IR 05000237/2024003

Integrated Inspection Report 05000237/2024003 and 05000249/2024003

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

Enclosure

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 Report Aspect Section Mitigating Green [H.12] - Avoid 71152A Systems NCV 05000237/202400301 Complacency Open/Closed 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.

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:

(1) Ultimate heat sink

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,

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 Report Aspect Section Mitigating Green [H.12] - Avoid 71152A Systems NCV 05000237/202400301 Complacency Open/Closed 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 Type Designation Description or Title Revision or

Procedure Date

71111.04 Drawings M27 Diagram of Core Spray Piping AAO

Procedures DOP 1400E1 Unit 2 Core Spray System Electrical Checklist 4

DOP 1400M1 Unit 2 Core Spray System 24

71111.05 Fire Plans 100 Pre-fire Plan Dresden Generating Station Pre-Fire Plan 3

Master Legend

24 U3RB26 FZ 1.1.1.3 Unit 3 General Area Elev. 545' 6

145 U2TB48 FZ 8.2.6.A Unit 2 RFP Vent H2 Seal Area Elev. 538' 7

161 U3TB72 FZ 8.25E Unit 3 Reactor Feed Pumps Elev. 517' 3

2 U1CH FZ 11.3 Unit 1 Crib House 3

Miscellaneous 2410 Fire Drill Scenario U3 TB RFP Room - Trash Can Fire 09/10/2024

Procedures ER-DR6001069 Site List of High Risk Fire Areas 0

OP-AA201007 Fire Protection System Impairment Control 2

OP-AA201009 Control of Transient Combustible Material 31

71111.07A Corrective Action 4704643 2/3B Screen Refuse Pump Abnormal Noise 09/24/2023

