IR 05000237/2020004

Integrated Inspection Report 05000237/2020004 and 05000249/2020004

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: DPR-19 and DPR-25 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 Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Dresden Nuclear Power Station, Units 2 and 3, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors.

Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.

List of Findings and Violations

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.

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

• Ultrasonic (UT) Examination, core bore hole drywell steel liner surface, 112.5.1.1A and 112.5.1.1B

• Visual VT-1 Examination, reactor pressure vessel (RPV) head vent piping flange bolting 3/1/0215-4/4A-1(A)-FLG

• Visual VT-1 Examination, RPV head vent piping flange bolting 3/1/0215-2/HV2-18-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,

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

(2) Multiple failures of the FLEX SAWA pumps during surveillance runs

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 71152 Refueling Outage 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 71152 Runs.

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 Type Designation Description or Title Revision or

Procedure Date

71111.04 Corrective Action 4380442 3-1001-4A Valve Stem Corrosion 10/27/2020

Documents

Corrective Action 4379748 D3R26 3-1999-325 Packing Leak 10/26/2020

Documents

Resulting from

Inspection

Engineering 632343 D3R26 Spent Fuel Pool Cooling Evaluation During 00

Evaluations Transition to ADHR

Procedures DOP 1000-M1/E1 Unit 3 Shutdown Cooling Checklist 14

DOP 1900-E1 Fuel Pool Cooling Electrical 01

DOP 1900-M1 Unit 3 Fuel Pool Cooling System Checklist 15

DOP 6500-30 Attachment E: Bus Crosstie Amps 16

DOS 1000-02 Alternate Decay Heat Removal Using Shutdown Cooling 21

and Fuel Pool Cooling Systems

71111.05 Corrective Action 4380385 Transient Combustibles Located Under Stairwell 10/28/2020

Documents

Engineering Various Transient Combustible Permits for D3R26, Unit 3 0

Evaluations Refueling Outage, Work Activities

Fire Plans 121 URB-23A Dresden Generating Station Pre-Fire Plan 2

FZ 8.2.2B Unit 3 CCSW Pumps, Elevation 495' 04

FZ 8.2.5D Unit 3 Low Pressure Heater Bay, Elevation 517' 03

FZ 8.2.6D Unit 3 Low Pressure Heater Bays, Elevation 538' 03

Miscellaneous Hot Work Permits for Welding in Unit 3 Low Pressure and

High-Pressure Heater Bays during D3R26

Procedures OP-AA-201-007 Fire Protection System Impairment Control 00

71111.06 Miscellaneous DR-PSA-012 Internal Flood Evaluation Summary and Notebook 04

71111.07A Corrective Action 4380814 3A LPCI Tubes Stuck Cleaning Scrapers 10/30/2020

Documents 4381431 3-1599-112, CCSW Heat Exchanger Sample Line Flush 11/01/2020

Valve, Failed Inspection

4381473 D3R26 3A LPCI Heat Exchanger Coating Repairs 11/01/2020

4383193 3A LPCI Heat Exchanger D3R26 Coatings Repairs 10/31/2020

Lessons Learned

Inspection Type Designation Description or Title Revision or

Procedure Date

NDE Reports 2020-10 Eddy Current Examination Final Report for Exelon Nuclear 11/02/2020

Dresden, Unit 3, 3A LPCI Heat Exchanger

(3-1503-A)

Work Orders 4590891 D3R26 Clean/Inspect/Eddy Current 'A' LPCI Heat 11/02/2020

Exchanger

71111.08G Calculations 1801382.301 Dresden Iso Condenser Flaw Evaluation 0

Corrective Action 00949941 Corrosion on Unit 3 Torus Baseplate Anchor 08/03/2009

Documents 04013601 Degraded Unit 3 CCSW Piping Identified 05/22/2017

04379976 D3R26 Drywell Basement Moisture Barrier Relevant 10/27/2020

Conditions

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 IWE Component Detail, Drywell Floor Core Hole Locations A

2B and Details

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 EC 626262 ASME Code Case N-586-1 Evaluation for Unit 3 Isolation 0

Evaluations Condenser 3/2/1302A-12/12-8 Nozzle to Shell Weld

NDE Reports20-375 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 11/02/2020

