ML24107B135
| ML24107B135 | |
| Person / Time | |
|---|---|
| Site: | 07003103 |
| Issue date: | 04/17/2024 |
| From: | Robert Williams NRC/RGN-II/DFFI |
| To: | Kirkpatrick J Louisiana Energy Services, URENCO USA |
| References | |
| EN56840 IR 2024001 | |
| Download: ML24107B135 (21) | |
Text
EN56840 John Kirkpatrick Managing Director UUSA (Acting)
Louisiana Energy Services (LES) dba URENCO USA (UUSA)
URENCO USA P.O. Box 1789 Eunice, NM 88231
SUBJECT:
URENCO USA - INTEGRATED INSPECTION REPORT 07003103/2024001
Dear John Kirkpatrick:
On March 21, 2024, the U.S. Nuclear Regulatory Commission (NRC) completed inspections at URENCO USA and discussed the results of these inspections with you 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 these inspections.
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 April 17, 2024 Signed by Williams, Robert on 04/17/24
Enclosure U.S. NUCLEAR REGULATORY COMMISSION Inspection Report Docket Number:
07003103 License Number:
SNM-2010 Report Number:
07003103/2024001 Enterprise Identifier:
I-2024-001-0080 Licensee:
Louisiana Energy Services (LES) dba URENCO USA (UUSA)
Facility:
URENCO USA Location:
Eunice, NM Inspection Dates:
January 1 - March 31, 2024 Inspectors:
G. Goff, Fuel Facility Inspector T. Shewmaker, Fuel Facility Inspector P. Startz, Fuel Facility Inspector C. Taylor, Sr. Fuel Facility Project 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 07003103/2023-005-00 ALERT - Seismic Event Felt Onsite (EN56840) 88020 Closed
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 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 70.61, 70.62, and Chapter 11, Management Measures, of the 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 and 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 and accident sequences selected for review are listed below:
VR1-3, Ventilated Room (Respiratory Protection and direction of airflow away from worker during positive pressure testing of UF6 cylinder)
VR2-1, Ventilated Room (Respiratory Protection and direction of airflow away from worker during loss of containment of a chemical trap)
VR2-2, Ventilated Room (Respiratory Protection and direction of airflow away from worker during loss of containment of a dump trap)
VR2-9, Ventilated Room (Respiratory Protection and direction of airflow away from worker during loss of containment of a vacuum filter in the Ventilated Room during vacuum filter change out)
VR2-11, Ventilated Room (Respiratory Protection and direction of airflow away from worker during loss of containment of a chemical trap containing carbon due to deflagration of the contents of the trap into the Ventilated Room)
4 EC7-1, UF6 Feed System (Determine assay of cylinder contents prior to installation at feed station)
EC7-2, UF6 Feed System (Determine assay of cylinder contents prior connection at feed station for 30B transfer)
UF1-1, UF6 Feed System (Testing heater trip values to prevent rupture of cylinders)
UF2-3, UF6 Feed System (Restriction of UF6 flow upon failure of vacuum pump)
LW1-4, Liquid Effluent Collection and Transfer System (LECTS) (Limit enrichment level in LECTS Bulk Storage Tanks, Release Tank or Tote) additionally, the inspectors walked down the UF6 Feed System, Ventilated Room and LECTS areas Review of Safety Controls and Related Programs (IP Section 02.02)
The inspectors reviewed information related to administrative, engineered, and passive safety controls or items relied on for safety (IROFS) for the accident sequences selected above, including the identification of the licensees assumptions and bounding cases as they apply to each of the selected accident sequences, safety controls, or IROFS. This review was performed to verify that the controls or 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 safety controls selected for review are listed below:
