IR 05000237/2024003
| ML24302A305 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 10/29/2024 |
| From: | Nestor Feliz-Adorno NRC/RGN-III/DORS/RPB1 |
| To: | Rhoades D Constellation Energy Generation |
| References | |
| IR 2024003 | |
| Download: ML24302A305 (1) | |
Text
SUBJECT:
DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3-INTEGRATED INSPECTION REPORT 05000237/2024003 AND 05000249/2024003
Dear David Rhoades:
The U.S. NRC identified an administrative error in the NRC Integrated Inspection Report 05000237/2024002 and 05000249/2024002 (ADAMS Accession Number ML24227A058), dated August 14, 2024. Specifically, two findings (NCV 05000237,05000249/2024002-01 and NCV 05000237,05000249/2024002-02) were incorrectly applied to both Units 2 and 3. These findings only applied to Unit 2 (Docket Number 05000237).
On September 30, 2024, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Dresden Nuclear Power Station, Units 2 and 3. On October 21, 2024, the NRC inspectors discussed the results of this inspection with J. Biegelson, Director Organizational Performance and Regulatory, and other members of your staff. The results of this inspection are documented in the enclosed report.
One finding of very low safety significance (Green) is documented in this report. This finding involved a violation of NRC requirements. We are treating this violation as a non-cited violation (NCV) consistent with Section 2.3.2 of the Enforcement Policy.
If you contest the violation or the significance or severity of the violation documented in this inspection report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region III; the Director, Office of Enforcement; and the NRC Resident Inspector at Dresden Nuclear Power Station, Units 2 and 3.
If you disagree with a cross-cutting aspect assignment in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region III; and the NRC Resident Inspector at Dresden Nuclear Power Station, Units 2 and 3.
October 29, 2024 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, Néstor J. Féliz Adorno, Chief Reactor Projects 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:
DPR-19 and DPR-25 Report Numbers:
05000237/2024003 and 05000249/2024003 Enterprise Identifier:
I2024003-0059 Licensee:
Constellation Energy Generation, LLC Facility:
Dresden Nuclear Power Station, Units 2 and 3 Location:
Morris, IL Inspection Dates:
July 01, 2024 to September 30, 2024 Inspectors:
J. Cassidy, Senior Health Physicist Z. Helgert, Acting Resident Inspector T. Hooker, Health Physicist M. Porfirio, Illinois Emergency Management Agency C. St. Peters, Resident Inspector J. Steffes, Senior Resident Inspector Approved By:
Néstor J. Féliz Adorno, 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
Failure to Implement Seismic Requirements for Portable Equipment Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000237/202400301 Open/Closed
[H.12] - Avoid Complacency 71152A The inspectors identified a finding of very low safety significance (Green) and associated non-cited violation (NCV) of Technical Specifications (TS) Section 5.4.1.a for the failure to implement procedures to seismically restrain an unattended portable equipment located near safety-related instrumentation. Specifically, the licensee failed to seismically restrain a portable scaffold located near safety-related differential pressure switches as prescribed in procedure DAP 0320, Restraint of Portable Equipment, Revision 20. This could have resulted in the scaffold tipping over during a seismic event and potentially causing the loss of safety-related equipment.
Additional Tracking Items
None.
PLANT STATUS
Unit 2 began the inspection period at rated thermal power. On August 30, 2024, the site experienced an offsite electrical grid transient that caused generated power to change. The site was contacted by the grid operator and requested to lower power. The site lowered power to approximately 87 percent. The unit returned to rated thermal power later the same day. On September 6, 2024, power was reduced to perform rod sequence exchange and scram valve maintenance. During power reduction, the site experienced offgas flow instabilities and was challenged to maintain condenser vacuum. The site lowered power to approximately 21 percent.
The unit returned to rated thermal on September 8, 2024, following troubleshooting and repair of the offgas system. The unit remained at or near rated thermal power for the remainder of the inspection period.
