ML21113A229

Framatome - Richland, U.S. Nuclear Regulatory Commission Inspection Report Number 70-1257/2021-001

ML21113A229
Person / Time
Site:	Framatome ANP Richland
Issue date:	04/23/2021
From:	Eric Michel NRC/RGN-II/DFFI/FFB2
To:	Stephens L Framatome
References
IR 2021001
Download: ML21113A229 (9)

Text

April 23, 2021 Mr. Lance Stephens Acting Site Manager Framatome Inc.

2101 Horn Rapids Road Richland, WA 99354-0130

SUBJECT:

FRAMATOME-RICHLAND - NRC INSPECTION REPORT 07001257/2021001

Dear Mr. Stephens:

On March 31, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Framatome-Richland. On February 25, 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/

Eric C. Michel, Chief Projects Branch 2 Division of Fuel Facility Inspection Docket No. 07001257 License No. SNM-1227

Enclosure:

As stated cc w/ encl: Distribution via LISTSERV

ML21113A229 SUNSI Non-Sensitive Publicly Available Review Sensitive Non-Publicly Available OFFICE RII:DFFI/PB2 RII:DFFI/PB2 RII:DFFI/PB2 RII:DFFI/PB2 NAME T. Vukovinsky P. Glenn G. Goff E. Michel DATE 4/16/2021 4/16/2021 4/16/2021 4/23/2021 U.S. NUCLEAR REGULATORY COMMISSION INSPECTION REPORT REGION II Docket Number: 07001257 License Number: SNM-1227 Report Number: 07001257/2021001 Enterprise Identifier: I-2021-001-0110 Licensee: Framatome Inc.

Facility: Framatome-Richland Location: Richland, WA Inspection Dates: February 22, 2021 to February 25, 2021 Inspectors: P. Glenn, Fuel Facilities Inspector G. Goff, Fuel Facilities Inspector Approved By: Eric C. Michel, Chief 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 NRC 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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REPORT DETAILS 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 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, Chapter 3, "Integrated Safety Analysis (ISA) and ISA Summary," and Chapter 11, Management Measures, of the facilitys license application, and applicable licensee procedures.

Identification of Safety Controls and Related Programs (IP Section 02.01)

The inspectors selected specific process areas for inspection based on the safety basis information of the facility, the risk/safety significance of the process areas, the description of plant changes submitted to the NRC, and past plant performance documentation. For the process areas of interest, the inspectors selected a sample of accident sequences in nuclear criticality safety and chemical safety based on the information provided in the integrated safety analysis (ISA) summary and safety basis documentation. 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:

System 328 - Dry Conversion Facility (DCF) Scrap Download Hood Operations Accident sequences reviewed:

328-1.2, 328-1.5, 328-1.7, 328-3.1, 328-3.2, 328-3.3, 328-3.7, 328-4.5.1, 328-4.5.2, 328-4.11, 328-4.12, 328-6.1, and 328-6.2 System 270 - Scrap Uranium Recovery Facility (SURF) Solvent Extraction (SX) and Raffinate Treatment Accident sequences reviewed:

270-510, 270-512. and 270-526 2

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:

IROFS for System 328 (DC Scrap Download Hood Operations):

1502, 1614, 2203, 3602, 3604.1, 3608, 7002, 7003 IROFS for System 270 (Mixer-Settler process):

0.80, 816, and System 270 safety controls 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 11 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:

• Inspectors performed plant walkdowns to review selected safety controls

• Inspectors reviewed applicable procedures to review selected safety controls

• The inspectors discussed with the licensee the design basis assumptions and the assigned values such as the frequency index, the probability of failure on demand, the controlled event index, severity category, and the uncontrolled and unmitigated risk in order to verify compliance with NUREG 1520, process hazards analyses, and plant operational history. The inspectors also discussed the impact upon IROFS by configuration management and changes in generic chemical exposure sequences in order to determine that safety was not diminished.

