IR 05000341/2024010

NRC Inspection Report 05000341/2024010

ML24123A254
Person / Time
Site:	Fermi
Issue date:	05/06/2024
From:	Dariusz Szwarc NRC/RGN-III/DORS/ERPB
To:	Peter Dietrich DTE Electric Company
References
IR 2024010
Preceding documents:	ML23334A190 (1 December 2023)
Download: ML24123A254 (1)

Text

SUBJECT:

FERMI POWER PLANT, UNIT 2 - NRC INSPECTION REPORT 05000341/2024010

Dear Peter Dietrich:

On April 4, 2024, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Fermi Power Plant, Unit 2 and 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 findings or 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, Dariusz Szwarc, Acting Branch Chief Engineering and Reactor Projects Branch Division of Operating Reactor Safety Docket No. 05000341 License No. NPF-43

Enclosure:

As stated

Inspection Report

Docket Number: 05000341

License Number: NPF-43

Report Number: 05000341/2024010

Licensee: DTE Electric Company

Facility: Fermi Power Plant, Unit 2

Location: Newport, MI

Inspection Dates: March 25, 2024 to April 05, 2024

Inspectors: M. Domke, Reactor Inspector

Approved By: Dariusz Szwarc, Acting Branch Chief Engineering and Reactor Projects Branch Division of Operating Reactor Safety

Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a NRC inspection at Fermi Power Plant, Unit 2, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.

List of Findings and Violations

No findings or violations of more than minor significance were identified.

Additional Tracking Items

None.

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. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. 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.

OTHER ACTIVITIES

- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL

71003 - Post-Approval Site Inspection for License Renewal Post-Approval Site Inspection for License Renewal

(1) The Inspector conducted a Phase 1 license renewal inspection. The following aging management programs were evaluated by the Inspector:

• Flow Accelerated Corrosion o Commitment 15, in part, revises procedures to indicate that the flow-accelerated corrosion program manages loss of material due to erosion mechanisms of cavitation, flashing, liquid droplet impingement, and solid particle erosion for any material in treated water or steam environments.

o Inspectors conducted walkdowns of 3S Feedwater Heater and observed wall thickness examinations and reviewed associated inspection reports for implementation of acceptance criteria.

• Protective Coating Monitoring and Maintenance Program and Coating Integrity Program o Commitment 29, in part, revises plant procedures to include in the program Service Level I coating applied to steel and concrete surfaces of the steel containment vessel, (e.g., steel containment vessel shell, structural steel, supports, penetrations, and concrete walls and floors).

Revisions include information and instructions for monitoring Service Level I coating systems to be used for the inspection of coatings in accordance with guidelines identified in American Society for Testing and Materials (ASTM) standard ASTM D5163-08.

o Commitment 36, Coating Integrity Program, is a new program that included periodic visual examinations of coatings/linings applied to internal surfaces of in-scope piping, piping components, heat exchangers, and tanks where loss of coating or lining integrity could prevent accomplishment of license renewal intended functions.

o Inspectors conducted interviews with program owners, reviewed recently completed torus coating examination photos, and conducted walkdowns for activities associated with residual heat removal end bell coating refurbishment.

• Structures Monitoring o Commitment 34, in part, revises procedures to include the following for the detection of aging effects: Personnel involved with the inspection and evaluation of structures meet qualification guidance in American Concrete Institute (ACI) standard ACI 349.3R-02; Structures will be inspected at least once every 5 years; If normally inaccessible areas become accessible due to plant activities, then an inspection of these areas shall be conducted. It also revises plant procedures to prescribe quantitative acceptance criteria base on ACI 349.3R-02 and information provided in industry codes, standards, and guidelines including ACI 318, American National Standards Institute (ANSI)/American Society of Civil Engineers (ASCE) guideline 11, and relevant American Institute of Steel Construction (AISC)specifications.

o Inspectors conducted walkdowns of south reactor feed pump room during licensee structural examinations and reviewed associated inspection reports against acceptance standards. Inspectors also conducted documentation reviews for a sample of previously performed structures monitoring examinations to assure those examinations were conducted in accordance with programmatic requirements including referenced standards.

• Selective Leaching o Commitment 32 implements the new selective leaching program that will demonstrate the absence of selective leaching in a sample of components fabricated from gray cast iron and copper alloys that contain greater than 15% zinc or greater than 8% aluminum exposed to raw water, treated water, waste water, or soil.

o Inspectors reviewed a sample of completed examinations for fire protection ring header isolation valves to assure adequate detection methods were used to detect selective leaching. Licensee exams reviewed components for no visible porosity or honeycomb-like structure, color changes, structural removal from mechanical exams, or laboratory results analyzing for selective leaching presence.