Unit 3 began the inspection period at rated thermal power. On July 20, 2024, power was reduced to approximately 79 percent to perform rod sequence exchange and scram valve maintenance. The unit was returned to full rated power the same day. On August 23, 2024, the unit was shut down to perform replacement of the 3A recirculation pump seal. Following replacement and retest, the unit was synchronized to the grid on August 28, 2024, with full power achieved the same day. On September 12, 2024, power was reduced to approximately 78 percent to perform rod sequence exchange. The unit was returned to full rated power the next day. On September 28, 2024, the unit entered coast down operations in preparation for refueling outage D3R28 and remained in that condition for the remainder 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 on-site 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 2 'B' core spray on August 1315, 2024
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (3 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) 8.2.6A, Unit 2 Reactor Feed Pump Vent H2 Seal Area Elev. 538' on August 29, 2024
- (2) FZ 11.3, Unit 1 Crib House Fire Area on September 06, 2024
- (3) FZ 1.1.1.3, Unit 3 Reactor Building General Area Elev. 545' on September 25, 2024
Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the onsite fire brigade training and performance during an announced fire drill on September 19, 2024.
71111.07A - Heat Exchanger/Sink Performance
Annual Review (IP Section 03.01) (1 Sample)
The inspectors evaluated readiness and performance of:
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 planned down power for rod sequence exchange, rod recovery, and control rod drive testing on July 2021, 2024.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (2 Samples)
- (1) The inspectors observed and evaluated licensed crew performance in the main control room simulator on August 06, 2024.
- (2) The inspectors observed and evaluated licensed crew performance in the main control room simulator on September 19, 2024.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (1 Partial)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:
(1)
(Partial)
Fire protection system
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (3 Samples)
The inspectors evaluated the accuracy and completeness of risk assessments for the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed:
- (1) Unit 2 and Unit 3 aggregate risk review and recovery actions following severe weather/tornadic activity in the vicinity of the plant and resultant power perturbations on July 16-18, 2024
- (2) Protected pathways for the Unit 3 maintenance outage D3M23, on August 22-27, 2024
- (3) Emergent work activities on Unit 3 due to a suspected condenser tube leak, on September 26-30, 2024
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (6 Samples)
The inspectors evaluated the licensees justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Technical support center heating, ventilation and air conditioning emergency train filters high differential pressure during surveillance as documented in CR 4787477
- (2) Screen refuse pump system following several noted degraded conditions
- (3) Unit 2 fuel impact evaluation associated with elevated flow noted during high pressure coolant injection surveillance due to failed motor gear unit
- (4) Fuel pool rad monitor intermittent spiking, as documented in AR 4782581
- (5) Discolored oil noted in motor oil reservoirs of low-pressure coolant injection pumps as documented in CR 4792117
- (6) Unit 3 drywell temperature deviation and equipment qualification review as documented in CR 4799351
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02)
(1 Partial)
The inspectors evaluated the following temporary or permanent modifications:
(1)
(Partial)
Unit 3 feedwater regulating valve modification
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated D3M23, Unit 3 maintenance outage for recirculation pump 3A seal replacement, activities from August 22-27, 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) (1 Sample 1 Partial)
- (1) Unit 3 containment cooling service water system surveillance following maintenance window per work order 5556794 (2)
(Partial)
Unit 2 high pressure coolant injection post-maintenance testing following replacement of Servo card, per work order 5552589
Surveillance Testing (IP Section 03.01) (2 Samples)
- (1) DIS 050007, SCRAM Bypass Pressure Switches Functional Checks, on September 4, 2024
- (2) DOS 660008, Diesel Generator Water Pump Quarterly or Comprehensive Preservice Test, on September 10, 2024
Inservice Testing (IST) (IP Section 03.01) (1 Sample)
- (1) DOS 110004, Unit 2 2A Standby Liquid Control System Quarterly/Comprehensive Pump Test for the Inservice Testing (IST) Program, on July 3,
RADIATION SAFETY
71124.05 - Radiation Monitoring Instrumentation
