ML21189A004

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Framatome-Richland Integrated Inspection Report 07001257/2021002
ML21189A004
Person / Time
Site: Framatome ANP Richland
Issue date: 07/07/2021
From: Noel Pitoniak
NRC/RGN-II/DFFI
To: Stephens L
Framatome
References
IR 2021002
Download: ML21189A004 (20)
v • d • e


Text

July 7, 2021 Mr. Lance Stephens Site Manager Framatome Inc.

2101 Horn Rapids Rd Richland, WA 99354-0130

SUBJECT:

FRAMATOME-RICHLAND - INTEGRATED INSPECTION REPORT 07001257/2021002

Dear Mr. Stephens:

On June 30, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Framatome-Richland. On May 20, 2021, the NRC inspectors discussed the results of this inspection with you 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,

/RA/

Noel A. Pitoniak, Chief (Acting)

Projects Branch 2 Division of Fuel Facility Inspection Docket No. 07001257 License No. SNM-1227

Enclosure:

As stated cc w/ encl: Distribution via LISTSERV

ML21189A004 X Non-Sensitive X Publicly Available X SUNSI Review Sensitive Non-Publicly Available OFFICE RII/DFFI RII/DFFI RII/DFFI RII/DFFI NAME T. Vukovinsky G. Goff D. Edwards N. Pitoniak DATE 07/01/2021 07/01/2021 07/01/2021 07/07/2021 U.S. NUCLEAR REGULATORY COMMISSION Inspection Report Docket Number: 07001257 License Number: SNM-1227 Report Number: 07001257/2021002 Enterprise Identifier: I-2021-002-0115 Licensee: Framatome Inc.

Facility: Framatome-Richland Location: Richland, WA Inspection Dates: May 17 to May 20, 2021 Inspectors: D. Edwards, Allegations & Enforcement Specialist G. Goff, Fuel Facilities Inspector Approved By: Noel A. Pitoniak, Chief (Acting)

Projects Branch 2 Division of Fuel Facility Inspection Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Framatome-Richland, 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.

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PLANT STATUS The Framatome facility converts uranium hexafluoride (UF6) into uranium dioxide (UO2) for the fabrication of low-enriched fuel assemblies used in commercial light water reactors. 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 88015 - Nuclear Criticality Safety The inspectors evaluated selected aspects of the licensees Nuclear Criticality Safety program to verify compliance with selected portions of 10 CFR 70, including 70.24, 70.61, and 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 nuclear criticality safety analyses (NCSAs), and associated assumptions and calculations, to verify compliance with 10 CFR 70 and applicable sections of the license application, including, 5.4. Specifically, the inspectors interviewed licensee staff and reviewed the following NCSAs in areas and/or systems:

  • E04-NCSA-150, "Miscellaneous Uranium Recovery System (MURS)," Version 24.0;
  • E04-NCSA-080, "Line 2 Uranium Recovery." Version 22.0; and
  • E04-NCSA-120, "UNH Reprocessing," Version 23.0 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, plant walkdowns, and operator interviews to verify compliance with 10 CFR 70 and applicable sections of the license application. Specifically, the inspectors interviewed licensee staff and reviewed the following controls, and their management measures, associated with the CSAs listed above and selected areas:

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  • passive engineered spacing control IROFS 6514 in the facility area;
  • administrative mass control IROFS 6511, 6512, 6202 and associated NCS Postings and operating procedures; and
  • administrative poison control IROFS 6224 and associated operating procedures 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. Specifically, the inspectors performed the following activities:

  • reviewed and discussed with NCS staff the flow down of NCSAs to SOPs for E04-NCSA-150, "Miscellaneous Uranium Recovery System (MURS)," Version 24.0; E04-NCSA-080, "Line 2 Uranium Recovery." Version 22.0; E04-NCSA-130, "Conversion of UO2 Pellets to U3O8 Powder," Version 12.0 and E04-NCSA-370, "UO2 Pellet Pressing," Version 15.0;
  • reviewed operator training for a selected number of operators for the Systems 120, 190, 260, 280, and 800; and
  • accompanied Criticality Safety Specialist and trainee performing periodic assessment audits of 380 sintering furnace, 400 vaults and 390 grinding inspection and reviewed associated NCSAs.

