IR 05000237/2022002
| ML22220A283 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 08/08/2022 |
| From: | Robert Ruiz NRC/RGN-III/DRP/B1 |
| To: | Rhoades D Constellation Energy Generation |
| References | |
| EA-22-055 IR 2022002 | |
| Download: ML22220A283 (23) | |
Text
August 8, 2022
SUBJECT:
DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3 - INTEGRATED INSPECTION REPORT 05000237/2022002; 05000249/2022002 AND 07200037/2022001 AND EXERCISE OF ENFORCEMENT DISCRETION
Dear Mr. Rhoades:
On June 30, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Dresden Nuclear Power Station, Units 2 and 3. On July 26, 2022, the NRC inspectors discussed the results of this inspection with Mr. Pat Boyle, Site Vice President, and other members of your staff. The results of this inspection are documented in the enclosed report.
No findings or violations of more than minor significance were identified during this inspection. This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely, Robert Ruiz, Chief Branch 1 Division of Reactor Projects
Docket Nos. 05000237, 05000249 and
07200037 License Nos. DPR-19 and DPR-25
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000237 and 05000249
License Numbers:
Report Numbers:
05000237/2022002; 05000249/2022002 and 07200037/2022001
Enterprise Identifier: I-2022-002-0048
Licensee:
Constellation Energy Generation, LLC
Facility:
Dresden Nuclear Power Station, Units 2 and 3
Location:
Morris, IL
Inspection Dates:
April 01, 2022 to July 23, 2022
Inspectors:
A. Demeter, Resident Inspector
G. Edwards, Health Physicist
R. Edwards, Senior Reactor Inspector
M. Learn, Transportation and Storage Inspector
A. Nguyen, Senior Resident Inspector
M. Porfirio, Illinois Emergency Management Agency
C. St. Peters, Resident Inspector
Approved By:
Robert Ruiz, Chief
Branch 1
Division of Reactor Projects
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
Type Issue Number Title Report Section Status EDG EA-22-055 Tornado Hazards Protection at Independent Spent Fuel Storage Installations 60855 Closed LER 05000249/2021-001-01 LER 2021-001-01 for Dresden Nuclear Power Station, Unit 3, Reactor Scram due to Main Power Transformer Failure 71153 Closed
PLANT STATUS
Unit 2 began the inspection period at rated thermal power. On June 11, 2022, the unit was downpowered to approximately 62 percent for a scheduled control rod pattern adjustment, scram time testing, turbine valve testing, and repairs to the 2B feedwater pump and regulating valve. The unit was returned to rated thermal power on June 12, 2022, and 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 April 9, 2022, the unit was downpowered to approximately 35 percent to investigate elevated drywell leakage values. The unit was shut down on April 10, 2022, for forced outage, D3F55 to repair the cause of the elevated drywell leakage, a packing leak on the 1B main steam isolation valve. Following repairs, the unit was returned to rated thermal power on April 13, 2022. On June 4, 2022, the unit was downpowered to approximately 75 percent for a scheduled control rod pattern adjustment, scram time testing, and turbine bypass valve testing. The unit was returned to rated thermal power on June 5, 2022 and remained at or near rated thermal power 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
71111.01 - Adverse Weather Protection
Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of extreme hot weather for the following systems:
Service water, reactor building closed cooling water, turbine building closed cooling water, containment cooling service water, the emergency diesel generators and auxiliaries, and station batteries on May 10-11, 2022.
The inspectors also evaluated the plants offsite AC power systems and onsite alternate AC power systems, including the switchyard and transformers to ensure prior issues had been addressed before the onset of summer weather conditions. The inspectors verified that weather-related equipment deficiencies on susceptible plant systems identified during the previous year had been corrected prior to the onset of summer weather.
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (3 Samples)
- (1) Unit 2 core spray system on May 6-9, 2022
- (2) Unit 2 and Unit 3 service water and associated cooling water systems on May 9-10, 2022
- (3) Unit 2 and Unit 3 turbine building and reactor building closed cooling water systems on May 10-11, 2022
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated system configurations during a complete walkdown of the Unit 2 isolation condenser system on April 25-27, 2022.
