IR 05000237/2022003
| ML22304A178 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 10/31/2022 |
| From: | Robert Ruiz NRC/RGN-III/DORS/RPB1 |
| To: | Rhoades D Constellation Energy Generation, Constellation Nuclear |
| References | |
| IR 2022003 | |
| Download: ML22304A178 (18) | |
Text
SUBJECT:
DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3 - INTEGRATED INSPECTION REPORT 05000237/2022003 AND 05000249/2022003
Dear Mr. Rhoades:
On September 30, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Dresden Nuclear Power Station, Units 2 and 3. On October 13, 2022, the NRC inspectors discussed the results of this inspection with Ms. C. Joseph, Plant Manager, 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 31, 2022 This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely, Robert Ruiz, Chief Reactor Projects Branch 1 Division of Operating Reactor Safety Docket Nos. 05000237 and 05000249 License Nos. DPR-19 and DPR-25
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000237 and 05000249
License Numbers:
Report Numbers:
05000237/2022003 and 05000249/2022003
Enterprise Identifier:
I-2022-003-0048
Licensee:
Constellation Energy Generation, LLC
Facility:
Dresden Nuclear Power Station, Units 2 and 3
Location:
Morris, IL
Inspection Dates:
July 01, 2022 to September 30, 2022
Inspectors:
A. Nguyen, Senior Resident Inspector
M. Porfirio, Illinois Emergency Management Agency
C. St. Peters, Resident Inspector
Approved By:
Robert Ruiz, Chief
Reactor Projects Branch 1
Division of Operating Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Dresden Nuclear Power Station,
Units 2 and 3, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.
List of Findings and Violations
Failure to Select Appropriate Packing for the Unit 3 1B Main Steam Isolation Valve Cornerstone Significance Cross-Cutting Aspect Report Section Initiating Events Green NCV 05000237,05000249/2022003-01 Open/Closed
[H.9] - Training 71152A A self-revealed Green finding and associated non-cited violation of Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix B, Criterion III, Design Control, was identified for the failure to select appropriate packing for use in the Unit 3 1B main steam isolation valve (MSIV) that resulted in leakage from the valve during operation and eventual shut down of Unit 3 to perform emergent maintenance on April 10, 2022. Specifically, the licensee installed a packing set that was later determined to be unsuitable for the application and had torque values less than the vendor's recommended minimum, which caused the packing to relax while in-service and led to the leakage.
Additional Tracking Items
None.
PLANT STATUS
Unit 2 began the inspection at full rated thermal power. On July 12, 2022, the reactor automatically scrammed due to a failure of the 2A feedwater regulating valve. The licensee executed forced outage D2F61 to repair the valve. Unit 2 restarted and achieved full rated thermal power on July 14, 2022. The unit remained at or near full power for the remainder of the inspection period.
Unit 3 began the inspection period at full rated thermal power. On July 23, 2022, power was reduced to 75 percent power for a control rod pattern adjustment and the unit returned to full rated power on July 24, 2022. On August 20, 2022, another downpower to 73 percent power was performed for an end-of-cycle control rod sequence exchange and control rod testing. The unit was returned to full rated power on August 21, 2022. On September 19, 2022, the unit entered coast down in preparation for refueling outage D3R27 and remained in that condition for the rest 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 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
Impending Severe Weather Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the adequacy of the overall preparations to protect risk-significant systems from impending severe weather, high winds, and thunderstorm warning, on August 29, 2022.
External Flooding Sample (IP Section 03.03) (1 Sample)
- (1) The inspectors evaluated flood protection barriers, mitigation plans, procedures, and equipment are consistent with the licensees design requirements and risk analysis assumptions for coping with external flooding the week of July 18, 2022.