Criticality Programmatic Oversight (IP Section 02.04)

The inspectors reviewed NCS program procedures and NCS staff qualifications to verify compliance with 10 CFR 70 and applicable sections of the license application, including, 5.2 and 5.3. Specifically, the inspectors interviewed licensee NCS staff and reviewed the following documents:

  • Criticality Safety Specialist qualification records;
  • NCS program procedures, including E04-06-002, "Routine Nuclear Criticality Safety Audits," Version 6; and
  • interviewed NCS staff concerning NCS review of changes, including changes to operating procedures that may effect NCS, and changes to the facility Criticality Incident Response and Corrective Action (IP Section 02.05)

The inspectors reviewed the licensees criticality accident alarm system (CAAS) and corrective action program (CAP) to verify compliance with 10 CFR 70 and applicable sections of the license application, including, 5.5. Specifically, the inspectors observed activities, reviewed documents, and interviewed licensee staff concerning the following:

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  • CR 2021-0489, and associated documentation for licensee's response to the 2/26/21 SCALE User Notification of a cross section error concerning the h-poly material. The inspectors interviewed NCS staff regarding their response to this error. The inspectors also reviewed the licensee's assessment of the impact of the issue on SCALE calculations that used h-poly;
  • reviewed the CAAS maintenance records;
  • reviewed and discuss the detector placement/minimum accident of concern calculations with NCS;
  • reviewed the licensee's dose in tissue justification and reference document "Criticality Detection and Alarm System," 12/1977; and
  • reviewed recent NCS-related infractions and non-reportable events RADIOLOGICAL CONTROLS 86740 - Inspection of Transportation Activities The inspectors evaluated select aspects of the licensees Transportation Activities program to determine whether the licensee has established and is maintaining an effective, management-controlled program; to ensure radiological and nuclear safety in the receipt, packaging, delivery to a carrier and, as applicable, the private carriage of licensed radioactive materials; and to determine whether transportation activities are in compliance with the applicable Nuclear Regulatory Commission 10 CFR Parts 20 and 71 regulations and Department of Transportation (DOT) (49 CFR Parts 171-178) transport regulations.

Preparation of Packages for Shipment (IP Section 02.01)

The inspectors examined the licensees procedures and shipment records and observed actual package preparations and operations to verify compliance with the regulations above. Specifically, the inspectors reviewed or observed the following:

  • loading of heeled 30B cylinders into the UX-30s (overpacks) with the valve at the 12 o'clock position;
  • placement and lockdown of the UX-30 lid;
  • tamper indicating devices (seals) being placed onto each UX-30 in the proper locations;
  • contamination surveys;
  • radiation surveys;
  • E11-01-004;
  • MCP-3012;
  • SWI-40319 A, C, & D Delivery of Completed Packages to Carriers (IP Section 02.02)

The inspectors examined the licensees procedures and shipment records and observed actual preparations and operations to verify compliance with the regulations above. Specifically, the inspectors reviewed or observed the following:

  • the bill of lading and shipping manifest were completed by the licensee to verify all required information (gross weight, size, shipper information, consignee information, radioactivity level, container identification, etc.) was included;
  • the driver of the flat bed reviewed the shipping record and subsequently provided his signature for transfer of custody;
  • SOP-40670 Receipt of Packages (IP Section 02.03)

The inspectors examined the licensees procedure for an incoming shipment to verify compliance with 10 CFR 20.1906 and applicable license requirements. Specifically, the inspectors reviewed or observed the following:

  • the removal of the UX-30 (overpack) lids;
  • the removal of the 30B cylinders from the overpacks;
  • the placement of the 30B cylinders onto saddles in the cylinder yard;
  • orientation of the 30B so that the valve was at a 12 o'clock position;
  • radiation and contamination survey records;
  • shipping manifest;
  • bill of lading;
  • SWI-40319 A, C, & D The inspectors observed the receipt of a second incoming shipment to verify compliance with 10 CFR 20.1906 and applicable license requirements. Specifically, the inspectors reviewed or observed the following:
  • radiation surveys;
  • contamination surveys;
  • labels and corresponding information such as: container identification, radioactive material, excepted packages, limited quantity of material, 7(E),

shipper/receivers addresses, and gross weight;

