IR 05000237/2020004
| ML21041A483 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 02/10/2021 |
| From: | Kenneth Riemer NRC/RGN-III/DRP/B1 |
| To: | Rhoades D Exelon Generation Co, Exelon Nuclear |
| References | |
| IR 2020004 | |
| Download: ML21041A483 (23) | |
Text
February 10, 2021
SUBJECT:
DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3 - INTEGRATED INSPECTION REPORT 05000237/2020004 AND 05000249/2020004
Dear Mr. Rhoades:
On December 31, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Dresden Nuclear Power Station, Units 2 and 3. On January 21, 2021, the NRC inspectors discussed the results of this inspection with Mr. P. Boyle, Plant Manager, and other members of your staff. The results of this inspection are documented in the enclosed report.
No findings or violations of more than minor significance were identified during this inspection.
This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely,
/RA/
Kenneth R. Riemer, Chief Branch 1 Division of Reactor Projects
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:
05000237/2020004 and 05000249/2020004
Enterprise Identifier: I-2020-004-0061
Licensee:
Exelon Generation Company, LLC
Facility:
Dresden Nuclear Power Station, Units 2 and 3
Location:
Morris, IL
Inspection Dates:
October 1, 2020 to December 31, 2020
Inspectors:
J. Cassidy, Senior Health Physicist
G. Edwards, Health Physicist
R. Elliott, Resident Inspector
M. Garza, Emergency Preparedness Inspector
V. Meghani, Reactor Inspector
A. Nguyen, Senior Resident Inspector
C. Phillips, Project Engineer
M. Porfirio, Illinois Emergency Management Agency
Approved By:
Kenneth R. Riemer, 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
None.
PLANT STATUS
Unit 2 began the inspection period at full power. On December 5, 2020, the unit was down powered to 66 percent for routine control rod drive scram time testing, a control rod sequence exchange, main turbine surveillances, and feedwater regulating valve maintenance. The unit returned to full power on December 6, 2020. The unit remained at or near full power for the remainder of the inspection period.
Unit 3 began the inspection period in coast down to prepare for refueling outage D3R26. On October 26, 2020, the unit was shut down to commence D3R26. The unit synchronized to the grid on November 7, 2020, and ascended to full power shortly thereafter. The unit was down powered to 65 percent power on November 14, 2020, for beginning-of-life control rod sequence exchanges and returned to full power on November 15, 2020. An additional down power was performed on November 21, 2020, to 70 percent power for additional control rod sequence exchanges. The unit returned to full power on November 22, 2020, and operated at or near full 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 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.
Starting on March 20, 2020, in response to the National Emergency declared by the President of the United States on the public health risks of the Coronavirus Disease 2019 (COVID-19),resident inspectors were directed to begin telework and to remotely access licensee information using available technology. During this time, the resident inspectors performed periodic site visits each week; conducted plant status activities as described in IMC 2515, Appendix D, Plant Status; observed risk-significant activities; and completed on-site portions of IPs. In addition, resident and regional baseline inspections were evaluated to determine if all or portions of the objectives and requirements stated in the IP could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable IP. In some cases, portions of an IP were completed remotely and on-site. The inspections documented below met the objectives and requirements for completion of the IP.