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Service water system and supported systems on July 30 - August 3, 2022
- (2) Unit 3 station blackout (SBO) diesel generator during Unit 2 SBO diesel generator endurance run on August 17, 2022
- (3) Unit 3 instrument air following the 3A instrument air compressor tripping off the week of August 29, 2022
- (4) Unit 3 isolation condenser during routine surveillance on Unit 3 high pressure coolant injection (HPCI) on September 15-16, 2022
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:
- (1) Fire Zone 8.2.6A, Unit 2 reactor feed pump vent H2 seal area, elevation 538' on August 4, 2022
- (2) Fire Zone 8.2.4, Unit 2 cable tunnel east and Unit 3 cable tunnel west, elevation 502' on August 9, 2022
- (3) Fire Zone 11.3, Unit 2/3 crib house, elevations 490', 509', and 517' on August 12, 2022
- (4) Turbine building elevation 517' during hot work for service water piping replacement on August 22-23, 2022
Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the onsite fire brigade training and performance during an unannounced fire drill on September 23, 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 Unit 2 reactor startup from forced outage D2F61 on July 13, 2022.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated a crew performance evaluation scenario in the main control room simulator on July 21, 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) Electrohydraulic control system due to weld failures on the turbine control valve accumulators
- (2) Fire protection system due to repeated issues with the diesel driven fire pump
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (2 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) Emergent plant challenges associated with grassing event at the ultimate heat sink from July 29 - August 5, 2022
- (2) Elevated plant risk due to planned activities on the Unit 3 125V station batteries and L1202, the week of September 12, 2022
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (4 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Unit 3 standby liquid control 3A squib valve circuit failure
- (3) Unit 2 emergency diesel generator (EDG) control switch contacts needing to be burnished
- (4) Air void identified on Unit 2 HPCI discharge piping above torus
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (2 Samples)
The inspectors evaluated the following temporary or permanent modifications:
- (1) Unit 2 and Unit 3 HPCI signal converter modification [permanent]
- (2) Bay 13 water level indication modification [temporary]
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated the following post-maintenance testing activities to verify system operability and/or functionality:
- (1) DOS 1500-01, low pressure coolant injection system valve operability, following emergent repairs to the 2-1501-18B, torus spray valve, breaker after it tripped during surveillance testing on July 25, 2022
- (2) Valve timing, fail safe testing, and local leak rate testing of AOV 3-1601-24 after valve stem sheared during surveillance testing per Work Order 5279666-04
- (3) DOS 1500-02, containment cooling service water pump test and inservice test, following planned maintenance on the 2-3999-252, U2 service water supply to emergency room coolers check valve, on September 16, 2022
- (4) DOS 6600-01, diesel generator surveillance tests, following planed replacement of the U3 EDG lubricator (3-6699-106), on September 20, 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) (4 Samples)
- (1) DIS 0700-10, Unit 3 source range monitor rod block calibration, on July 25, 2022
- (2) DOS 6620-01, SBO 2 diesel generator endurance and margin/full load test/full load reject test, on August 17-18, 2022
- (3) DOS 1300-05, 2/3A(B) isolation condenser makeup pump capacity test, on August 19, 2022
- (4) DOS 0500-25, reactor protection system channels A1, A2, B1, and B2 automatic scram contactor test, and DOS 0500-01, manual scram circuit sensor test, on September 1, 2022
Inservice Testing (IP Section 03.01) (1 Sample)
- (1) DOS 1400-05, Unit 2 core spray system pump test with torus available (IST) on August 2, 2022
FLEX Testing (IP Section 03.02) (1 Sample)
- (1) D2/3 1Y UHS SAWA/FLEX pump assembly performance test, Work Order 511103401
71114.06 - Drill Evaluation
Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)
The inspectors evaluated:
- (1) Off-year emergency preparedness exercise on September 27,
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
MS08: Heat Removal Systems (IP Section 02.07)===
- (1) Unit 2 (July 1, 2021 - June 30, 2022)
- (2) Unit 3 (July 1, 2021 - June 30, 2022)
MS09: Residual Heat Removal Systems (IP Section 02.08) (2 Samples)
- (1) Unit 2 (July 1, 2021 - June 30, 2022)
- (2) Unit 3 (July 1, 2021 - June 30, 2022)
MS10: Cooling Water Support Systems (IP Section 02.09) (2 Samples)
- (1) Unit 2 (July 1, 2021 - June 30, 2022)
- (2) Unit 3 (July 1, 2021 - June 30, 2022)
71152A - Annual Follow-up Problem Identification and Resolution Annual Follow-up of Selected Issues (Section 03.03)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- (1) Evaluation and corrective actions for the Unit 3 1B main steam isolation valve (MSIV)packing leak that led to an emergent unit shut down and forced outage for repairs under AR 4491749
71153 - Follow-Up of Events and Notices of Enforcement Discretion Event Follow-up (IP Section 03.01)
- (1) The inspectors evaluated failure of the Unit 2 2A feedwater regulating valve and licensees response on July 12-14, 2022
- (2) The inspectors evaluated impacts to the ultimate heat sink and supported systems from grass that blocked the intake and the licensees response on July 29 - August 5,
INSPECTION RESULTS
Failure to Select Appropriate Packing for the Unit 3 1B Main Steam Isolation Valve Cornerstone Significance Cross-Cutting Aspect Report Section Initiating Events Green NCV 05000237,05000249/2022003-01 Open/Closed
[H.9] - Training 71152A A self-revealed Green finding and associated non-cited violation of Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix B, Criterion III, Design Control, was identified for the failure to select appropriate packing for use in the Unit 3 1B main steam isolation valve (MSIV) that resulted in leakage from the valve during operation and eventual shut down of Unit 3 to perform emergent maintenance on April 10, 2022. Specifically, the licensee installed a packing set that was later determined to be unsuitable for the application and had torque values less than the vendor's recommended minimum, which caused the packing to relax while in-service and led to the leakage.