IROFS4, an active engineered control (AEC) for automatic trip of feed station heater to ensure cylinder integrity IROFS5, an AEC for automatic trip of feed station heater to ensure cylinder integrity IROFS53a, an administrative control to ensure feed cylinder contents are correct prior placing them into production IROFS53b, an administrative control to ensure feed cylinder contents are correct prior placing them into production IROFS55a, an administrative control to limit enrichment levels prior to transfer to Bulk Storage Tanks, Release Tank or Tote IROFS55b, an administrative control to limit enrichment levels prior to transfer to Bulk Storage Tanks, Release Tank or Tote IROFS60, an administrative control to establish an inert gas environment over trap opening to prevent deflagration IROFS61, an administrative control to purge trap with inert gas prior to trap opening to prevent deflagration IROFS62, an administrative control to verify lockout prior to connection of a cylinder for feed to 30B transfer IROFS63, an administrative control to verify lockout prior to connection of a cylinder for feed to 30B transfer IROFS23b, an administrative control on the use of personal respiratory protection to ensure that inhalation of uranic material consequence is low IROFS24a, an administrative control to establish airflow away from the worker to ensure that inhalation of uranic material consequence is low IROFSC21, a passive engineered control for flow restriction to ensure in the event of a release that worker consequences of inhalation are low
5 Implementation of Safety Controls (IP Section 02.03)
For the 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 the selected safety 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 following activities to verify the implementation of selected safety controls:
observed a walk-through of IROFS55a/b LECTS sampling observed IROFS4 and IROFS5 surveillances, performed under work order 1000631474 observed feed cylinder connection and IROFS53a/b implementation, including interviewing plant performance staff regarding assay assignment sheets and documentation interviewed a Shift Manager regarding IROFS53a/b, IROFS62, IROFS63, IROFS23b, IROFS24a, IROFS60 and IROFS61 interviewed Maintenance staff regarding IROFSC21 qualifications and installation work interviewed quality control (QC) staff regarding QC hold points in the IROFSC21 installation work orders reviewed procedures, operating requirements manuals (ORMs), and boundary definition documents for the IROFS listed in section 2.02 reviewed RW-3-5000-03, "Emptying of Chemical and NaF Traps," Revision (Rev.) 11 for implementation of IROFS23b and IROFS24a reviewed chemistry qualifications for IMU200 on-line Mass Spectrometer (MS), Nexion ICP-MS, Nu Plasma HR-ICP MS and the Optima ICP-OES for support of IROFS53a/b and IROFS55a/b reviewed condition reports regarding failed or degraded IROFS and associated compensatory measures interviewed radiation protection (RP) technicians on maintenance and testing of respiratory protection equipment being used during UF6 cylinder pressure testing, chemical and dump trap activities to support IROFS23b and IROFS24a interviewed maintenance staff on the operation, daily testing, and maintenance of the Ventilated Room and LECTS areas interviewed three Pre-Build Pump Technicians, assigned to the Ventilated Room, for their knowledge of radiation and chemical safety hazards while performing work duties as trained Radiation Protection Task Qualified Individuals (RPTQIs); also discussed their understanding of the implementation of IROFS23b and IROFS24a during the course of their work activities reviewed OP-3-1000-27, "Infrequently Performed Test or Evolution (IPTE),"
Rev. 6; as it applies to accident sequence VR2-2 for IROFS23b and IROFS24a, and inactive IROFS and IPTE activities observed RP technician inspections of powered air purifying respirators, hood type and helmet type reviewed Radiation Work Permits (RWPs)23-104 and 24-104, "Work Evolutions to Remove and Decontaminate Chemical Traps," for calendar years 2023 and 2024
6 Safety Control Support Programs (IP Section 02.04)
The inspectors assessed additional management measures that support the availability and reliability of the selected safety controls to verify these were implemented in accordance with 10 CFR 70 and applicable sections of the license application. Additionally, the inspectors followed-up on WER 07003103/2023-005-00, "ALERT - Seismic Event Felt on Site."
