IR 05000237/2024004
| ML25041A150 | |
| Person / Time | |
|---|---|
| Site: | Dresden  (DPR-019, DPR-025) |
| Issue date: | 02/10/2025 |
| From: | Robert Ruiz NRC/RGN-III/DORS/RPB1 |
| To: | Rhoades D Constellation Energy Generation |
| References | |
| EPID I-2024-004-0058 IR 2024004 | |
| Download: ML25041A150 (1) | |
Text
SUBJECT:
DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3 - INTEGRATED INSPECTION REPORT 05000237/2024004 AND 05000249/2024004
Dear David Rhoades:
On March 31, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Dresden Nuclear Power Station, Units 2 and 3. On January 21, 2025, the NRC inspectors discussed the results of this inspection with H. Patel, Plant Manager, 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, Robert Ruiz, Chief Reactor Projects Branch 1 Division of Operating Reactor Safety Docket Nos. 05000237 and 05000249 License Nos. DPR-19; DPR-25
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000237 and 05000249
License Numbers:
Report Numbers:
05000237/2024004 and 05000249/2024004
Enterprise Identifier:
I2024004-0058
Licensee:
Constellation Energy Generation, LLC
Facility:
Dresden Nuclear Power Station, Units 2 and 3
Location:
Morris, IL
Inspection Dates:
October 01, 2024 to December 31, 2024
Inspectors:
J. Cassidy, Senior Health Physicist
Z. Coffman, Resident Inspector
J. Kulp, Senior Reactor Inspector
J. Kutlesa, Senior Emergency Preparedness Inspector
M. Porfirio, Illinois Emergency Management Agency
C. St. Peters, Resident Inspector
J. Steffes, Senior Resident Inspector
Approved By:
Robert Ruiz, Chief
Reactor Projects Branch 1
Division of Operating Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated 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.
PLANT STATUS
Unit 2 began the inspection period at rated thermal power. On December 4, 2024, reactor power was lowered to 59 percent to perform a rod pattern adjustment and control rod recovery following maintenance. The unit was returned to full power on December 5, 2024, and remained at or near full power for the remainder of the inspection period.
Unit 3 began the inspection period in coast down to prepare for refueling outage D3R28. On October 1, 2024, reactor power was lowered to approximately 26 percent to troubleshoot and repair condenser inleakage. Condenser inleakage was addressed, and the unit was returned to full power on October 5, 2024. On October 28, 2024, the unit was shut down to commence D3R28. The unit was synchronized to the grid on November 15, 2024, and full power was achieved on November 18, 2024. On November 23, 2024, reactor power was lowered to approximately 68 percent to perform rod pattern adjustment. The unit was returned to full power the next day and remained at or near full power for the remained of the inspection period.
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 performed activities described in IMC 2515, Appendix D, Plant Status, observed risk significant activities, and completed onsite portions of IPs. 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
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (1 Sample)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Unit 3 fuel pool cooling on October 29 - November 22, 2024
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated system configurations during a complete walkdown of the low pressure coolant injection (LPCI) system on October 16 - November 22, 2024
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:
- (1) Fire zone (FZ) 8.2.5 D Unit 3 low pressure heater bay elev. 517' on October 29, 2024
- (2) FZ 8.2.5E Unit 3 high pressure heaters/steam line elev. 517' on November 1, 2024
- (3) FZ 1.2.1 Unit 3 drywell primary containment elev. 517' on November 3, 2024
- (4) Unit 2 station blackout diesel generator on December 17, 2024
71111.08 G - Inservice Inspection Activities (BWR) BWR Inservice Inspection Activities Sample-Nondestructive Examination and Welding Activities (IP Section 03.01)
The inspectors evaluated boiling water reactor nondestructive testing by reviewing the following examinations from October 28-November 1, 2024 (1)
1. Ultrasonic Examination (UT) of A Reactor Recirculation Pump Discharge
Pipe to Tee Weld 3/1/0201 A28/RRA47F
2. UT of Reactor Vessel Head Vent Line Pipe to Flange Dissimilar Metal Weld
3/1/02154/41
3. UT of N122 Nozzle to Shell Weld 3/1/RPV LWR HD/N122
4. Visual Examination (VT1) of Core Spray Sparger Bracket Weld CSS 12
SB 045
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (1 Sample)
- (1) The inspectors observed and evaluated licensed operator performance in the control room during shutdown on October 28, 2024, for refueling outage D3R28