Description:
On April 9, 2022, operators identified a significant increase in the Unit 3 drywell leakage rate from the previous shift. The operators saw corresponding step changes in drywell pressure, activity, and temperature. Further investigation revealed that the 1B MSIV pilot temperature had a step change increase as well. Unit 3 commenced an emergent downpower to approximately 40 percent reactor power for a drywell entry to identify the cause of the parameter step changes. This entry identified a ~180-degree circumferential leak of the 1B (inboard) MSIV packing around the valve stem.
The site Outage Control Center (OCC) was staffed and a call with subject matter experts was held to discuss the observations from the drywell entry to determine potential repairs and testing. Subsequently, maintenance technicians attempted to re-torque the packing bolts on the valve but were unsuccessful at stopping the leakage. On April 10, 2022, a manual scram was inserted on Unit 3 to commence forced outage, D3F55, to repack the MSIV. During the forced outage, the licensee repacked the 1B MSIV with a new style of packing. They also performed extent of condition torque checks on all of the outboard and the other inboard MSIVs with movement noted on only one other valve (1A, inboard).
The licensee conducted a causal evaluation of the issue. The apparent cause was determined to be less than adequate packing stress which caused in-service relaxation of the packing. It was determined that the packing stress value was less than the vendors minimum preferred value for this valve. One contributing cause identified that the selection of the packing set that was installed in this valve did not allow for the packing stress to be raised to the preferred value recommended by the vendor. A lower packing stress value was used in order to maintain the packing friction below the maximum value. This was judged to be acceptable at the time of installation. After consulting the packing vendor, the vendor recommended a different selection of packing to improve performance with less friction and greater compressive force. The 1B valve was repacked with this different style packing. The other inboard MSIVs will be repacked in the upcoming Unit 3 refueling outage (November 2022) with this newer style packing as well. The licensees other corrective actions included creating more formal guidance to assist in the selection of packing and utilizing a Desktop Users Guide to select the best packing for a variety of valve styles. Also, a certification guide was created for individuals involved in the site valve packing program.
Corrective Actions: The licensee repacked the 1B MSIV during the forced outage with a new style of packing. Extent of condition torque checks were performed on the other inboard and outboard MSIVs during the forced outage as well. The licensee also consulted with the packing vendor to determine more appropriate styles of packing that can be used to meet the system requirements at Dresden and this new packing, and the revised maintenance procedure, will be used during the upcoming Unit 3 refueling outage to repack the other inboard MSIVs. Finally, the licensee is creating site-specific valve packing qualification guides and guidance documents.
Corrective Action References: AR 4491749, Unit 3 Drywell Pressure Step Change Up
Performance Assessment:
Performance Deficiency: The inspectors determined that the licensee failed to select packing that was suitable for application in the Unit 3 1B MSIV, as required by 10 CFR 50 Appendix B, Criterion III, which resulted in leakage from the valve during operation and eventual shut down of Unit 3 to perform emergent maintenance on April 10, 2022.
Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Equipment Performance attribute of the Initiating Events cornerstone and adversely affected the cornerstone objective to limit the likelihood of events that upset plant stability and challenge critical safety functions during shutdown as well as power operations. Specifically, failure to select appropriate packing for the 1B MSIV led to an emergent unit shut down for increased drywell leakage.