Documents 4705152 2/3A Screen Refuse Pump Not Pumping 09/26/2023

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 38

Work Orders 4761963 Screen Refuse Pit Discharge Line to Bay 13 Flush 01/16/2020

25890 Screen Refuse Pit Discharge Line to Bay 13 Flush 04/14/2023

71111.11Q Miscellaneous LT 2408E Simulator Training Scenario 1

LT SEG 2408A Simulator Training Scenario 0

NF-AB720F-5 Special Maneuver Rob Move Sheet Sequence 07/20/2024

ID: D328021

REMA Plan D3C28 EOC Rod Pull - 9D and 9B Array 07/20/2024

D328021

Procedures OBE2407F LORT Scenario 01

OP-AA101113-4.0 Crew Critique Guidelines 14

1006

TQ-AA155 Conduct of Simulator Training and Evaluation 14

71111.12 Corrective Action 4465252 Unexpected XL3 Alarm 4330 12/07/2021

Inspection Type Designation Description or Title Revision or

Procedure Date

Documents 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

4803443 2/3 Diesel Fire Pump (DFP) Oil Leak 09/20/2024

Engineering 398559 Remove XL3 Devices (Tamper Switches) to Eliminate 2

Changes Nuisance Alarms

Miscellaneous Fire Protection System Health Summary 09/20/2024

Maintenance Rule (a)(1) Status 09/5/2024

Work Orders 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

5194571 D2/3 18M TSTR/Com Diesel Fire Pump Flow Capacity Test 03/24/2023

71111.13 Corrective Action 4787261 Severe Weather Results in Line Trips and DOA Entries 07/16/2024

Documents 4804468 Elevated Conductivity for Unit 3 Condensate Pump 09/25/2024

Discharge

4804619 D3 Condensate Pump Discharge Conductivity in Action 09/26/2024

Level 1

4805204 D3 Condensate Pump Discharge Conductivity Increase 09/28/2024

Miscellaneous DRE1683 Support Refute 09/26/2024

DRE32024-0263 ODM: U3 Condenser Conductivity 0

Procedures DAN 902(3)-7 Cond PP Disch Conduct Hi 8

D16

DOA 001021 Plant Chemistry Excursions 3

DOP 440008 Circulating Water System Flow Reversal 67

DOP 440012 Circulating Water Isolation to Half of Unit Condenser 14

OP-AA1018111 Attachment 1 - Adverse Condition Monitoring and 19

Contingency Plan

OP-AA108117 Protected Equipment List 7

71111.15 Corrective Action 4742819 Spiking of 3B Fuel Pool Rad Monitor 02/07/2024

Documents 4749187 3B Fuel Pool Rad HI Spike Causes RBV Isolation 02/15/2024

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

4782581 U3 Channel B Fuel Pool Rad Monitor Spiking 06/25/2024

Inspection Type Designation Description or Title Revision or

Procedure 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 09/17/2024

Temperatures

Engineering EC 641989 High Pressure Coolant Injection Elevated Flow Rate Impact 0

Evaluations Evaluation for Dresden 2 Cycle 29

Miscellaneous GEK13957C Operation and Maintenance Instructions Process Radiation 05/01/1995

Monitor 194X900 G8

GEK802G Operation and Maintenance Instructions Area Radiation 12/01/1996

Monitor Sensor and Converter 194X927G1 - G7

TDP0087 OPL3 Design Guide 12

TODI NF230273 Dresden Unit 2 Cycle 29 OPL3 0

TODI OPS LTR: TODI Provides Various Operating Data for Dresden Unit 2 1

20 during the Period of High HPCI Flow

71111.20 Procedures 3I.9 NF-AB720F-1 Control Rod Sequence Review and 2

Approval Sheet

3I.9 NF-AB715 Critical Prediction Checklist 08/25/2024

3S.9 NF-AB720F-1 Control Rod Sequence Review and 2

Approval Sheet

DGP 0101 Unit Startup 207

DGP 0201 Unit Shutdown 179

71111.24 Drawings M33 Diagram of Standby Liquid Control Piping IB

Engineering EC 389076 Evaluation of SBLC Test Tanks 21104 and 31104 Detailed 05/31/2012

Changes Evaluation

Procedures DIS 050007 38.5% Rated Core Thermal Power SCRAM Bypass 22

Pressure Switches Calibration and Functional Checks

DOS 110004 Standby Liquid Control System Quarterly/Comprehensive 55

Pump Test for the Inservice Testing (IST) Program

DOS 660008 Diesel Generator Cooling Water Pump Quarterly and 67

Comprehensive/Preservice Test for Operational Readiness

and In-Service Test Program

Inspection Type Designation Description or Title Revision or

Procedure Date

Work Orders 05524571 OP D2 QTR TS 2A SBLC Pump Test For In-Service Testing 07/03/2024