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated licensed crew performance in the main control room simulator during just in time training prior to D3R28 refueling outage, on October 3, 2024
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (4 Samples)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:
- (1) Fire protection system
- (2) High pressure injection system
- (3) Instrument air
- (4) Unit 2 offgas system erratic operation as documented in action report (AR) 4799921
Quality Control (IP Section 03.02) (1 Sample)
The inspectors evaluated the effectiveness of maintenance and quality control activities to ensure the following SSC remains capable of performing its intended function:
- (1) Containment cooling service water system (CCSW)
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (3 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Unit 3 emergency diesel generator 36641-181Y1 timer relay issue, as documented in AR 4769615 and AR 4771354
- (2) Unit 3 motor operated valve (MOV) 31501-13 A motor failed to reengage with actuator for pre-outage MOV diagnostic testing, as documented in AR 4811673
- (3) Unit 3 undervoltage relay failed during surveillance test as documented in AR
===4813364
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02)
=
The inspectors evaluated the following temporary or permanent modifications:
- (1) Unit 3 feedwater regulating valve control systems
- (2) NRC staff review of hypothetical rupture and subsequent release of natural gas of the Three Rivers Lateral pipeline lateral to Dresden Power Station Unit 2 and 3. The inspectors performed onsite verification of the installation of the pipeline on July 26, 2024, to complete the modification sample begun in the 2024 first quarter report ML24121A249. The inspector noted the pipeline proximity to the meteorological tower to be closer than initially designed and the connection manifold to be above ground and exposed to an open-air environment. The NRC staff reevaluated the noted differences in Assessment of Potential Hazards from the Three Rivers Pipeline to the Dresden Power Station Units 2 and 3 - Reduced Distance to the Meteorological Tower and Presence of the Pipeline Manifold, ML25027A415 and did not identify any safety or regulatory concerns.
- (3) EC629911, Update Piping Spec to Expand Use of Lokring, Revision 0
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated refueling outage D3R28 activities from October 28 to November 15, 2024
71111.24 - Testing and Maintenance of Equipment Important to Risk
The inspectors evaluated the following testing and maintenance activities to verify system operability and/or functionality:
Post Maintenance Testing (PMT) (IP Section 03.01) (12 Samples)
(1)2/3 B control room heating, ventilation and air conditioning (HVAC) post maintenance testing following planned work window, on September 25, 2024
- (2) Unit 2 high pressure coolant injection (HPCI) post maintenance testing following replacement of Servo card, per WO 5552589
- (3) Unit 3 2D main steam isolation valve (MSIV) asleft local leak rate test (LLRT)following maintenance, per WO 1704798
- (4) U3 CCSW run following pipe welding and planned maintenance on November 12, 2024
- (5) Unit 3 control rod scram time testing following routine maintenance during refueling outage, per WO 5432497
- (6) Unit 3 fuel pool radiation monitor channel B calibration and functional test following maintenance, on November 26, 2024
- (7) Hydrostatic testing on November 10, 2024
- (8) Unit 2 reactor protection system channel A testing following fuse replacement, on November 22, 2024
- (9) Unit 2 CCSW test following A heat exchanger discharge valve maintenance per WO 5550335
- (10) Unit 3 west LPCI/core spray corner room sump pump system test following discharge check valve maintenance per WO 5042133
- (11) Unit 3 2B MSIV post maintenance testing following maintenance, per WO 5128802 (12)3A main steam line target rock relief valve testing following maintenance per WO 5432493
Surveillance Testing (IP Section 03.01) (2 Samples)
- (1) Unit 3 Division I Undervoltage test per DOS 660003, on October 29-31, 2024
Containment Isolation Valve Testing (IP Section 03.01) (1 Sample)
- (1) Asfound LLRT of valve 30299-99 A & 116 A, 0299100 A & 117 A,
029998 A & 117 A, and 029997 A &116 A, reactor vessel water level instrumentation system (RVWLIS) backfill, on October 31, 2024 Diverse and Flexible Coping Strategies (FLEX) Testing (IP Section 03.02)
- (1) Ultimate heat sink FLEX pump 2 performance test in accordance with WO 542103301
71114.04 - Emergency Action Level and Emergency Plan Changes
Inspection Review (IP Section 02.0102.03) (1 Sample)
- (1) The inspectors evaluated the following submitted Emergency Action Level and Emergency Plan changes.