Floor Liner in 22 Core Hole Locations

D3R26-VT-001 VT-1 for 3/1/0215-2/HV2-18-FLG 10/31/2020

D3R26-VT-002 3/1/0215-4/4A-1(A)-FLG 10/31/2020

Procedures ER-AA-335-004 Ultrasonic (UT) Measurement of Material Thickness and 9

Interfering Conditions

ER-AA-335-014 VT-1 Visual Examination 10

ER-AA-335-016 VT-3 Visual Examination of Component Supports, 12

Attachments and Interiors of Reactor Vessels

Inspection Type Designation Description or Title Revision or

Procedure Date

ER-AA-335-018 Visual Examination of ASME IWE Class MC and MET 14

ALLIC Liners of Class CC Components

GEH-VT-203 Procedure for In-Vessel Visual Inspection (IVVI) of BWR 3 25

RPV Internals

Work Orders 04678175-01 CM Replace CCSW Pump 3-1501-44-D, Degraded 11/02/2018

Discharge Elbow

04615093-11 Through Wall Pipe Leak on CCSW Line 3-1514-16 03/23/2017

71111.12 Corrective Action 4382882 D3R26 - Steam Leak from HPCI Rupture Disc 11/07/2020

Documents 4377284 3C Circulating Water Pump Bearing High Temperature 10/17/2020

Engineering 632912 HPCI Steam Rupture Disc - Allow Use of 140 psig Rated 00

Changes Set

Engineering 448508 Evaluate Torque Value for HPCI Rupture Discs with Fully 00

Evaluations Lubricated Flange Bolts

448508 Evaluate Torque for HPCI Rupture Disc Based on 00

Lubricated Stud Bolts

Procedures DMP 2300-14 HPCI Rupture Disc Maintenance 08 and 09

Work Orders 1925035 IST Replace Both Unit 3 HPCI Turbine Steam Exhaust 11/03/2020

Rupture Discs

71111.13 Corrective Action 4379974 NRC Questions During D3R26 10/27/2020

Documents 4380495 NRC Concern on Protected Pathway 10/29/2020

Resulting from 4382296 Protected Pathway Concerns 11/04/2020

Inspection 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, 10/13/2020

Compensatory Action Plans and Related Work Evaluation

D3R26 Protected Equipment Summary 10/23/2020

Protected Equipment Schemes for Various Plant

Configurations Reviewed this Quarter

Procedures DOP 6400-13 Electrical Yard Switching 55

DOP 6400-14 Transformer 86 Load Tap Changer Operation 17

DOP 6500-08 Bus 24-1 to Bus 34-1 Tie Breaker Operation 25

DOP 6500-30 Bus 23-1 to Bus 33-1 Tie Breaker Operation 16

Inspection Type Designation Description or Title Revision or

Procedure Date

DOS 1100-04 Standby Liquid Control System Quarterly/Comprehensive 53

Pump Test for the Inservice Testing (IST) Program

DOS 5750-04 Control Room Train B HVAC and Air Filtration Unit 55

Surveillance

OP-AA-108-117 Protected Equipment Program 05

71111.15 Corrective Action 4379382 LLRT Results Above Alarm Limit for Penetration X-138 10/25/2020

Documents 4379385 LLRT Results Above Warning Limit for Penetration 10/25/2020

X-149B

4379698 LLRT Results Above Warning Limit for AOV 3-2001-6 10/26/2020

4379747 Cardox Tank Low 0

4379969 3-1501-26A Leakage During LPCI Single Loop Test 10/27/2020

4380023 High Resistance Contacts - Control Switches for HPCI 10/27/2020

Valves

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 0

4382613 3-1501-25B Failed to Indicate Full Open during Testing 11/05/2020

4389199 2A Reactor Feedwater Pump Indicating Light Out 12/09/2020

Drawings 12E-2349 Schematic Diagram: 480V Bus 29 Main Feed and Bus AH

28-29 Crosstie Breakers

Engineering 632250 Blocked Drywell Spray Nozzle Evaluation for AST Dose 0

Changes Analyses

Procedures DOS 0040-07 Verification of Remote Position Indication for Valves 48

Included in Inservice Testing (IST) Program

Work Orders 4855292 Primary Containment Type B&C Leakage Rate Test 11/11/2020

Summation

71111.18 Engineering 625677 ASD Obsolescence and Cooling Upgrades 0

Changes 628647 ASD NXG Circuit Card on ASD Digital Card Rack 0

Procedures DOS 0202-25 ASD Testing in Open Loop Test Mode 1

71111.19 Corrective Action 4379710 Failed Recirculation Sample Valve, 3-0220-44; Did Not 10/26/2020

Documents Open with Control Switch

4380424 Rupture Disc Failure During Install 10/29/2020

Inspection Type Designation Description or Title Revision or

Procedure Date

4381583 D3R26 Results of U3 LPCI Containment Spray Testing 0

4382189 Unit 3 HPCI MGU/MSC PMTs 11/04/2020

4382306 D3R26 Flowscan Testing of the 3-0220-44 Recirculation 11/04/2020

Sample Valve

4382356 AOV 3-0220-44 Showing Dual Indication on Position 11/05/2020

4382501 D3R26 System Leakage Test: 84 dpm Leak from 11/05/2020

HCU 14-11

4382541 D3R26 RCPB Class 1 System Leakage Test Results 11/05/2020

4382602 AO 3-0220-45 Valve will Not Open from Main Control 11/05/2020

Room during PMT

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 11/06/2020

(As-Left)