REACTOR SAFETY
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (3 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Unit 3 shutdown cooling system during D3R26 on October 26, 2020
- (2) Electrical alignment during D3R26: 4kV crossties on October 29, 2020, and November 2, 2020
- (3) Unit 3 alternate delay heat removal and fuel pool cooling system alignment during D3R26 on November 2, 2020
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:
- (1) Fire Zone (FZ) 8.2.5D and FZ 8.2.6D, Unit 3 low pressure heater bays on October 27,2020
- (2) FZ 8.2.2B, Unit 3 containment cooling service water pump floor, elevation 495', and comp measures for out of service fire hose stations on October 30, 2020
- (3) FZ 1.1.1.3, Unit 3 reactor building general area, elevation 545' on November 2, 2020
- (4) FZ 1.2.1, Unit 3 drywell primary containment on November 3, 2020
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) Cable tunnel on December 18, 2020
71111.07A - Heat Sink Performance
Annual Review (IP Section 03.01) (1 Sample)
The inspectors evaluated readiness and performance of:
- (1) Unit 3 'A' low pressure coolant injection heat exchanger
71111.08G - Inservice Inspection Activities (BWR)
BWR Inservice Inspection Activities Sample - Nondestructive Examination and Welding
Activities (IP Section 03.01)
- (1) The inspectors verified that the reactor coolant system boundary, reactor vessel internals, risk-significant piping system boundaries, and containment boundary were appropriately monitored for degradation and that repairs and replacements were appropriately fabricated, examined and accepted by reviewing documents for the following activities from October 26, 2020, to November 5, 2020:
03.01.a - Nondestructive Examination and Welding Activities
1. Nondestructive Examinations
- Visual VT-1 Examination, reactor pressure vessel (RPV) head vent piping flange bolting 3/1/0215-4/4A-1(A)-FLG
- Visual VT-3 Examination, rigid support, M-3410-09, containment
- Visual VT-3 Examination, spring hanger, M-3411-04, containment
- Visual VT-3 Examination, supports 01 /02/06, torus ring girder - support columns/inner support column base plates/ outer support column base plates
- In-Vessel Visual Inspection (IVVI) of RPV Internals, component IDs CSS 1 S3 a, b 008-080 (Core Spray Sparger) and JP 09 WD-1 (Jet Pump), part of the boiling water reactor vessel and internals project (VIP)
2. Examination records with relevant indications accepted for continued service
- Recordable UT Indications, D3R25, Weld 3/2/02A-12/12-8, isolation condenser shell to nozzle weld (AR 04190585)
3. Pressure boundary welds
- Welds 1 through 4, replace CCSW [component cooling service water] pump 3-1501-44-D degraded discharge elbow (Work Order 04678175-01)
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 reactor shutdown/cool down on October 26, 2020
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (1 Sample)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:
- (1) Unit 3 C circulating water pump bearing identified as failed during Unit 3 refueling outage on October 17, 2020
Quality Control (IP Section 03.02) (1 Sample)
The inspectors evaluated the effectiveness of maintenance and quality control activities to ensure the following SSC remains capable of performing its intended function:
- (1) High-pressure coolant injection rupture disc maintenance and quality control, failures during installation during D3R26
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) Division 1 and 2 low pressure coolant injection and core spray work windows during the week of October 19 - 23, 2020
- (2) Unit 3 transfer of AC feed to and from 4kV crossties during D3R26 on October 29, 2020, and November 2, 2020
- (3) Unit 3 Yellow shutdown risk during lowered inventory conditions on October 27, 2020, and November 4, 2020
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (6 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
(1)2A reactor feedwater pump lost indication
- (2) Cardox tank level low causing CO2 to be inoperable to emergency diesel generator rooms
- (3) Many partially blocked containment spray nozzles identified during Unit 3 testing
- (4) Unit 3 isolation condenser 3-1301-3 valve over-torqueing during testing
- (5) Emergency core cooling system valve issues identified during D3R26
- (6) Local leak rate test leakage identified during D3R26
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (1 Sample)
The inspectors evaluated the following temporary or permanent modifications:
- (1) Adjustable speed drive NXG circuit card obsolescence and cooling upgrades
[Permanent]
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (7 Samples)
The inspectors evaluated the following post-maintenance test activities to verify system operability and functionality:
- (1) DOS 0201-01, Unit 3 reactor pressure vessel ASME B&PV (American Society of Mechanical Engineers Boiler and Pressure Vessel) Code 1000 psi system leakage test, after work that affected the reactor coolant system and boundaries during D3R26 on November 5, 2020
- (2) Unit 3 control rod drive exercising and timing after repairs during D3R26 on November 5 and 6, 2020
- (3) DOS 0040-07, Unit 3 verification of remote position indication for valves in the inservice testing program, after troubleshooting and repair of the 3-0220-44 and 3-0220-46 valves per WOs 5096172 and 5092566 during D3R26
- (4) Division 1 core spray post-maintenance tests (PMTs) D3R26
- (5) Unit 3 low pressure coolant injection and containment cooling service water PMTs D3R26
- (6) DOS 2300-03, Unit 3 high-pressure coolant injection system operability and quarterly IST (inservice testing) verification test, after system maintenance completed during D3R26 on November 7, 2020
- (7) Troubleshoot and repair Unit 3 rod select matrix per WO 5086646
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated the Unit 3 refueling outage, D3R26, activities from October 26, 2020, through November 7, 2020
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Surveillance Tests (other) (IP Section 03.01)
- (1) DOS 6600-03, Unit 3 Division 1 undervoltage test on October 27 and 28, 2020
- (2) DIP 0260-01, Refuel outage reactor vessel level and cavity instrumentation on October 26 and November 5, 2020
Inservice Testing (IP Section 03.01) (1 Sample)
- (1) DOS 7100-06, Unit 3 seat leakage testing of valve 3-2301-7, high-pressure coolant injection check valve, on October 30, 2020
Containment Isolation Valve Testing (IP Section 03.01) (1 Sample)
- (1) Local leak rate testing of Unit 3 main steam isolation valves and feedwater check valves during D3R26 on October 27-29, 2020
FLEX Testing (IP Section 03.02) (1 Sample)
- (1) WO 4718444, FLEX SAWA pump run on November 10, 2020
71114.04 - Emergency Action Level and Emergency Plan Changes
Inspection Review (IP Section 02.01-02.03) (1 Sample)
- (1) The inspectors completed an evaluation of submitted emergency action level and emergency plan changes on December 2, 2020. This evaluation does not constitute NRC approval.