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 determined that this finding was of very low safety significance, or Green, since it could not reasonably cause a small LOCA, did not cause a reactor trip and loss of mitigating equipment, and it did not affect any support systems.
Cross-Cutting Aspect: H.9 - Training: The organization provides training and ensures knowledge transfer to maintain a knowledgeable, technically competent workforce and instill nuclear safety values. Specifically, the licensee identified that the packing installed on the 1B MSIV had a stress value that was less than the vendors minimum preferred value for the type of packing. To maintain the packing friction value below its maximum, a lower packing stress was needed, as calculated by the packing software used to calculate require torque and gland stress values during installation. It was not recognized that this lower value could lead to relaxation of the packing while in-service, which eventually caused the leakage. As a corrective action, the licensee will create a formal guidance document for site-specific valve packing and create a certification guide for individuals who will be responsible for selecting packing and using the software calculation program.
Enforcement:
Violation: 10 CFR Part 50, Appendix B, Criterion III, Design Control, requires, in part, that measures be established for the selection and review for suitability of application of materials, parts, equipment, and processes that are essential to the safety-related functions of the structures, systems, and components. Contrary to the above, from 2018 to April 10, 2022, packing used in the Unit 3 1B MSIV was not suitable for the application when the licensee failed to ensure site-specific valve packing criteria essential to the safety-related functions of the MSIV were met, and eventually caused the packing to relax while in-service and leak into the drywell.
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 13, 2022, the inspectors presented the integrated inspection results to Ms. C. Joseph, Plant Manager, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
DOA 0010-02
Tornado Warnings/ High Winds
DOA 0010-04
Floods
Procedures
MA-DR-MM-6-
00101
Maintenance Activities for Site Flooding
Corrective Action
Documents
Resulting from
Inspection
4517430
NRC Identified 3A SBO Engine Jacket Water Electric
Immersion Heater
08/17/2022
DOP 1300-M1/E1
Unit 3 Isolation Condenser System Checklist
DOP 1500-M1
Unit 2 Low Pressure Coolant Injection System and
Containment Cooling Service Water System Checklist
DOP 1500-M1
Unit 3 Low Pressure Coolant Injection System and
Containment Cooling Service Water System Checklist
DOP 3700-M2/E2
Unit 3 Reactor Building Closed Cooling Water System
Checklist
DOP 3700-M2/E2
Unit 2 Reactor Building Closed Cooling Water 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-M1
Unit 2/3 Service Water and Screen Wash System
Mechanical Checklist
DOP 4700-M1
3A Instrument Air Compressor (3-4706) Checklist
DOP 4700-M2
3B Instrument Air Compressor (3-4715-B) Checklist
DOP 6600-M1
Unit 2 Standby Diesel Generator Checklist
DOP 6600-M1
Unit 3 Standby Diesel Generator Checklist
DOP 6600-M2
Unit 2/3 Standby Diesel Generator Mechanical Checklist
DOP 6620-E2
Unit 3 Station Blackout Electrical Checklist
Procedures
DOP 6620-M2
Unit 3 Station Blackout Mechanical Checklist
Corrective Action
Documents
28225
4.0 Critique Crew 3 Q3 Unannounced Fire Drill
09/23/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
Resulting from
Inspection
4516052
2/3 Cable Tunnel Drain
08/10/2022
145 U2TB-48
Fire Zone 8.2.6A Unit 2 RFP Vent H2 Seal Area Elev. 538'
175 U2/3TB-92
