IR 05000237/2022004

Integrated Inspection Report 05000237/2022004, 05000249/2022004 and 07200037/2022002

ML23041A043
Person / Time
Site:	Dresden
Issue date:	02/10/2023
From:	Robert Ruiz NRC/RGN-III/DORS/RPB1
To:	Rhoades D Constellation Energy Generation
References
IR 2022004, IR 2022002
Download: ML23041A043 (1)

Text

SUBJECT:

DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3-INTEGRATED INSPECTION REPORT 05000237/2022004, 05000249/2022004 AND 07200037/2022002

Dear David Rhoades:

On December 31, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Dresden Nuclear Power Station, Units 2 and 3. On January 12, 2023, the NRC inspectors discussed the results of this inspection with P. Boyle, Site Vice President, and other members of your staff. The results of this inspection are documented in the enclosed report.

No findings or violations of more than minor significance were identified during this inspection.

February 10, 2023 This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely, Robert Ruiz, Chief Reactor Projects Branch 1 Division of Operating Reactor Safety Docket Nos. 05000237, 05000249 and 07200037 License Nos. DPR19 and DPR25

Enclosure:

As stated

Inspection Report

Docket Numbers:

05000237, 05000249, and 07200037

License Numbers:

DPR-19 and DPR-25

Report Numbers:

05000237/2022004, 05000249/2022004, and 07200037/2022002

Enterprise Identifier:

I2022004-0048 and I-2022-002-0700

Licensee:

Constellation Energy Generation, LLC

Facility:

Dresden Nuclear Power Station, Units 2 and 3

Location:

Morris, IL

Inspection Dates:

October 01, 2022 to December 31, 2022

Inspectors:

Z. Coffman, Resident Inspector

A. Demeter, Project Engineer

G. Edwards, Health Physicist

G. Hansen, Senior Emergency Preparedness Inspector

C. Hunt, Senior Resident Inspector

A. Nguyen, Senior Resident Inspector

J. Park, Reactor Inspector

M. Porfirio, Illinois Emergency Management Agency

P. Smagacz, Resident Inspector

C. St. Peters, Resident Inspector

J. Steffes, Senior Resident Inspector

Approved By:

Robert Ruiz, Chief

Reactor Projects Branch 1

Division of Operating Reactor Safety

SUMMARY

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

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

List of Findings and Violations

No findings or violations of more than minor significance were identified.

Additional Tracking Items

Type Issue Number Title Report Section Status LER 05000237/2022001-00 LER 2022001-00 for Dresden Nuclear Power Station, Unit 2, Reactor Scram due to Turbine Trip on High Reactor Water Level Caused by Feedwater Regulating Valve Failure 71153 Closed LER 05000237/2022001-01 LER 2022001-01 for Dresden Nuclear Power Station, Unit 2, Reactor Scram due to Turbine Trip on High Reactor Water Level Caused by Feedwater Regulating Valve Failure 71153 Closed

PLANT STATUS

Unit 2 began the inspection period at rated thermal power. On December 10, 2022, reactor power was lowered to 58 percent to perform routine control rod drive scram time testing, control rod sequence exchange, main turbine surveillances and feedwater regulating valve maintenance. The unit was returned to full power on December 11, 2022, and 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 D3R27. On October 31, 2022, the unit was shut down to commence D3R27. The unit was synchronized to the grid on November 18, 2022, and ascended to full power shortly thereafter. On November 29, 2022, reactor power was lowered to 65 percent to perform maintenance on the 3B condensate/condensate booster pump seal leak. Reactor power was further lowered to 50 percent to monitor the 3A, 3C and 3D condensate/condensate booster pumps and rod pattern adjustment. Following repair to the 3B condensate/condensate booster pump the unit was returned to full power on December 2, 2022, and remained at or near full power for the remained of the inspection period.

INSPECTION SCOPES

Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors performed activities described in IMC 2515, apendix D, Plant Status, observed risk significant activities, and completed onsite portions of IPs. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.

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 on November 1, 2022 (2)4 kilovolt electrical crossties during D3R27 on November 7-10, 2022

(3) Unit 3 spent fuel pool cooling system and alternate decay heat removal alignment during D3R27 on November 7-9, 2022

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (IP Section 03.01) (3 Samples)

The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:

(1) Fire Zone (FZ) 1.1.1.1, Unit 3 torus basement elevation 476' and torus catwalk, November 3, 2022

(2) FZ 6.2, Unit 2/3 computer room and auxiliary electrical room elevation 517' on November 4, 2022

(3) FZ 8.2.5E, Unit 3 high pressure heaters, elevation 517', FZ 8.2.5 D, Unit 3 low pressure heater bay, elevation 517', and FZ 8.2.6 D, Unit 3 low pressure heater bays, elevation 538' on November 2-4, 2022

71111.07A - Heat Exchanger/Sink Performance

Annual Review (IP Section 03.01) (1 Sample)

The inspectors evaluated readiness and performance of:

(1) Unit 3 'B' low pressure coolant injection (LPCI)/containment cooling service water (CCSW) 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 are appropriately monitored for degradation and that repairs and replacements were appropriately fabricated, examined and accepted by reviewing the following activities from October 31, 2022-November 18, 2022:

03.01.a - Nondestructive Examination and Welding Activities.

