sheet 1 Rev. 0 88072 Miscellaneous NEF-SDD-100-664 System Description For Local Extract Gaseous Effluent Ventilation System Rev. 1 88072 Miscellaneous NEF-SDD-1100-666 System Description For Cylinder Receipt and Dispatch Building Gaseous Effluent Ventilation System Rev. 0 88072 Procedures CH-3-1050-01 Chemistry Surveillance Rev. 4, 5, 6 88072 Procedures EG-3-4100-02 Plant Modifications Rev. 24 88072 Procedures ISA Summary Integrated Safety Analysis Summary Rev. 33b 88072 Procedures OP-3-0660-01 Gaseous Effluent Vent System Rev. 24 88072 Procedures QAPD Quality Assurance Program Description Rev. 44 88072 Procedures RW-3-4000-02 Startup, Operation and Shutdown of the Multi-Functional Decontamination Train Rev. 17, 18, 19 88072 Procedures RW-3-5000-03 Emptying of Chemical and NaF Traps Rev. 7, 8, 9 88072 Procedures RW-3-5000-04 Heeled, Cleaned, or Partially Filled 30B and 48Y Cylinder Rev. 7, 8, 9
14 Inspection Procedure Type Designation Description or Title Revision or Date Component Replacement and Testing 88072 Procedures SAR Safety Analysis Report Rev. 49c 88072 Work Orders EG-4-4100-06 Engineering Support Request for GEVs 664-2UI Multiple High Pressure Alarms Rev. 1 88072 Work Orders WO 1000228964 Install 7 Bar Test Facility Components 12/23/2015 88072 Work Orders WO 1000398505 CRDB NCR 2019-131863 GEVS Station Rework 07/03/2019 88072 Work Orders WO 1000530511 Monthly MFDT OPS and IROFS 57a/b Samples 04/01/2022 88072 Work Orders WO# 1000396596 Work Order for GEVs 664-2UI Multiple High Pressure Alarms 09/23/2019