  • removal of the waste drums from the sealand containers;
  • removal of the labels from the sealand containers;
  • the reloading of the empty sealand containers; 6
  • the fastening/locking of each sealand container;
  • confirmation of accuracy of information with the driver on the return shipment of empties; and
  • the procedures listed above in this section Records and Reports (IP Section 02.04)

The inspectors examined the licensees procedures and records for recordkeeping and reports to verify compliance with the regulations above. Specifically, the inspectors reviewed:

  • Safety Analysis Reports (SARs) for DOT Specification 7A Type A packaging, which demonstrated the safety analysis/testing and any special form testing.
  • SARS for the following types of packages were verified to be on file: UX-30 package; TNF-XI package; TN-B1 package; SP-1, SP-2, SP-3 shipping containers; NPC packages; MAP PWR fuel shipping package; and DN30 package.

General License Requirements (IP Section 02.05)

The inspectors reviewed the certificates of compliance (CofCs) utilized for shipment of radioactive material packages to verify compliance with 10 CFR 71, Subpart C. Specifically, the inspectors reviewed CofCs for:

  • 9196 for UX-30 packages;
  • 381 for TNF-XI packages;
  • 9372 for TN-B1 packages;
  • 9294 for NPC packages;
  • 0535 for MFC-1 packages;
  • 9319 for MAP-12 & MAP-13 packages;
  • 9362 for DN30 packages;
  • 0827 for ANF-10 packages; and
  • 0411 for 30B cylinders Management Controls (IP Section 02.06)

The inspectors reviewed the system of management controls for transportation activities to verify compliance with licensee instructions and procedures. Specifically, the inspectors reviewed:

  • the maintenance records for the past 12 months for the high purity geranium counters (used for determining enrichment level) for 30B cylinders; 7
  • the maintenance records for the past 12 months for the digital scale for 30B cylinders;
  • calibration of the radiation survey meters used for incoming and outgoing shipments; and
  • shipment records for authorization signatures from managers Indoctrination and Training Program (IP Section 02.07)

The inspectors reviewed training documentation for workers involved in transport activities to verify compliance with Chapter 11 of the licensee application. Specifically, the inspectors:

  • reviewed the curriculum and training records for the handlers of the UX-30 overpacks and 30B cylinders to verify all required training and refresher training was satisfied Quality Assurance Program (IP Section 02.08)

The inspectors reviewed the quality assurance documents to verify compliance with the licensees quality assurance (QA) program. Specifically, the inspectors reviewed:

  • SWI-40525 A, C, & F;
  • SWI 40083 A, B, & F;
  • SWI-50254 A;
  • SWI-40083 D;
  • SWI-41040 A; and
  • SWi-50072 E MAP Audit Program (IP Section 02.09)

The inspectors reviewed the latest audit to verify compliance with 10 CFR 71.137. Specifically, the inspectors reviewed the following:

  • 2020 SH-2 Licensed Packaging Audit Report, 01/14-15/2021 Procurement and Selection of Packagings (IP Section 02.10) 8

The inspectors examined the licensees packages and certificates of compliance (CofC),

listed above, to verify compliance with the federal regulations above. Specifically, for packagings that are used by the licensee to transport or to deliver licensed material to a carrier for transport, the inspectors walked down the following packages:

  • TN-B1
  • SP1
  • SP2
  • SP3
  • NPC
  • MAP-12
  • MAP-13
  • MFC-1 Preparation of Packages for Shipment (IP Section 02.11)

The inspectors examined the licensees package condition, markings, labeling, and documentation to verify compliance with applicable parts of the federal regulations above. Specifically, the inspectors observed:

  • the outside of DOT-revalidation packages (sealand containers) were durably and legibly marked with the package identification marking indicated in the COC or the DOT Competent Authority Certificate; and
  • no serious damage such as punctures, holes, intense corrosion, etc., on the sealand containers Periodic Maintenance of Packagings (IP Section 02.12)

The inspectors examined the licensees procedures to verify compliance with applicable parts of the federal regulations above. Specifically, the inspectors reviewed the following:

  • SOP-40829 Records, Reports, and Notifications (IP Section 02.13)

The inspectors reviewed the licensees procedure for recordkeeping and reports to verify that a system was in place to verify compliance with the federal regulations above. Specifically, the inspectors reviewed the following records in the record retention system:

  • MAP-12-SHA1-24 Fuel Shipment (03/16/2021);
  • DN30 - EMPTY - Capenhurst UF6 Shipment (03/10/2021);
  • NPC - EMPTY - BWXT UF6 Shipment (02/02/2021);
  • SP QCI1 - 27 Truck 7 (02/05/2021);
  • TN-B1 - BRK2-25 Truck 9 (01/31/2021);
  • UX-30 Heels - URENCO USA (04/09/2021);
  • MAP PVE2-23 (02/17/2020);
  • ANF EMPTY to ANF (04/01/2021);

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  • US Fuel Internal Audit Report, 07/15 - 8/19/2020; and
  • E12-03-059-FRM-001, Checklist for Annual EHS Records Management Audit, 07/15 - 08/19/2020 INSPECTION RESULTS No issues were identified.

EXIT MEETINGS AND DEBRIEFS The inspectors verified no proprietary information was retained or documented in this report.

  • On May 20, 2021, the inspectors presented the integrated inspection results to Lance Stephens and other members of the licensee staff.

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DOCUMENTS REVIEWED Inspection Type Designation Description or Title Revision or Procedure Date 86740 Calibration C000I001-001 IROFS Scale - Cyl Storage Facility, West (May 2020 - Version 2 Records (Monthly) May 2021)

C000I001-002 IROFS Scale - Cyl Storage Facility, East (May 2020 - Version 2 (Monthly) May 2021)

C000I002 (Annual) Assay UF6 Cyl (West) - for the last two years Version 8 C000I003 (Annual) Assay UF6 Cyl (East) - for the last two years Version 10 Corrective Action CR-2021-0382 TN-B1 potential fuel assembly configuration not bounded 02/17/2021 Documents by license CR-2021-0921 NIAC Audit #26076 (21:23) Finding #2 04/16/2021 CR-2021-1064 Tenex 30B Cylinder Valve Condition 04/28/2021 Corrective Action CR2021-1274 Observations and Follow-Up items from NRC Inspection 05/20/2021 Documents 2021-002 Resulting from Inspection Drawings TN-B1 Drawings (Various)

SP1, SP2, and SP3 NPC Containers MFC-1 Containers MAP-12 and MAP-13 ANF-10 UX-30 (Overpack)

Miscellaneous DOT Certification for SP-1, SP-2, and SP-3 packages Safety Analysis Report For Model UX-30 Package Revision 4 Safety Analysis Report for TNF-XI Package Revision 12 Safety Analysis Report - TN-B1 Packages Revision 9.0 Safety Analysis Report - SP1, SP2, and SP3 Shipping Revision 15 Containers Safety Analysis Report for NPC Packages - Section 7 Revision 2 Packaging, Handling, Storage, and Shipping of PWR Revision 1.0 Fuel Assemblies in MFC-1 Containers Safety Analysis Report for MAP PWR Fuel Shipping Revision 4.0 Package - USA/9319/B(U)F-96 11

Inspection Type Designation Description or Title Revision or Procedure Date IRM Change Notice - UF6 Cylinder Assay 0814/1995 Transportation Organizational Chart List of Licensed Packaging Used at HRR DOT Certification for UX-30 package DOT Certification for TNF-XI package DOT Certification for NPC package DOT Certification for MFC-1 package DOT Certification for ANF-10 package DOT Certification for Cylinder Model 30B 0023-BSH-2016-002 Safety Analysis Report DN30 Package Revision 1 0023-HA-2015-001 Use and Handling of the DN30 Package Revision 5 22125.NP1.025.00.01- UF6 Shipment (LES) - Shipping Package 05/17/2021 13 ANFG-11.106 (03E) Safety Analysis for the ANF-10 Fuels Assembly Shipping Revision 12 Container for the Transport of BWR Fuel Assemblies FRM-20198 30B Cylinder Receiving and In-Service Checklist Version 3.1 NRC Form 618 Certificate of Compliance (for NPC package) Revision 9 NRC form 618 Certificate of Compliance 9319 (for MAP-12 and MAP-13 Revision 12 packages)

NRC Form 618 Certificate of Compliance 9362 (for DN30 package) Revision 2 NRC Form 618 Certificate of Compliance (for SP-1, SP-2, and SP-3 Revision 26 packages)