1. Ultrasonic testing (UT) of component IDs 3/2/1302A12/127 and -8, Cat. RA,

item R1.16

4. Magnetic particle exam of component 3/2/150120/2012, Cat. CB,

item C2.31

5. NDE report 7480332222-EB3RPVID for component ID 3/1/RPV

SHELL/3SC4B-VERT with relevant indication accepted for continued service

6. Weld repair of 3B LPCI heat exchanger support component under

work order (WO) 488633602, weld No. 1, 1A, 11, and 11A

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 3 shutdown and startup for D3R27 on October 31 and November 17, 2022.

Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)

(1) The inspectors observed and evaluated licensed crew performance in the simulator on October 18, 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) Compressed air due to repeated failures of the Unit 2 and Unit 3 instrument air compressors

(2) High pressure injection system

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) Safety related service water

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) Unit 3 refueling outage, D3R27, yellow work windows for lowered inventory conditions on November 1 and November 12, 2022

(2) Unit 3 refueling outage, D3R27, planned and emergent elevated risk activities on October 31-November 18, 2022

(3) Unit 3 condensate booster pump 3B emergent work due to seal degradation on November 28-December 2, 2022

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (8 Samples)

The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:

(1) Unit 3 high pressure coolant injection leak detection temperature switch 32372-A found broken on November 2, 2022

(2) Unit 3 high pressure coolant injection steam chest and turbine control valve NDE indications identified on November 4, 2022

(3) Unit 3 incorrect fuse found in Bus 39 UV circuitry, on November 4, 2022

(4) Unit 3 125 V DC grounds

(5) Bypassing Unit 3 mechanical vacuum pump trips (6)

===30220-44, recirculation loop sample line isolation air-operated valve, failed its local leak rate test on November 13, 2022

(7) Unit 3 hotwell basement flood seal missing bolts on November 7, 2022

(8) Unit 3 low pressure coolant injection loop I coolant injection inboard isolation MOV, 31501-22A, thrust unacceptable for asleft maximum, on November 15, 2022

71111.18 - Plant Modifications

Severe Accident Management Guidelines (SAMG) Update (IP Section 03.03)===

(1) The inspectors verified the site SAMG were updated in accordance with the BWR generic sever accident technical guidelines and validated in accordance with NEI 14-01, Emergency Response Procedures and Guidelines for Beyond Design Basis Events and Severe Accidents, Revision 1.

71111.19 - Post-Maintenance Testing

Post-Maintenance Test Sample (IP Section 03.01) (6 Samples)

The inspectors evaluated the following post-maintenance testing activities to verify system operability and/or functionality:

(1) Unit 3 1000 psi system leakage test/hydrostatic test per WO 5126822

(2) DOS 700027, local leak rate testing of Unit 2

(3) reactor vessel water level instrumentation system valves, following work on valve 30299-98A, on November 15, 2022

(3) DOS 030015, control rod scram time testing, November 13, 2022

(4) Non-destructive examination and pressure test of 31501-26A, low pressure coolant loop injection valve, after repairs during D3R27 per WO 1183382

(5) DOS 150012, CCWS loop flow verification, per WO 5022790 and WO 4830134

(6) DES 830020, Unit 3 250-volt station battery modified performance test, per WO 5260976

71111.20 - Refueling and Other Outage Activities

Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated Unit 3 refueling outage, D3R27, activities from October 31 to November 18, 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) (3 Samples)

(1) DOS 660004, bus undervoltage and emergency core cooling system integrated functional test for Unit 3 diesel generator, on November 6, 2022

(2) DTS 160007, Unit 2(3) primary containment integrated leak rate test on November 15, 2022

(3) DIS 050020, reactor mode switch (start, hot standby, shutdown, and refuel, positions) logic system functional test, on November 16, 2022

Inservice Testing (IP Section 03.01) (1 Sample)

(1) DOS 710003 seat leakage testing of valves 2 (3)-029997A(B), 2 (3)-029998A(B), 2 (3)-029999A(B) and 2 (3)-0299100A(B), on November 3, 2022

Containment Isolation Valve Testing (IP Section 03.01) (1 Sample)

(1) DOS 700001, local leak rate test of main steam isolation valves (dry tests), and DOS

===700002, local leak rate test of main steam isolation valves (wet test), on October 31-November 1, 2022

71114.04 - Emergency Action Level and Emergency Plan Changes

Inspection Review (IP Section 02.0102.03)===

(1) The inspectors evaluated the following submitted Emergency Action Level and Emergency Plan changes:

Evaluation No. 2158, Emergency Action Levels for Dresden Station, November 20, 2021 This evaluation does not constitute NRC approval.

