ML23024A231
| ML23024A231 | |
| Person / Time | |
|---|---|
| Site: | Westinghouse |
| Issue date: | 01/30/2023 |
| From: | Eric Michel NRC/RGN-II/DFFI/FFB2 |
| To: | Pope A Westinghouse |
| References | |
| IR 2022004 | |
| Download: ML23024A231 (1) | |
Text
January 27, 2023 EN 56070 Annette Pope Plant Manager Westinghouse Electric Company 5801 Bluff Road Hopkins, SC 29061
SUBJECT:
WESTINGHOUSE COLUMBIA FUEL FABRICATION FACILITY - INTEGRATED INSPECTION REPORT 07001151/2022004
Dear Annette Pope:
This letter refers to the U.S. Nuclear Regulatory Commission inspection activities conducted during the period from October 1 to December 31, 2022, for the Westinghouse Columbia Fuel Fabrication Facility. On November 17, 2022, the NRC inspectors discussed the results of this inspection with you. 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, Eric C. Michel, Chief Projects Branch 2 Division of Fuel Facility Inspection Docket No. 07001151 License No. SNM-1107
Enclosure:
As stated cc w/ encl: Distribution via LISTSERV Signed by Michel, Eric on 01/27/23
SUNSI Review x
Non-Sensitive
Sensitive x
Publicly Available
Non-Publicly Available OFFICE RII/DFFI/PB2 RII/DFFI/PB2 RII/DFFI/PB2 NAME L. Pitts T. Vukovinsky E. Michel DATE 1/30/2023 1/25/2023 1/27/2023
Enclosure U.S. NUCLEAR REGULATORY COMMISSION Inspection Report Docket Number:
07001151 License Number:
SNM-1107 Report Number:
07001151/2022004 Enterprise Identifier:
I-2022-004-0056 Licensee:
Westinghouse Electric Company Facility:
Westinghouse Columbia Fuel Fabrication Facility Location:
Hopkins, SC Inspection Dates:
November 14, 2022, to November 17, 2022 Inspectors:
L. Pitts, Sr. Fuel Facility Projects Inspector J. Raudabaugh, Fuel Facility Inspector T. Vukovinsky, Sr. Fuel Facility Project Inspector Approved By:
Eric C. Michel, Chief Projects Branch 2 Division of Fuel Facility Inspection
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SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Westinghouse Columbia Fuel Fabrication Facility, 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 EN 56070, "Criticality Accident Alarm System (CAAS) Inoperable," closed.
3 INSPECTION SCOPES Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Inspections were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2600, Fuel Cycle Facility Operational Safety and Safeguards Inspection Program. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
SAFETY OPERATIONS 88020 - Operational Safety The inspectors evaluated selected aspects of the licensees operational safety program to verify compliance with selected portions of 10 CFR 70, Domestic Licensing of Special Nuclear Material, including 70.24, 70.61, 70.62, and Chapter 3, Management Measures, of the facilitys license application, and applicable licensee procedures.
Identification of Safety Controls and Related Programs (IP Section 02.01)
The inspectors selected specific process areas for inspection based on the safety basis information of the facility, the risk/safety significance of the process areas, the description of plant changes submitted to the NRC, and past plant performance documentation. For the process areas of interest, the inspectors selected a sample of accident sequences in nuclear criticality safety 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:
Bulk Blending o
CSE-5-A Scenario #1 Bulk Container has High Water Content Because of High Moisture Polypaks
Integral Fuel Burnable Absorber (IFBA) Area o
CSE-14-A, Material Handling in the IFBA Area o
CSE-14-B, IFBA Coaters o
CSE-14-C, Miscellaneous Operations in the IFBA Area 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 specific safety controls selected for review are listed below:
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ADUBB-102, Bulk Blending Dump Hood Interlock Failure, active engineered control (AEC), functional area criticality safety
ADUBB-106, Fail Properly Record and Enter MM2 Lab Results in Computer System, administrative control (AC), functional area criticality safety
ADUBB-107, 1st Sampling Process Execution Fails, AC, functional area criticality safety
ADUBB-119, Outer Roof Structure Fails Allowing Moderation, passive engineered control (PEC), functional area criticality safety
ADUBB-120, Inner Roof Structure Fails Allowing Moderation, PEC, functional area criticality safety
ADUBB-121, Failure Structural Integrity of Equipment and Covers, PEC, functional areas criticality safety, and radiation safety
ADUBB-911, Failure Structural Integrity of tumbler cradle and supports, PEC, functional area criticality safety
ADUBB-914, Bulk Container in Raised Position Interlock Re-Mill Station #1, AEC, functional area criticality safety