Specifically, the inspectors reviewed:
the 2023 and 2024 audit schedules 2023-A-08-013, "NQA-1 Compliance Audit of Administrative IROFS" 2023-A-09-015, "UUSA Quality Assurance Program Audit" SA-2023-012, "Self-Assessment Plant Modifications" ISA-IAD-0017, "Assessment of Releases from Product Vent or Feed Purification Chemical Trap and Pump Sets due to Blockage and Seal Failure" list of qualified operations personnel against the operations watch bill for 2/12/24 and 2/13/24 IROFS qualification cards including a list of IROFS qualified personnel Apparent Cause documents associated with EV 152996 OP-3-0490-10-F-1, "Setup, Calibration and Performance Check of the Ortec Micro UF6 Meter;" for SN 17074753 (12/1/23 calibration and performance checks from 12/1/23 to 2/7/24) and SN 17264052 (12/2/23 calibration and performance checks from 3/26/23 to 2/3/24) used to support IROFS53a/b OP-3-0410-01-F-1, "IROFS53a/b Data Verification Form" for the third and fourth quarters of 2023 MA-3-3400-04/05, surveillances for IROFS4/5 Station Heater Fan High Temperature Trip - RTD and Thermocouples Work Orders for LECTS sampling IROFS55a/b OP-3-0410-02-F-3, "IRORFS62/63 Hotbox Leak Checks," for dates 4/5/23, 3/16/22 and 3/18/21 ESOMS documentation on verification of lockout and leak check in periodicity for IROFS62 and IROFS63 pump technician refresher qualification cards for operations (Course ID:
OSIROFSQCOO100) and logistics (Course ID: LOIROFSQC00) dated 11/22/22 and 11/29/22 for IROFS23b, IROFS24a, IROFS61, and IROFS60 EV 163215 that discusses potential deflagration hazard in the ventilated room for applicability to IROFS23b and IROFS24a, which was initially identified and discussed in EV 163099 EV 162743 and corrective actions, including seismic walkdowns, event termination notice, event report and EN56840 EV 162288 and corrective actions associated with IROFS EVs evaluated for potential negative trend EV 163215, "Operations Standing Order for Ventilated Room" and AC 178233 associated with work activities for IROFS23b and IROFS24a AD-3-1000-10, "Change Process Management" for procedures changes to RW-3-2001-01, "LECTS Operations," Rev. 17 to Rev. 18 and the associated configuration package ORM-23b-24a, "Personal Respiratory Use of Establishment of Airflow Away from the Worker for Handling Designated Uranic Material in the CRDB,"
Rev. 1; for IROFS23b and IROFS24a
7 RADIOLOGICAL CONTROLS IP 88030 - Radiation Protection The inspectors evaluated selected aspects of the licensees RP and radiological waste (RW) programs to verify compliance with selected portions of 10 CFR 19, 20, 61, and 70; Chapter 4, Radiation Protection, of the license application; and applicable licensee procedures.
Radiation Protection Program Review (IP Sections 02.01, 02.02, 02.03, 02.23)
The inspectors interviewed licensee staff and reviewed licensee procedures and other documentation related to the implementation of the RP and RW programs to verify compliance with 10 CFR 20.1101(a), 20.1101(b), 20.1101(c), and 20.2102; 10 CFR 61.55 -
56; commitments to the as low as reasonably achievable (ALARA) program, and sections 4.1 and 4.2 of the license application. Specifically, the inspectors:
Radiation Protection/Waste Program Implementation and Procedures (IP Section 02.01 & 02.03) reviewed numerous procedure revisions (refer to the "Documents Reviewed" section) to verify that changes did not diminish safety reviewed RP-2-1000-01, "Radiation Protection Program," Rev. 12 and RW 1000-01, "Waste Acceptance Program," Rev. 9 reviewed the licensee's latest RP organization structure reviewed the qualification requirements and resume of the current RP manager reviewed the qualification requirements and resumes for newer RP technicians reviewed the qualification requirements and resumes for RW technicians Radiation Protection/Waste Program Review and ALARA (IP Section 02.02 & 02.23) observed an operator shift meeting regarding the transfer of uranium hexafluoride (UF6) from 48Y cylinders observed Plan-of-the-Day meetings and noted that communications included radiological safety and the ALARA concept observed a Radiation Safety Committee (RSC) meeting and noted that the ALARA concept was included in the discussions walked down the small component decontamination train (SCDT) and the multi-function decontamination train (MFDT) interviewed licensee staff on:
o how the RP/RW programs are independent of production activities o
the required minimum air flow rate in gloveboxes, hoods, and other enclosures o
radiological posting compliance with 10 CFR 20.1904 and 20.1905 reviewed the 2022 ALARA Program Review reviewed Safety Review Committee (SRC) meeting minutes (refer to the "Documents Reviewed" section) reviewed the following procedures:
o RP-2-1000-02, "ALARA Program," Rev. 8 o
RP-3-1000-01, "ALARA Engineering and TEDE ALARA Evaluation,"
Rev. 10
8 o
RP-3-1000-04, "Radiation Safety Committee," Rev. 1 o
RP-3-1000-05, "Annual ALARA Report," Rev. 1 o
RW-3-1000-01, "Waste Management," Rev. 11 o
RW-3-1000-09, "Radioactive Waste Container Setup, Handling and Disposition," Rev. 21 o
RW-3-2000-01, "LECTS Operations," Rev. 18 reviewed the following audits/assessments:
o 2022-A-12-023, "Report for UUSA Louisiana Energy Services, LLC, Radiation Protection and ALARA, NQA-1 Audit," dated February 3, 2022 o
SA-2022-004, "Pump Rebuild and Recycling Self-Assessment of IROFS/BDD/ORM Procedure Alignment and Accuracy," dated August 2022 o