Fire Zone 8.2.5.C, Unit 2/3 EHC Reservoir Area, elev. 517'
2 U2 Cable
Tunnel
Fire Zone 8.2.4 Unit 2 Cable Tunnel East Elev. 502'
183 Cable Tunnel
Fire Zone 8.2.4 Unit 3 Cable Tunnel West Elev. 502'
196 Circ PPs-124
Fire Zone 11.3 Unit 2/3 Circulating Water Pumps Elev. 490'
197 SW PPs-125
Fire Zone 11.3 Unit 2/3 Service Water Pumps / Traveling
Screens Elev. 509'
Fire Plans
198 U2/3 CH-126
Fire Zone 11.3 Unit 2/3 Crib House Ground Floor Elev. 517'
Hot Work Precautions and Safety Practices
Procedures
Fire Prevention for Hot Work
4510764
2-3201-B 2B Reactor Feedwater Pump Discharge Valve
Breaker Trips after Open Signal
07/13/2022
4510802
2B Reactor Feedwater Pump Abnormal Seal Indications on
Initial Start
07/13/2022
4510825
Unit 2 Mechanical Vacuum Pump Tripped on Overload
07/13/2022
Corrective Action
Documents
4514373
Critique for Hot Fast Restart
07/28/2022
Procedures
DGP 01-01
Unit Startup
203
4486119
3B EHC Pump Trip upon Start Attempt
03/20/2022
4490467
Unit 2 EHC Fluid Consumption Greater than Historical Norm
04/05/2022
4494315
Engineering to Perform Self-Assessment on Digital
Electrohydraulic Control System
04/20/2022
4498686
Unit 2 Control Valve 3 Electrohydraulic Control Accumulator
Leak
05/09/2022
4507600
2/3 DDP Tripped During Surveillance
06/26/2022
4512699
2/3 DFP Tripped
07/25/2022
4515415
Unexpected Alarm, 902-7 B-6, EHC Reservoir Level Hi/Lo
08/07/2022
Corrective Action
Documents
4516285
Work Request Needed for Extent of Condition NDE on Unit 2
Control Valve 4
08/11/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Main Turbine Health Group Report
08/15/2022
Miscellaneous
Fire Protection System Health Report
08/23/2022
4513847
3A Stator Water Cooling Heat Exchange Differential
Pressure High
07/30/2022
4513885
2/3 Main Control Room HVAC Train 'A', 'B' Air Compressor
Tripped
07/30/2022
Corrective Action
Documents
4514429
'A' and 'B' Main Control Room HVAC Heat Exchangers
07/31/2022
Protected Equipment List
09/15/2022
Procedures
WC-DR-104-1001
Dresden 345 kV Switchyard Configuration Risk Assessment
Work Orders
280509
2/3 Main Control Room HVAC 'A', 'B' Air Compressor
Tripped
08/02/2022
4505049
Control Switch Contacts Need to be Burnished
06/11/2022
4509034
Unexpected Alarm 903-5 H-6, SBLC Squib Valve Circuit
Failure
07/02/2022
4511662
Unit 3 HCU 34-43 (J-11) Buzzing Solenoid on SSPV
07/19/2022
Corrective Action
Documents
20324
Air Void Identified on U2 HPCI Discharge Piping Above
Torus
09/01/2022
Drawings
M-33
Diagram of Standby Liquid Control Piping
Procedures
DAN 902(3)-5 H-
SBLC Squib Valve Circuit Failure
4468573
HPCI Signal Converter Mod Temperature Qual Concerns
2/28/2021
Corrective Action
Documents
4479219
HPCI Signal Converter-Commercial Grade Dedication Issue
2/18/2022
395525
Replace U2 HPCI Signal Converter and Flow Indicating
Controller
397957
Replace U3 HPCI Signal Converter and Flow Indicating
Controller
Engineering
Changes
455347
Bay 13 Level Recorder Temporary Modification
08/24/2022
4512613
2-1501-18B, Unit 2 'B' Torus Spray Valve, Breaker Tripped
07/24/2022
4513269
AOV 3-1601-24 Valve Stem Sheared While Performing DIS
1600-24
07/27/2022
4513807
Air Leak from Fitting for AOV 3-1601-24
07/29/2022
4513810
AOV 3-1601-62 Failed to Open
07/29/2022
Corrective Action
Documents
4514560
Inspect / Replace the U3 D/G Starting Air Lubricator
08/02/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
DOS 1500-01
LPCI System Valve Operability
DOS 1500-02
Containment Cooling Service Water Pump Test and
Inservice Test (IST)
Procedures
DOS 6600-01
Diesel Generator Surveillance Tests
146
278802
2-1501-18B, Torus Spray Valve, Breaker Tripped
07/25/2022
279666
3-1601-24 Valve Stem Sheared While Performing DIS 1600-
07/29/2022
Work Orders
