IR 05000237/2022003

Integrated Inspection Report 05000237/2022003 and 05000249/2022003

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

October 31, 2022

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. 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, Signed by Ruiz, Robert on 10/31/22 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: DPR-19 and DPR-25 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 Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Dresden Nuclear Power Station,

Units 2 and 3, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.

List of Findings and Violations

Failure to Select Appropriate Packing for the Unit 3 1B Main Steam Isolation Valve Cornerstone Significance Cross-Cutting Report Aspect Section Initiating Events Green [H.9] - Training 71152A NCV 05000237,05000249/2022003-01 Open/Closed 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.

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

(2) Unit 3 HCU 34-43 buzzing solenoid on scram solenoid pilot valve

(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 Report Aspect Section Initiating Events Green [H.9] - Training 71152A NCV 05000237,05000249/2022003-01 Open/Closed 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 Type Designation Description or Title Revision or

Procedure Date

71111.01 Procedures DOA 0010-02 Tornado Warnings/ High Winds 26

DOA 0010-04 Floods 59

MA-DR-MM-6- Maintenance Activities for Site Flooding 06

00101

71111.04 Corrective Action 4517430 NRC Identified 3A SBO Engine Jacket Water Electric 08/17/2022

Documents Immersion Heater

Resulting from

Inspection

Procedures DOP 1300-M1/E1 Unit 3 Isolation Condenser System Checklist 26

DOP 1500-M1 Unit 2 Low Pressure Coolant Injection System and 50

Containment Cooling Service Water System Checklist

DOP 1500-M1 Unit 3 Low Pressure Coolant Injection System and 39

Containment Cooling Service Water System Checklist

DOP 3700-M2/E2 Unit 3 Reactor Building Closed Cooling Water System 20

Checklist

DOP 3700-M2/E2 Unit 2 Reactor Building Closed Cooling Water System 18

Checklist

DOP 3800-M1 Unit 3 Turbine Building Closed Cooling Water System 14

Checklist

DOP 3800-M1 Unit 2 Turbine Building Closed Cooling Water System 16

Checklist

DOP 3900-M1 Unit 2/3 Service Water and Screen Wash System 63

Mechanical Checklist

DOP 4700-M1 3A Instrument Air Compressor (3-4706) Checklist 09

DOP 4700-M2 3B Instrument Air Compressor (3-4715-B) Checklist 04

DOP 6600-M1 Unit 2 Standby Diesel Generator Checklist 30

DOP 6600-M1 Unit 3 Standby Diesel Generator Checklist 29

DOP 6600-M2 Unit 2/3 Standby Diesel Generator Mechanical Checklist 29

DOP 6620-E2 Unit 3 Station Blackout Electrical Checklist 03

DOP 6620-M2 Unit 3 Station Blackout Mechanical Checklist 05

71111.05 Corrective Action 4528225 4.0 Critique Crew 3 Q3 Unannounced Fire Drill 09/23/2022

Documents

Inspection Type Designation Description or Title Revision or

Procedure Date

Corrective Action 4516052 2/3 Cable Tunnel Drain 08/10/2022

Documents

Resulting from

Inspection

Fire Plans 145 U2TB-48 Fire Zone 8.2.6A Unit 2 RFP Vent H2 Seal Area Elev. 538' 06

175 U2/3TB-92 Fire Zone 8.2.5.C, Unit 2/3 EHC Reservoir Area, elev. 517' 04

2 U2 Cable Fire Zone 8.2.4 Unit 2 Cable Tunnel East Elev. 502' 05

Tunnel

183 Cable Tunnel Fire Zone 8.2.4 Unit 3 Cable Tunnel West Elev. 502' 05

196 Circ PPs-124 Fire Zone 11.3 Unit 2/3 Circulating Water Pumps Elev. 490' 02

197 SW PPs-125 Fire Zone 11.3 Unit 2/3 Service Water Pumps / Traveling 03

Screens Elev. 509'