ADUBB-915, Bulk Container in Raised Position Interlock Re-Mill Station #2, AEC, functional area criticality safety
IFBA-101, IFBA Pellet Tray Design, PEC, functional area criticality safety
IFBA-104, Coating Fixture Structure Design, PEC, functional area criticality safety
IFBA-106, Drying Oven Capture Row Tray Structure Design, PEC, functional area criticality safety
IFBA-120, IFBA Area Ceiling Integrity, PEC, functional area criticality safety
IFBA-147, IFBA Area Piping Integrity, PEC, functional area criticality safety
IFBACTR-110, Coater Cooling System Design, PEC, functional area criticality safety
IFBACTR-116, Target Rotation or Replacement Procedure, AA, functional area criticality safety
IFBACTR-117, Shield and Coater Drum Replacement Procedure, AC, functional area criticality safety
IFBA-MISC-101, Filter Press Plate Peg-and-Hole Features, PEC, functional area criticality safety
IFBA-MISC-125, Filter Press Plate Peg Inspection, AC, functional area criticality safety Implementation of Safety Controls (IP Section 02.03)
For the selected safety controls listed above, the inspectors reviewed management measures to verify proper implementation in accordance with 10 CFR 70 and chapter 3 of the license application. This review was performed to verify that 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:
walkdowns performed to verify implementation of IROFS detailed above
observed maintenance staff performing inspections associated with IROFS ADUBB-901
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interviewed maintenance staff assigned to perform inspections to verify they were knowledgeable of the requirements associated with their assigned inspections 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 chapter 3 of the license application. Additionally, the inspectors followed-up on event notification56070, "Criticality Accident Alarm System (CAAS) Inoperable."
Specifically, the inspectors conducted the following:
reviewed preventative maintenances (PMs) and procedures for testing, inspection, and repair of bulk containers for IROFS ADUBB-901
reviewed PMs for testing and inspection associated with IROFS ADUBB-119, ADUBB-120, ADUBB-121, ADUBB-911, ADUBB-914, and ADUBB-915
reviewed failure and degradation records for IROFS in IFBA and bulk blending
reviewed corrective action program entries for IFBA and bulk blending
reviewed the Environmental Health and Safety Formal Compliance Audit Report (EHS-AUDIT-22-7)
reviewed training documents for two welders and interviewed one welder assigned to perform the inspections associated with ROFS ADUBB-901
observed activities related to bulk blending operations
walkdowns and interviews performed to review EN 56070, "Criticality Accident Alarm System (CAAS) Inoperable" INSPECTION RESULTS Minor Violation 88020 Minor Violation: An event follow-up inspection was conducted from November 14 to 17, 2022, for EN 56070 (ML22277A460). The event resulted in the reported loss or degradation of the CAAS due to a circuit breaker tripping. Power was subsequently restored to the detectors approximately 90 minutes later. Further investigation determined that power was also lost to seven CAAS horns and one strobe light. In the unlikely event of a criticality anywhere in the plant, the emergency response is to evacuate the entire plant. Therefore, since a portion of the horn system was unavailable all special nuclear material (SNM) movements should have been suspended in the plant within an hour. It was not recognized until completion of the extent of condition review that the horn loop was out of service for approximately 90 minutes due to this incident.
Screening: The inspectors determined the violation was minor. Per NRC IMC 0616, Fuel Cycle Safety and Safeguards Inspection Reports, Appendix B, Minor/More-than-Minor Examples, this issue aligns closely with example 2k. This issue is considered minor because the failure occurred for an insignificant duration (e.g., less than or equal to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />).
Enforcement: The licensee took immediate corrective actions to suspend SNM movements at the UF6 cylinder storage pad and to verify that no personnel were in the affected area at the time. Power was subsequently restored to the detectors approximately 90 minutes later. Additionally, corrective actions were put in place to determine reason for power loss and to move the power supply to an alternate power source.
6 This failure to comply with the Emergency Plan Section 5.1.1, Onsite Protective Actions, and license application Chapter 6.1.8, CAAS, constitutes a minor violation that is not subject to enforcement action in accordance with the NRC Enforcement Policy. EN 56070 is closed.