2023-A-04-006, "Report for UUSA Louisiana Energy Services, LLC, Waste Handling, NQA-1 Audit," dated May 8, 2023 o
SA-2023-004, "2023 Radiation Protection Self-Assessment," dated June 2023 Training (IP Section 02.04)
The inspectors interviewed licensee staff and reviewed RP and RW related training records and training material to verify compliance with 10 CFR 19.12, 19.13, 70.61(f)(2), and section 4.5 of the license application. Specifically, the inspectors:
interviewed the licensee training point of contact and reviewed the training curriculum/qualification card for a RP technician, a RPTQI, and a RW technician reviewed the listing of qualified RP technicians, RPTQIs, and RW technicians reviewed the qualification and training records for the RP manager, an RP technician, a RPTQI technician, and a RW technician Safety-Significant Events (IP Section 02.05)
The inspectors reviewed the licensees review of safety-significant events for RP and RW related corrective action program (CAP) entries to verify compliance with 10 CFR 20.2201, 20.2202, 20.2202(a), 20.2202(b), 20.2203, 70.74, Part 70 Appendix A, as applicable, and applicable sections of the license application. Specifically, the inspectors:
reviewed CAP entries, including:
o EV 164388, "Leak from Overhead Pipework in the LECTS Room,"
dated March 5, 2024 o
EV 164567, "Personnel monitored above 5000 DPM - possible contamination, follow-up found no contamination, possible radon,"
dated March 18, 2024 reviewed work order (WO) 1000652883 - CRDB 1100-681 LECTS Room Leak, standard RWP 24-110, LOTO, scaffolding, temporary spill catch containment under valve 1100-681-1A82 (03/06/2023)
9 Radiation Exposure Controls (IP Sections 02.06, 02.18)
The inspectors reviewed radiological work permits and, for keeping exposures ALARA, observed engineering controls for limiting the concentration of airborne radioactive material by controlling the air flow from areas of lesser contamination to areas of higher contamination to verify compliance with 10 CFR 20.1101(b), 20.1701, 20.1702 and sections 4.4.1, 4.6, and 4.8 of the license application. Specifically, the inspectors:
observed that chemical hoods and gloveboxes were maintained at a slightly negative air flow compared to the air flow outside of these containment units walked down the gaseous effluent ventilation system (GEVS) for the Cylinder Receipt and Dispatch Building (CRDB) and Separations Building Module (SBMs) and observed the flow was through banks of pre-filters and high efficiency particulate air (HEPA) filters prior to stack discharge walked down the storage area for respiratory protection and verified that all cartridges were National Institute for Occupational Safety and Health (NIOSH)
-approved respirator cartridges walked down the cylinder yard, which included the observation of a wall that had been constructed around cylinders as a barrier for ALARA purposes interviewed the licensee regarding the minimum air flow rates through enclosures and acceptable differential pressures across HEPA filters and what actions would be taken if either were outside of allowable limits Instrument Calibration and Surveys (IP Sections 02.07, 02.08, 02.14, 02.15)
The inspectors reviewed licensees procedures and documentation for RP instrument calibration, radiation surveys, contamination surveys; observed use of radiation detecting instruments and equipment; and interviewed licensee staff to verify compliance with 10 CFR 20.1501(a) & (c) and 70.24, 20.1902, 20.2103 and sections 4.7, 4.8.1.2, 4.8.4, and 4.8.5.1 of the license application. Specifically, the inspectors:
Instrument and Equipment/Calibration (IP Sections 02.07 & 02.08) observed calibration stickers and performance response on whole-body contamination monitors and hand-and-foot monitors observed calibration stickers and performance checks for alpha, beta, and gamma survey meters, a neutron detector, and Tennelec counters observed usage of whole-body contamination monitors and hand-and-foot monitors by licensee personnel reviewed records for criticality accident alarm system (CAAS) detectors and observed the source used for testing/calibration reviewed the following WOs:
o 1000585793 - Criticality Alarm System (08/20/2023) o 1000631530 - Alpha Monitor (ABPM 201 S Calibration)
(03/20/2024) reviewed calibration records for alpha, beta, and gamma survey meters, and a neutron detector reviewed the database and status for RP instruments
10 Radiation Surveys & Contamination Control (IP Sections 02.14 & 02.15) observed contamination surveys performed on 48Y cylinders and noted that results were well-below the site action limits (IROFS 30 A, B, & C) observed the collection and processing of fixed air monitor filters and noted that all results were below site action limits observed air filter processing on Tennelec counters reviewed procedure RP-3-2000-04, "Radiation and Contamination Surveys," Rev. 16 reviewed procedure RP-3-2000-07, "Contaminated Individual Response," Rev. 14 reviewed radiation surveys related to the following areas:
o CRDB o
SBM 1001 o
SBM 1003 o
SBM 1005 reviewed radiation and contamination survey logs from 2022 and 2023 Postings and Labeling (IP Sections 02.09, 02.10, 02.16)
The inspectors observed the posting of radiation areas, radioactive material storage areas, and the labeling of packages and containers with radioactive material to verify compliance with 10 CFR 20.1902, 20.1903, 20.1905, and section 4.7.3 of the license application.