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 6.1, Unit 3 250V Battery Charger Room, elev. 538' and Fire Zone 7.0.B, Unit 3 Battery Room, elev. 551' on June 1, 2022
- (2) Fire Zone 1.1.1.3, Unit 3 General Area, elev. 545' on June 1, 2022
- (3) Fire Zone 8.2.5.C, Unit 2/3 EHC Reservoir Area, elev. 517', on June 6, 2022
71111.06 - Flood Protection Measures
Inspection Activities - Internal Flooding (IP Section 03.01) (1 Sample)
The inspectors evaluated internal flooding mitigation protections in the:
- (1) Unit 2 and Unit 3 torus basement and ECCS corner rooms
71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance
Requalification Examination Results (IP Section 03.03) (1 Sample)
- (1) The inspectors reviewed and evaluated the licensed operator examination failure rates for the requalification annual operating exam administered between April 4, 2022, and May 16, 2022.
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 the Unit 3 emergent shutdown and startup activities for forced outage, D3F55, on April 10-12, 2022
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated the performance of a complex casualty graded scenario by a crew of licensed plant operators in the facility's simulator on May 4, 2022.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (2 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) Closed cooling water systems
- (2) AC/DC Distribution System
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (6 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 3 emergent shutdown risk for D3F55 concurrent with 'A' CST inoperable to both units for repairs to an ECCS suction valve on April 10-12, 2022
- (2) Dry cask storage evolutions during the week of April 25, 2022
- (3) Elevated plant risk during scheduled Unit 3 EDG maintenance window on April 25-27, 2022
- (4) Elevated plant and fire risk during scheduled 3A core spray maintenance window on May 9-10, 2022
- (5) Elevated plant and fire risk on Unit 2 and Unit 3 during work week May 16-20, 2022, for ECCS divisional work windows, common unit SBGT work window, and Dry Fuel Storage elevated risk
- (6) Unit 3 emergent work to troubleshoot and repair issues with the plant process computer and rod block monitor, June 4-6, 2022
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (5 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Historical operability of the isolation condenser batteries (2)2A LPCI Motor Bearing Oil Sample had High Moisture Content
- (3) Unit 3 LPCI Relay, 3-1530-127, Contacts had High Resistance
- (4) Unit 3 Diesel Generator Resistor, R19, Degradation
- (5) Impact on Unit 3 Batteries due to degraded ventilation system and warm weather
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 2 and Unit 3 High Pressure Core Injection Signal Converter Modification
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (3 Samples)
The inspectors evaluated the following post-maintenance testing activities to verify system operability and/or functionality:
- (1) Intermediate range monitor (IRM) functional testing per DOS 0700-02, 0700-04, and 0700-05, after troubleshooting and calibration of Unit 3 IRM 14 on April 11, 2022
- (2) DOS 0250-02, full closure timing and exercising of MSIVs and DOS 0250-03, MSIV fail safe closure test, after repairs to packing on the Unit 3 1B MSIV on April 11, 2022
- (3) DOS 1400-05, core spray system pump operability and quarterly IST test with torus available, after the 3A core spray maintenance window on May 10, 2022
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated forced outage (D3F55) activities on Unit 3 for increased drywell leakage due to a 1B MSIV packing leak from April 10-13, 2022.
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance testing activities to verify system operability and/or functionality:
Surveillance Tests (other) (IP Section 03.01) (2 Samples)
- (1) Unit 2 diesel generator endurance run and full load reject on April 19 and 20, 2022
- (2) Unit 2 and Unit 3 38.5 percent rated core thermal power scram bypass pressure switches calibration and functional checks on date April 19, 2022
71114.06 - Drill Evaluation
Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)
The inspectors evaluated:
- (1) Dresden 2Q2022 focus area drill on June 28,
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 used on the refuel floor
- (2) Frisker used at the radiologically controlled area exit
- (3) Continuous Air Monitor used to monitor the Unit 2 drywell
- (4) Small Article Monitor used at the radiologically controlled area exit
- (5) Continuous Air Monitor used on the refuel floor
- (6) Continuous Air Monitor used to monitor the Unit 3 drywell
- (7) Portable Alpha/Beta smear counter used on the refuel floor
- (8) Frisker used in the radiological waste building
Calibration and Testing Program (IP Section 03.02) (13 Samples)
The inspectors evaluated the calibration and testing of the following radiation detection instruments:
- (1) ThermoFisher Scientific SAM12, SN#12095
- (2) ThermoFisher Scientific SAM12, SN#152
- (3) ThermoFisher Scientific SAM12, SN#151
- (4) ThermoFisher Scientific PM12, SN#011
- (5) ThermoFisher Scientific PM12, SN#121
- (6) ThermoFisher Scientific PM12, SN#011
- (7) Ludlum Model 177, SN#0024972
- (8) Ludlum Model 3030P, SN#001631
- (9) Ludlum Model 177, SN#0017414
- (10) Mirion Argos 5, SN#1503-039
- (11) Mirion Argos 5, SN#1012-305
- (12) Mirion Argos 5, SN#1206-085
- (13) Mirion DMC3000, SN#950999 Effluent Monitoring Calibration and Testing Program Sample (IP Sample 03.03) (2 Samples)
The inspectors evaluated the calibration and maintenance of the following radioactive effluent monitoring and measurement instrumentation:
- (1) Unit 2/3 Particulate, Iodine, and Noble Gas (SPING-3/4) chimney effluent monitor
- (2) Unit 3 Service Water effluent sample radiation monitor
71124.07 - Radiological Environmental Monitoring Program
Environmental Monitoring Equipment and Sampling (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated environmental monitoring equipment and observed collection of environmental samples.