NRC Form 618 Certificate of Compliance 9196 (for UX-30 Packages) Revision 30 NRC Form 618 Certificate of Compliance 9372 (for TN-B1 package) Revision 2 Organizational Chart for TN Americas -

Waste and Transportation Group (Orano)

Procedures AID-10755 Reference 1175 Ludlum Survey Meter with Version 4.0 Alpha/Beta/Gamma Detectors E07-02-410 Certification of Mass Standards Version 5.0 E11-01-004 Radioactive Material Shipping Standard Version 33.0 12

Inspection Type Designation Description or Title Revision or Procedure Date MCP-30112 Current Shipping Container Information Version 25.0 MCP-30222 Configuration and Packing SP1/SP2/SP3 Shipping Version 4.2 Containers MCP-30325 Instrument Repetitive Maintenance Version 17.0 SOP-40065 Nuclear Materials Shipping and Receiving - General Version 23.0 Rules SOP-40071 Radioactive Package Marking and Labeling Version 28.0 SOP-40072 Shipping Container Maintenance and Rework Version 27.0 SOP-40074 Annual Inspection of UF6 Protective Overpacks Version 6.2 SOP-40082 Coplanarity Inspection of BWR Shipping Packages Version 4.2 SOP-40083 Shipping and Receiving of UO2 Fuel Assemblies in SP- Version 15.2 1/SP-2/SP-3 Shipping Containers SOP-40088 Weighing and Assaying of Scrap Uranium Shipments Version 6.2 Received in TNF-XI Shipping Containers SOP-40319 General Packaging, Shipping and Receiving UF6 Version 11.0 Cylinders and Protective Overpacks SOP-40408 Bundle Assembly General Packing Procedure Version 14.0 SOP-40509 Packing and Shipping UO2 Powder in TNF-XI Shipping Version 26.0 Packages SOP-40525 Refurbishment of TN-B1 Shipping Containers and the Version 13.0 Shipping and Receiving of UO2 Fuel Assemblies and Fuel Rods in TN-B1 Shipping Containers SOP-40668 Visual Inspection of Shipping Container Welds Version 7.0 SOP-40670 Shipment Release for Licensed Radioactive Material Version 6.0 Packages SOP-40829 Maintenance Weld Repairs on Licensed Shipping Version 5.1 Containers SOP-40903 Shipping and Receiving NPC Shipping Packages Version 7.0 SOP-40932 Visual Inspection of UX-30 Welds Version 3.2 SOP-40937 Shipping and Receiving of MAP-12/MAP-13 Shipping Version 9.0 Containers SOP-40993 Calibration of Weights Version 4.0 SOP-41024 Storage of Shipping Containers Version 6.0 SOP-41040 MFC-1 Shipping Containers - Receipt, Refurbishment Version 4.0 13

Inspection Type Designation Description or Title Revision or Procedure Date and Shipment SOP-41117 Seal Verification and Application Version 4.0 SWI-40083 A Station #1 Outer Container Inspections Version 9.0 SWI-40083 B Station #1 Inner Container Inspections Version 14.0 SWI-40083 D Station #2 Inner Container Inspections Version 6.2 SWI-40083 F Station #3 Outer Container Inspections Version 10.0 SWI-40319 A Receiving Cylinder Overpacks, Weighing and Assaying Version 18.0 of UF6 Cylinders SWI-40319 C Shipping UF6 Cylinders and Protective Overpacks Version 8.1 SWI-40319 D Loading UF6 Cylinders into Protective Overpacks Version 8.2 SWI-40408 A MFC-1 Shipping Container Bundle Packing Version 9.0 SWI-40408 C MFC-1 Container Unloading Fuel Bundle(s) Version 2.0 SWI-40409 A BWR Bundle Packing SP1, SP2, SP3 Shipping Version 21.0 Containers SWI-40409 B Assigning Bundles and Seals to Inner and Outer Version 6.0 Shipping Containers SWI-40409 C TN-B1 Shipping Container Packing and Unpacking Version 29.0 SWI-40409 D Replacing Foam in BWR Inner Shipping Containers Version 4.1 SWI-40409 E Replacing Heliserts - TN-B1 Containers Version 3.2 SWI-40525 A TN-B1 Outer Container Inspection - Station #1 Version 11.0 SWI-40525 C Station #2 Inner Container Inspections - TN-B1 Version 10.0 Containers SWI-40525 F Station #3 Inner/Outlet Container Verifications - RAJ- Version 10.0 II/TN-B1 Containers SWI-41040 A Container Inspection - MFC-1 Version 2.2 SWI-41056 H Building 9 - Removing Fuel Assembly from Shipping Version 1.0 Container SWI-50046 A Opening and Closing NPC Shipping Container Version 8.0 SWI-50046 B Removing Inner Containers from NPC Container Version 2.2 SWI-50072 B MAP 12 and 13 Shipping Container Packing Fuel Version 21.0 Assemblies SWI-50072 E MAP 12 and 13 Shipping Container - Container Cleaning, Version 9.0 Inspection and Up-Ending 14