71114.06 - Drill Evaluation
Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)
The inspectors evaluated:
- (1) EP Drill on December 3,
RADIATION SAFETY
71124.01 - Radiological Hazard Assessment and Exposure Controls
Radiological Hazard Assessment (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated how the licensee identifies the magnitude and extent of radiation levels and the concentrations and quantities of radioactive materials and how the licensee assesses radiological hazards.
Instructions to Workers (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated radiological protection-related instructions to plant workers
Contamination and Radioactive Material Control (IP Section 03.03) (1 Sample)
The inspectors evaluated licensee processes for monitoring and controlling contamination and radioactive material.
- (1) Observed licensee surveys of potentially contaminated material leaving the Radiologically Controlled Area (RCA) and workers exiting the RCA at Unit 3 during a refueling outage.
Radiological Hazards Control and Work Coverage (IP Section 03.04) (1 Sample)
The inspectors evaluated in-plant radiological conditions during facility walkdowns and observation of radiological work activities.
- (1) Initial entry into reactor cavity and decontamination after refueling during D3R26 under radiation work permit (RWP) DR-03-20-00906
Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 03.06) (1 Sample)
- (1) The inspectors evaluated radiation worker and radiation protection technician performance as it pertains to radiation protection requirements
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below:
MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04)===
- (1) Unit 2 (October 1, 2019 through September 30, 2020)
- (2) Unit 3 (October 1, 2019 through September 30, 2020)
MS08: Heat Removal Systems (IP Section 02.07) (2 Samples)
- (1) Unit 2 (July 1, 2019 through June 30, 2020)
- (2) Unit 3 (July 1, 2019 through June 30, 2020)
MS09: Residual Heat Removal Systems (IP Section 02.08) (2 Samples)
- (1) Unit 2 (July 1, 2019 through June 30, 2020)
- (2) Unit 3 (July 1, 2019 through June 30, 2020)
MS10: Cooling Water Support Systems (IP Section 02.09) (2 Samples)
- (1) Unit 2 (July 1, 2019 through June 30, 2020)
- (2) Unit 3 (July 1, 2019 through June 30, 2020)
BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10) (2 Samples)
- (1) Unit 2 (October 2019 through September 2020)
- (2) Unit 3 (October 2019 through September 2020)
BI02: RCS Leak Rate Sample (IP Section 02.11) (2 Samples)
- (1) Unit 2 (October 1, 2019 through September 30, 2020)
- (2) Unit 3 (October 1, 2019 through September 30, 2020)
OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)
(1)
(June 2019 through September 2020)
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)
(April 2019 through September 2020)
71152 - Problem Identification and Resolution
Semiannual Trend Review (IP Section 02.02) (1 Sample)
- (1) The inspectors reviewed the licensees corrective action program for potential adverse trends during D3R26, specifically focused on Human Performance events that could be indicative of a more significant safety issue.
Annual Follow-up of Selected Issues (IP Section 02.03) (2 Samples)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- (1) Safety-related valve degradation issues identified during D3R26, the Unit 3 refueling outage, from October 26 through November 7, 2020
INSPECTION RESULTS
Observation: Potential Negative Trend in Human Performance Events 71152 The inspectors performed a semiannual review of issues entered into the corrective action program (CAP) and a cognitive review of observations conducted over the period of July 1, 2020, to December 31, 2020, to identify any potential trends that might indicate the existence of a more significant safety issue. Based on these reviews, the inspectors concluded that there was a potential negative trend in the area of Human Performance.