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 hazard.

Instructions to Workers (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated how the licensee instructs workers on plant-related radiological hazards and the radiation protection requirements intended to protect workers from those hazard.

Contamination and Radioactive Material Control (IP Section 03.03) (2 Samples)

The inspectors observed/evaluated the following licensee processes for monitoring and controlling contamination and radioactive material:

(1) Workers exiting the RCA at the Unit 3 drywell equipment hatch during a refueling outage

(2) Workers exiting the RCA from the refuel floor during a refueling outage

Radiological Hazards Control and Work Coverage (IP Section 03.04) (4 Samples)

The inspectors evaluated the licensee's control of radiological hazards for the following radiological work:

(1) Unit 3 turbine building moisture separator activities (inspection, repair, maintenance as applicable)

(2) Unit 3 main steam line crossover piping inspections

(3) Main condenser repair activities

(4) Unit 3 turbine building feedwater systems maintenance High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (3 Samples)

The inspectors evaluated licensee controls of the following high radiation areas and very high radiation areas:

(1) Unit 3 drywell main steam isolation valves areas

(2) Unit 3 reactor building equipment drain tank room

(3) Unit 3 reactor vessel head platform 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.

71124.03 - InPlant Airborne Radioactivity Control and Mitigation

Temporary Ventilation Systems (IP Section 03.02) (1 Sample)

The inspectors evaluated the configuration of the following temporary ventilation systems:

(1) Temporary HEPA ventilation systems used on the refuel floor during refueling activities.

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, 2021 through September 30, 2022)

(2) Unit 3 (October 1, 2021 through September 30, 2022)

BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10) (2 Samples)

(1) Unit 2 (October 1, 2021 through October 31, 2022)

(2) Unit 3 (October 1, 2021 through October 31, 2022)

OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)

(1) October 1, 2021 through October 31, 2022 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) October 1, 2021 through October 31, 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 of and corrective actions associated with the Unit 2 2A feedwater regulating valve failing open and subsequent scram under AR 4510475

71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02)

(1) The inspectors reviewed the licensees corrective action program for potential adverse trends in work planning and execution that might be indicative of a more significant safety issue.

71153 - Follow-up of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02)

The inspectors evaluated the following licensee event reports (LERs):

(1) LER 237/2022001-01, Reactor Scram due to Turbine Trip on High Reactor Water Level caused by Feedwater Regulating Valve Failure (ADAMS Accession No. ML22304A228). The inspectors determined that it was not reasonable to foresee or correct the cause discussed in the LER therefore no performance deficiency was identified. The inspectors did not identify a violation of NRC requirements. The inspectors reviewed the updated LER submittal. The previous LER submittal was also reviewed in this inspection report.

OTHER ACTIVITIES

-TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL

60853 - OnSite Fabrication of Components and Construction on an ISFSI OnSite Fabrication of Components and Construction on an ISFSI

(1) The inspectors evaluated the licensees Independent Spent Fuel Storage Installation (ISFSI) pad expansion activities from July 2022 to November 2022. Throughout construction, the inspectors evaluated the following:

Preparation of the subsurface, formwork, and type and condition of reinforcing steel

The materials used were consistent with the design and procurement specifications

Aggregates were tested for potential reactivity

Design changes, modifications, and non-conformance reports

Qualifications of individuals performing quality assurance (QA) functions including non-destructive evaluations

QA oversight

American Concrete Institute (ACI) and American Society for Testing and Materials (ASTM) concrete sample test results, including verifying compressive strength tests met design specifications The inspectors were onsite on September 12 and 15, 2022, and observed the following during construction:

Placement of reinforcing steel was consistent with design requirements

Concrete placement was consistent with ACI standards

Concrete testing was consistent with ASTM and ACI standards

Overall pad dimensions were consistent with the design documents

INSPECTION RESULTS

Observation: Failure of 2A Feedwater Regulating Valve 71152A On July 12, 2022, the 2A feedwater regulating valve (FWRV), a non-safety related valve, failed to the full-open position. The 2B reactor feed pump (RFP) tripped on low suction pressure, followed by the 2A and 2C RFPs tripping due to high reactor level. This caused a high reactor water level turbine trip, and subsequently Unit 2 received an automatic reactor Scram. The licensee replaced the 2A FWRV Joucomatic solenoid valve and returned to full power.