Specifically, the inspectors:
Posting/Container Labeling (IP Sections 02.09 & 02.10) observed postings for containers in the CRDB and SBMs observed the exemption to labeling each container that may contain radioactive material as per 10 CFR 20.1905 observed signage with the wording "Caution Radioactive Material" with the proper color scheme and radiation symbol (trefoil) in areas were special nuclear material (SNM) was handled, processed, or stored observed proper labeling of full and empty 48Y containers reviewed procedure RP-3-2000-03, "Labeling of Radioactive Material," Rev. 7 Sealed Sources (IP Section 02.16) observed the storage room for sealed and unsealed sources observed the sealed source used for the criticality detector tests Posting of Notices (IP Section 02.11)
The inspectors observed the Posting of Notices to verify compliance with 10 CFR 19.11.
Specifically, the inspectors:
observed the posting of NRC Form 3 in the main security check-in/check-out area for the site
11 Access Control (IP Section 02.12)
The inspectors observed the licensees access control measures for radiation areas to verify compliance with section 4.7.2 of the license application. Specifically, the inspectors:
observed whether access to radiation areas were posted with signage bearing the radiation trefoil and wording, "CAUTION - RADIATION AREA" - in magenta lettering on a yellow background observed the usage of yellow and magenta rope to denote container storage areas in the CRDB observed the posting of contamination areas with yellow and magenta rope or tape and signage in the SBMs and chemistry lab observed reading and signing the appropriate RWP as required prior to entry into a radiation area observed that access for a licensee employee was computer-controlled at the entry point of the CRDB reviewed procedure RP-3-2000-02, "Radiological Postings and Access Controls," Rev. 1 Licensed Material Control (IP Section 02.13)
The inspectors observed the licensees measures to control and maintain constant surveillance of licensed material not in storage to verify compliance with 10 CFR 20.1802.
Specifically, the inspectors:
observed that SNM was stored in labeled containers behind yellow/magenta rope with proper radiological postings in the following areas:
o CRDB o
SBM 1001 o
SBM 1003 o
SBM 1005 Dose Assessment Program (IP Sections 02.17, 02.22)
The inspectors interviewed licensee staff and reviewed records and calculations related to the licenses assessment and assignment of doses to workers to verify compliance with 10 CFR 20.1201, 20.1202, 20.1204, 20.1502(b), 20.2104, 20.2106, and section 4.2 of the license application. Specifically, the inspectors:
interviewed the licensee person in charge of dose records and assessment reviewed the ALARA report for highest dose to an individual to verify that the dose was below federal regulations and site action limits reviewed electronic records of the highest internal, external, and total doses over the last eight calendar quarters to verify that doses were below federal regulations and site action levels Dosimetry Program (IP Sections 02.19, 02.20, 02.21)
The inspectors interviewed licensee staff and reviewed the implementation and documentation of the internal and external dosimetry programs including bioassay, whole-
12 body counting, and use of dosimetry in the field to verify compliance with 10 CFR 20.1502(a), 20.1502(b), 10 CFR 20.2103(b)(3) and section 4.7 of the license application.