Specifically, there were a number of issues where the implementation of human performance tools was not adequate to prevent errors, emergent work scheduling changes led to unintended challenges for completing (or in some cases missing) work activities, and general attention to detail and appropriate focus on work activities was not demonstrated to ensure proper engagement by plant personnel to prevent errors. Examples of these human performance issues, and their associated CAP documents, are listed below:
- IR 4372663, Temporary Loss of Fire Watch
- IR 4378033, Security Response to Turnstile Alarm
- IR 4381193, D3R26, Fuel Handling Error during Fuel Shuffle 2
- IR 4381800, Reseat of Fuel Support Casting Location 18-23
- IR 4383120, 2 Valves Still Need Required Surveillance Testing
- IR 4385280, D3R26, Near Miss of PMT Required Prior to Mode 2
- IR 4385543, D3R26, Hydro Preps Conflict with IM Logic Testing
- IR 4390417, Entered DOA 4450-03 for Loss of Lift Station and
- IR 4384354, Ops Crew Clock Reset, Quarterly Valve Timing
The residents discussed these observations with the licensee. The licensee created corrective actions to address some of these items for the specific issue in the CAP system.
However, the licensee, at the time of this report, had not performed a holistic review of the issues to determine if there were more widespread actions that could be taken to improve performance. The licensee will convene a group to review the data and determine any actions going forward.
Observation: Safety-Related Valves Found Degraded during D3R26, Unit 3 Refueling Outage 71152 During the refueling outage on Unit 3, several safety-related valves were identified as being degraded and documented in the corrective action program. The inspectors reviewed the current corrective actions associated with ensuring these valves remained in compliance with licensing and design basis requirements. No issues were identified that would challenge the safety function or operability of these valves. The corrective actions taken were determined to be timely and appropriate for the conditions identified.
The inspectors also reviewed previous condition reports and corrective actions for prior degradation issues identified with a select number of these valves. The inspectors found that a few of the valves had repetitive degradation issues identified in the CAP and reviewed the prior evaluation of these issues to determine if the issues were addressed appropriately. The inspectors determined that previous evaluations were appropriate for the conditions identified at the time and that the corrective actions taken were adequate. Some of the degradation mechanisms were different over time, and/or maintenance frequencies were appropriately changed to identify potential issues sooner.
Observation: Multiple Failures of the FLEX SAWA Pumps during Surveillance Runs.
71152 The inspectors reviewed multiple issue reports associated with the licensee's attempts to operate the FLEX SAWA pumps per the required monthly test runs which were unsuccessful.
The degraded conditions were documented adequately in the CAP in a timely manner. The inspectors reviewed the current corrective actions associated with ensuring FLEX SAWA pumps remained in compliance with licensing and design basis requirements. No issues were identified that would challenge or pose a threat to the licensee's FLEX strategy or implementation. The corrective actions taken were determined to be timely and appropriate for the conditions identified.
The inspectors also reviewed previous condition reports and corrective actions for previous FLEX pump issues identified during surveillance runs. The inspectors found repetitive degradation issues identified during the surveillances that were entered in the CAP and reviewed the prior evaluation of these issues to determine if the issues were addressed appropriately. The inspectors determined that previous evaluations were appropriate for the conditions identified at the time and that the corrective actions taken were adequate. The licensee also identified and entered the trend of FLEX issues into their CAP program IR 4374740, Trend IR FLEX Equipment.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On January 21, 2021, the inspectors presented the integrated inspection results to Mr. P. Boyle, Plant Manager, and other members of the licensee staff.
- On November 5, 2020, the inspectors presented the Inservice Inspection Exit D3R26 inspection results to Mr. P. Karaba, Site Vice President, and other members of the licensee staff.
- On December 2, 2020, the inspectors presented the IP 71114.04 exit meeting inspection results to Mr. D. Moore, Senior Manager Emergency Preparedness, and other members of the licensee staff.