The inspectors reviewed the licensee's root cause report and supporting failure analysis report from a third party to determine the cause of the FWRV failing full-open. The licensee determined that the root cause was the 2A FWRV pilot valve assembly did not operate as demanded by the feedwater control system due to manufacturing byproduct inside the pilot valve that was introduced during the manufacturing process.

The third-party vendor concluded a piece of plastic migrated from another location within the pilot valve and settled on the seat surface of the movable pilot plunger. This resulted in the movable pilot plunger not full seating against the fixed seat. The failure mode was identified as the pilot valve not seating in a deenergized state. The piece of plastic was believed to be the same plastic used to manufacture the body components, and likely left over from the manufacturing process.

The site developed corrective actions to have incoming Joucomatic solenoid valves with specific identification related to the failure inspected by a second-or third-party vendor and certified to be free of foreign material. The site also reclassified the FWRV as a single-point vulnerability.

The inspectors did not identify any findings or violations associated with their review.

Observation: Maintenance Preparation and Execution Trend Review 71152S The inspectors performed a semiannual review of issues entered into the corrective action program (CAP) and a cognitive review of plant observations over the period of July 1, 2022, to December 31, 2022, to identify any potential trends that might indicate the existence of a more significant safety issue. In the second half of 2022, the licensee and NRC identified a rise in the number of work processes that were not accomplished first time with quality or resulted in multiple instances to fix issues. The first example was the main power transformer lovoltage bushing sensors not being installed during the work window due to a fitment issue that went undiscovered until work execution. Following issue review, the inspectors concluded due to work complications on the main power transformer and additional outage, delayed work bushing sensor replacement was removed from the outage scope to the next Unit 3 refueling outage incurring 2 more years of wear and tear.

On September 15, 2022, the licensee entered DOA 740001, Failure of the Stator Coolant System, for the failure of the motor cooling fan which resulted in overheating and ultimately the failure of the stator water cooling (SWC) pump motor. The inspectors noted, as documented in condition report (CR) 04522803, 3B Stator Water Cooling Pump Trip.

Entered DOA 7400-01, that the licensee had previously extended the maintenance frequency of the SWC pump motors and that the motors failed during the extended maintenance window. Following 3B SWC pump motor replacement the licensee documented in CR 04538065, Elevated Temperatures on 3B SWC, on November 19, 2022, further elevated temperature issues associated with the motor inboard bearing which resulted in another motor replacement. On December 1, 2022, post maintenance testing of the replaced 3B SWC pump motor revealed elevated temperatures on the pump to motor coupling. The inspectors noted that licensee evaluation suggested that side loading of the bearing was most likely the cause of the increased temperatures following maintenance. The inspectors noted that in an approximate three-month period the licensee had documented four separate condition reports associated with the 3B SWC pump.

Inspector review also noted condition reports associated with the scram air header. In CR 04535612, 3B Scram Air Header Filter Air Leak, the inspectors noted that post maintenance system inspection noted air leaks on the inlet and outlet piping connections to the 3B scram air header filter housing. Licensee assessment resulted in the issue being scoped into the ongoing refueling outage for Unit 3 for resolution. The licensee further documented in CR 04538075, 3B Scram Air Header Filter Air Leak, that the air leak appeared to be from a spot where the Oring was protruding from the flange on the side of the filter. Isolation of the air leak using inlet and outlet valves did not arrest the leak but slowed it, so it did not represent a challenge system function.

Finally, in conversation with plant management the inspectors discussed the previously noted issues and ongoing efforts by the licensee to address equipment reliability. The inspectors noted that challenges in work process preparation and execution could also present challenges to, and hamper efforts to broadly address and improve equipment reliability. The inspectors did not identify any findings or violations associated with the inspection activities.

EXIT MEETINGS AND DEBRIEFS

The inspectors verified no proprietary information was retained or documented in this report.

On January 12, 2023, the inspectors presented the integrated inspection results to P. Boyle, Site Vice President, and other members of the licensee staff.

On November 15, 2022, the inspectors presented the radiation protection inspection results to P. Boyle, Site Vice President, and other members of the licensee staff.

On November 18, 2022, the inspectors presented the inservice inspection results to D. Avery, Acting Regulatory Assurance Manager, and other members of the licensee staff.

