IR 05000237/2024010
| ML24220A241 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 08/09/2024 |
| From: | Karla Stoedter NRC/RGN-III/DORS/EB1 |
| To: | Rhoades D Constellation Energy Generation, Constellation Nuclear |
| References | |
| IR 2024010 | |
| Download: ML24220A241 (1) | |
Text
SUBJECT:
DRESDEN NUCLEAR POWER STATION - NRC AGE-RELATED DEGRADATION INSPECTION REPORT 05000237/2024010 AND 05000249/2024010
Dear David Rhoades:
On July 2, 2024, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Dresden Nuclear Power Station, Units 2 and 3 and discussed the results of this inspection with C. Joseph, Site Vice President 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, Karla K. Stoedter, Chief Engineering Branch 1 Division of Operating Reactor Safety Docket Nos. 05000237 and 05000249 License Nos. DPR-19 and DPR-25
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000237 and 05000249
License Numbers:
Report Numbers:
05000237/2024010 and 05000249/2024010
Enterprise Identifier:
I-2024-010-0057
Licensee:
Constellation Energy Generation, LLC
Facility:
Dresden Nuclear Power Station, Units 2 and 3
Location:
Morris, IL
Inspection Dates:
June 10, 2024 to July 02, 2024
Inspectors:
E. Fernandez, Senior Reactor Inspector
I. Hafeez, Senior Reactor Inspector
A. Shaikh, Senior Reactor Inspector
Approved By:
Karla K. Stoedter, Chief
Engineering Branch 1
Division of Operating Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a NRC inspection at Dresden Nuclear Power Station, Units 2 and 3, 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.
REACTOR SAFETY
71111.21N.04 - Age-Related Degradation Age-Related Degradation
The inspectors selected a sample of components and structures to verify that engineering performance and maintenance activities addressed age-related degradation and that problems were appropriately identified, addressed and corrected.
Samples were selected considering risk insights and the potential for degradation.
Specifically, the inspectors selected samples that were risk-significant and either had indications of age-related degradation or were exposed to environments that could cause age-related degradation. The inspectors considered site-specific and industry-wide operating experience to identify samples and included both active and passive sub-components within each component or structure.
For each selected sample below, the inspectors reviewed the licensee's engineering and maintenance activities credited to address age-related degradation to assess whether they were being performed using applicable standards and procedures, evaluated against appropriate acceptance criteria, and that maintenance and condition monitoring was completed at an appropriate interval. The inspectors also assessed whether issues identified during licensee activities were being entered into and addressed by the applicable station processes including the corrective action program, and whether periodic assessments of maintenance effectiveness and operating experience were being completed, including feedback and process adjustments.
- (1) Primary Containment Isolation Valves 2-1301-20 and 3-1301-1
- (2) Unit 2 and Unit 3 High Pressure Coolant Injection Room Coolers
- (3) Unit 2 and Unit 3 Emergency Diesel Generator Air Accumulator Tanks
- (4) Unit 2 and Unit 3 Reactor Building Closed Cooling Water Heat Exchangers
- (5) Unit 2 and Unit 3 Condensate Storage Tanks
- (6) Diesel Fire Pumps
- (7) Unit 2 and Unit 3 Instrument Air Dryers
- (8) Electromatic Relief Valves
- (9) Reactor Manual Control System
- (10) Safety Related 480 Vac Breakers
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On July 2, 2024, the inspectors presented the NRC inspection results to C. Joseph, Site Vice President and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Calculations
DRE98-0077
Dresden HPCI Room Thermal Response with Reduced
Room Cooler
001
U2 HPCI Room Cooler Outboard Fan Vibe Reading in
Alert Range
10/14/2016
Discolored Cables in Riser 325
11/07/2016
U2 HPCI Room Cooler Abnormal Noise
10/16/2018
U2 HPCI Room Cooler Leak Identified
04/08/2019
U2 HPCI Room Cooler Noise Change
2/22/2019
Packing Leak on AO 3-1301-17 Main Steam Line Inbd Iso
Vlv
07/14/2020
3-1301-17 Iso Cond Vent Valve Solenoid Buzzing
01/31/2022
Packing Leak on 3-1301-17
Vibration Data Anomaly on the U2HPCI Room Cooler
04/05/2023
Corrective Action
Documents
Light Corrosion on 2-1301-20 Valve Bolting
06/13/2024
NRC ID: Identified Loose Fasteners Behind Bus 2B
06/12/2024
NRC ID: Identified Loose Fasteners Behind Bus 3B
Perform NDE Inspection of Piping for U3 HPCI Room
Cooler
06/13/2024
NRC ID: Identified BCD Device Near Bus 39
06/14/2024
NRC ID: NRC CONCERN CALC CHANGES/BASIS
06/27/2024
Corrective Action
Documents
Resulting from
Inspection
ARDI NRC ID: NRC Question ERV Solenoid Conductor
Temperature
07/01/2024
Drawings
Schematic Diagram Reactor Manual Control Sheet 2
Rev. L
CDBI-DRE02-
066A
Emergency Diesel Generator & Auxiliaries License
Renewal
CDBI-DRE02-
66A
Emergency Diesel Generators & Auxiliaries License
Renewal
ER-DR-330-1001
ISI Program Plan Sixth Inspection Interval
LRTI-15
AMR Gas and Ventilation Air (M01)
71111.21N.04
Miscellaneous
Preventative Maintenance Inspection of GE Types AK-25
Circuit Breakers
Rev. 11
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Preventative Maintenance Inspection of GE 480V Types
AK-50/75, AKS-50, & AKR-75/100 Circuit Breakers and
Cubicles
Rev. 13
PO# 12382
Certificate of Conformance HPCI Cooling Coil Material
10/18/2018
05142242
U3 Eddy Current Test HPCI CLR Coil
05/05/2023
05145356
U2 Eddy Current Test HPCI RM CLR Coil
05/08/2023
UT Thickness U2 Air Dryers
NDE Reports
UT Thickness Sheet U3 Air Dryers
04949809
Pressure Gauge Out of Tolerance During Power Labs
Calibration
Rev. 1
Procedures
MA-DR-EM-4-
200
Dresser Electromatic Solenoid Actuator Rebuild
Instructions
Rev. 13
00986900-01
Inspect/Replace HPCI Room Cooler Fan Bearings
03/18/2013
01490829
Replace HPCI Room Cooler Coiling Coil U2
01/09/2019
01804350
Unit 2/3 Internal UT Inspection of CST-B Tank Bottom
10/23/2023
01805284
Unit 2/3 Internal UT Inspection of CST-A Tank Bottom
09/24/2023
04589133
2A RBCCW HX Inspection and Eddy Current Testing
01/03/2022
04599405
3A RBCCW HX Inspection and Eddy Current Testing
2/05/2019
04601529
3B RBCCW HX Inspection and Eddy Current Testing
01/27/2020
04749723
2B RBCCW HX Inspection and Eddy Current Testing
01/02/2023
04949809
PRESSURE GAUGE OUT OF TOLERANCE DURING
POWER LABS CALBRATION
10/31/2020
05145356-01
Eddy Current HPCI Room Cooler
03/09/2023
05194571
Unit 2/3 Diesel Fire Pump Flow Capacity Test
03/23/2023
275017
Unit 1 Diesel Fire Pump Flow Capacity Test
01/31/2024
Work Orders
05397632-01
Eddy Current HPCI Room Cooler Coils
03/03/2023