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 395859 Evaluation of Leakage at Mechanical Connections for 01

Evaluations Class 1 and 2 System Leakage Test

448626 IRM 13 Fuses Replaced with 2 Amp due to 1 Amp Fuses 00

Blowing when Attempting to Withdraw IRM During Startup

2929 Evaluation of Leakage at Mechanical Connection for LPCI 00

Valve 3-1501-26A

Procedures DIS 1500-20 Division 1 and II Low Pressure Coolant Injection Pumps 23

Suction and Injection Valves Circuitry Logic System

Functional Test

DOS 0040-07 Verification of Remote Position Indication for Valves 48

Included in Inservice Testing Program

DOS 0201-02 Unit 3 RPV ASME B and PV Code 1000 PSI System 63

Leakage Test

DOS 0300-08 CRD Exercising with Mode Switch in Refuel 25

DOS 0300-15 Control Rod Drive SCRAM Timing Test during Hydro 23

DOS 2300-03 High-Pressure Coolant Injection System Operability and 117

Quarterly IST Verification Test

DTS 1500-03 LPCI Containment Spray Test 06

Inspection Type Designation Description or Title Revision or

Procedure Date

Work Orders 01784322 D3 4Y TS LPCI Containment Spray Test of D/W Spray 0

Nozzle

1610562 Replace Regulator and Diaphragm and Repack 11/06/2020

3-0220-44 Valve

4570360 D3 24M TS Division 1 and 2 LPCI Suction and Injection 0

Valves LSFT

4852964 Replace ASCO Solenoid for Valve 3-0220-44 11/06/2020

4872264 Unit 3 Refuel Outage ISI 1000 PSI Reactor Vessel 11/05/2020

Leakage Test (Hydrostatic Test)

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, 11/06/2020

Troubleshoot and Repair

71111.20 Corrective Action 4382043 D3R26: FME ECCS Suction Strainer Inspection Results 11/03/2020

Documents 4382206 Deviation to Implementation of the Work Hour Rule 0

4382403 Deviation to Implementation of the Work Hour Rule 0

4382946 2203-5 Instrument Rack Leak 11/07/2020

4382985 3C Reactor Feedwater Pump Auxiliary Oil Pump Did Not 11/08/2020

Automatically Shut Off

4382993 3A Reactor Feedwater Pump Discharge Valve Binding 11/08/2020

4382994 MFDLRX Mismatch during D3R26 Power Ascension 11/07/2020

Engineering 632956 MR-90 Jumpers to Support D3R26 Hydro Test Prior to 0

Changes Startup

Miscellaneous D3R26 Refuel Outage Key Safety Function Review 10/23/2020

Tagout 03-03- D3R26: Unit 3 West SCRAM Discharge Volume Work 10/27/2020

SDVWEST-001

Tagout 03-15- D3R26: Division I CCSW Loop and 3A LPCI Heat 10/26/2020

CCSW+HX-001 Exchanger

Tagout 03-83- D3R26: 250V Battery Modified Performance Test 11/02/2020

250VDC-001

Operability OP-AA-108-108 Unit Restart Review 20

Evaluations

Procedures DFP 0800-07 Fuel Movements during Refueling Operations 41

DGP 01-S1 Startup Checklist 103

Inspection Type Designation Description or Title Revision or

Procedure Date

DGP 04-01 Fuel Moves and Refueling 40

DOP 0201-04 Reactor Pressure Vessel Water Inventory Control 15

DOP 1000-09 Bypassing Shutdown Cooling Isolation 04

DOP 1900-03 Reactor Cavity, Dryer/Separator Storage Pit and Fuel Pool 58

Level Control

DOS 1600-10 Drywell Closeout Inspection Plan 52

LS-AA-119 Fatigue Management and Work Hour Limits 14

OU-DR-104 Shutdown Safety Management Program 23

71111.22 Corrective Action 4380835 D3R26 3-2301-7 Excessive Leakage 10/30/2020

Documents

Procedures DIP 0260-01 Refuel Outage Reactor Vessel and Cavity Level 21

Instrumentation

DOS 6600-03 Bus Undervoltage and ECCS Integrated Functional Test 47

for Unit 3 Diesel Generator

DOS 7000-26 Local Leak Rate Testing of Unit 2(3) Feedwater System 11

Valves

DOS 7100-06 Seat Leakage Testing of Valve 3-2301-7 09

Work Orders 4596470 Unit 3 Refueling Cycle Bus 33-1 Undervoltage and ECCS 10/28/2020