Surveillance

05546013 EWP IM D2 QTR TS 38.5% SCRAM Bypass Turbine 09/04/2024

1st Stage Pressure Switch Calibration

05549071 D2 QTR TS D/G Cooling Water Pump Test for IST Program 09/10/2024

Surveillance

555258907 IM TS&R HPCI Signal Converter 22386A 08/28/2024

555258918 IM Replace SERVO Amp Card 22386A-SA1 09/23/2024

5554973 OP D2 QTR TS HPCI Pump Oper Test and IST Surv 09/24/2024

71124.05 Calibration 0146608301 2/3 DISCHARGE TO RIVER RAD MON BENCH CAL 10/30/2013

Records RECORDER

0189832901 D2 2Y PM RBCCW RADIATION MONITOR CAL/FUNCT 05/27/2022

CK

0500506301 D3 4Y PM RBCCW RADIATION MONITOR CAL/FUNCT 06/04/2024

CK

0514955301 D3 2Y PM PRI CNMT WATER LEVEL INSTR CAL 02/15/2023

0555423501 Post-LOCA Containment Hydrogen and Oxygen Analyzer 07/31/2024

Functional Calibration Test

DIS 390006 Service Water Effluent Sample Radiation Monitor 02/06/2024

Calibration

DRS 582156 SPING Effluent Monitor Calibration 14

OPS3725 Calibration of the Mirion FASTSCAN WBC System 07/03/2024

RP-AA7001209 Shepherd 89 Calibration and Preventive Maintenance 07/21/2023

Corrective Action 04525715 RB VENT SPING CH 5 INOP 09/30/2022

Documents 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

04762575 UNEXPECTED ALARM: 9023 D2, Offgas Rad Monitor Hi 03/31/2024

Miscellaneous NSLD03691 SPING Technical Basis Documents 05/14/1991

SRRS: 2B.111 Dresden Contamination Monitor and Portal Monitor Weekly 07/29/2024

Operational Checks

Procedures RP-AA700 Controls for Radiation Protection Instrumentation 10

RP-AA7001210 Operation and Calibration of IPM Whole Body Frisking 3

Inspection Type Designation Description or Title Revision or

Procedure Date

Monitor

RP-AA7001215 Calibration of Low-Vol Air Samplers 4

RP-AA7001216 Calibration of Hi-Vol Air Samplers 4

RP-AA7001235 Operation and Calibration of the PM12 Gamma Portal 5

Monitor

RP-AA7001239 Operation and Calibration of the Model SAM12 Small 8

Articles Monitor

RP-AA7001240 Operation and Calibration of the Canberra Argos-5 8

Personnel Contamination Monitors

Self-Assessments 451738427 Pre-NRC SA IP 71124.05Instrumentation 05/30/2024

PI-AA1261001-Exelon Power Labs Self Assessment 08/11/2022

F01

71124.06 Corrective Action AP20241829 Radiochemistry Quality Control 07/31/2024

Documents AR 04789265 SampleIQ Database Missing Reportable Isotopes 07/24/2024

AR 04790815 MET Tower to MCR Equipment Going Obsolete 07/31/2024

Miscellaneous 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-Gas Permit Post-Release Data

C

L20221201301-C Liquid Permit Post-Release Data 01/18/2023

SVP LTR 240017 Dresden Nuclear Power Station 2023 Radioactive Effluent 04/30/3034

Release Report

Procedures CY-DR120340 Offgas Sampling 34

CY-DR170215 Unit 2/3 Main Chimney Sampling 21

CY-DR170220 Reactor Building Vent 29

CY-DR170301 Offsite Dose Calculation Manual 17

71124.06 Self-Assessments 04786525 NRC Inspection: Radioactive Gaseous and Liquid Effluent 07/19/2024

Treatment

71151 Miscellaneous 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 04/01/2023

Leakage through

03/31/2024

ED Dose and Dose-Rate Alarm Log 08/01/2024

LS-AA2090 Monthly Data Elements for NRC ROP Indicator - Reactor various

Coolant System (RCS) Specific Activity

LS-AA2150 Monthly Data Elements for NRC ROP various

Indicator - RETS/ODCM Radiological Effluent Occurrences

Procedures LS-AA2001 Collecting and Reporting of NRC ROP Performance 17

Indicator Data

LS-AA2140 Monthly Data Elements for NRC Performance 6

Indicator - Occupational Exposure Control Effectiveness

71152A Calculations DRE140006 FLEX Hydraulic Analysis 1

DRE170008 HCVS Phase 2 SAWA/SAWM Hydraulic Analysis 0

Corrective Action 4696206 Annual FLEX Inventory Deficiencies 08/18/2023

Documents 4778175 Annual FLEX Inventory (DOS 001043) Deficiencies 06/03/2024

4783565 NRC ID: Question About Scaffold Ladder by 07/02/2024

U2 HCU CRD A7

4793839 Baker Scaffold Left Unattended 08/19/2024

Procedures CC-DR1181003 Dresden FLEX Final Integrated Plan Document 5

DAP 0320 Restraint of Portable Equipment 20

DOS 001043 Operations FLEX Equipment Inventory 9

FSG04 Aligning FLEX Pumps for Operation 3

FSG09 Ultimate Heat Sink Supply to FLEX/SAWA Manifold 3

FSG60 FLEX Flood Pump Deployment/Operation 3

MA-AA716026 Station Housekeeping/Material Condition Program 23

MA-AA796024 Scaffold Installation, Inspection, and Removal 13

NES-MS04.1 Seismic Prequalified Scaffolds 7

Work Orders 0549893303 MM Repair 20305-103 Stem to Disc Separation on 06/24/2024

HCU A07

18