- On December 10, 2020, the inspectors presented the radiation protection inspection results to Mr. T. Casagrande, Radiation Protection Manager, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
4380442
3-1001-4A Valve Stem Corrosion
10/27/2020
Corrective Action
Documents
Resulting from
Inspection
4379748
D3R26 3-1999-325 Packing Leak
10/26/2020
Engineering
Evaluations
2343
D3R26 Spent Fuel Pool Cooling Evaluation During
Transition to ADHR
Procedures
DOP 1000-M1/E1 Unit 3 Shutdown Cooling Checklist
DOP 1900-E1
Fuel Pool Cooling Electrical
DOP 1900-M1
Unit 3 Fuel Pool Cooling System Checklist
DOP 6500-30
E: Bus Crosstie Amps
DOS 1000-02
Alternate Decay Heat Removal Using Shutdown Cooling
and Fuel Pool Cooling Systems
Corrective Action
Documents
4380385
Transient Combustibles Located Under Stairwell
10/28/2020
Engineering
Evaluations
Various Transient Combustible Permits for D3R26, Unit 3
Refueling Outage, Work Activities
Fire Plans
21 URB-23A
Dresden Generating Station Pre-Fire Plan
FZ 8.2.2B
Unit 3 CCSW Pumps, Elevation 495'
FZ 8.2.5D
Unit 3 Low Pressure Heater Bay, Elevation 517'
FZ 8.2.6D
Unit 3 Low Pressure Heater Bays, Elevation 538'
Miscellaneous
Hot Work Permits for Welding in Unit 3 Low Pressure and
High-Pressure Heater Bays during D3R26
Procedures
Fire Protection System Impairment Control
Miscellaneous
DR-PSA-012
Internal Flood Evaluation Summary and Notebook
Corrective Action
Documents
4380814
3A LPCI Tubes Stuck Cleaning Scrapers
10/30/2020
4381431
3-1599-112, CCSW Heat Exchanger Sample Line Flush
Valve, Failed Inspection
11/01/2020
4381473
D3R26 3A LPCI Heat Exchanger Coating Repairs
11/01/2020
4383193
3A LPCI Heat Exchanger D3R26 Coatings Repairs
Lessons Learned
10/31/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
NDE Reports
20-10
Eddy Current Examination Final Report for Exelon Nuclear
Dresden, Unit 3, 3A LPCI Heat Exchanger
(3-1503-A)
11/02/2020
Work Orders
4590891
D3R26 Clean/Inspect/Eddy Current 'A' LPCI Heat
Exchanger
11/02/2020
Calculations
1801382.301
Dresden Iso Condenser Flaw Evaluation
Corrective Action
Documents
00949941
Corrosion on Unit 3 Torus Baseplate Anchor
08/03/2009
04013601
Degraded Unit 3 CCSW Piping Identified
05/22/2017
04379976
D3R26 Drywell Basement Moisture Barrier Relevant
Conditions
10/27/2020
04380663
D3R26 FAC, Area on 3D2 Heater found Below Min Wall
10/29/2020
04381396
D3R26 Nonrelevant Condition on Support M-3410-09
10/31/2020
Drawings
3-CISI-1000 SHT
2B
IWE Component Detail, Drywell Floor Core Hole Locations
and Details
A
M-3410-09 SHT
Vacuum Relief 3-16040 18 IN LX
B
M-3410-09 SHT
Vacuum Relief 3-16040 18 IN LX
E
M-3411-04 SHT
Support Drawing
D
Engineering
Evaluations
ASME Code Case N-586-1 Evaluation for Unit 3 Isolation
Condenser 3/2/1302A-12/12-8 Nozzle to Shell Weld
VT-3 Report for License Renewal Supports 1, 2, 6
10/31/2020
20-393
VT-3 - Component No. M-3410-09
11/02/2020
20-403
VT-3 for Component No. M-3411-04
11/02/2020
20-427
UT Thickness Measurements of the Drywell Basement
Floor Liner in 22 Core Hole Locations
11/02/2020
VT-1 for 3/1/0215-2/HV2-18-FLG
10/31/2020
3/1/0215-4/4A-1(A)-FLG
10/31/2020
Procedures
Ultrasonic (UT) Measurement of Material Thickness and
Interfering Conditions
VT-1 Visual Examination
VT-3 Visual Examination of Component Supports,
Attachments and Interiors of Reactor Vessels
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Visual Examination of ASME IWE Class MC and MET
ALLIC Liners of Class CC Components
GEH-VT-203
Procedure for In-Vessel Visual Inspection (IVVI) of BWR 3
RPV Internals
Work Orders
04678175-01
CM Replace CCSW Pump 3-1501-44-D, Degraded
Discharge Elbow
11/02/2018
04615093-11