Walkdowns and Observations (IP Section 03.01) (8 Samples)
The inspectors evaluated the following radiation detection instrumentation during plant walkdowns:
- (1) Area radiation monitors on the refueling floor
- (2) Counter for smear checks in the turbine building
- (3) Small article monitor at the main radiologically controlled area exit
- (4) Small article monitor at chemistry's radiologically controlled area exit
- (5) Personnel contamination monitors at chemistry's radiologically controlled area exit
- (6) Counting instruments in the chemistry hot lab
- (7) Chimney gaseous effluent monitor in radiation waste
- (8) Portable friskers in multiple locations
Calibration and Testing Program (IP Section 03.02) (13 Samples)
The inspectors evaluated the calibration and testing of the following radiation detection instruments:
- (1) Thermo Scientific SAM12, 151
- (2) Ludlum 177, 0022693
- (3) Thermo Scientific PM12, 121
- (4) Canberra Argos-5, 1206085
- (5) Mirion Ram Gam, 0027541
- (6) Eberline R020, 0015810
- (7) MGP Telepole, 0002954632
- (8) MGP Amp-100, 0028226
- (9) Radeco Inc. AVS28A, 7929
- (10) Radeco Inc. H809, 8113
- (11) Shephard 89 Irradiator, S9
- (12) Mirion FASTSCAN
- (13) Unit 3 primary containment water level instrumentation Effluent Monitoring Calibration and Testing Program Sample (IP Section 03.03) (2 Samples)
The inspectors evaluated the calibration and maintenance of the following radioactive effluent monitoring and measurement instrumentation:
- (1) Unit 2/3 chimney particulate, iodine, and noble gas (SPING) gaseous effluent monitor
- (2) Unit 3 service water effluent sample radiation monitor
71124.06 - Radioactive Gaseous and Liquid Effluent Treatment
Walkdowns and Observations (IP Section 03.01) (4 Samples)
The inspectors evaluated the following radioactive effluent systems during walkdowns:
- (1) Unit 2/3 Reactor Building ventilation system
- (2) Unit2/3 Main Chimney ventilation system
- (3) Unit 2/3 Offgas system
- (4) Unit 2 Service Water radiation monitor system
Sampling and Analysis (IP Section 03.02) (3 Samples)
Inspectors evaluated the following effluent samples, sampling processes and compensatory samples:
- (1) Unit 2/3 Reactor Building vent particulate and iodine sample
- (2) Unit2/3 Main Chimney vent particulate and iodine sample
- (3) Unit 2/3 Offgas sample
Dose Calculations (IP Section 03.03) (2 Samples)
The inspectors evaluated the following dose calculations:
- (1) Storm Sewer Liquid Release; L20221201301-C
- (2) Main Chimney Gaseous Release; G202304011016-C
OTHER ACTIVITIES
BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
MS06: Emergency AC Power Systems (IP Section 02.05)===
- (1) Unit 2 (April 1, 2023 through March 31, 2024)
- (2) Unit 3 (April 1, 2023 through March 31, 2024)
MS07: High Pressure Injection Systems (IP Section 02.06) (2 Samples)
- (1) Unit 2 (April 1, 2023 through March 31, 2024)
- (2) Unit 3 (April 1, 2023 through March 31, 2024)
BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10) (2 Samples)
- (1) Unit 2 (June 1, 2023 through June 30, 2024)
- (2) Unit 3 (June 1, 2023 through June 30, 2024)
BI02: RCS Leak Rate Sample (IP Section 02.11) (2 Samples)
- (1) Unit 2 (April 1, 2023 through March 31, 2024)
- (2) Unit 3 (April 1, 2023 through March 31, 2024)
OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)
(1)
(June 1, 2023 through June 30, 2024)
PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent Occurrences Sample (IP Section 02.16) (1 Sample)
(1)
(June 1, 2023 through June 30, 2024)71152A - Annual Follow-up Problem Identification and Resolution Annual Follow-up of Selected Issues (Section 03.03) (1 Sample 1 Partial)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- (1) Evaluation and corrective actions for the placement of an unrestrained non-seismically qualified scaffold in support of maintenance, as documented in AR 4783565 (2)
(Partial)
Evaluation and corrective actions for deficiencies in FLEX inventory discovered in yearly audit, as documented in AR
INSPECTION RESULTS
Failure to Implement Seismic Requirements for Portable Equipment Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000237/202400301 Open/Closed
[H.12] - Avoid Complacency 71152A The inspectors identified a finding of very low safety significance (Green) and associated non-cited violation (NCV) of Technical Specifications (TS) Section 5.4.1.a for the failure to implement procedures to seismically restrain an unattended portable equipment located near safety-related instrumentation. Specifically, the licensee failed to seismically restrain a portable scaffold located near safety-related differential pressure switches as prescribed in procedure DAP 0320, Restraint of Portable Equipment, Revision 20. This could have resulted in the scaffold tipping over during a seismic event and potentially causing the loss of safety-related equipment.