- EPAA1004, Constellation Radiological emergency Plan Annex for Dresden Station, Rev 40
- EPAA1004 Addendum 1, Dresden Station OnShift Staffing Technical basis, Rev 3
- EPAA1004 Addendum 2, Dresden Evacuation Time Estimates, Rev 2
- EPAA1201001, ReLink DRE Emergency Plan to the Fleet and Revise Plan to Reflect IPAWS Implementation, Evaluation No. 2326 This evaluation does not constitute NRC approval.
71114.06 - Drill Evaluation
Additional Drill and/or Training Evolution (1 Sample)
The inspectors evaluated:
- (1) Dresden technical support center qualification drill on December 10,
RADIATION SAFETY
71124.01 - Radiological Hazard Assessment and Exposure Controls
Radiological Hazard Assessment (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated how the licensee identifies the magnitude and extent of radiation levels and the concentrations and quantities of radioactive materials and how the licensee assesses radiological hazards.
Instructions to Workers (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated how the licensee instructs workers on plant-related radiological hazards and the radiation protection requirements intended to protect workers from those hazards.
Contamination and Radioactive Material Control (IP Section 03.03) (2 Samples)
The inspectors observed/evaluated the following licensee processes for monitoring and controlling contamination and radioactive material:
- (1) Licensee surveys of potentially contaminated material leaving the radiologically controlled area
- (2) Workers exiting the radiologically controlled area at Main Control Point during a refueling outage
Radiological Hazards Control and Work Coverage (IP Section 03.04) (4 Samples)
The inspectors evaluated the licensee's control of radiological hazards for the following radiological work:
- (1) D3R28 - Torus dive activities
- (2) D3R28 - Rx flange repairs
- (3) D3R28 - Control rod drive (CRD) activities
- (4) D3R28 - Cavity decontamination High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (3 Samples)
The inspectors evaluated licensee controls of the following high radiation areas and very high radiation areas (VHRAs):
- (1) Unit 3 torus sludge filters
- (2) Unit 3 torus
- (3) Unit 2 steam tunnel XO area Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 03.06) (1 Sample)
- (1) The inspectors evaluated radiation worker and radiation protection technician performance as it pertains to radiation protection requirements.
71124.03 - InPlant Airborne Radioactivity Control and Mitigation
Use of Respiratory Protection Devices (IP Section 03.03) (1 Sample)
- (1) The inspectors evaluated the licensees use of respiratory protection devices.
OTHER ACTIVITIES-BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
MS05: Safety System Functional Failures Sample (IP Section 02.04)===
- (1) Unit 2 (October 1, 2023 through September 30, 2024)
- (2) Unit 3 (October 1, 2023 through September 30, 2024)
MS08: Heat Removal Systems (IP Section 02.07) (2 Samples)
- (1) Unit 2 (July 1, 2023 through June 30, 2024)
- (2) Unit 3 (July 1, 2023 through June 30, 2024)
MS09: Residual Heat Removal Systems (IP Section 02.08) (2 Samples)
- (1) Unit 2 (July 1, 2023 through June 30, 2024)
- (2) Unit 3 (July 1, 2023 through June 30, 2024)
MS10: Cooling Water Support Systems (IP Section 02.09) (2 Samples)
- (1) Unit 2 (July 1, 2023 through June 30, 2024)
- (2) Unit 3 (July 1, 2023 through June 30, 2024)
71152 A - Annual Follow-up Problem Identification and Resolution Annual Follow-up of Selected Issues (Section 03.03)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- (1) Evaluation and corrective actions for deficiencies in FLEX inventory discovered in yearly audit, as documented in AR 4778175
71152 S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02)
- (1) The inspectors reviewed the licensees corrective action program to identify potential trends in human performance that might be indicative of a more significant safety issue.