198 U2/3 CH-126 Fire Zone 11.3 Unit 2/3 Crib House Ground Floor Elev. 517' 03

Procedures CC-AA-501-1027 Hot Work Precautions and Safety Practices 02

OP-AA-201-004 Fire Prevention for Hot Work 19

71111.11Q Corrective Action 4510764 2-3201-B 2B Reactor Feedwater Pump Discharge Valve 07/13/2022

Documents Breaker Trips after Open Signal

4510802 2B Reactor Feedwater Pump Abnormal Seal Indications on 07/13/2022

Initial Start

4510825 Unit 2 Mechanical Vacuum Pump Tripped on Overload 07/13/2022

4514373 Critique for Hot Fast Restart 07/28/2022

Procedures DGP 01-01 Unit Startup 203

71111.12 Corrective Action 4486119 3B EHC Pump Trip upon Start Attempt 03/20/2022

Documents 4490467 Unit 2 EHC Fluid Consumption Greater than Historical Norm 04/05/2022

4494315 Engineering to Perform Self-Assessment on Digital 04/20/2022

Electrohydraulic Control System

4498686 Unit 2 Control Valve 3 Electrohydraulic Control Accumulator 05/09/2022

Leak

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

4516285 Work Request Needed for Extent of Condition NDE on Unit 2 08/11/2022

Control Valve 4

Inspection Type Designation Description or Title Revision or

Procedure Date

Miscellaneous Main Turbine Health Group Report 08/15/2022

Fire Protection System Health Report 08/23/2022

71111.13 Corrective Action 4513847 3A Stator Water Cooling Heat Exchange Differential 07/30/2022

Documents Pressure High

4513885 2/3 Main Control Room HVAC Train 'A', 'B' Air Compressor 07/30/2022

Tripped

4514429 'A' and 'B' Main Control Room HVAC Heat Exchangers 07/31/2022

Procedures OP-AA-108-117 Protected Equipment List 09/15/2022

WC-DR-104-1001 Dresden 345 kV Switchyard Configuration Risk Assessment 08

Work Orders 5280509 2/3 Main Control Room HVAC 'A', 'B' Air Compressor 08/02/2022

Tripped

71111.15 Corrective Action 4505049 Control Switch Contacts Need to be Burnished 06/11/2022

Documents 4509034 Unexpected Alarm 903-5 H-6, SBLC Squib Valve Circuit 07/02/2022

Failure

4511662 Unit 3 HCU 34-43 (J-11) Buzzing Solenoid on SSPV 07/19/2022

20324 Air Void Identified on U2 HPCI Discharge Piping Above 09/01/2022

Torus

Drawings M-33 Diagram of Standby Liquid Control Piping IA

Procedures DAN 902(3)-5 H- SBLC Squib Valve Circuit Failure 07

71111.18 Corrective Action 4468573 HPCI Signal Converter Mod Temperature Qual Concerns 12/28/2021

Documents 4479219 HPCI Signal Converter- Commercial Grade Dedication Issue 02/18/2022

Engineering 395525 Replace U2 HPCI Signal Converter and Flow Indicating 07

Changes Controller

397957 Replace U3 HPCI Signal Converter and Flow Indicating 06

Controller

455347 Bay 13 Level Recorder Temporary Modification 08/24/2022

71111.19 Corrective Action 4512613 2-1501-18B, Unit 2 'B' Torus Spray Valve, Breaker Tripped 07/24/2022

Documents 4513269 AOV 3-1601-24 Valve Stem Sheared While Performing DIS 07/27/2022

1600-24

4513807 Air Leak from Fitting for AOV 3-1601-24 07/29/2022

4513810 AOV 3-1601-62 Failed to Open 07/29/2022

4514560 Inspect / Replace the U3 D/G Starting Air Lubricator 08/02/2022

Inspection Type Designation Description or Title Revision or

Procedure Date

Procedures DOS 1500-01 LPCI System Valve Operability 45

DOS 1500-02 Containment Cooling Service Water Pump Test and 97

Inservice Test (IST)