On November 28, 2022, the inspectors presented the emergency action level and emergency plan changes inspection results to A. Clements and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Corrective Action

Documents

Resulting from

Inspection

04522444

NRC Final Rebar Inspection Prior to ISFSI Pad Concrete

Pour

09/14/2022

B2287 Sheet 1

South ISFSI Pad General Notes

B2287 Sheet 2

South ISFSI Pad Geotechnical Notes

Drawings

B2287 Sheet 3

South ISFSI Pad Plan, Sections, and Details

Engineering

Changes

EC 628118

South ISFSI Expansion Pad

9411106

Concrete Inspection Report-Mud Mat for ISFSI

08/18/2022

9411125

Concrete Inspection Report-North & South ISFSI Pad

10/13/2022

9411130

Concrete Inspection Report-Middle ISFSI Pad

10/21/2022

D2018001

Concrete Construction Specification for South ISFSI Pad,

Construction Pad, Turning Pad/Apron, and Heavy Haul Path

08/22/2022

D3000

Dresden ISFSI Concrete Mix Report

03/14/2022

G22.112

Plate Load Test Data Report

07/15/2022

60853

Miscellaneous

PO# 341479

Certified Mill Test Report

04/22/2022

Corrective Action

Documents

4534445

Leak Identified on PI 31407-C, 3C Shutdown Cooling Pump

Discharge

11/03/2022

Drawings

2E2328

Emergency Power System

O

Engineering

Evaluations

637324

Alternate Decay Heat Removal (ADHR) Qualification for

D3R27

DOP 1000M1/E1

Unit 3 Shutdown Cooling Checklist

DOP 1900M1

Unit 3 Fuel Pool Cooling System Checklist

DOP 650008

Bus 241 to Bus 341 Tie Breaker Operation

71111.04

Procedures

DOP 650030

Bus 231 to Bus 331 Tie Breaker Operation

Corrective Action

Documents

Resulting from

Inspection

4534891

NRC ID: Housekeeping/Hot Work Issues

11/04/2022

71111.05

Fire Plans

FZ 1.1.1.1

Unit 3 Torus Basement Elevation 476' and Torus Catwalk

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

FZ 6.2

Unit 2/3 Computer Room and Auxiliary Electrical Room

Elevation 517'

FZ 8.2.5C

Unit 2/3 EHC Reservoir Area, Elevation 517'

FZ 8.2.5D

Unit 3 Low Pressure Heater Bay, Elevation 517'

FZ 8.2.5E

Unit 3 High Pressure Heaters/Steam Line, Elevation 517'

FZ 8.2.6D

Unit 3 Low Pressure Heater Bays, Elevation 538'

Procedures

OPAA201004

Fire Prevention for Hot Work

71111.07A

NDE Reports

3B LPCI Heat Exchanger Eddy Current Examination Final

Report

11/01/2022

2635334

Shroud Weld Inspection Does Not Meet BWRVIP Criteria

03/03/2016

4381004

FM Identified in RPV

10/30/2020

4445276

Previously Identified Leak on ASME Class 2 Valve

31501-11A

09/08/2021

4491094

D3R27 IVVI Emergent OPEX-Access Hole Cover Inspection

04/07/2022

4494861

Deviation from BWRVIP Inspection U2/3 Core Shroud Vert

Welds

04/22/2022

4534671

D3R27 M1192D260 VT3 IWF Support Cold Setting OOT

11/03/2022

Corrective Action

Documents

4535096

IVVI D3R27 Indications in Access Hole Covers

11/06/2022

21307

Technical Justification to Support Deviation from BWRVIP

Inspection Guidance for Dresden Station Unit 2 and Unit 3

Core Shroud Vertical Welds

637904

Technical Evaluation of the Dresden Unit-3 Access Hole

Cover 155°

Engineering

Evaluations

637945

Technical Evaluation of Dresden Unit-3 Access Hole Cover

335°

71111.08G

Miscellaneous

BWRVIP180

BWR Vessel and Internals Project - Access Hole Cover

Inspection and Flaw Evaluation Guidelines

7480332222-

EB3RPVID for

RPV Weld No.

3SC4B

UT Report for Component No. 3/1/RPV

SHELL/3SC4B-VERT

11/06/2022

71111.08G

NDE Reports

7480332222-

EB3RPVID for

UT Report for Component No. 3/1/RPV

SHELL/3SC4D-VERT

11/05/2022

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

RPV Weld No.