INSPECTION RESULTS
Observation: FLEX Annual Inventory Discrepancies 71152 A The inspectors performed a review of FLEX equipment and implementing procedures based on issues noted during annual inventory review as documented on June 2, 2024, in AR 4778175, Annual FLEX Inventory (DOS 0010-43) Discrepancies. The purpose for the inventory/inspection is to ensure availability of the Operations FLEX equipment required in the event of a FLEX scenario. The inspectors noted that similar issues had been discovered during the last two performances of the annual FLEX inventory procedure. The inspectors noted that 5-inch diameter hoses were found missing in the last two prior inventories.
Specifically, during the annual inventory in 2023, 4 of the required 21 hoses in FLEX building B were missing and during the annual inventory in 2024, 6 of the required 21 hoses were missing.
The inspectors reviewed the annual FLEX inventory procedure and noted that the inventory of hoses in FLEX building B were associated with FLEX support guidelines (FSG)procedure 9, Ultimate Heat Sink Supply to FLEX/SAWA (Severe Accident Water Addition)
Manifold. In general, FSGs are guidelines to provide a flexible and diverse means of coping with plant problems when normal procedures have failed or are insufficient to mitigate the problems. The purpose of FSG09 procedure is to provide guidance to supply FLEX/SAWA manifold during ultimate heat sink pump operation.
The inspectors concluded that two questions remained associated with the licensees ability to implement the FLEX support guidelines.
1. With the missing hoses in both annual inventories being the same, were corrective
actions implemented in a timely manner; and
2. Does the missing FLEX equipment adversely impact any of the FLEX strategies?
The inspectors reviewed AR 4696206, Annual FLEX Inventory Discrepancies, as documented on August 13, 2023, and noted that corrective action assignment 2 was created to direct the operations department to correct the FLEX inventory deficiencies. The inspectors determined that the missing hose corrective action was tasked to WO 4698269, D2/3 10Y[Year] FLEX Hose Replacement. The work order was to be completed August 24, 2024, a full year after the hose discrepant condition was discovered. The inspectors questioned the licensee on the timely assignment of corrective actions associated with hose replacement to ensure FLEX guideline implementation since the same discrepant condition occurred during the next annual inventory on June 2, 2024. At the time of inspection, the licensee had created a task to correct the FLEX inventory deficiencies by February 12, 2025.
The inspectors reviewed calculation DRE170008, HCVS Phase 2 SAWA/SAWM Hydraulic Analysis, Revision 0, to determine the most limiting scenario that would require the use of 5-inch hoses. The inspectors determined that 5000 feet of hose would be required to implement the FLEX strategies. Furthermore, the inspectors reviewed procedure FSG-4, Aligning FLEX Pumps for Operation, Revision 3, and FSG-9, Ultimate Heat Sink Supply to FLEX/SAWA Manifold, Revision 3, to ensure the FLEX implement strategies could be implemented with the available hose as determined during the annual inventory. The inspectors determined that available hose inventory would have allowed the licensee to implement the FLEX procedures and did not adversely affect the FLEX strategies.
Observation: Human Performance Trend Review 71152 S The inspectors performed a semiannual review of issues entered into the corrective action program and a cognitive review of plant observations over the period of July 1, 2024, to December 31, 2024, to identify any potential trends that might indicate the existence of a more significant safety issue. In the second half of 2024, the NRC inspectors identified several potential examples of issues with human performance.
On November 5, 2024, the site issued an AR 4815214, Significant Cross-Cutting Aspect Trend. The cross-cutting aspect (CCA) with the trend was in the human performance area of avoiding complacency. This AR was generated due to the site receiving four or more findings in the specific CCA in a rolling four quarter timeframe. The site identified four non-cited violations (NCVs), two in the second quarter of 2024 and two in the third quarter of 2024.