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, 2021 through March 31, 2022)
- (2) Unit 3 (April 1, 2021 through March 31, 2022)
MS07: High Pressure Injection Systems (IP Section 02.06) (2 Samples)
- (1) Unit 2 (April 1, 2021 through March 31, 2022)
- (2) Unit 3 (April 1, 2021 through March 31, 2022)
BI02: RCS Leak Rate Sample (IP Section 02.11) (2 Samples)
- (1) Unit 2 (April 1, 2021 through March 31, 2022)
- (2) Unit 3 (April 1, 2021 through March 31, 2022)
===71152S - Semiannual Trend Problem Identification and Resolution
Semiannual Trend Review (Section 03.02)===
- (1) The inspectors reviewed the licensees corrective action program for potential adverse trends in equipment reliability that might be indicative of a more significant safety issue.
71153 - Follow Up of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02)
The inspectors evaluated the following licensee event reports (LERs):
- (1) LER2021-001-01, Reactor Scram due to Main Power Transformer Failure (ADAMS Accession No. ML22165A204). The inspectors reviewed the updated LER submittal. The previous LER submittal was reviewed in Inspection Report
===05000237/2021004 and 05000249/2021004.
OTHER ACTIVITIES
- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL
60855 - Operation of an ISFSI Operation of an ISFSI===
- (1) The inspectors assessed the licensees Independent Spent Fuel Storage Installation (ISFSI) cask loading activities from May 9 through May 26, 2022. Specifically, the inspectors observed the following activities during the loading of multi-purpose canister (MPC) No. 787:
- heavy lift of the loaded transfer cask (HI-TRAC) from the spent fuel pool to the cask processing area
- canister processing including blowdown and forced helium dehydration
- stack-up and download of the MPC from the HI-TRAC into the storage cask (HI-STORM)
- radiological field surveys
The inspectors performed walkdowns of the ISFSI pad, including walkdowns of the ISFSI haul path.
The inspectors evaluated the following:
- spent fuel selected for loading into dry cask storage during this loading campaign
- selected corrective action program documents
- selected 72.48 screenings and evaluations
INSPECTION RESULTS
Enforcement Discretion Enforcement Action EA-22-055: Tornado Hazards Protection at Independent Spent Fuel Storage Installations 60855
Description:
Upon issuance of U.S. NRC Enforcement Guidance Memorandum (EGM) 22-001 (ML22087A496), dated April 15, 2022, the licensee performed an assessment of all outdoor dry cask storage activities that are not explicitly analyzed for tornado hazards in the cask licensing basis. One configuration was identified by the licensee when a loaded Holtec HI-STORM 100 storage overpack is brought out of the reactor building without a lid installed.
This configuration is not explicitly analyzed in the HI-STORM 100 FSAR. Title 10 of the Code of Federal Regulations (CFR) 72.212 (b)(6), states, in part, that the general licensee must:
review the Safety Analysis Report referenced in the [Certificate of Compliance] CoC or amended CoC and the related NRC Safety Evaluation Report, prior to use of the general license, to determine whether or not the reactor site parameters, including analyses of earthquake intensity and tornado missiles, are enveloped by the cask design bases considered in these reports. The results of this review must be documented in the evaluation made in paragraph (b)(5) of this section. Tornado hazards are evaluated in the Holtec HI-STORM Final Safety Analysis Report (FSAR) section 3.4.8, Tornado Wind and Missile Impact, and section 11.2.6.2, Tornado
Analysis.
These sections of the FSAR do not include an analysis for tornado hazards with the storage overpack lid removed. Similarly, the licensee did not have an evaluation demonstrating the reactor site parameters enveloped the cask design basis for tornado missiles specifically for the configuration where a loaded storage overpack was outdoors with the lid off.