3SC4D

CNF-AHC01

Indication Results for Access Hole Cover at 155°

CNF-AHC02

Indication Results for Access Hole Cover at 335°

CNF-AHC03

Weld Crown Measurements for the Access Hole Cover at

335°

D3R27MT-003

Magnetic Particle Examination Report for Component

No. 3/2/150120/2012

11/04/2022

D3R27PA-001

UT Report for Component No. 3/2/1302A12/127

11/08/2022

D3R27PA-002

UT Report for Component No. 3/2/1302B12/128

11/08/2022

EPRI-DMW-

PA1

Procedure for Manual Phased Array Ultrasonic Examination

of Dissimilar Metal Welds

ERAA335003

Magnetic Particle (MT) Examination

ERDR3311001

Dresden Reactor Pressure Vessel and Internals Program

Bases Document

GEH-UT562

Procedure for Phased Array Ultrasonic Examination of

Access Hole Cover Welds

GEH-UT737

Procedure for the Examination of Reactor Pressure Vessel

Welds from the Inside Surface with the ZScan UT System in

Accordance with Appendix VIII

Procedures

WPS 11-GTSM-

PWHT

ASME Welding Procedure Specification Record

Work Orders

488633602

Repair Identified Deficiencies on U3 B LPCI HX Support

11/04/2020

DGP 0101

Unit Startup

204

71111.11Q

Procedures

DGP 0201

Unit Shutdown

176

4465461

U2 CCSW Division 1 Thru Wall Leak

2/08/2021

4513848

Bar Rack Plugging DOA Entries

07/30/2022

4519442

Unexpected Alarm 9231 U3A IAC Trip

08/29/2022

24121

2B Instrument Air Compressor Fails to Load/Unexpected

21 E6 Alarm

09/22/2022

4534701

2A IAC Trending

11/04/2022

4535921

3A IAC Trip on High Temp

11/09/2022

71111.12

Corrective Action

Documents

4537312

Unit 3 High Pressure Coolant Injection Room Cooler Motor

11/16/2022

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Vibration Increase

4540539

Maintenance Rule High Safety System Maintenance Rule

Functional Failure Were Not Screened in a Timely Manner

2/02/2022

4542415

Unit 3 High Pressure Coolant Injection Room Cooler Motor

Vibration Increase

2/13/2022

Engineering

Changes

635679

Code Repair of a Through Wall Leak on CCSW

Line 21510-16"-D

High Pressure Injection System Health Report

2/20/2022

Compressed Air System Health Report

2/02/2022

SR Service Water System Health Report

2/13/2022

Miscellaneous

NOAA10

Quality Assurance Topical Report (QATR)

4830134

CM Replace Division 1 CCSW Piping 517 TB to RBDT

Room EC 624725

11/12/2022

22790

CM Replace Division 1 CCSW Piping 517 to RBEDT Room

EC 624726

11/12/2022

211916

MM Repair the CCSW Pipe per EC 635679

2/10/2021

Work Orders

211916

MM EWP Remove Paint/Prep Pipe for NDE of 2nd Leak

2/09/2021

24978

Unit 3 ESS Current Low per DOS 680001

11/05/2022

4539461

3B Condensate Pump Seal Degraded

11/28/2022

Corrective Action

Documents

4539818

Unexpected Load Drop

11/30/2022

Engineering

Changes

637260

MR90 Temporary 250VDC Power to Bus 383250-3A/B

D3R27 Shutdown Safety Analysis

Miscellaneous

Various Protected Pathway Schemes During D3R27

10/31/2022 -

11/18/2022

DOA 650001

4kV Bus Failure

DOP 380001

Essential Service System

DOP 670014

Bus 39 Outage

OPAA108117

Protected Equipment Program

71111.13

Procedures

OUDR1041001

Shutdown Risk Management Contingency Plans

MIDACALC Results DRE31501-22A (DRE3) AC Motor

Operated GL9605 Gate Valve

71111.15

Calculations

CEDR027

Weak Link Analysis for Dresden Unit 2 & 3 Mark-I MOVs

2B

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

(MO2(3)-150122A(B))