Corrective actions were generated for each of the NCVs, as well as for the aforementioned AR to include reviewing and analyzing the trend, and to complete an organization effectiveness checklist per site procedure. The residents had briefed out each NCV in quarterly exit meetings and communicated with the site the reasoning for the assigned cross-cutting aspect. No additional violations or findings have been identified in this specific area for the fourth quarter 2024.
In addition, the inspectors noted two ARs generated for improperly stored transient combustibles, AR 4816292 and AR 4821303. These ARs were generated following the inspectors bringing the observations to the site and were not identified by site personnel. The site had implemented a fire protection blitz in June 2024 following a noticeable trend in fire protection program implementation issues, which the NRC also documented in the second quarter 2024 report. The inspectors determined that these two specific ARs represented a continued human performance issue with challenging the unknown as the two items documented in the referenced ARs included items being stored on an equipment locker with a floor marking noting the area should not store transient combustibles, and the other documenting combustibles being stored behind a motor control center (MCC) in an area that was frequently passed by licensee staff. In both situations, site employees did not stop to question the storage of combustibles in zones they should not have been stored in. No performance deficiencies were noted with these two items; however, the inspectors noted the link between human performance and the degrading trend identified in implementation of the fire protection program as documented in the second quarter report 2024.
The inspectors noted that challenges in human performance could present challenges to plant operation and equipment. However, for each potential example discussed above, the site took steps and actions to address the discrepant condition. The inspectors did not identify any findings or violations associated with the inspection activities.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On January 21, 2025, the inspectors presented the integrated inspection results to H. Patel, Plant Manager, and other members of the licensee staff.
- On November 1, 2024, the inspectors presented the inservice inspection results to T. Noah, Regulatory Compliance, and other members of the licensee staff.
- On November 8, 2024, the inspectors presented the radiation protection inspection results to J. Jaegers, Radiation Protection Manager, and other members of the licensee staff.
- On December 16, 2024, the inspectors presented the emergency action level and emergency plan changes inspection results to A. Clements, Emergency Preparedness Manager, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or Date
Drawings
M362
Diagram of Fuel Pool Cooling Piping
BI
DOP 1500E1 U3
Unit 3 LPCI and CCSW System Electrical Checklist
DOP 1500M1
Unit 3 LPCI and Containment Cooling Valve
Checklist
Procedures
DOP 1900M1
Unit 3 Fuel Pool Cooling System Checklist
21 U3RB23 A
Unit 3 Drywell Primary Containment Elev. 517'
159 U3TB70
Unit 3 Low Pressure Heater Bay Elev. 517'
160 U3TB71
Unit 3 H.P. Heaters/Steam Line Elevation 517'