Inspection Type Designation Description or Title Revision or Procedure Date SWI-50211 A Preparation of MAP-12/MAP-13 Containers Version 10.0 SWI-50211 B MAP-12/MAP-13 Container Gasket Replacement Version 3.0 SWI-50211B MAP-12/MAP-13 Container Gasket Replacement Version 3.0 SWI-50254 A Packing Rods in a TN-B1 Container Version 7.0 Radiation O-20210519-1 Survey of Incoming Radioactive Shipment (19 Packages) 05/19/2021 Surveys O-20210519-2 Survey of Incoming Radioactive Shipment (46 Packages) 05/19/2021 Shipping Records CHSU 2015752 Shipment Summary CHSU 2016002 Shipment Summary CHSU 2016255 Shipment Summary 88015 Calculations E04-09-002 Criticality Accident Alarm System Coverage Analysis for Version 2.1 FANP Richland Corrective Action CR 2020-2378 CS Infraction 20-021 - Two dry SBCs discovered stacked 10/21/2020 Documents in I3A Dry Storage Array - IROFS 2107 Failed CR-2020-1612 NCS Infraction 20-014; IROFS 1614 Failed - Water Leak 08/07/2020 in ELO Basement Led to Moderator in a Moderation Controlled Area CR-2021-0339 NCS Infraction 21-002, IROFS 1410.10 Degraded: SBC 02/14/2021 found in I3A with an unsecured lid.

CR-2021-0489 SCALE User Notice: h1-poly incoherent elastic 03/02/2021 scattering can cause k-eff underprediction-2/26/2021 CR-2021-0489 Additional time is needed to assess the impact of the h- 03/15/2021 REQ01 poly error on the TN-B1 criticality analysis Corrective Action CR-2021-1274 Observations and Follow up items from NRC Inspection 05/20/2021 Documents 2021-002 Resulting from Inspection Miscellaneous Richland Site Access Refresher Training - Emergency 08/31/2020

Response

General Site Access Refresher Training - Criticality 08/31/2020 Safety Awareness Criticality Detection and Alarm System 12/1977 Training Records for System 120, 190, 260, 280, and 800 On-the-Job Training (OJT) EHS&L - Criticality Safety 05/19/2021 15

Inspection Type Designation Description or Title Revision or Procedure Date Specialist Records E04-03-002 HRR Site NCSP Location Listing Version 27.0 E04-06-002 Routine Nuclear Criticality Safety Audits Version 6.0 E04-07-202012 NCS Audit/Inspection Report - December 2020 01/22/2021 E04-07-202101 NCS Audit/Inspection Report - January 2021 03/03/2021 E04-07-202102 NCS Audit/Inspection Report - February 2021 03/15/2021 E04-09-001 HRR Criticality Accident Alarm System Coverage Version 6.0 Demonstration E04-09-002 Criticality Accident Alarm System Coverage Analysis for Version 2.1 FANP Richland E04-NCSA-000 UF6 Cylinder Receiving and Storage Version 11.0 E04-NCSA-005 UF6 Cylinder Recertification Operation Version 7.0 E04-NCSA-065 UF6 Cylinder Washing Operation Version 12 E04-NCSA-080 Line 2 Uranium Recovery Version 22.0 E04-NCSA-100 ADU Process Off-Gas System Version 13.0 E04-NCSA-120 UNH Reprocessing Version 23.0 E04-NCSA-130 Conversion of UO2Pellets to U3O8Powder Version 12.0 E04-NCSA-135 BLEU Scrap Recovery Version 17.0 E04-NCSA-150 Miscellaneous Uranium Recovery System (MURS) Version 24.0 E04-NCSA-205 MOP Powder Dissolver Facility Version 25.0 E04-NCSA-370 UO2 Pellet Pressing Version 15.0 E04-NCSA-375 BLEU Pellet Pressing Version 17.0 E04-NCSA-380 Pellet Sintering Area Version 10.0 E04-NCSA-385 BLEU (Line-6) Pellet Sintering Version 11.0 E04-NCSA-390 UO2 Pellet Grinding & Inspection Version 22.0 E04-NCSA-400 UO2 and SF Pellet Vault Storage Areas Version 11.0 E04-NCSA-490 Rod and Pellet Vault Downloading Version 14.0 E04-NCSA-550 Bundle Disassembly Version 8.0 E04-NCSA-615 NAF Pellet Sintering & Storage Version 9.0 E04-NCSA-840 Dry Conversion Liquid Effluent & HF Recovery Version 7.0 E04-NCSS-G01 NCS Guide Rules & Generic Program Requirements Version 22.0 E04-NCSS-G02 Generic Criticality Safety Container Labeling Version 15.0 Requirements 16