EXIT MEETINGS AND DEBRIEFS The inspectors verified no proprietary information was retained or documented in this report.
On November 17, 2022, the inspectors presented the integrated inspection results to Annette Pope and other members of the licensee staff.
7 DOCUMENTS REVIEWED Inspection Procedure Type Designation Description or Title Revision or Date 348F03PI09,01 Bulk Blending Process Flow Rev. 3 500F00CR02 Criticality Badge and Criticality Alarm Zones (Outside)
Rev. 03 500F00CR02 Criticality Badge and Detector Locations and Coverage Rev. 17 510F08EL05 Electrical Emergency Panel Schedules Rev. 78 510F08EL05 Plant Utilities Rev. 78 and 79 510F08EL05 Electrical Emergency Panel Schedules Rev. 79 510F16EL03 Single Line Standby Generator-3 Rev. 44 605F00PI0S IFBA / Facilities ROD LINE Piping & Instrumentation Drawing (P&ID)
Rev. 12 802F01PI01 COATER 1 (PK-7066) P&I D Rev. 05 802F03P101,02 Pellet Coating #3 Rev. 4 802F03PI01 COATER 3 (PK-7068) P&I D Rev. 04 802F05P101,02 Pellet Coating #5 Rev. 8 802F05PI01 COATER 5 (PK-7069) P&I D Rev.08 805F02PI02 VACUUM OVEN P&I D Rev. 02 807F04EQ02 FILTER PRESS (FP-7092) POLY PLATE MODIFICATIONS Rev. 01 807F04PI01 IFBA Facility / MOP Water Rev. 25 Drawings VACUUM OVEN P&ID FURNACE
- 1 805F01PI02 Rev. 02 CSE-14-A Material Handling (Pellet Receipt through Collating or Pre-stacking) in the Integral Fuel Burnable Absorber (IFBA) Area Rev. 17 CSE-14-B Integral Fuel Burnable Absorber (IFBA) Coaters Rev. 10 CSE-14-C Miscellaneous Operations in the Integral Fuel Burnable Absorber (IFBA) Area Rev. 16 Engineering Evaluations CSE-5-A Ammonium Diuranate (ADU) Bulk Blending System Rev. 2 CF-10-009 Continuity Log for Certified Welders 12/14/2008 ISA 05 ADU Bulk Blending System Rev. 17 Miscellaneous ISA 14 IFBA Processing Rev. 16 88020 Procedures CF-10-009 Qual Training Record - Certified Welders Rev. 3
8 Inspection Procedure Type Designation Description or Title Revision or Date CF-81-113 SAFETY SIGNIFICANT INTERLOCKS FUNCTIONALITY VERIFICATION Rev. 4 CF-96-016 IFBA Cassette H2 Sample Blend Rev. 5 COCL-PO4 DETERMINATION OF WATER BY COULOMETRIC Rev. 37 COP-811001 Fitzmill Rev. 61 COP-811002 Automatic Sampler Rev. 5 COP-814201 Re-sampling of Line Product Materials Rev. 38 COP-814760 Functional Verification of Safety Significant Controls - ADU Dump Hood Rev. 4 COP-816019 Operation of the Automatic UO2 Powder Sampler Rev. 8 MCP-108151 ADU Bulk Blending Container Inspection and Repair Rev. 5 PM20321 HEPA FILTER HOUSE INSPECTION CHECKLIST 11/16/2022 RA-304 Criticality Accident Alarm System Rev. 17 Self-Assessments EHS-AUDIT-22-7 Formal Compliance Audit Report 08/11/2022 146345 HEPA FILTER HOUSE INSOECTION - 13 WEEK 11/16/2022 Dispatch 101979 Safety Inspection of Moderation Control Barriers 04/07/2022 Dispatch 146083 Bulk Container Inspection 11/14/2022 Dispatch 146207 Bulk Container 55 Inspection 11/15/2022 Dispatch 146483 Bulk Container #17 Dispatch 11/14/2022 OEM83106 CFF - Dispatch #113282 06/01/2022 OM81217 Safety Interlock - ADU Dump Hood 04/29/2022 PM 81070 Checklist Bulk Container Inspection Checklists for Bulk Containers 04, 17 and 55 11/15/2022 PM20321 HEPA Filter House Inspection 11/16/2022 Work Orders PM81070 Bulk Container Inspection 11/17/2022