24 SBO U2DG
Station Blackout Diesel Generator Unit 2
230 SBO GEN
AREA
SBO General Area 1st and 2nd Floors
2 SBO U2 6A
25V
SBO Unit 2 6A 125 Battery Room
244 SBO U2
MER
SBO MER 2 Unit 2 Mechanical Equipment Room
Fire Plans
Unit 2 SBO SWG EER 3rd Floor East
Corrective Action
Documents
4815204
Core Spray Sparger Bracket Indications
11/05/2024
D3R28 IVVI Technical Evaluation
Engineering
Changes
D3R28 IVVI Indications
3/1/130312/ISO15F
11/02/2024
3/1/02154/41
11/03/2024
D3R28VEN001
3/1/RPV LWR HD/N122
11/04/2024
NDE Reports
RI INR D3R28
IVVI 2401
CSS12 SB 045
10/31/2024
DGP 0101
Unit Startup
210
Procedures
DGP 0201
Unit Shutdown
179
4519442
Unexpected Alarm 9231 U3A IAC Trip
08/29/2022
4694214
HPCI Signal Converter Servo Amp Hardening
Opportunity
08/02/2023
Corrective Action
Documents
20508
3A Instrument Air Dryer Trouble
11/29/2023
Inspection
Procedure
Type
Designation
Description or Title
Revision or Date
4732306
IM 12Y Replace 3C IAC TICs Scheduled Late due
to 3C IAC Push
01/18/2024
4755133
U2 HPCI RM Cooler Outlet Spins Freely
03/04/2024
4763825
U3 Inst Air Comp Trip (3A IAC), Entered DOA
470001
04/05/2024
4783211
06/26/2024
4788769
4.0 Critique - U3 DOA 470001 Entry - Ops Crew 4
07/23/2024
4790344
Red Light Found on for U2 HPCI Signal Converter
07/29/2024
4796906
Received XL3 4324 and 4330
08/26/2024
4800798
Unexpected Alarm: XL3 4330 2TB Mezz Sprinkler
Sys Charged
09/11/2024
4801923
2/3 DFP Lube Oil and Jacket Temps High, Coolant
Overflow
09/15/2024
4806378
MRULE - AR 04801923 to Exceed Screening Date
10/02/2024
4814567
Indications in Heat Affected Zone
11/02/2024
405067
Seismic Qualification of HPCI Turbine Signal
Converter Nutherm Model No. 73315
634420
Add Throttle Valve to SW Pipe to Reduce Its
Pressure to Match CCSW Pressure and Flow in
Line to ECCS Room Coolers
637623
Replace 1TR Relays on Air Compressors
Engineering
Changes
638016
Code Repair of a Through Wall Leak on Line
31510-16"-D Next to Support M1200 D292
Compressed Air System Health Report
11/25/2024
Maintenance Rule (a)(1) Status
10/02/2024
High Pressure Injection System Health Report
10/08/2024
Miscellaneous
NOAA10
Quality Assurance Topical Report (QATR)
ERAA2002
System and Equipment Health Monitoring
ERAA320
Maintenance Rule Implementation Per NEI 18-10
Procedures
NOAA3001001
Nuclear Oversight Independent Inspection Plan
0552950
6RFL PM Insp DC Mtr/Brush HPCI Motor Gear Unit
11/15/2013
473163701
CM Replace CCSW Piping Torus Catwalk
11/08/2018
Work Orders
473163763
CM Replace Div 2 CCSW Piping Torus Catwalk
11/08/2024
Inspection
Procedure
Type
Designation
Description or Title
Revision or Date
473163768
NDE Perform AsLeft VT3 Insp of CCSW Pipe
Support
11/09/2024
473163769
EP Perform VT2 Inspection at System Pressure
11/14/2024
5159854
D3 2Y PM 3B IA Comp Repl Time Delay Relay
"1TR"
08/30/2022
211916
U2 CCSW Div 1 Thru Wall Leak
2/16/2021
4769615
U3 EDG 225310 Panel 26641-181Y1 Timer Relay
Issue
04/25/2024
4771354
U3 EDG 225310 Panel 36641-181Y1 Timer Relay
Issue
05/02/2024
4811673
D3R28 Pre-Outage MOV Diagnostic Test of
31501-13 A
10/23/2024
Corrective Action
Documents
4811956
MOV 31501-13 A Grade 4 Grease in Motor Pinion
Cavity
10/24/2024
2E3346
Schematic Diagram 4160V Bus 341 Standby
Diesel 3 Feed & 241 Tie Breaker
Drawings
2E3350B