04534040

HPCI Leak Detection Temperature Switch Found Broken

11/01/2022

1135936

NDE Indications Discovered in HPCI Control Valve #4

11/05/2010

4534722

Incorrect Fuse Found in Bus 39 UV Relay Circuitry

11/04/2022

4534843

D3R27 NDE LR VT3 Exam Identified Recordable

Indications

11/04/2022

4535038

U3 Sporadic Alarms

11/05/2022

4535195

Missing Bolts U3 Hotwell Basement Flood Seals

11/07/2022

4535761

345kV BT 910 and 1011 Breakers Tripped Open

11/09/2022

4536021

Unit 3 HPCI Turbine Control Valve Inspection

11/10/2022

4536615

Unit 3 HPCI Turbine Control Valve Adjustment

11/12/2022

4536679

220-44 LLRT Results

11/13/2022

Corrective Action

Documents

4537098

D3R27 MO 31501-22A WR for Contingent Stem Nut Work

11/15/2022

B527

Turbine Building Foundation Sections DD and FF

06/20/1966

B533

Turbine Building Foundation Section

EC 406664

FL19 Sheets 1

and 2

Flood Barrier Turbine Building

FL20

Flood Barrier Turbine Building Section 20

05/26/1995

M284

Turbine Building Ventilation Misc. Plans and Sections

07/21/1967

Drawings

M357, Sheet 2

Diagram of Nuclear Boiler & Reactor Recirculation Piping

BT

637989

D3R27 125 VDC Ground Evaluation

Engineering

Changes

637993

PCTCC for Bypassing Mechanical Vacuum Pump Trips

EC 382146

Unit 3 HPCI Control Valve Seat 4 Crack Indications

ECR 456524

Multiple Recordable Indications Identified Inside HPCI

Steam Chest

11/06/2022

Engineering

Evaluations

ECR 456583

Indication on U3 HPCI Control Valve 3 Seat

11/10/2022

CCAA206

Fuse Control

Procedures

DAN 902(3)-3 C7

HPCI Auto Isolation Initiated

DIS 230007

High Pressure Coolant Injection Area Temperature Switch

Calibration

DOP 540010

Condenser Vacuum Pump Startup

ERAA450

Structures Monitoring

71111.15

Procedures

OPAA108101

Control of Equipment and System Status

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Work Orders

WR 01527760

Work Request to Replace the Missing Bolts on the U3

Hotwell Basement Flood Seals

11/07/2022

4534079

Evidence of Packing Leak on 32301-4 Valve

11/01/2022

4536760

Body to Bonnet Leak on 38941-705 SDC to HRSS XCV

11/14/2022

4536774

D3R27 RCPB Class 1 and Class 2 System Leakage Test

Results

11/14/2022

4536866

Rod H15 Scram Time Did Not Meet TS Requirements

11/14/2022

4536880

Rod R6 Scram Time Did Not Meet TS Requirements

11/14/2022

4536908

Scram Timing Results

11/14/2022

4536929

U3 CRD G13 Stuck at Overtravel In

11/14/2022

4536931

U3 CRD H5 Stuck at Overtravel In

11/14/2022

Corrective Action

Documents

4537035

Control Rod M08 Scram Time Data Not Found

11/15/2022

NDE Reports

2186

D3R27 Class 1 & Class 2 System Leakage Test

11/14/2022

DES 830020

Unit 3 250 Volt Station Battery Modified Performance Test

DOS 030014

Control Rod Drive Scram Testing at Power

DOS 030015

Control Rod Drive Scram Timing Test During Hydro

DOS 700027

Local Leak Rate Testing of Unit 2 (3) Reactor Vessel Water

Level Instrumentation System (RVWLIS) Valves

Procedures

OPDR300101

Average Scram Time Determination

4830134

OPD PMTT Perform DOS 150012 CCSW Flow Verification

for Division 1

11/16/2022

22790

OPD PMT Perform DOS 150012 CCSW Flow Verification

for Division 2

11/16/2022

71111.19

Work Orders

26822

D3 Refueling TS (ISI) 1000psi Reactor Vessel System

Leakage Test/Hydrostatic Test

11/15/2022

4535057

Foreign Material Recovered from 3B Feedwater Regulating

Valve Cage

11/05/2022

Corrective Action

Documents

4536522

CMO Review of 3A RR Motor Bridge and Megger

Unacceptable

11/12/2022

DRMODE4

TS 3.0.4.b Evaluation-Mode Change with Division 2 CCSW

Out of Service

EC 624726

CCSW 16" Pipe Replacement

71111.20

Engineering

Evaluations

EC 637369

D3R27 Spent Fuel Pool Cooling Evaluation During

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Transition to ADHR Dresden Station Unit 3

ECR 456634

Determine Minimum Acceptable Resistance to Ground

Reading for Cabling from ASD Trailers

11/11/2022

Miscellaneous

D3R27 Shutdown Safety Analysis

DFP 080007

Fuel Movements during Refueling Operations

DGP 01S1

Start-up Checklist

106

DGP 01S5

Mode 3 to Mode 2 Restart Checklist

DGP 0401

Fuel Moves and Refueling

DOP 020104

Reactor Pressure Vessel Water Inventory Control

MAAA716008-

1008

Reactor Services Refuel Floor FME Plan

MAAA716021

Rigging and Lifting Program

Procedures

OUDR104

Shutdown Safety Management Program

22790

Replace Division 2 CCSW Piping 517' to RBEDT Room per

EC 624726

11/02/2022

Work Orders

5119099

Bridge and Megger Recirculation Pump Motor, 30202-A

11/12/2022

4533563

203-1D MSIV Slow to Close (Hot)