Corrective Actions: The licensee entered the issue into its corrective action program to address the actions specified in EGM 22-001. Specifically, the licensee established additional measures that:
- (1) mitigate tornado hazards, through procedures, during periods of ISFSI handling operations which include:
- (a) precluding outdoor dry cask storage activities during periods of adverse weather;
- (b) establishing meteorological criteria and designating staff to monitor weather during ISFSI handling operations;
- (c) describing actions to take in the event of severe weather necessary to place the cask in an analyzed condition; and
- (d) minimizing the duration of ISFSI handling operations during which ISFSI important to safety structures, systems, and components are in an unanalyzed condition.
- (2) document that required weather checks are complete prior to the start of ISFSI handling operations
- (3) document in the CAP a request for the CoC holder to request an amendment within six months of the date of the EGM
Because the licensee implemented compensatory measures and plans to take necessary actions to restore compliance in accordance with the EGM, the NRC is allowing continued ISFSI handling operations.
Corrective Action References: IR 04494731; NRC Issuance of EGM 22-001 for ISFSI Tornado Hazard; 04/21/2022
Enforcement:
Significance/Severity: The inspectors assessed the issue as being more than minor significance but not more than Severity Level IV. Consistent with the guidance in EGM 22-001 discussed below, the NRC is exercising enforcement discretion.
Violation: Title 10 of the Code of Federal Regulations (CFR) 72.122 (b)(6), states, in part, that the general licensee must: review the Safety Analysis Report referenced in the CoC or amended CoC and the related NRC Safety Evaluation Report, prior to use of the general license, to determine whether or not the reactor site parameters, including analyses of earthquake intensity and tornado missiles, are enveloped by the cask design bases considered in these reports. The results of this review must be documented in the evaluation made in paragraph (b)(5) of this section.
Contrary to the above, on April 15, 2022, the licensee did not have a documented evaluation determining whether the reactor site parameters, including analyses of tornado missiles, were enveloped by the cask design bases considered in the Safety Analysis Report. Specifically, the licensee failed to have an analysis for tornado hazards when the loaded storage overpack is outside the reactor building without a lid installed.
Basis for Discretion: Because this violation was identified during the discretion period covered by Enforcement Guidance Memorandum 22-001, Enforcement Discretion for Noncompliance of Tornado Hazard Protection requirements at Independent Spent Fuel Storage Installations, and because the licensee was implementing compensatory measures and has taken or plans to take the necessary actions to restore compliance, the NRC is exercising enforcement discretion by not issuing an enforcement action for the violation and is allowing continued ISFSI handling operations.
Observation: Equipment Reliability Trend and Improvement Actions 71152S The inspectors performed a semiannual review of issues entered into the corrective action program (CAP) and a cognitive review of plant observations over the period of January 1, 2022, to June 30, 2022, to identify any potential trends that might indicate the existence of a more significant safety issue. The inspectors also reviewed the licensee's Equipment Reliability Excellence Plan to evaluate their corrective actions being taken to address gaps in this area.
In 2021, as a result of several impactful equipment deficiencies, the licensee and NRC identified a decline in their equipment reliability program. The licensee created the Excellence Plan to holistically review the equipment reliability program, identify gaps, and create corrective actions to address identified vulnerabilities. This Plan is a broad-scope, on-going effort that the inspectors reviewed to check-in on the licensee's progress in addressing equipment issues. To this point, the licensee has conducted several training and knowledge management activities for the engineering organization, as well as others throughout the site, to ensure all those involved in the process understood their critical roles in ensuring equipment deficiencies are properly identified, evaluated, and resolved to improve reliability. The licensee has also performed several benchmarking activities, within and external to the Constellation fleet, to identify best practices and improve their program for better results. Finally, the licensee has conducted a number of system reviews to identify specific vulnerabilities in the system and create targeted corrective actions to address those vulnerabilities. For example, a review of the Nuclear Instrumentation system created corrective actions to implement new maintenance strategies for replacement of undervessel cables and connectors for the instruments that repeatedly have caused inoperability/unreliability of these components.