Description:
During a walkdown on June 27, 2024, of the Unit 2 reactor building west hydraulic control units (HCU), the inspectors identified an unsecured scaffold placed for ongoing HCU maintenance that started that day. The scaffold was identified to be a baker scaffold, a prebuilt design with variable height and no wheels on its footings. Maintenance staff had been pulled from the HCU work area due to shifting priorities for work in the plant and left the scaffold unattended after halting work.
This scaffold was located within 8 feet of instrument rack 22028, which includes differential pressure switches 20261-34B and 20261-34D. The safety-related differential pressure switches are responsible for determining if a recirculation loop has a large break in piping integrity as compared to the pressure of the other loop. The pressure output feeds into logic that directs low pressure coolant injection (LPCI) flow to the recirculation loop that is intact in the scenario that a break has occurred. The inspectors were concerned that during a seismic event the scaffold could tip over and impact the differential pressure switches, potentially affecting the LPCI loop select logics safety function in the event of a design-basis loss of coolant accident. The inspectors communicated the discovery to operations who walked down the area and decided to remove the scaffold the same day.
Additionally, the inspectors inquired on whether the prebuilt scaffold was qualified seismically to be left near safety-related equipment without being secured. The licensee stated that per their procedures the baker scaffold is not a seismically prequalified scaffold. Specifically, NES-MS04.1, Seismic Prequalified Scaffolds, Revision 7, defines several different scaffold designs that are prequalified: tube and coupler, excel, cuplock (manufactured by Brand, SGB, or Millenium), mason frame, open-end frame, and hanging.
Due to the baker scaffold not meeting any of the designs described in NES-MS04.1 it is considered portable equipment. Thus, the equipment is governed by the requirements of DAP 0320, Restraint of Portable Equipment, Revision 20. DAP 0320 augments its requirements based on the aspect ratio of the portable equipment. The procedure defines Aspect ratio as the height of an item divided by the narrowest base dimension. If the aspect ratio is greater than 2, the requirements for spacing are stricter due to a higher potential for tipping during a seismic event. The portable scaffold was deployed at a height with an aspect ratio of greater than 2 which means that its spacing requirements near safety-related equipment are defined in paragraph F.4 of DAP 0320. Paragraph F.4 states, in part, If the item will be left unattended in an area requiring seismic restraint It shall be stored greater than its height plus 24 [inches] from safety-related equipment or seismically restrained per paragraph F.7 Paragraph F.7 describes how to attach or restrain an item to a seismically stable structure. DAP 0320 was not implemented for the staging of the portable scaffold due to the scaffold having an aspect ratio greater than 2, staged within the distance of its height plus 24 inches to safety-related equipment, and was not seismically restrained per paragraph F.7 or continually monitored.
Corrective Actions: The licensee entered this issue into their corrective action program and immediately removed the portable scaffold from the work area. An action tracking item was generated to reinforce the standards and procedures for portable equipment. Additionally, the licensee planned to incorporate DAP 0320 into their model work orders when portable scaffolds are being utilized.
Corrective Action References: ARs 04783565, 04793839
Performance Assessment:
Performance Deficiency: The inspectors determined that the licensee's failure to seismically restrain unattended portable equipment near safety-related instrumentation was contrary to procedure DAP 0320, Restraint of Portable Equipment, Revision 20, paragraph F.4 and was a performance deficiency.
Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Protection Against External Factors attribute of the Mitigating Systems cornerstone and adversely affected the cornerstone objective to ensure the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences. Specifically, the failure to seismically restrain the unattended portable scaffold does not ensure the availability of the Unit 2 LPCI loop select logic emergency core cooling system instrumentation to direct LPCI injection to the unbroken recirculation loop.
Significance: The inspectors assessed the significance of the finding using IMC 0609 Appendix A, The Significance Determination Process (SDP) for Findings At-Power. The inspectors dispositioned the finding per Exhibit 2, Section B due to it being associated with an external event (seismic) affecting the Mitigating Systems cornerstone. Specifically, the inspectors determined the finding was of very low safety significance (Green) because the inspectors answered No to the screening question, Does the finding involve the loss or degradation of equipment or function specifically designed to mitigate a seismic, flooding, or severe weather initiating event for greater than 14 days?
Cross-Cutting Aspect: H.12 - Avoid Complacency: Individuals recognize and plan for the possibility of mistakes, latent issues, and inherent risk, even while expecting successful outcomes. Individuals implement appropriate error reduction tools. Specifically, when the licensee changed their work plan, they did not recognize for the possibility of mistakes being introduced by the change itself. They did not evaluate the configuration of the work site when they left it and the associate risk. As a result, they did not verify procedure prerequisites were met before leaving a non-seismically qualified portable scaffold near safety-related equipment.
Enforcement:
Violation: Technical Specification Section 5.4.1.a states that written procedures shall be established, implemented, and maintained covering the applicable procedures recommended in Regulatory Guide 1.33, Revision 2, Appendix A, February 1978. NRC Regulatory Guide 1.33, Appendix A, Section 9 covers Procedures for Performing Maintenance.
Section 9 states, in part, that maintenance that can affect the performance of safety-related equipment should be properly preplanned and performed in accordance with written procedures, documented instructions, or drawings appropriate to the circumstances. The licensee established procedure DAP 0320, Restraint of Portable Equipment, Revision 20, to provide instructions on restraining portable equipment. Paragraph F.4 states, in part, If the item will be left unattended in an area requiring seismic restraint It shall be stored greater than its height plus 24 [inches], from safety-related equipment or seismically restrained per paragraph F.7. Paragraph F.7 describes how to attach or restrain an item to a seismically stable structure.
Contrary to the above, on June 27, 2024, the licensee failed to implement written procedures covered in Regulatory Guide 1.33, Revision 2, Appendix A, February 1978. Specifically, while performing maintenance, the licensee positioned a portable scaffold near safety-related differential pressure switches. The licensee left the scaffold unattended without storing it at a distance greater than its height plus 24 inches from the safety-related instruments or seismically restraining it per paragraph F.7 of procedure DAP 0320, as required by paragraph F.4.
Enforcement Action: This violation is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On October 21, 2024, the inspectors presented the integrated inspection results to J. Biegelson, Director Organizational Performance and Regulatory, and other members of the licensee staff.