10/31/2022

4533856

Severe Packing Leak from 30220-90A

11/01/2022

4533867

Inboard MSIV 30203-1B Exceeded Technical Specification

LLRT Limit

11/01/2022

4533874

203-1A MSIV LLRT Unfavorable Performance

11/01/2022

4533878

203-2A MSIV LLRT Unfavorable Performance

11/01/2022

4533881

203-2D MSIV LLRT Unfavorable Performance

11/01/2022

4534189

D3R27 IST Seat Leakage Test Exceeded <3 ml/hr (AC)

11/02/2022

4534966

590111B Did Not Initially Pick Up During DIS 050020, Ch B

11/05/2022

4535103

TR32 to Bus 34 Breaker Cubicle Contacts Malfunctioned

During DOS 660004

11/06/2022

4535342

Need WR Created for IR 4534966

11/07/2022

4536998

ILRT Drywell Temperature Sensor T12 Failed

11/15/2022

4537140

Local Leakage During D3R27 ILRT

11/15/2022

Corrective Action

Documents

4537218

Packing Leak on U3 LPCI A Pump Suction Valve from CST

11/15/2022

71111.22

Procedures

DIS 050020

Reactor Mode Switch (Start, Hot Standby, Shutdown, and

Refuel, Positions) Logic System Functional Test

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

DOS 660004

Bus Undervoltage and ECCS Integrated Functional Test for

Unit 3 Diesel Generator

DOS 700001

Local Leak Rate Test of Main Steam Isolation Valves

(Dry Tests)

DOS 700002

Local Leak Rate Test of Main Steam Isolation Valves

(Wet Test)

DOS 710003

Seat Leakage Testing of Valves 2 (3)-029997A(B),

(3)-029998A(B), 2 (3)-029999A(B) and

(3)-0299100A(B)

DTS 160007

Dresden Integrated Leakage Rate Test

Work Orders

4850420

EM Burnish Reactor Mode Switch Contacts 88C(B)

IR 04534966

11/11/2022

Miscellaneous

Q 2158

Emergency Action Levels for Dresden Station

11/20/2021

EPAA1004,

Addendum 3

Emergency Action Levels for Dresden Station

71114.04

Procedures

EPAA1004,

Addendum 3

Emergency Action Levels for Dresden Station

DR0322-00816

D3R27 TB Feedwater Systems Maintenance

71124.01

ALARA Plans

DR0322-00901

D3R27 Reactor Disassembly/Reassembly and Related

Activities

Miscellaneous

RPAA302,

Alpha Area Level Assessment

20

NISP-RP002

Radiation and Contamination Surveys

RPAA302

Determination of Alpha Levels and Monitoring

Procedures

RPAA4011003

Contamination Control Best Practice Application

22181001

Main Steam Isolation Valves

11/04/2022

Radiation

Surveys

22181049

Main Steam Isolation Valves

11/05/2022

DR0322-00509

D3R27 DW Main Steam Isolation Valve (MSIV) Activities

DR0322-00510

D3R27 DW Main Steam ERV, SRV, Target Rock VLVs

DR0322-00802

D3R27 TB Main Condenser Activities

DR0322-00807

D3R27 TB Moisture Separator Activities

DR0322-00808

D3R27 TB Valve Maintenance (Excluding XArea)

Radiation Work

Permits (RWPs)

DR0322-00810

D3R27 TB Water Box Maintenance Activities

71124.01

Self-Assessments PIAA1261001-

F01

Pre-NRC 71124.01 ALARA

10/29/2022

71124.03

ALARA Plans

DR0322-00906

D3R27 Cavity Decon

Monthly Data Elements for NRC Radiological Effluent

Technical Specifications/Offsite Dose Calculation Manual

Radiological Effluent Occurrences (RETS/ODCM)

Radiological Effluent Occurrences Sample

(10/01/2021-10/31/2022)

10/01/2021 -

10/31/2022

Monthly Data Elements for NRC Reactor Coolant System

(RCS) Specific Activity (10/01/2021-10/31/2022)

10/01/2021 -

10/31/2022

Monthly Data Elements for NRC Occupational Exposure

Control Effectiveness Sample (10/01/2021-10/31/2022)

10/01/2021 -

10/31/2022

71151

Miscellaneous

Data Validation Package for Safety System Functional

Failure Performance Indicator, Unit 2 and Unit 3

10/01/2021

09/30/2022

Corrective Action

Documents

4510475

2A FRV Failed Open

07/12/2022

71152A

Procedures

PIAA1251001

Root Cause Investigation Report Template

6