The inspectors reviewed these system certifications, actions, and due dates. Currently, the actions appear appropriate; however, the inspectors emphasized that continued focus on executing aggressive schedules were needed to address some of the issues because of the age of the issue and/or the potential risk from allowing the issues to linger for an extended period of time. For example, the inspectors identified a Fire Protection (FP) system pipe that had a leak during a routine plant walkdown. This was one of several leaks on piping in this system that had revealed itself over the past year. The leak identified also impacted (dripped on) a Containment Cooling Service Water (CCSW) pipe and was creating a rust spot on that pipe. Both of these systems, FP and CCSW, have long-range plans to replace known degraded sections of piping due to the age and raw water conditions of the pipes. Based on issues self-revealed over the past year, these long-range plans have been re-scheduled to first available opportunities (either on-line or next refueling outage) to ensure more timely resolution. This is just one of several examples over the past six months, where leaks have occurred on raw water system piping. Also, during this time frame, the licensee had to emergently address a service water piping leak associated with the main turbine lube oil cooler. This issue could have had a significant operational impact on the unit if it hadn't been identified in a timely manner.
In the first half of 2022, the plant had still encountered many equipment deficiencies that have resulted in emergent responses on behalf of the organization to resolve, some of these also included emergent system inoperabilities and unit downpowers. For example, in March during a downpower, Unit 2 conducted emergent repairs to the 2B Feedwater pump breaker. In April, Unit 3 emergently shut down to repair packing leakage from the 1B Main Steam Isolation Valve (MSIV). Both of these issues were similar to or the same as prior equipment deficiencies on those components. The inspectors emphasized that the licensee ensure they are thoroughly evaluating all new events, and their extent-of-conditions, for lessons-learned and any gaps that could be addressed in their Equipment Reliability Excellence Plan.
Overall, for the first half of the year's activities associated with the Equipment Reliability Excellence Plan, the inspectors determined that, generally, the system reviews the licensee conducted were comprehensive and took into account some long-standing equipment degradation issues and deficiencies that need to be addressed in a timely manner. Currently, the corrective actions have due dates that are commensurate with the safety significance/risk impact of the deficiencies. The inspectors did not identify any findings or violations associated with the activities in the Plan up to this point.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On July 26, 2022, the inspectors presented the integrated inspection results to Mr. P. Boyle, Site Vice President, and other members of the licensee staff.
- On May 6, 2022, the inspectors presented the radiation protection inspection results to Mr. C. Joseph, Plant Manager, and other members of the licensee staff.
- On May 26, 2022, the inspectors presented the Operation of an ISFSI inspection results to Mr. C. Joseph, Plant Manager, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
60855
ALARA Plans
DR-0-22-00204/5
22 Dry Cask Activities
Corrective Action
Documents
East ISFSI Walkdown Quarterly Results
03/29/2019
West ISFSI Walkdown Quarterly Results
03/29/2019
2019 Dry Cask #2 WIP
05/07/2019
2019 Dry Cask Post Job Review
06/25/2019
West ISFSI 3Y Structural Inspection Finding
07/29/2019
East ISFSI 3Y Structural Inspection Findings
07/29/2019
West ISFSI Walkdown Quarterly Results
10/04/2019
West ISFSI Walkdown Quarterly Results
2/13/2019
West ISFSI Annual Walkdown Results
2/19/2019
East ISFSI Annual Walkdown Results