- On August 2, 2024, the inspectors presented the radiation protection 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
Drawings
M27
Diagram of Core Spray Piping
AAO
DOP 1400E1
Unit 2 Core Spray System Electrical Checklist
Procedures
DOP 1400M1
Unit 2 Core Spray System
100 Pre-fire Plan
Master Legend
Dresden Generating Station Pre-Fire Plan
24 U3RB26
FZ 1.1.1.3 Unit 3 General Area Elev. 545'
145 U2TB48
FZ 8.2.6.A Unit 2 RFP Vent H2 Seal Area Elev. 538'
161 U3TB72
FZ 8.25E Unit 3 Reactor Feed Pumps Elev. 517'
Fire Plans
2 U1CH
FZ 11.3 Unit 1 Crib House
Miscellaneous
2410
Fire Drill Scenario U3 TB RFP Room - Trash Can Fire
09/10/2024
ER-DR6001069
Site List of High Risk Fire Areas
OP-AA201007
Fire Protection System Impairment Control
Procedures
OP-AA201009
Control of Transient Combustible Material
4704643
2/3B Screen Refuse Pump Abnormal Noise
09/24/2023
4705152
2/3A Screen Refuse Pump Not Pumping
09/26/2023
Corrective Action
Documents
4781352
2/3B Screen Refuse Pump Abnormal Noise Slow to Pump
06/18/2024
Miscellaneous
Bathymetric/Volume Survey Summary Report
11/01/2023
Procedures
DOA 001001
Dresden Lock and Dam Failure
4761963
Screen Refuse Pit Discharge Line to Bay 13 Flush
01/16/2020
Work Orders
25890
Screen Refuse Pit Discharge Line to Bay 13 Flush
04/14/2023
LT 2408E
Simulator Training Scenario
LT SEG 2408A
Simulator Training Scenario
NF-AB720F-5
Special Maneuver Rob Move Sheet Sequence
ID: D328021
07/20/2024
Miscellaneous
REMA Plan
D328021
D3C28 EOC Rod Pull - 9D and 9B Array
07/20/2024
OBE2407F
LORT Scenario
OP-AA101113-
1006
4.0 Crew Critique Guidelines
Procedures
TQ-AA155
Conduct of Simulator Training and Evaluation
Corrective Action
4465252
Unexpected XL3 Alarm 4330
2/07/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
4773815
Unexpected XL3 Alarms 2A IAC Area
05/13/2024
4796906
Received XL3 4324 and 4330
08/26/2024
4803442
2/3 Diesel Fire Pump (DFP) Failed Overcrank Test
09/20/2024
Documents
4803443
2/3 Diesel Fire Pump (DFP) Oil Leak
09/20/2024
Engineering
Changes
398559
Remove XL3 Devices (Tamper Switches) to Eliminate
Nuisance Alarms
Fire Protection System Health Summary
09/20/2024
Miscellaneous
Maintenance Rule (a)(1) Status
09/5/2024
4634466
OP D2/3 TSTR/Com Diesel Fire Pump Flow Capacity Test
09/14/2018
4832450
D2/3 18M TSTR/Com Diesel Fire Pump Flow Capacity Test
04/9/2020
5036427
D2/3 18M TSTR/Com Diesel Fire Pump Flow Capacity Test
09/30/2021
Work Orders
5194571
D2/3 18M TSTR/Com Diesel Fire Pump Flow Capacity Test
03/24/2023
4787261
Severe Weather Results in Line Trips and DOA Entries
07/16/2024
4804468
Elevated Conductivity for Unit 3 Condensate Pump
Discharge
09/25/2024
4804619
D3 Condensate Pump Discharge Conductivity in Action
Level 1
09/26/2024
Corrective Action
Documents
4805204
D3 Condensate Pump Discharge Conductivity Increase
09/28/2024
DRE1683 Support Refute
09/26/2024
Miscellaneous
DRE32024-0263
ODM: U3 Condenser Conductivity
DAN 902(3)-7
D16
Cond PP Disch Conduct Hi
DOA 001021
Plant Chemistry Excursions
DOP 440008
Circulating Water System Flow Reversal
DOP 440012
Circulating Water Isolation to Half of Unit Condenser
OP-AA1018111
- Adverse Condition Monitoring and
Contingency Plan
Procedures
OP-AA108117
Protected Equipment List
4742819
Spiking of 3B Fuel Pool Rad Monitor
2/07/2024
4749187
3B Fuel Pool Rad HI Spike Causes RBV Isolation
2/15/2024
4760107