Integrated Functional Test

4852650 Local Leak Rate Test for Valves 3-0220-57B and 10/29/2020

3-0220-62B, Feedwater Outboard Check Valves

4852651 Local Leak Rate Testing of Valves 3-0220-57B and 10/29/2020

3-0220-58B, Feedwater Inboard Check Valves

4855824 Unit 3 Refueling Reactor Vessel and Cavity Level 11/05/2020

Instrumentation

4881509 Unit 3 IST Seat Leak Test for HPCI Inlet to Feedwater 11/06/2020

Check Valve

71114.04 Corrective Action 4325295 Perform Impact Review of EAL Revisions from 03/10/2020

Documents EOP/SAMG, Rev. 4

Miscellaneous 19-29 Exelon Nuclear Standardized Radiological Emergency 09/04/2020

Plan

19-65 Exelon Nuclear Standardized Radiological Emergency 09/06/2019

Plan

19-79 Various Station Emergency Preparedness Annexes 11/08/2019

Inspection Type Designation Description or Title Revision or

Procedure Date

19-80 On-Shift Staffing Assessments 11/08/2019

20-05 EALs for Dresden Station; Dresden PAR Flowchart 02/07/2020

20-36 EALs for Dresden Station 06/09/2020

71124.01 ALARA Plans DR-03-20-00512 D2R26 Drywell Control Rod Drive Exchange / CRD 10/13/2020

Support Activities

DR-03-20-00513 D2R26 Drywell Control Rod Drive Exchange / CRD 10/13/2020

Support Activities

DR-03-20-00906 D3R26 Cavity Decon 10/13/2020

Corrective Action 014383624 D3R26 RP Lessons Learned 11/11/2020

Documents

Miscellaneous Reactor Cavity Decontamination Plan N/A

Radiation 2020-084355 Reactor Cavity - Post Decon Survey 11/04/2020

Surveys 2020-084374 Reactor Cavity - Post Decon Survey 11/04/2020

20-084435 Reactor Cavity - Initial Survey 11/04/2020

71151 Corrective Action 04367428 NRC Request Follow-Up on ED Alarm 09/04/2020

Documents

Miscellaneous CY-AA-130- Dose Equivalent Iodine Determination - Unit 2 October

3010-F-03 2019 -

September

20

CY-AA-130- Dose Equivalent Iodine Determination - Unit 3 October

3010-F-03 2019 -

September

20

LS-AA-2090 Monthly Data Elements for NRC Reactor Coolant System October

(RCS) Specific Activity 2019 -

September

20

LS-AA-2140 Monthly Data Elements for NRC ROP Indicator - June 2019 -

Occupational Exposure Control Effectiveness September

20

LS-AA-2150 NRC RETS/ODCM Radiological Effluent Occurrences and April 2019 -

Supporting Information September

20

Inspection Type Designation Description or Title Revision or

Procedure Date

Radiation 2019-056188 2/3 Radwaste 507' Barrel Area 10/22/2019

Surveys

71152 Corrective Action 1138794 D3R21 LLRT 3-1501-19A Exceeded Admin Alarm Limit 11/11/2010

Documents 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 2 Valves Still Need Required Surveillance Testing 11/09/2020

4385280 D3R26 Lessons Learned - Near Miss of PMT Required 11/06/2020

Prior to Mode 2

4385543 D3R26 Lessons Learned: Hydro Preps Conflict with IM 11/05/2020

Logic Testing

4385550 D3R26 Lessons Learned: Near Miss with PMT - Partial 11/06/2020

Procedure and New Conditions

4387354 Ops Crew Clock Reset: Quarterly Valve Timing 11/22/2020

4390417 Entered DOA 4450-03 for Loss of Lift Station 12/15/2020

Corrective Action 4379644 NRC Questioned PPE Requirements for Racking Breakers 10/26/2020

Documents 4379684 Issues Identified During NRC Walkdown 10/26/2020

Resulting from 4379958 NRC Concern 10/26/2020

Inspection

Work Orders 1386628 Repair 3-1501-19A Valve 11/28/2012

21