• Containment In-service Inspection - IWE o Commitment 9, in part, revises plant procedures to determine drywell shell thickness in the sand cushion areas before the period of extended operation and once each 10-year interval during the period of extended operation. From the results, develop a corrosion rate to demonstrate that the drywell shell will have sufficient wall thickness to perform its intended function through the period of extended operation.

o Inspectors conducted documentation reviews of engineering evaluations that provided estimates of the corrosion rate in the Unit 2 drywell shell in the sand cushion area that provides guidance and direction on the current shell thickness in this area, an estimate of the current corrosion rate based on available data and industry experience, and recommendations for future monitoring of this area based on regulatory guidance and applicable licensee operating experience.

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

The inspectors verified no proprietary information was retained or documented in this report.

• On April 4, 2024, the inspectors presented the NRC inspection results to Peter Dietrich, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71003 Corrective Action CARD 22-21848 FWH 3S Shell Thickness 02/15/2022

Documents CR-2024-37514 Div 2 EESW Return Line Support Loose Pipe Clamp Bolt 03/29/2024

CR-2024-37619 RF22 IVVI: Jet Pumps 11-20 WD-1 Wedge Assembly 03/31/2024

Monitoring

CR-2024-37620 FWH 3S Shell Thickness Evaluation Acceptable for Operation 03/31/2024

in Cycle 23

CR-2024-37682 HPCI Test Line Spring Settlings Out of Tolerance 04/01/2024

CR-2024-37688 RF22 IVUT: Relevant Indications Identified at Core Shroud H3 04/01/2024

Weld

CR-2024-37722 Frayed Cloth Jacketing on Individual Conductors in N22P400, 04/02/2024

EDP 600010

CR-2024-37750 RF22 IVVI: Jet Pumps 01-10 WD-1 Wedge Assembly 04/02/2024

Monitoring

CR-2024-37751 RF22 IVVI: Jet Pump Auxiliary Wedge Monitoring 04/02/2024

CR-2024-37762 RF22 MES83-114 Inspection -Torus Immersion 04/02/2024

Space -Indications Identified in Bays 4 and 5

Corrective Action CR-2024-36948 NRC IP 71003 License Renewal Phase I Inspection - OTI 03/15/2024

Documents Form Signature

Resulting from CR-2024-37063 2024 NRC License Renewal Phase I Inspection - CRs Not 03/21/2024

Inspection Written as Required for Selective Leaching Inspections Not

Meeting Acceptance Criteria

Drawings M 83761 Low Pressure Feedwater Heater No. 3N & 3S 6

Engineering 2101251.302 Fermi Buckling Analysis of Six Feedwater Heaters 03/22/2022

Evaluations SL-017546 Drywell Sand Cushion Corrosion Rate Evaluation 0

TBI-1F Structures Monitoring Program Walkdown Record of Reactor 03/31/2020

Feed Pump Rooms

TBI-1F (Reactor Structures Monitoring Program Walkdown Record 03/26/2024

Feed Pump

Rooms)

NDE Reports 38130919-175 N3021F004B Valve Body and Upstream & Downstream Piping 10/02/2018

Internals One Time Inspection

65196083 High Pressure Control Valve 4 One Time Inspection Report 04/04/2024

Inspection Type Designation Description or Title Revision or

Procedure Date

275885 FWH 3S, FWH 3S1, FWH3S-3, FWH 3S-4 03/27/2024

Procedures MES26 Flow Accelerated Corrosion Prediction, Detection, and 21

Correction

MMR14 Structures Monitoring 7

Work Orders 42417424 Fire Protection Ring Header Isolation Valve 03/09/2022

50788457 Fire Protection Ring Header Supply to Hydrants #6, #7, and #8 04/06/2023

Isolation Valve

59080129 (FAC 15) Perform Erosion/Corrosion Inspection of Heater 03/30/2022

Drains System Piping

60727483 Fire Protection Ring Header Isolation Valve 08/16/2023

60807250 Fire Protection Ring Header Isolation Valve 08/17/2023

275885 FAC 20-RF22-FWH 3S Shell UT Perform Erosion/Corrosion 03/26/2024

Inspection of Heater Drains System Piping

7