Unit 3 Ch B FP Rad Monitor Spiking Above Trip Setpoint
04/02/2024
4781352
2/3B Screen Refuse Pump Abnormal Noise Slow to Pump
06/18/2024
Corrective Action
Documents
4782581
U3 Channel B Fuel Pool Rad Monitor Spiking
06/25/2024
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
4783211
U2 High Pressure Coolant Injection Motor Gear Unit
06/26/2024
4783304
Temporary Screen Refuse Pumps Not Pumping Efficiently
06/26/2024
4794840
31705-16B, U3 FP Rad Monitor Spiked HI
08/28/2024
4796390
3B FP Rad Mon Connector Possible Degradation
08/27/2024
4802524
Update to IR 4799351 for Unit 3 Elevated Drywell
Temperatures
09/17/2024
Engineering
Evaluations
High Pressure Coolant Injection Elevated Flow Rate Impact
Evaluation for Dresden 2 Cycle 29
GEK13957C
Operation and Maintenance Instructions Process Radiation
Monitor 194X900 G8
05/01/1995
GEK802G
Operation and Maintenance Instructions Area Radiation
Monitor Sensor and Converter 194X927G1 - G7
2/01/1996
TDP0087
OPL3 Design Guide
TODI NF230273
Dresden Unit 2 Cycle 29 OPL3
Miscellaneous
20
TODI Provides Various Operating Data for Dresden Unit 2
during the Period of High HPCI Flow
3I.9
NF-AB720F-1 Control Rod Sequence Review and
Approval Sheet
3I.9
NF-AB715 Critical Prediction Checklist
08/25/2024
3S.9
NF-AB720F-1 Control Rod Sequence Review and
Approval Sheet
DGP 0101
Unit Startup
207
Procedures
DGP 0201
Unit Shutdown
179
Drawings
M33
Diagram of Standby Liquid Control Piping
IB
Engineering
Changes
Evaluation of SBLC Test Tanks 21104 and 31104 Detailed
Evaluation
05/31/2012
DIS 050007
38.5% Rated Core Thermal Power SCRAM Bypass
Pressure Switches Calibration and Functional Checks
DOS 110004
Standby Liquid Control System Quarterly/Comprehensive
Pump Test for the Inservice Testing (IST) Program
Procedures
DOS 660008
Diesel Generator Cooling Water Pump Quarterly and
Comprehensive/Preservice Test for Operational Readiness
and In-Service Test Program
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
05524571
OP D2 QTR TS 2A SBLC Pump Test For In-Service Testing
Surveillance
07/03/2024
05546013
EWP IM D2 QTR TS 38.5% SCRAM Bypass Turbine
1st Stage Pressure Switch Calibration
09/04/2024
05549071
D2 QTR TS D/G Cooling Water Pump Test for IST Program
Surveillance
09/10/2024
555258907
IM TS&R HPCI Signal Converter 22386A
08/28/2024
555258918
IM Replace SERVO Amp Card 22386A-SA1
09/23/2024
Work Orders
5554973
OP D2 QTR TS HPCI Pump Oper Test and IST Surv
09/24/2024
0146608301
2/3 DISCHARGE TO RIVER RAD MON BENCH CAL
RECORDER
10/30/2013
0189832901
D2 2Y PM RBCCW RADIATION MONITOR CAL/FUNCT
CK
05/27/2022
0500506301
D3 4Y PM RBCCW RADIATION MONITOR CAL/FUNCT
CK
06/04/2024
0514955301
D3 2Y PM PRI CNMT WATER LEVEL INSTR CAL
2/15/2023
0555423501
Post-LOCA Containment Hydrogen and Oxygen Analyzer
Functional Calibration Test
07/31/2024
DIS 390006
Service Water Effluent Sample Radiation Monitor
Calibration
2/06/2024
DRS 582156
SPING Effluent Monitor Calibration
OPS3725
Calibration of the Mirion FASTSCAN WBC System
07/03/2024
Calibration
Records
RP-AA7001209
Shepherd 89 Calibration and Preventive Maintenance
07/21/2023
04525715
09/30/2022
04550582
Conflicting ODCM Interpretation
01/26/2023
04695055
Hard to Detect Fe-55 Detected in Effluent Vents
08/07/2023
04717046
RFF Evacuated due to CAM Alarm on RFF
11/11/2023
Corrective Action
Documents
04762575
UNEXPECTED ALARM: 9023 D2, Offgas Rad Monitor Hi