Through Wall Pipe Leak on CCSW Line 3-1514-16
03/23/2017
Corrective Action
Documents
4382882
D3R26 - Steam Leak from HPCI Rupture Disc
11/07/2020
4377284
3C Circulating Water Pump Bearing High Temperature
10/17/2020
Engineering
Changes
2912
HPCI Steam Rupture Disc - Allow Use of 140 psig Rated
Set
Engineering
Evaluations
448508
Evaluate Torque Value for HPCI Rupture Discs with Fully
Lubricated Flange Bolts
448508
Evaluate Torque for HPCI Rupture Disc Based on
Lubricated Stud Bolts
Procedures
DMP 2300-14
HPCI Rupture Disc Maintenance
and 09
Work Orders
25035
IST Replace Both Unit 3 HPCI Turbine Steam Exhaust
Rupture Discs
11/03/2020
Corrective Action
Documents
Resulting from
Inspection
4379974
NRC Questions During D3R26
10/27/2020
4380495
NRC Concern on Protected Pathway
10/29/2020
4382296
Protected Pathway Concerns
11/04/2020
4382308
NRC ID: 2/3 RBCCW Oiler Empty
11/04/2020
4382310
NRC ID: 3A CCSW Pump Seal Leakage
11/04/2020
Miscellaneous
D3R26 Shutdown Safety Contingency Plans,
Compensatory Action Plans and Related Work Evaluation
10/13/2020
D3R26 Protected Equipment Summary
10/23/2020
Protected Equipment Schemes for Various Plant
Configurations Reviewed this Quarter
Procedures
DOP 6400-13
Electrical Yard Switching
DOP 6400-14
Transformer 86 Load Tap Changer Operation
DOP 6500-08
Bus 24-1 to Bus 34-1 Tie Breaker Operation
DOP 6500-30
Bus 23-1 to Bus 33-1 Tie Breaker Operation
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
DOS 1100-04
Standby Liquid Control System Quarterly/Comprehensive
Pump Test for the Inservice Testing (IST) Program
DOS 5750-04
Control Room Train B HVAC and Air Filtration Unit
Surveillance
Protected Equipment Program
Corrective Action
Documents
4379382
LLRT Results Above Alarm Limit for Penetration X-138
10/25/2020
4379385
LLRT Results Above Warning Limit for Penetration
X-149B
10/25/2020
4379698
LLRT Results Above Warning Limit for AOV 3-2001-6
10/26/2020
4379747
Cardox Tank Low
4379969
3-1501-26A Leakage During LPCI Single Loop Test
10/27/2020
4380023
High Resistance Contacts - Control Switches for HPCI
Valves
10/27/2020
4380323
Unable to Close Breaker for 3-1501-21A
10/28/2020
4380764
LLRT Results Above Warning Limit for MOV 3-1501-19A
10/30/2020
4380783
Open Contacts on Torque Switch
10/30/2020
4381583
D3R26 Results of U3 LPCI Containment Spray Testing
4382613
3-1501-25B Failed to Indicate Full Open during Testing
11/05/2020
4389199
2A Reactor Feedwater Pump Indicating Light Out
2/09/2020
Drawings
Schematic Diagram: 480V Bus 29 Main Feed and Bus
28-29 Crosstie Breakers
AH
Engineering
Changes
2250
Blocked Drywell Spray Nozzle Evaluation for AST Dose
Analyses
Procedures
DOS 0040-07
Verification of Remote Position Indication for Valves
Included in Inservice Testing (IST) Program
Work Orders
4855292
Primary Containment Type B&C Leakage Rate Test
Summation
11/11/2020
Engineering
Changes
25677
ASD Obsolescence and Cooling Upgrades
28647
ASD NXG Circuit Card on ASD Digital Card Rack
Procedures
DOS 0202-25
ASD Testing in Open Loop Test Mode
Corrective Action
Documents
4379710
Failed Recirculation Sample Valve, 3-0220-44; Did Not
Open with Control Switch
10/26/2020
4380424
Rupture Disc Failure During Install
10/29/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
4381583
D3R26 Results of U3 LPCI Containment Spray Testing
4382189
11/04/2020
4382306
D3R26 Flowscan Testing of the 3-0220-44 Recirculation
Sample Valve
11/04/2020
4382356
AOV 3-0220-44 Showing Dual Indication on Position
11/05/2020
4382501
D3R26 System Leakage Test: 84 dpm Leak from
HCU 14-11
11/05/2020
4382541
D3R26 RCPB Class 1 System Leakage Test Results
11/05/2020
4382602
AO 3-0220-45 Valve will Not Open from Main Control