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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. Specifically, the inspectors conducted the following:

• Reviewed numerous preventive maintenance and instrument repetitive maintenance records (includes work orders) for applicable IROFS listed above

• Conducted walk-downs to verify passive engineered controls (PECs) were within the stated dimensions listed in the ISA Summary for the Mixer-Settler process

• Observed a nuclear criticality safety analysis (NCSA) audit of System 163 of the Ammonia Recovery Facility

• Reviewed select corrective actions program (CAP) entries as noted in the documents reviewed section of this inspection report

• Reviewed select audits and self-assessments associated with plant-wide nuclear operations including chemical safety and process areas that implement IROFS

• Reviewed training documents and interviewed select operators assigned to DC Scrap Download Hood Operations

• Reviewed the safety-significant evaluation process which included a review of select non-reportable internal incidents and the associated investigation INSPECTION RESULTS No violations of more than minor significance were identified.

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

• On February 25, 2021, the inspectors presented the NRC 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 88020 Corrective Action CR 2020-0840 Documents CR 2020-2628 CR 2020-2817 CR 2020-2870 Corrective Action CR 2021-0443 Documents Resulting from Inspection Miscellaneous Plant Safety Committee 11/17/2020 DCF Scrap Download Hood Operator Training Records HRR-CRT- System 328 - DCF Scrap Download Hood Operations 000328-007 EXAM 2020-114 IRM CHANGE ATTACHMENT E04-NCSA-163 Industrial Waste Division of Fuel Facility Inspection Water Version 32.0 Treatment Facilities E04-NCSA-260 SURF Dissolution Version 3.0 E04-NCSA-270 SURF Solvent Extraction (SX) and Raffinate Treatment Version 7.0 E04-NCSA-328 DCF Scrap Download Hood Operations Version 9.0 E04-NCSA-328 DCF Scrap Download Hood Operations Version 9 E04-NCSS-G07 Building and Facilities NCS Design Requirements Including Version 10.0 Initial Conditions and Bounding Assumptions E04-NCSS-G08 Plant Wide Chemical Safety IROFS Version 11.0 E04-NCSS-G20 Receipt of UOx Powders & Pellets from Off-Site Vendors Version 15.0 E04-NCSS-G81 45-Gallon Powder Drums with Neutron Absorbing Inserts Version 22.0 E14-01-G08 Generic Comingled Chemical Exposure Version 2.0 E15-01-1, Hazardous Materials Interaction Matrix Version 26 Appendix A E15-03-002 Integrated Safety Analysis Program Standard - Risk Matrix Version 10.0 E15-03-002 Integrated Safety Analysis Program Standard - Risk Index Version 10.0 Definitions & Table 6 Resultant Risk Category E15-03-002 Consequence Category Table - Table 2 Consequence Version 10.0 Categories EMF-S35128 S35128-2 Incoming Conversion Uranium Feed Materials Revision 2.0 6

Inspection Type Designation Description or Title Revision or Procedure Date ISA Summary - Part 2 - Chapter 23 - Generic Comingled Chemical Exposure Version 1.0 E15-01-2.23 Process Hazards Accident Sequences # 008 Revision 412 Analysis (PHA)

STD-20-003 2020 Biannual Chemical Safety Audit, Part 1 04/13/2020 STD-20-012 2020 Biannual Chemical Safety Audit, Part 2 10/30/2020 Procedures MCP-30340 Essential Material Class I: 45-Gallon Powder Containers Version 6.0 with Neutron Absorber Inserts SOP-40251 Removing and Returning Poisoned 45-Gallon Drums into Version 11.1 Service SOP-40915 DCF Scrap Downloading Hood Operation Version 12.0 SWI-50044 Neutron Absorber Insert Weld Repair/Barrel (Skin) Version 4.0 Replacement Procedure SWI-50301 Installing Absorbing Inserts in Drum Skins 3.0 Self-Assessments E04-06-002 Routine Nuclear Criticality Safety Audits Version 5.2 Work Orders 13444889 / SCALE DCF 6 MO IN C328I001 7