03/31/2024
NSLD03691
SPING Technical Basis Documents
05/14/1991
Miscellaneous
SRRS: 2B.111
Dresden Contamination Monitor and Portal Monitor Weekly
Operational Checks
07/29/2024
RP-AA700
Controls for Radiation Protection Instrumentation
Procedures
RP-AA7001210
Operation and Calibration of IPM Whole Body Frisking
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Monitor
RP-AA7001215
Calibration of Low-Vol Air Samplers
RP-AA7001216
Calibration of Hi-Vol Air Samplers
RP-AA7001235
Operation and Calibration of the PM12 Gamma Portal
Monitor
RP-AA7001239
Operation and Calibration of the Model SAM12 Small
Articles Monitor
RP-AA7001240
Operation and Calibration of the Canberra Argos-5
Personnel Contamination Monitors
451738427
Pre-NRC SA IP 71124.05Instrumentation
05/30/2024
Self-Assessments
PI-AA1261001-
F01
Exelon Power Labs Self Assessment
08/11/2022
AP20241829
Radiochemistry Quality Control
07/31/2024
SampleIQ Database Missing Reportable Isotopes
07/24/2024
Corrective Action
Documents
MET Tower to MCR Equipment Going Obsolete
07/31/2024
Dresden Nuclear Power Station 2022 Radioactive Effluent
Release Report
Dresden Nuclear Power Station 2021 Radioactive Effluent
Release Report
CY-AA1701000
CY-AA1701000, LAND USE CENSUS, 2023
09/30/2023
G202304011016-
C
Gas Permit Post-Release Data
L20221201301-C
Liquid Permit Post-Release Data
01/18/2023
Miscellaneous
Dresden Nuclear Power Station 2023 Radioactive Effluent
Release Report
04/30/3034
CY-DR120340
Offgas Sampling
CY-DR170215
Unit 2/3 Main Chimney Sampling
CY-DR170220
Reactor Building Vent
Procedures
CY-DR170301
Offsite Dose Calculation Manual
Self-Assessments 04786525
NRC Inspection: Radioactive Gaseous and Liquid Effluent
Treatment
07/19/2024
MSPI High Pressure Injection Prepared Data Package
04/01/2023
through
03/31/2024
MSPI Emergency AC Power Prepared Data Package
04/01/2023
through
03/31/2024
Performance Indicator Data: Barrier Integrity - RCS
Leakage
04/01/2023
through
03/31/2024
ED Dose and Dose-Rate Alarm Log
08/01/2024
LS-AA2090
Monthly Data Elements for NRC ROP Indicator - Reactor
Coolant System (RCS) Specific Activity
various
Miscellaneous
LS-AA2150
Monthly Data Elements for NRC ROP
Indicator - RETS/ODCM Radiological Effluent Occurrences
various
LS-AA2001
Collecting and Reporting of NRC ROP Performance
Indicator Data
71151
Procedures
LS-AA2140
Monthly Data Elements for NRC Performance
Indicator - Occupational Exposure Control Effectiveness
DRE140006
FLEX Hydraulic Analysis
Calculations
DRE170008
HCVS Phase 2 SAWA/SAWM Hydraulic Analysis
4696206
Annual FLEX Inventory Deficiencies
08/18/2023
4778175
Annual FLEX Inventory (DOS 001043) Deficiencies
06/03/2024
4783565
NRC ID: Question About Scaffold Ladder by
07/02/2024
Corrective Action
Documents
4793839
Baker Scaffold Left Unattended
08/19/2024
CC-DR1181003
Dresden FLEX Final Integrated Plan Document
DAP 0320
Restraint of Portable Equipment
DOS 001043
Operations FLEX Equipment Inventory
FSG04
Aligning FLEX Pumps for Operation
FSG09
Ultimate Heat Sink Supply to FLEX/SAWA Manifold
FSG60
FLEX Flood Pump Deployment/Operation
MA-AA716026
Station Housekeeping/Material Condition Program
71152A
Procedures
MA-AA796024
Scaffold Installation, Inspection, and Removal
NES-MS04.1
Seismic Prequalified Scaffolds
Work Orders
0549893303
MM Repair 20305-103 Stem to Disc Separation on
HCU A07
06/24/2024