Specifically, the inspectors:
Bioassay Program & Whole-Body Counting (IP Section 02.19 & 02.20) interviewed licensee staff regarding the respirator protection program and the bioassay program reviewed the following procedures:
o RP-2-4000-01, "Respiratory Protection Program," Rev. 7 o
RP-3-3000-08, "Bioassay," Rev. 9 o
RP-3-4000-01, "Respiratory Protection," Rev. 9 Dosimetry (IP Section 02.21) interviewed licensee staff about the occupational doses within the last two years and noted that the highest dose to a worker in 2023 was 254 mrem, which was below the site action limit reviewed the accreditation records to verify that the vendor that processes the licensee's thermoluminescent dosimetry is accredited by the National Voluntary Laboratory Accreditation Program reviewed procedure RP-3-3000-06, "External Dosimetry Program," Rev. 14 INSPECTION RESULTS WER (Closed)
ALERT - Seismic Event Felt Onsite (EN56840)
WER 07003103/2023-005-00 88020
==
Description:==
On November 8, 2023, the licensee reported an alert at 0337 Mountain Standard Time (MST) for a seismic event detected near the facility (EN56840). A 5.2 magnitude earthquake occurred in western Texas with an epicenter 36.7 km west-southwest of Mentone, Texas. The licensee reported that no radioactive releases had occurred, no structural damage to equipment or the facility was detected, and no protective actions were recommended to the surrounding public. The report was made in accordance with 10 CFR 70.50(c)(1).
The inspectors interviewed licensee staff, including the control room operators on shift November 8, reviewed the licensee's CAP entry (EV 162734, "Alert Declaration Seismic Event"), reviewed the licensee's Emergency Plan implementing procedures for timely notification to local authorities, state and federal agencies, Earthquake Response Procedure, OP-3-2000-04-F-1, and the results of the Seismic Damage Walkdowns for the Separation Building Modules and vital equipment, the licensee's 60-day report (Agencywide Documents Access and Management System (ADAMS) Accession No.: ML23353A116, ML23353A117).
No violations were identified.
This closes WER 07003103/2023-005-00, "ALERT - Seismic Event Felt Onsite (EN56840)."
13 EXIT MEETINGS AND DEBRIEFS The inspectors verified no proprietary information was retained or documented in this report.
On February 15, 2024, the inspectors presented the operational safety inspection results to Karen Fili and other members of the licensee staff.
On March 21, 2024, the inspectors presented the radiation protection inspection results to John Kirkpatrick and other members of the licensee staff.
14 DOCUMENTS REVIEWED Inspection Procedure Type Designation Description or Title Revision or Date Corrective Action Documents
- EV152996, EV163210,
- EV161413, EV161636,
- EV163215, EV14970,
- EV163099, EV152996,
- EV162743, EV162288 Operational Safety related CAP entries Various 32-2400503 LES, Attachment J ISA Consequence Assessments for Airborne Releases Attachment J: Miscellaneous Accident Scenarios 10/22/2021 Engineering Evaluations ISA-IAD-0017 Assessment of Releases from Product Vent or Feed N/A Purification Chemical Trap and Pump Sets due to Blockage and Seal Failure (with Supplemental Assessment for Tails Evacuation Pump Trap Set) 02/18/2015 Ongoing Negative Trend in Radiological Practices 08/03/2023 32-2400503 LES Attachment J ISA Consequences Assessments for Airborne Releases Rev. 7 CC-EG-2014-0150 Removal of IROFS C21 from Tails Evacuation Pump/Chemical Trap Set in all SBMs Rev. 0 ISA-IAD-0017 Assessment of Releases from Product Vent or Feed Purification Chemical Trap and Pump Sets due to Blockage and Seal Failure (with Supplemental Assessment for Tails Evacuation Pump Trap Set)
Rev. 1 LOIROFSQCOO Qualification Guide - Logistics - Items Relied On for Safety (IROFS)
Rev. 4 ORM-23b-23a Personal Respiratory Use and Establishment of Airflow Away from the Worker for Handling Designated Material in the CRDB 11/25/2019 OSIROFSQC00100 Operations Training Program Rev. 9 88020 Miscellaneous TQ-5-0100-01 Training Requirement Manual, Radiation Protection Rev. 9
15 Inspection Procedure Type Designation Description or Title Revision or Date Training Requirement AD-3-1000-10 Change Process Management Rev. 17 and Rev. 18 EP-3-0200-02 Emergency Notification Rev. 29 MA-3-0400-03 Installation and Verification of Flow Restriction Orifice (IROFS C21)
