IR 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 | |
| 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:
Report Number:
Enterprise Identifier:
I-2024-010-0033
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
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:
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
Procedure
Type
Designation
Description or Title
Revision or
Date
CARD 22-21848
FWH 3S Shell Thickness
2/15/2022
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
Monitoring
03/31/2024
CR-2024-37620
FWH 3S Shell Thickness Evaluation Acceptable for Operation
in Cycle 23
03/31/2024
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
CR-2024-37722
Frayed Cloth Jacketing on Individual Conductors in N22P400,
EDP 600010
04/02/2024
CR-2024-37750
RF22 IVVI: Jet Pumps 01-10 WD-1 Wedge Assembly
Monitoring
04/02/2024
CR-2024-37751
RF22 IVVI: Jet Pump Auxiliary Wedge Monitoring
04/02/2024
Corrective Action
Documents
CR-2024-37762
RF22 MES83-114 Inspection -Torus Immersion
Space -Indications Identified in Bays 4 and 5
04/02/2024
CR-2024-36948
NRC IP 71003 License Renewal Phase I Inspection - OTI
Form Signature
03/15/2024
Corrective Action
Documents
Resulting from
Inspection
CR-2024-37063
24 NRC License Renewal Phase I Inspection - CRs Not
Written as Required for Selective Leaching Inspections Not
Meeting Acceptance Criteria
03/21/2024
Drawings
M 83761
Low Pressure Feedwater Heater No. 3N & 3S
2101251.302
Fermi Buckling Analysis of Six Feedwater Heaters
03/22/2022
SL-017546
Drywell Sand Cushion Corrosion Rate Evaluation
TBI-1F
Structures Monitoring Program Walkdown Record of Reactor
Feed Pump Rooms
03/31/2020
Engineering
Evaluations
TBI-1F (Reactor
Feed Pump
Rooms)
Structures Monitoring Program Walkdown Record
03/26/2024
38130919-175
N3021F004B Valve Body and Upstream & Downstream Piping
Internals One Time Inspection
10/02/2018
71003
NDE Reports
65196083
High Pressure Control Valve 4 One Time Inspection Report
04/04/2024
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
275885
FWH 3S, FWH 3S1, FWH3S-3, FWH 3S-4
03/27/2024
MES26
Flow Accelerated Corrosion Prediction, Detection, and
Correction
Procedures
MMR14
Structures Monitoring
2417424
Fire Protection Ring Header Isolation Valve
03/09/2022
50788457
Fire Protection Ring Header Supply to Hydrants #6, #7, and #8
Isolation Valve
04/06/2023
59080129
(FAC 15) Perform Erosion/Corrosion Inspection of Heater
Drains System Piping
03/30/2022
60727483
Fire Protection Ring Header Isolation Valve
08/16/2023
60807250
Fire Protection Ring Header Isolation Valve
08/17/2023
Work Orders
275885
FAC 20-RF22-FWH 3S Shell UT Perform Erosion/Corrosion
Inspection of Heater Drains System Piping
03/26/2024