281939-02
OPs PMT The U3 D/G Starting Air Lubricator
09/20/2022
4512696
Unit 3 SRM 21 24V DC Input Fuse Failed during DIS 0700-
07/25/2022
Corrective Action
Documents
4516786
Issues with SAWA/Flex Pump 2, 2/3-1501-161
08/14/2022
DOS 0500-01
Manual Scram Circuit Sensor Test
DOS 0500-25
RPS Channels A1, A2, B1, and B2 Automatic Scram
Contactor Test
DOS 1400-05
Core Spray System Pump Operability and Quarterly IST
Test with Torus Available
Procedures
DOS 6620-01
Station Blackout 2 Diesel Generator Endurance and
Margin/Full Load Test/Full Load Reject Test
4958656
'B' Isolation Condenser Make-up Pump Capacity Test
08/19/2022
5111034
D2/3 1Y UHS SAWA/FLEX Pump (Pump 2) Assembly
Performance Test
09/23/2022
Work Orders
253824
Unit 3 Quarterly SRM Channel Calibration
07/29/2022
25264
Dresden Off-Year Exercise: EOF Objective Failures and
Others
09/28/2022
25291
Dresden Off-Year DEP Failure-SCR
09/28/2022
27609
EP Off-Year Exercise TSC Determination Criteria Failures
and Satisfactory Criteria with Comments
10/07/2022
27612
EP Off-Year Exercise Simulator Control Room Determination
Criteria Failures and Satisfactory Criteria with Comments
10/07/2022
Corrective Action
Documents
27624
EP Off-Year Exercise OSC Determination Criteria Failures
and Satisfactory Criteria with Comments
10/07/2022
71151
Miscellaneous
MSPI Residual Heat Removal Systems Prepared Data
Package
07/01/2021
to
06/03/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
MSPI Cooling Water Support Systems Prepared Data
Package
07/01/2021
to
06/30/2022
MSPI Heat Removal System Prepared Data Package
07/01/2021
to
06/30/2022
4189081
3-0203-1B Degraded Condition Identified for D3R25 Scope
Addition
10/29/2018
4491749
Unit 3 Drywell Pressure Step Change Up
04/09/2022
4491974
Extent of Condition Torque Check Inboard MSIV 3-0203-1C
04/10/2022
4491975
Extent of Condition Torque Check Inboard MSIV 3-0203-1D
04/10/2022
4492009
Extent of Condition Torque Check Outboard MSIV 3-0203-
2A
04/10/2022
4492010
Extent of Condition Torque Check Outboard MSIV 3-0203-
2B
04/10/2022
4492011
Extent of Condition Torque Check Outboard MSIV 3-0203-
2C
04/10/2022
4492013
Extent of Condition Torque Check Outboard MSIV 3-0203-
2D
04/10/2022
4492781
3-0203-1A Extent of Condition Torque Check
04/13/2022
4501438
Repack 3-0203-1D in D3R27
05/23/2022
4501439
Repack 3-0203-1C in D3R27
05/23/2022
4501440
Repack 3-0203-1A in D3R27
05/23/2022
Corrective Action
Documents
4501441
Repack 3-0203-1B in D3R27
05/23/2022
Procedures
DMP 0040-40
Valve Packing Installation Procedure
4410220
Evaluation of Mitigation Strategies for Intake Bay Fouling
03/19/2021
4510475
2A Feedwater Regulating Valve Failed Open
07/12/2022
4510475
2A FRV Failed Open
07/12/2022
4510480
2A Recirculation Pump Failed to Runback
07/12/2022
4510503
Unit 2 Turbine ISVs Failed to Open on Turbine Reset
07/12/2022
4510827
2A Reactor Feedwater Pump Discharge Valve Tripped on
Thermals
07/13/2022
Corrective Action
Documents
4511331
Unit 2 Recirculation Pump Seal Pressure Trend Before and
After Scram
07/16/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
4513955
Cribhouse Grassing Saturday
07/30/2022
4514253
Dresden EAL No Call - River Level EP Concurrence
08/01/2022
Corrective Action
Documents
Resulting from
Inspection
4517080
NRC Follow-up Question / EP Review EAL HU6 Basis
08/16/2022
M-14
Diagram of Reactor Feed Piping
MC
Drawings
M-14
Diagram of Reactor Feed Piping
MC
DOA 0010-01
Dresden Lock and Dam Failure
DOA 0010-04
Floods
DOA 4400-06
2/3 Crib House Screen Plugging
Procedures
Addendum 3
Emergency Action Levels for Dresden Station
Work Orders
260292
Perform OP-AA-108-114 Post-Transient Review for 2A
Feedwater Regulating Valve Failure
07/13/2022