Inspection Type Designation Description or Title Revision or Procedure Date E04-NCSS-G03 Glossary of Terms Version 14.0 E04-NCSS-G78 Generic Mass Control Containers & Workstations Version 22.0 E04-NCSS-G89 Uranium Slab Control Version 13.0 NCS Infraction 20-006 Evaluation of NCS Infraction 20-006 (CR 2020-0689) 03/25/2020 NCS Infraction 20-014 Evaluation of Reportability of NCS Infraction 20-014 (CR 08/17/2020 2020-1612)

NCS Infraction 20-021 Evaluation of Reportability for NCS Infraction 20-021 (CR 10/23/2020 2020-2378)

NCS Infraction 2021- Evaluation of Reportability for NCS Infraction 2021-002 02/23/2021 002 (CR 2021-0339)

NCSP-130-001 U3O8 Oxidation Furnaces and Hoods Version 1.1 NCSP-150-001 Wet Waste Uranium Recovery Station Version 1.1 NCSP-150-003 Ultrasonic Cleaner Version 3.0 NCSP-150-004 Mop Powder Furnace Hood Version 1.1 NCSP-G01-007 Unfavorable Geometry Containers Are Not Allowed in Version 1.0 this Room / Area NCSP-G78-010 Utility Hood - U3O8 Version 2.0 NCSP-G81-003 Dry Uranium Container Single Tier Storage Version 4.0 Procedures E12-01-007 Justification for Continued Operation Under Version 7.2 Compensatory Safety Measures MCP-30365 Essential Material Class I: ADU Process Uranium Version 6.0 Recovery Ion Exchange Resin SOP-40239 U3O8 Oxidation Ovens Version 11.1 SOP-40240 Sweco Operations Version 11.0 SOP-40244 Miscellaneous Uranium Recovery Version 16.0 SOP-40245 MURS Furnace Operation Version 6.3 SOP-40248 Ultrasonic Cleaning Operations Version 7.0 SOP-40249 Cleaning and Repairing DCF Reactor Distributor Plates Version 6.2 SOP-40250 Cleaning Metal Filters for Reuse Version 7.0 SOP-40273 Ion Exchange Operations and Regeneration - ADU Line Version 8.0 2

SOP-40274 Process Startup - ADU Line 2 Version 21 SOP-40280 Changing or Downloading of Ion Exchange Resins Version 7.0 17

Inspection Type Designation Description or Title Revision or Procedure Date SOP-40282 UNH Powder Dissolution Version 20.0 SOP-40486 Richland Operations General Rules Version 37.0 SWI-40245 A MURS Furnace Operation Version 6.0 SWI-40248 A Operation of Ultrasonic Cleaner Version 3.2 SWI-40252 A Decontamination Station Version 3.0 SWI-40488 A Mop Head, Filter and Rag Neutralization Station Version 3.0 SWI-50321 A ULF to MURS Version 2.0 Work Orders Order: 13468043 PM005495 Criticality Howlers 6 MO EL 09/19/2020 Order: 13481984 PM005502 CAAS 3S Probe Check 1 MO EL 12/11/2020 Order: 13487812 PM005495 Criticality Howlrs 6 MO EL 03/27/2021 18

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