DOS 6600-01 Diesel Generator Surveillance Tests 146

Work Orders 5278802 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

281939-02 OPs PMT The U3 D/G Starting Air Lubricator 09/20/2022

71111.22 Corrective Action 4512696 Unit 3 SRM 21 24V DC Input Fuse Failed during DIS 0700- 07/25/2022

Documents 10

4516786 Issues with SAWA/Flex Pump 2, 2/3-1501-161 08/14/2022

Procedures DOS 0500-01 Manual Scram Circuit Sensor Test 23

DOS 0500-25 RPS Channels A1, A2, B1, and B2 Automatic Scram 18

Contactor Test

DOS 1400-05 Core Spray System Pump Operability and Quarterly IST 56

Test with Torus Available

DOS 6620-01 Station Blackout 2 Diesel Generator Endurance and 26

Margin/Full Load Test/Full Load Reject Test

Work Orders 4958656 'B' Isolation Condenser Make-up Pump Capacity Test 08/19/2022

5111034 D2/3 1Y UHS SAWA/FLEX Pump (Pump 2) Assembly 09/23/2022

Performance Test

253824 Unit 3 Quarterly SRM Channel Calibration 07/29/2022

71114.06 Corrective Action 4525264 Dresden Off-Year Exercise: EOF Objective Failures and 09/28/2022

Documents Others

25291 Dresden Off-Year DEP Failure- SCR 09/28/2022

27609 EP Off-Year Exercise TSC Determination Criteria Failures 10/07/2022

and Satisfactory Criteria with Comments

27612 EP Off-Year Exercise Simulator Control Room Determination 10/07/2022

Criteria Failures and Satisfactory Criteria with Comments

27624 EP Off-Year Exercise OSC Determination Criteria Failures 10/07/2022

and Satisfactory Criteria with Comments

71151 Miscellaneous MSPI Residual Heat Removal Systems Prepared Data 07/01/2021

Package to

06/03/2022

Inspection Type Designation Description or Title Revision or

Procedure Date

MSPI Cooling Water Support Systems Prepared Data 07/01/2021

Package to

06/30/2022

MSPI Heat Removal System Prepared Data Package 07/01/2021

to

06/30/2022

71152A Corrective Action 4189081 3-0203-1B Degraded Condition Identified for D3R25 Scope 10/29/2018

Documents Addition

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- 04/10/2022

2A

4492010 Extent of Condition Torque Check Outboard MSIV 3-0203- 04/10/2022

2B

4492011 Extent of Condition Torque Check Outboard MSIV 3-0203- 04/10/2022

2C

4492013 Extent of Condition Torque Check Outboard MSIV 3-0203- 04/10/2022

2D

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

4501441 Repack 3-0203-1B in D3R27 05/23/2022

Procedures DMP 0040-40 Valve Packing Installation Procedure 15

71153 Corrective Action 4410220 Evaluation of Mitigation Strategies for Intake Bay Fouling 03/19/2021

Documents 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 07/13/2022

Thermals

4511331 Unit 2 Recirculation Pump Seal Pressure Trend Before and 07/16/2022

After Scram

Inspection Type Designation Description or Title Revision or

Procedure Date

4513955 Cribhouse Grassing Saturday 07/30/2022

4514253 Dresden EAL No Call - River Level EP Concurrence 08/01/2022

Corrective Action 4517080 NRC Follow-up Question / EP Review EAL HU6 Basis 08/16/2022

Documents

Resulting from

Inspection

Drawings M-14 Diagram of Reactor Feed Piping MC

M-14 Diagram of Reactor Feed Piping MC

Procedures DOA 0010-01 Dresden Lock and Dam Failure 38

DOA 0010-04 Floods 59

DOA 4400-06 2/3 Crib House Screen Plugging 08

EP-AA-1004 Emergency Action Levels for Dresden Station 13

Addendum 3

Work Orders 5260292 Perform OP-AA-108-114 Post-Transient Review for 2A 07/13/2022

Feedwater Regulating Valve Failure

15