Rev. 2 MA-3-3400-04 IROFS4 Station Heaters High Temperature Trip - RTD Rev. 14 MA-3-3400-05 IROFS5 Station Heaters High Temperature Trip - TC Rev. 14 NEF-BD-4 Auto Trip of Station Heater on High Temperature (RTD)
Rev. 3 NEF-BD-5 Auto Trip of Station Heater on High Temperature (RTD)
Rev. 4 NEF-BD-53a Administratively Ensure Uranium Assay Measurement of Feed Cylinder Rev. 6 NEF-BD-53b Administratively Ensure Uranium Assay Measurement of Feed Cylinder Rev. 6 NEF-BD-55a Limit Liquid Effluent Collection and Transfer System (LECTS) Tank and Tote Uranium Enrichment Inventory Rev. 5 NEF-BD-55b Limit Liquid Effluent Collection and Transfer System (LECTS) Tank and Tote Uranium Enrichment Inventory Rev. 5 NEF-BD-62 Administratively Verify Manual Valve Lockout Prior to Feed to 30B Transfer Rev. 1 NEF-BD-63 Administratively Verify Manual Valve Lockout Prior to Feed to 30B Transfer Rev. 1 NEF-BD-C21 Flow Restriction for Vacuum Pumps Used for Sampling or Evacuation Rev. 8 OP-3-0410-01 Feed System Rev. 67 OP-3-0410-02 Transferring Feed Material to 30B Cylinders - Attachments 1, 2 and 12 Rev. 15 OP-3-0660-01 Gaseous Effluent Vent System Rev. 24 ORM 4-5 Auto Trip of Station Heater on High Temperature Rev. 1 ORM 53a-b Administratively Ensure Uranium Assay Measurement of Feed Cylinder (IROFS 53a and IROFS 53b)
Rev. 1 ORM 55a-b Limit Liquid Effluent Collection and Transfer System (LECTS) Tank and Tote Uranium Enrichment Inventory Rev. 2 Procedures ORM 62-63 Administratively Verify Manual Valve Lockout Prior to Feed Rev. 0
16 Inspection Procedure Type Designation Description or Title Revision or Date to 30B Transfer ORM 62-63 Administratively Verify Manual Valve Lockout Prior to Feed to 30B Transfer Rev. 0 ORM C21 Flow Restriction for Vacuum Pumps Used for Sampling or Evacuation Rev. 4 RW-3-2000-01 LECTS Operation Rev. 18 RW-3-5000-03 Emptying of Chemical and NaF Traps Rev. 11 RW-3-5000-04 Heeled, Cleaned, or Partially Filled 30b and 48Y Cylinder Component Replacement and Testing Rev. 10 TQ-3-0100-13 Training and Qualifications Guidelines Rev. 19 RWP 23-104 Work Evolutions to Remove and Decontaminate Chemical Traps Rev. 0 Radiation Work Permits (RWPs)
RWP 24-104 Work Evolutions to Remove and Decontaminate Chemical Traps Rev. 0 2023-A-09-015 UUSA Quality Assurance Program Audit 10/31/2023 Self-Assessments SA-2023-012 Plant Modifications Self-Assessment 7/17/23-11/06/2023 WO# 1000092873, 1000213337, 100051048, 1000327191, 1000380296, 1000327192 Installation and Verification of Flow Restrictive Orifice (IROFSC21)
Various Work Orders WO# 1000583934, 1000599515 LECTS SLAB/BST OPS IROFS55a/b Various Annual ALARA Report (Calendar Year 2022)
Rev. 1 ALARA Plans RP-1-1000-02 ALARA Policy 10/15/2012 Calibration records for four (4) Ludlum Model 3002 alpha-beta digital survey meters 2023-2024 Calibration records for four (4) Ludlum Model 79/1 gamma stretch scope survey meters 2023-2024 Calibration records for one (1) Ludlum Model 9 beta-gamma survey meter 2023-2024 88030 Calibration Records Calibration records for one (1) neutron detector (REM ball) 2023-2024
17 Inspection Procedure Type Designation Description or Title Revision or Date Calibration records for three (3) ThermoFisher Scientific beta-gamma survey meters EV 164388 Leak from Overhead Pipework in the LECTS Room 03/05/2024 Corrective Action Documents EV 164567 Personnel monitored above 5000 DPM - possible contamination, follow-up found no contamination, possible radon 03/18/2024 Shift Turnover Form 03/18/2024 Organizational (Org) Chart for Decontamination &
Recycling, Chemistry, and Radiation Protection 02/23/2024 Radiation Safety Committee Minutes 03/28/2023 Radiation Safety Committee Minutes 09/22/2023 Weely Log for 1100-662 GEVS - HEPA Filter Differential Pressures 03/03/2024 Letter - Rn Progeny Rejection Settings (Mirion Technologies/Canberra) 06/11/2020 Functional System Description No:
114489-D-M-0662-0 Nuclear Technology Solutions, LLC - Flexible Exhaust Hose-Safe-By-Design GEVS - Local Extraction GEVS MEMORANDUM Organizational Changes - Core Operations Management Team 02/22/2024 NVLAP Dosimeter Accreditation Accreditation for Mirion Technologies GDS, Inc., 10 2023 through 06-30-2024 10/03/2023 Radon Progeny Rejection Settings Mirion Technologies Inc. recommendation to minimize Radon False Alarms 06/11/2020 RP-1-1000-01 Radiation Protection Policy 10/15/2012 SRC Meeting No.