Schematic Diagram Diesel Generator 3 Auxiliaries
& Start Relays
BO
Miscellaneous
DAN DG2 (3)
(2/3)B A4
Under Frequency Trip
Procedures
DOA 660001
Diesel Generator Failure
5093099
D3 2Y TS LPCI MO Valve Operability and IST Surv
10/17/2022
Work Orders
5359158
D3 2Y TS LPCI MO Valve Operability and IST Surv
10/14/2024
Engineering
Changes
638687
Upgrade Unit 3 FWRV Control Systems to
Eliminate SPV
K4080
General Work Specification
Maintenance/Modification Work Dresden Station
Units 2 & 3
NES-MS03.6
Guidelines for Use of Lokring Technology
Miscellaneous
USAS B31.1.0
Power Piping
1967
Work Orders
5346557
Upgrade Unit 3 Feedwater Regulating Valve
Control System to Eliminate Single Point
Vulnerability
11/21/2024
Inspection
Procedure
Type
Designation
Description or Title
Revision or Date
Corrective Action
Documents
Resulting from
Inspection
4816292
NRC ID: Transient Combustibles
11/08/2024
641540
Alternate Decay Heat Removal (ADHR)
Qualification for D3R28
Engineering
Changes
641541
D3R28 Spent Fuel Pool Cooling Evaluation during
Transition to ADHR
Miscellaneous
D3R28 SSMP
D3R28 Shutdown Safety Analysis
DGP 0203
Reactor SCRAM
20
Procedures
DOP 070009
APRM System Gain Adjustments
4804152
Procedure DOS 230003 Revision
09/24/2024
4816268
D3R28 32301-7 and 31201-158 Challenging
Hydro Execution
11/08/2024
Corrective Action
Documents
20077
11/26/2024
DOS 150012
Containment Cooling Service Water Loop Flow
Verification
DOS 230003
High Pressure Coolant Injection System Operability
and Quarterly IST Verification Test
23
DOS 575004
Control Room Train B HVAC and Air Filtration Unit
Surveillance
DOS 700008
Local Leak Rate Testing of Primary Containment
Isolation Valves
DOS 700027
Local Leak Rate Testing of Unit 2 (3) Reactor
Vessel Water Level Instrumentation System
(RWVLIS) Valves
Procedures
DTS 575004
Control Room Air Filter Unit Performance
Requirements (DOP Test)
170479801
MM Overhaul 30203-2D MSIV Based Upon LLRT
(OPCC)
11/06/2024
170479807
OP Perform 2D MSIV AsLeft Wet or Dry LLRT
(DOS 700001/02)
11/07/2024
Work Orders
4852520
D3 3RFL/75M TS LLRT Vlv 029997A & 116A
RVWLIS Backfill
11/01/2024
Inspection
Procedure
Type
Designation
Description or Title
Revision or Date
4852544
D3 3RFL/75M TS LLRT Vlv 0299100A & 117A
RVWLIS Backfill
11/01/2024
4852547
D3 3RFL/75M TS LLRT Vlv 029999A & 116A
RVWLIS Backfill
11/01/2024
4874604
D3 3RFL/75M TS LLRT Vlv 30299-98A RVWLIS
Backfill
11/01/2024
509770901
Op Perform OP Surveillance Per DOS 710006
11/12/2024
2880201
MM D3 2RFL PM Insp 2032B MSIV Air Op/AVCO
Mnfld Asy (OPCC)
11/03/2024
2880202
EM 2RFL PM Insp 2032B MSIV Air Op/AVCO
Mnfld Assy Surv (OPCC)
11/04/2024
2880203
MM Repair 30203-2B MSIV Air Line (OPCC)
11/05/2024
531394401
OP D3 Qtr/CSD PM Main Steam Isol Vlv Fail-Safe
Test
11/14/2024
531524409
Op PMT Perform AsLeft Seat Leak Test Per DOS
710006
11/11/2024
5352891
D2/3 24M TS Visual Inspection CR Filter Train
09/27/2024
536384801
D3 RFL Full Closure Timing and Exercising of
11/14/2024
536457602
Op Unit 3 1000 PSI System Leakage
Test/Hydrostatic Test
11/10/2024
536457615
Ops Pressure Test 3B Core Spray Post-Hydro
11/10/2024
543249323
Main Steam PMTs Required for Mode 2
11/17/2024
5432497
OPB PMT CRD SCRAM Timing Dresden
Generating Station
11/11/2024
555187408
IM Replace Sensor/Converter 31743-B (D3 Refuel
Floor 'B' A.R.M.)