2/19/2019
20 Dresden Dry Cask Storage Campaign Critique & LL
07/01/2020
Corrosion on Top of Dry Casks
07/24/2020
West ISFSI Quarterly Walkdown Results Vent Holes and
Dents
07/31/2020
West ISFSI Quarterly Walkdown Results Surface Rust on
Casks
07/31/2020
NOS ID: West ISFSI 72.212 has Incorrect 72.48 Revisions
10/15/2020
22 14M ISFSI Cask Surveillance Inspection Results
04/01/2022
Miscellaneous
DCS Approval PCI Qualification Records
03/30/2022
DCS Approval LTS Qualification Records
03/31/2022
2.212 Evaluation
Report
East ISFSI 72.212 Evaluation Report
2.212 Evaluation
Report
West ISFSI 10 CFR 72.212 Evaluation Report
DRE22-0001
Dresden Unit 3 Fuel Selection Packages and Alternate
Assembly List for 2022 Campaign
2/04/2022
Procedures
DFP 0800-72
HI-STORM Processing
DOA 0800-01
Spent Fuel Cask Abnormal Conditions
GQP 9.2
High Temperature Liquid Penetrant Examination and
Acceptance Standards for Welds, Base Materials, and
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Cladding
GQP 9.6
Visual Examination of Welds
Fuel Selection and Documentation for Dry Cask Loading
OU-MW-671-200
FHD for BWRs
PI-CNSTR-OP-
EXE-H-01
Closure Welding of Holtec Multi-Purpose Canisters at Exelon
Facilities
Self-Assessments NOSA-DRE-20-
Independent Spent Fuel Storage Installation Audit Report
10/21/2020
Work Orders
05016349
D2/3 1Y COM Reactor Building Overhead Crane Inspection
2/11/2021
05044995
D2/3 1Y COM ISFSI Test of HI-TRAC Trunnions
05/27/2021
05046564
D2/3 1Y COM ISFSI Test of HI-STORM Lift Bracket
06/01/2021
05049684
D2/3 AN COM ISFSI Test of U2/3 RB 125 Ton Lift Yoke
06/09/2021
05127655
D2/3 1Y COM OSHA INSP Crane - RX BLDG Overhead
04/05/2022
05127675
D2/3 1Y COM OSHA Reactor BLDG Overhead Crane
Inspection
04/07/2022
05137506
D2/3 12M COM ISFSI Test of MPC Lift Cleats
05/28/2021
Corrective Action
Documents
4498962
Unit 3 Battery Room Air Conditioning Unit Compressor
Unreliable
05/11/2022
4499142
Trend IR: HVAC Performance at the Onset of Warm
Weather
05/11/2022
4500938
Unexpected Alarm, 902-7, H-3, Turbine Vacuum Lo
05/20/2022
4501989
Contingency TCCP for Loss of All Isophase Bus Duct
Cooling
05/25/2022
4506261
Thermography Anomaly Found in Unit 3 MPT
06/18/2022
4506651
MPT 3 Winding #2 Temperature Setpoint Discrepancy
06/21/2022
Dresden 2022 Summer Readiness Actions Per WC-AA-107
08/24/2021
Miscellaneous
Site Certification Letter for Summer Readiness
05/06/2022
Procedures
DOP 4450-08
Dresden Cooling Lake Operation
Seasonal Readiness
WC-DR-104-1001 Dresden 345kV Switchyard Configuration Risk Assessment
Procedures
DOP 1300-M1/E1
Unit 2 Isolation Condenser System Checklist
DOP 1400-E1
Unit 2 Core Spray System Electrical Checklist
DOP 1400-M1
Unit 2 Core Spray System
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
DOP 1500-E1
Unit 2 LPCI and CCSW Electrical Checklist
DOP 1500-E1
Unit 3 LPCI and CCSW Electrical Checklist
DOP 1500-M1
Unit 2 LPCI and Containment Cooling Valve Checklist
DOP 1500-M1
Unit 3 LPCI and Containment Cooling Valve Checklist
DOP 3700-M2/E2
Unit 2 RBCCW System Checklist
DOP 3700-M2/E2
Unit 3 RBCCW System Checklist
DOP 3800-M1
Unit 3 Turbine Building Closed Cooling Water System
Checklist
DOP 3800-M1
Unit 2 Turbine Building Closed Cooling Water System
Checklist
DOP 3900-E1
Unit 2(3) Service Water and Screen Wash System Electrical
Checklist
DOP 3900-M1
Unit 2/3 Service Water and Screen Wash Valve Checklist
DOP 6600-M1
Unit 2 Standby Diesel Generator Checklist
DOP 6600-M1
Unit 3 Standby Diesel Generator Checklist
Fire Plans
24 U3RB-26
Fire Zone 1.1.1.3, Unit 3 General Area, Elev. 545'
168 U3TB-79
Fire Zone 7.0.B, Unit 3 Battery Room, Elev. 551'
169 U3TB-80
Fire Zone 6.1, Unit 3 250V Battery Charger Room, Elev. 538' 06
175 U2/3TB-92
Fire Zone 8.2.5.C, Unit 2/3 EHC Reservoir Area, Elev. 517'
Corrective Action
Documents
4496905
Groundwater In-Leakage into Unit 2 Reactor Building from
HRSS Pipe Tunnel
05/01/2022
4497744
Rainwater into Unit 3 Torus Basement from HRSS Pipe
Tunnel
05/03/2022
Engineering
Evaluations