Room during PMT
11/05/2020
4382606
3-0220-46, Reactor Head Vent Valve, will Not Operate
11/05/2020
4382650
LLRT Results above Warning Limit for AOV 3-0220-44
(As-Left)
11/06/2020
4382911
Entered DOA 0700-02 for IRM 13 Not Withdrawn
11/07/2020
4383070
Unit 3 Rod Select Matrix Issues
11/08/2020
4386073
D3R26 Unit 3 Rod Select Matrix Troubleshooting
11/18/2020
Engineering
Evaluations
395859
Evaluation of Leakage at Mechanical Connections for
Class 1 and 2 System Leakage Test
448626
IRM 13 Fuses Replaced with 2 Amp due to 1 Amp Fuses
Blowing when Attempting to Withdraw IRM During Startup
2929
Evaluation of Leakage at Mechanical Connection for LPCI
Valve 3-1501-26A
Procedures
DIS 1500-20
Division 1 and II Low Pressure Coolant Injection Pumps
Suction and Injection Valves Circuitry Logic System
Functional Test
DOS 0040-07
Verification of Remote Position Indication for Valves
Included in Inservice Testing Program
DOS 0201-02
Unit 3 RPV ASME B and PV Code 1000 PSI System
Leakage Test
DOS 0300-08
CRD Exercising with Mode Switch in Refuel
DOS 0300-15
Control Rod Drive SCRAM Timing Test during Hydro
DOS 2300-03
High-Pressure Coolant Injection System Operability and
Quarterly IST Verification Test
117
DTS 1500-03
LPCI Containment Spray Test
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Work Orders
01784322
D3 4Y TS LPCI Containment Spray Test of D/W Spray
Nozzle
1610562
Replace Regulator and Diaphragm and Repack
3-0220-44 Valve
11/06/2020
4570360
D3 24M TS Division 1 and 2 LPCI Suction and Injection
Valves LSFT
4852964
Replace ASCO Solenoid for Valve 3-0220-44
11/06/2020
4872264
Unit 3 Refuel Outage ISI 1000 PSI Reactor Vessel
Leakage Test (Hydrostatic Test)
11/05/2020
5068912
Inspect and Replace MSC and MGU Limit Switches
10/30/2020
5092566-02
(PMT) Perform Logic Testing of Valve 3-0220-44
11/06/2020
5096172
3-0220-46, Reactor Head Vent Valve, will Not Operate,
Troubleshoot and Repair
11/06/2020
Corrective Action
Documents
4382043
D3R26: FME ECCS Suction Strainer Inspection Results
11/03/2020
4382206
Deviation to Implementation of the Work Hour Rule
4382403
Deviation to Implementation of the Work Hour Rule
4382946
203-5 Instrument Rack Leak
11/07/2020
4382985
3C Reactor Feedwater Pump Auxiliary Oil Pump Did Not
Automatically Shut Off
11/08/2020
4382993
3A Reactor Feedwater Pump Discharge Valve Binding
11/08/2020
4382994
MFDLRX Mismatch during D3R26 Power Ascension
11/07/2020
Engineering
Changes
2956
MR-90 Jumpers to Support D3R26 Hydro Test Prior to
Startup
Miscellaneous
D3R26 Refuel Outage Key Safety Function Review
10/23/2020
Tagout 03-03-
SDVWEST-001
D3R26: Unit 3 West SCRAM Discharge Volume Work
10/27/2020
Tagout 03-15-
CCSW+HX-001
D3R26: Division I CCSW Loop and 3A LPCI Heat
Exchanger
10/26/2020
Tagout 03-83-
D3R26: 250V Battery Modified Performance Test
11/02/2020
Operability
Evaluations
Unit Restart Review
Procedures
DFP 0800-07
Fuel Movements during Refueling Operations
DGP 01-S1
Startup Checklist
103
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
DGP 04-01
Fuel Moves and Refueling
DOP 0201-04
Reactor Pressure Vessel Water Inventory Control
DOP 1000-09
Bypassing Shutdown Cooling Isolation
DOP 1900-03
Reactor Cavity, Dryer/Separator Storage Pit and Fuel Pool
Level Control
DOS 1600-10
Drywell Closeout Inspection Plan
Fatigue Management and Work Hour Limits
OU-DR-104
Shutdown Safety Management Program
Corrective Action
Documents
4380835
D3R26 3-2301-7 Excessive Leakage
10/30/2020
Procedures
DIP 0260-01
Refuel Outage Reactor Vessel and Cavity Level
Instrumentation
DOS 6600-03
Bus Undervoltage and ECCS Integrated Functional Test
for Unit 3 Diesel Generator
DOS 7000-26