11/26/2024
555258918
Replace Servo Amp Card 22386A-SA1 in Field
09/23/2024
555258919
OP PMT Motor Gear Unit 2303MGU
09/24/2024
5556986
EM T/S&R Thermal Anomaly on Fuse CF10
(20902-15C-F10)
11/22/2024
557481901
D3 Qtr TS Fuel Pool Channel A/B Channel
Cal & Functional
11/27/2024
Inspection
Procedure
Type
Designation
Description or Title
Revision or Date
5577855
D2 Qtr TS RPS Channel A1/A2 Automatic SCRAM
Contactor Test
11/22/2024
5577858
OP D2 Qtr TS Channel 2A Manual SCRAM Push
Buttons, Func. Test
11/22/2024
EPAA1004
Addendum 1
Dresden Station OnShift Staffing Technical Basis
EPAA1004
Addendum 2
Dresden Evacuation Time Estimates
Calculations
EPAA1201001
ReLink DRE Emergency Plan to the Fleet and
Revise Plan to Reflect IPAWS Implementation,
Evaluation No. 2326
26
Procedures
EPAA1004
Constellation Radiological Emergency Plan Annex
for Dresden Station
Miscellaneous
Dresden 4Q2024 Qual Drill
2/10/2024
DR0324-0053
D3R28 CRD Activities
10/23/2024
DR0324-00701
D3R28 Torus Dive Activities
DR0324-00906
D3R28 RFF Cavity Decon
10/22/2024
ALARA Plans
DR0324-00921
D3R28 - Rx Flange Repairs
11/04/2024
RPAA302
(Equivalent)
Alpha Chart
10/12/2023
Miscellaneous
RPAA4011002
Radiological Risk Assessment Worksheet - D3R28
RFF Cavity Decon
NISP-RP007
Control of Radioactive Material
RPAA302
Determination of Alpha Levels and Monitoring
Procedures
RPAA461
Radiological Controls for Contaminated Water
Diving Operations
24227981
CRD Platform
10/28/2024
24228459
Unit 3 Reactor Head
11/01/2024
24228509
CRD Platform
11/01/2024
Radiation
Surveys
24228633
Unit 3 Reactor Head
11/03/2024
DR0324-00906
D3R28 RFF Cavity Decon
Radiation Work
Permits (RWPs)
DR0324-00921
D3R28 RFF Emergent Work Activities
Inspection
Procedure
Type
Designation
Description or Title
Revision or Date
DR0324-0513
DW Control Rod Drive (CRD) Activities
DR0324-00921
TEDE ALARA Evaluation Screening
Worksheet - RX Head Emergent Flange Repair
11/04/2024
DR0324-00921
TEDE ALARA Evaluation Screening
Worksheet - Flange Repairs
11/03/2024
Miscellaneous
DR0324-00921
TEDE ALARA Evaluation Screening
Worksheet - Welding on RX Head Flange - High
Energy
11/05/2024
Data Verification Package for Safety System
Functional Failure Performance Indicator, Unit 2
and Unit 3
10/01/202309/30/2024
Data Verification Package for Residual Heat
Removal Systems Performance Indicator, Unit 2
and Unit 3
07/01/202306/30/2024
Data Verification Package for Cooling Water
Support Systems Performance Indicator, Unit 2 and
Unit 3
07/01/202306/30/2024
71151
Miscellaneous
Data Verification Package for Heat Removal
Systems Performance Indicator, Unit 2 and Unit 3
07/01/202306/30/2024
4776320
Trend IR: Fire Protection Performance
05/24/2024
4777635
Fire Protection Blitz
05/31/2024
4789559
Maintenance Trending CCR/HURB
07/25/2024
4796365
Station Trend: Procedure Use and Adherence
08/23/2024
4814543
NOS QV ID Hold Point Bypassed
11/02/2024
4815214
Significant Cross-Cutting Aspect Trend
11/05/2024
4816292
NRC ID: Transient Combustibles
11/08/2024
4817230
Trend IR Unsecured Doors
11/13/2024
Corrective Action
Documents
21303
IEMA Finding 11/1 Transient Combustible Trending
2/03/2024
MAMW796101
Welding, Brazing and Soldering Records
Procedures
PIAA1251006
Att 16
Organizational Effectiveness Evaluation
8