DR-PSA-012
Internal Flood Evaluation Summary and Notebook
71111.11Q Corrective Action
Documents
4500616
Follow-Up to IR 4496004 (DEP Failure in LORT Requal)
05/18/2022
Procedures
DGP 01-01
Unit Startup
2
DGP 02-01
Unit Shutdown
175
Corrective Action
Documents
4498962
Unit 3 Battery Room Air Conditioning Unit Compressor
Unreliable
05/11/2022
TBCCW Pump - Lessons Learned
03/06/2020
Request WGE to Evaluate Trend in RBCCW TCV
04/22/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Performance
D2R27: MOV 2-3703 Overtorque and Trace Anomalies
11/14/2021
IEMA ID - 3B TBCCW Pump Noise
03/29/2022
Engineering to Perform a SA for Raw Water Programs
04/13/2022
Generate WR to Inspect Actuator of MOV 2-3703 in D2R28
04/13/2022
Engineering
Changes
2098
Replace [Unit 3 Battery Room] HVAC Unit
Engineering
Evaluations
PMC-22-135043
Increase Frequency of PMRQ 789-01 to O1/1RFL (D3R27)
06/20/2022
Miscellaneous
Unit 3 AC/DC System Health Report
06/30/2022
Unit 3 Station Battery Maintenance Template
06/30/2022
Corrective Action
Documents
4482832
Increasing Floor Drain Leakage in Unit 3 Drywell
03/06/2022
4490878
Increasing Unit 3 Drywell Floor Drain Leakage
04/06/2022
4491049
Unit 3 Drywell Iodine 131 Increasing
04/07/2022
4491759
Unit 3 Drywell Beta Above NSO Appendix A Action Level
04/09/2022
4491906
3B RBCCW TCV Packing Leak
04/10/2022
4500354
Unexpected Main Control Room Alarm Unit 2 West Reactor
Building Floor Drain Sump Level Hi-Hi
05/17/2022
4502749
Unexpected Alarm: Core Thermal Power High
05/30/2022
4503851
Core Thermal Power Plant Process Computer Inputs Froze
06/04/2022
Corrective Action
Documents
Resulting from
Inspection
4495502
NRC ID: Small Oil Leak by Unit 2 EDG Immersion Heater
04/25/2022
Engineering
Evaluations
Safety Function
Determination 22-
05-001
Division 2 Containment Cooling Service Water System
05/17/2022
Miscellaneous
22 Dry Cask Storage (DCS) Flow Chart
Unit 3 Shutdown Safety Plan
Procedures
DAN 923-4, B-2
Unit 2 West Reactor Building Floor Drain Sump Level Hi-Hi
DEOP 0300-01
Secondary Containment Control
DFP 0850-01
Slow or Rapid Water Level Loss in Fuel Pool/Reactor Cavity
DFP 0850-02
New/Irradiated Fuel Damage
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
DFP 0850-03
High Radiation on Refuel Floor
OP-AA-107-F-01
Risk Screening/Mitigation Plan
Protected Equipment Lists (Various)
various
Corrective Action
Documents
4347579
Relay Contacts not Conducting
06/02/2020
4495629
Resistor Degradation
04/25/2022
4498962
Unit 3 Battery Room Air Conditioning Unit Compressor
Unreliable
05/11/2022
4499062
2A LPCI MUB Lube Oil Sample Returned with High Moisture
05/11/2022
4500689
3-1530-127 Relay Contact 3/4 had High Resistance
05/19/2022
2/3B Iso Condenser Makeup Pump Failed to Start on First
Try
2/28/2022
Engineering to Evaluate Iso Condenser Batteries
2/28/2022
Drawings
Schematic Diagram LPCI Containment Cooling System 1
Engineering
Evaluations
350673
Effects of Elevated Temperatures on the Unit 3 Station
Batteries
454497
Unit 3 DG Resistor Degradation
04/27/2022
Procedures
DOS 1300-03
2/3A(B) Isolation Condenser Makeup Pump Quarterly
Operability
Calculations
DRE98-0077
Dresden HPCI Room Thermal Response with Reduced
Room Cooler Capability
001
Corrective Action
Documents
Part 21: Continuously Energized Eaton D26 Relays
09/22/2020
HPCI Signal Converter Mod Temperature Qual Concerns
2/28/2021
HPCI Signal Converter - Commercial Grade Dedication
Issue
2/18/2022
Engineering
Changes
Replace U2 HPCI Signal Converter and Flow Indicating
Controller
008
Replace U3 HPCI Signal Converter and Flow Indicating
Controller
007
Procedures
50.59 Review Coversheet Replace U2 HPCI Signal
Converter and Flow Indicating Controller
50.59 Review Coversheet Replace U3 HPCI Signal
Converter and Flow Indicating Controller
006
50.59 Screening Form Replace Unit 2 HPCI Signal
Converter and Flow Indicating Controller
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
4491953
Unit 3 IRM 14 Issue
04/10/2022
4492293