Local Leak Rate Testing of Unit 2(3) Feedwater System
Valves
DOS 7100-06
Seat Leakage Testing of Valve 3-2301-7
Work Orders
4596470
Unit 3 Refueling Cycle Bus 33-1 Undervoltage and ECCS
Integrated Functional Test
10/28/2020
4852650
Local Leak Rate Test for Valves 3-0220-57B and
3-0220-62B, Feedwater Outboard Check Valves
10/29/2020
4852651
Local Leak Rate Testing of Valves 3-0220-57B and
3-0220-58B, Feedwater Inboard Check Valves
10/29/2020
4855824
Unit 3 Refueling Reactor Vessel and Cavity Level
Instrumentation
11/05/2020
4881509
Unit 3 IST Seat Leak Test for HPCI Inlet to Feedwater
11/06/2020
Corrective Action
Documents
25295
Perform Impact Review of EAL Revisions from
EOP/SAMG, Rev. 4
03/10/2020
Miscellaneous
19-29
Exelon Nuclear Standardized Radiological Emergency
Plan
09/04/2020
19-65
Exelon Nuclear Standardized Radiological Emergency
Plan
09/06/2019
19-79
Various Station Emergency Preparedness Annexes
11/08/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
19-80
On-Shift Staffing Assessments
11/08/2019
20-05
EALs for Dresden Station; Dresden PAR Flowchart
2/07/2020
20-36
EALs for Dresden Station
06/09/2020
ALARA Plans
DR-03-20-00512
D2R26 Drywell Control Rod Drive Exchange / CRD
Support Activities
10/13/2020
DR-03-20-00513
D2R26 Drywell Control Rod Drive Exchange / CRD
Support Activities
10/13/2020
DR-03-20-00906
D3R26 Cavity Decon
10/13/2020
Corrective Action
Documents
014383624
D3R26 RP Lessons Learned
11/11/2020
Miscellaneous
Reactor Cavity Decontamination Plan
N/A
Radiation
Surveys
20-084355
Reactor Cavity - Post Decon Survey
11/04/2020
20-084374
Reactor Cavity - Post Decon Survey
11/04/2020
20-084435
Reactor Cavity - Initial Survey
11/04/2020
71151
Corrective Action
Documents
04367428
NRC Request Follow-Up on ED Alarm
09/04/2020
Miscellaneous
CY-AA-130-
3010-F-03
Dose Equivalent Iodine Determination - Unit 2
October
2019 -
September
20
CY-AA-130-
3010-F-03
Dose Equivalent Iodine Determination - Unit 3
October
2019 -
September
20
Monthly Data Elements for NRC Reactor Coolant System
(RCS) Specific Activity
October
2019 -
September
20
Monthly Data Elements for NRC ROP Indicator -
Occupational Exposure Control Effectiveness
June 2019 -
September
20
NRC RETS/ODCM Radiological Effluent Occurrences and
Supporting Information
April 2019 -
September
20
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Radiation
Surveys
2019-056188
2/3 Radwaste 507' Barrel Area
10/22/2019
Corrective Action
Documents
1138794
D3R21 LLRT 3-1501-19A Exceeded Admin Alarm Limit
11/11/2010
1441994
D3R22 LLRT on 3-1501-19A Exceeded Admin Limit
11/19/2012
2737436
LLRT Exceeds Warning Limit
11/05/2016
4372663
Temporary Loss of Required Fire Watch
09/28/2020
4378033
Security Response to Turnstile Alarm
10/20/2020
4381193
D3R26: Fuel Handling Error During Fuel Shuffle 2
10/31/2020
4381227
Level 1 Fuel Move Error
10/31/2020
4381800
Reseat of Fuel Support Casting Location 18-23 Required
11/02/2020
4383120
Valves Still Need Required Surveillance Testing
11/09/2020
4385280
D3R26 Lessons Learned - Near Miss of PMT Required
Prior to Mode 2
11/06/2020
4385543
D3R26 Lessons Learned: Hydro Preps Conflict with IM
Logic Testing
11/05/2020
4385550
D3R26 Lessons Learned: Near Miss with PMT - Partial
Procedure and New Conditions
11/06/2020
4387354
Ops Crew Clock Reset: Quarterly Valve Timing
11/22/2020
4390417
Entered DOA 4450-03 for Loss of Lift Station
2/15/2020
Corrective Action
Documents
Resulting from
Inspection
4379644
NRC Questioned PPE Requirements for Racking Breakers
10/26/2020
4379684
Issues Identified During NRC Walkdown
10/26/2020
4379958
NRC Concern
10/26/2020
Work Orders
1386628
Repair 3-1501-19A Valve
11/28/2012