2023-001 SRC Meeting 03/28/2023 SRC Meeting No.
2023-002 SRC Meeting 06/05/2023 SRC Meeting No.
2023-003 SRC Meeting 08/31/2023 Miscellaneous SRC Meeting No.
2023-004 SRC Meeting 09/27/2023
18 Inspection Procedure Type Designation Description or Title Revision or Date SRC Meeting No.
2023-005 SRC Meeting 12/19/2023 MA-3-0660-01 GEVS HEPA Filter Testing and Maintenance Rev. 8 Ma-3-3561-01 CAAS Periodic Testing Rev. 7 OP-3-0410-01 Feed System - Attachment 1 - Connecting a Feed Cylinder in an Assay Feeding Natural Feed Rev. 67 OP-3-0410-01 Feed System - Attachment 7 - Disconnecting a Feed Cylinder Rev. 67 OP-3-0660-01 Gaseous Effluent Vent System Rev. 25 RP-2-1000-01 Radiation Protection Program Rev. 12 RP-2-4000-01 Respiratory Protection Program Rev. 7 RP-3-1000-01 ALARA Engineering and TEDE ALARA Evaluation Rev. 10 RP-3-2000-03 Labeling of Radioactive Material Rev. 7 RP-3-2000-04 Radiation and Contamination Surveys Rev. 16 RP-3-2000-07 Contaminated Individual Response Rev. 14 RP-3-3000-04 Declared Pregnant Woman Rev. 8 RP-3-3000-06 External Dosimetry Program Rev. 14 RP-3-3000-08 Bioassay Rev. 9 RP-3-3000-11 Radiological Dose Reports Rev. 9 RP-3-4000-01 Respiratory Protection Rev. 9 RP-3-4000-03 Dose Evaluation Reports Rev. 4 RP-3-4000-17 Personal Air Monitors Rev. 5 RW-3-1000-01 Waste Management Rev. 11 RW-3-2000-01 LECTS Operations Rev. 18 RW-3-4000-01 Startup, Shutdown, and Operation of the SCDT Rev. 12 RW-3-4000-02 Startup, Operation and Shutdown of the Multi-Functional Decontamination Train Rev. 20 Procedures WC-3-1000-02 Work Package Initiation through Closure Rev. 46 Radiation Surveys UF6 Contamination Survey Sample Report 03/20/2024 Radiation Work Permits (RWPs)
RWP 24-010 Job / Evolution
Description:
This RWP allows the performance of Recycling department tasks that are general in nature (e.g. tours, walk-downs, relocating plant Rev. 0
19 Inspection Procedure Type Designation Description or Title Revision or Date equipment, re-stocking PPE, handling operating equipment (Caps/Plugs, A-1 Bottles, 1-S Bottles, Pipettes, rad-waste collection, Slab Tank Berm area to conduct transfer evolutions by locking/unlocking valves and repositioning valves, etc.).
RWP 24-015 General facility access for inspections, planning, and surveillances in existing/potential Radiation Areas (RA)
Rev. 0 RWP 24-103 Test and actuate the CAAS alarms throughout UUSA facility utilizing a Cesium 137 source.
Rev. 0 RWP 24-001 General facility access for inspections, tours, planning, and surveillances Rev. 1 2022-A-12-023 Report for UUSA Louisiana Energy Services, LLC Radiation Protection and ALARA NQA-1 Audit 02/03/2022 2023-A-04-006 Report for UUSA Louisiana Energy Services, LLC Waste Handling NQA-1 Audit 05/08/2023 SA-2022-004 Pump Rebuild and Recycling Self-Assessment of IROFS/BDD/ORM Procedure Alignment and Accuracy August 2022 Self-Assessments SA-2023-004 2023 Radiation Protection Self-Assessment June 2023 1000585793 Criticality Alarm System 08/20/2023 1000631530 Alpha Monitor (ABPM 201 S Calibration) 03/20/2024 Work Orders 1000652883 CRDB 1100-681 LECTS Room Leak, standard RWP 24-110, LOTO, scaffolding, temporary spill catch containment under valve 1100-681-1A82 03/06/2024