Unit 3 IRM 14 Drawer Mode Switch Needs
Repair/Replacement
04/11/2022
Procedures
DIS 0700-45
IRM Channel Calibration
DOS 0250-02
Full Closure Timing and Exercising of Main Steam Isolation
Valves
DOS 0250-03
Main Steam Isolation Valve Fail Safe Closure Test
DOS 0700-02
Intermediate Range Monitor (IRM) Downscale Rod Block
Functional Test
DOS 0700-04
IRM Detector Position Rod Block Functional Test
DOS 0700-05
IRM Upscale and Inoperative Functional Testing
Work Orders
1514134
Unit 3 IRM 14 Issue
04/11/2022
1966818
Disassemble and Inspect 3-1402-13A Per DTP 48 and
Perform NDE-UT Unit 3 Division I Core Spray
05/10/2022
29976
3A Core Spray Pump Test with Torus Available
05/10/2022
247737
Unit 3 Drywell Pressure Step Change Up
04/11/2022
Corrective Action
Documents
4491749
Unit 3 Drywell Pressure Step Change Up
04/09/2022
4491934
Unit 3 Condenser Normal Makeup LCV Packing Leak
04/10/2022
4491970
Unit 3 Mechanical Vacuum Pump Suction Valve Interlock
Issues
04/10/2022
4492781
3-0203-1A Extent of Condition Torque Check
04/13/2022
4493866
Unit 3 Drywell Iodine Adverse Trend After D3F55
04/18/2022
Corrective Action
Documents
Resulting from
Inspection
4491932
NRC ID: 3B Reactor Feedwater Pump Inboard Seal Heat
Exchanger Leak
04/10/2022
4492231
Unit 3 Drywell Closeout D3F55
04/11/2022
Procedures
DIS 0500-07
38.5 Percent Rated Core Thermal Power Scram Bypass
Pressure Switches Calibration and Functional Checks
DOS 6600-12
Diesel Generator Tests Endurance and Margin/Full Load
Rejection/ECCS/Hot Restart
Calibration
Records
Work Order
04982780-1
Month Technical Specification Service Water Effluent
Sample Radiation Monitor Calibration
2/07/2022
Unit 2/3 18 Month Technical Specification Chimney SPING-4
Effluent Monitor Calibration
08/12/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
Upward Trend in Unit 2 Drywell CAM Activity.
06/03/2021
RP EP Instrumentation going out of Calibration
04/14/2022
Fastscan and Accuscan II WBC Inoperable
04/22/2022
Procedures
Controls for Radiation Protection Instrumentation
Operation and Calibration of the PM-12 Gamma Portal
Monitor
Operation and Calibration of the Canberra ARGOS-5
Personnel Contamination Monitor
Operation and Source Check of the Ludlum 3030P
Alpha/Beta Sample Counter
Operation and Calibration of the Model SAM-9/11 Small
Articles Monitor
RP-DR-905
Operation of the MTF, Refuel Floor and 2/3 Off-Gas Filter
Building NMC WIND-2B Continuous Air Monitor
Self-Assessments AR 04469158
22 Radiation Instrumentation Self-Assessment
04/18/2022
Miscellaneous
Monthly Report of the Meteorological Monitoring Program at
Dresden Nuclear Generating Station
2/2022
Dresden Nuclear Power Station 2020 Annual Radiological
Environmental Operating Report
05/2020
Procedures
EIML-SPM-1
Sampling Procedures Manual, Environmental Incorporated
Midwest Laboratory
71151
Miscellaneous
Performance Indicator Data: Barrier Integrity - RCS Identified
Leakage
04/01/2021
through
03/31/2022
MSPI Emergency AC Power Systems Prepared Data
Package
04/01/2021
through
03/31/2022
MSPI HPI Prepared Data Package
04/01/2021
through
03/31/2022
Procedures
DR-MSPI-01
Reactor Oversight Program MSPI Basis Document
Monthly Data Elements for NRC Reactor Coolant System
(RCS) Leakage
Corrective Action
4489659
Rust Found on Core Spray Piping/Nuts under Unit 2 East
04/02/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Documents
LPCI Room Cooler
4489931
Unit 2 Standby Coolant Line Recommendation for Guided
Wave
04/04/2022
4489933
Unit 3 Standby Coolant Line Recommendation for Guided
Wave
04/04/2022
4490647
MPT 3 Cooling Missed Opportunity
04/05/2022
4492766
Engineering to Perform FASA for Raw Water Programs
04/13/2022
4502154
System Certification Actions for RPS/NI
05/10/2022
4503201
System Certification Actions for Reactor Recirculation
05/31/2022
4504158
System Certification Actions for Service Water
06/07/2022
4504396
System Certification Actions for Main Steam
06/07/2022
4508872
ERVR4 Offgas Review - Engineering Follow-Up Action
Needed
07/01/2022