IR 05000237/2024010

NRC Age-Related Degradation Inspection Report 05000237/2024010 and 05000249/2024010

ML24220A241
Person / Time
Site:	Dresden
Issue date:	08/09/2024
From:	Karla Stoedter NRC/RGN-III/DORS/EB1
To:	Rhoades D Constellation Energy Generation, Constellation Nuclear
References
IR 2024010
Preceding documents:	ML24061A170 (1 March 2024)
Download: ML24220A241 (1)

Text

SUBJECT:

DRESDEN NUCLEAR POWER STATION - NRC AGE-RELATED DEGRADATION INSPECTION REPORT 05000237/2024010 AND 05000249/2024010

Dear David Rhoades:

On July 2, 2024, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Dresden Nuclear Power Station, Units 2 and 3 and discussed the results of this inspection with C. Joseph, 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.

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, Karla K. Stoedter, Chief Engineering 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:

05000237/2024010 and 05000249/2024010 Enterprise Identifier:

I-2024-010-0057 Licensee:

Constellation Energy Generation, LLC Facility:

Dresden Nuclear Power Station, Units 2 and 3 Location:

Morris, IL Inspection Dates:

June 10, 2024 to July 02, 2024 Inspectors:

E. Fernandez, Senior Reactor Inspector I. Hafeez, Senior Reactor Inspector A. Shaikh, Senior Reactor Inspector Approved By:

Karla K. Stoedter, Chief Engineering Branch 1 Division of Operating Reactor Safety

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a NRC 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.

INSPECTION SCOPES

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

REACTOR SAFETY

71111.21N.04 - Age-Related Degradation Age-Related Degradation

The inspectors selected a sample of components and structures to verify that engineering performance and maintenance activities addressed age-related degradation and that problems were appropriately identified, addressed and corrected.

Samples were selected considering risk insights and the potential for degradation.

Specifically, the inspectors selected samples that were risk-significant and either had indications of age-related degradation or were exposed to environments that could cause age-related degradation. The inspectors considered site-specific and industry-wide operating experience to identify samples and included both active and passive sub-components within each component or structure.

For each selected sample below, the inspectors reviewed the licensee's engineering and maintenance activities credited to address age-related degradation to assess whether they were being performed using applicable standards and procedures, evaluated against appropriate acceptance criteria, and that maintenance and condition monitoring was completed at an appropriate interval. The inspectors also assessed whether issues identified during licensee activities were being entered into and addressed by the applicable station processes including the corrective action program, and whether periodic assessments of maintenance effectiveness and operating experience were being completed, including feedback and process adjustments.

(1) Primary Containment Isolation Valves 2-1301-20 and 3-1301-1

(2) Unit 2 and Unit 3 High Pressure Coolant Injection Room Coolers

(3) Unit 2 and Unit 3 Emergency Diesel Generator Air Accumulator Tanks

(4) Unit 2 and Unit 3 Reactor Building Closed Cooling Water Heat Exchangers

(5) Unit 2 and Unit 3 Condensate Storage Tanks

(6) Diesel Fire Pumps

(7) Unit 2 and Unit 3 Instrument Air Dryers

(8) Electromatic Relief Valves

(9) Reactor Manual Control System

(10) Safety Related 480 Vac Breakers

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

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

• On July 2, 2024, the inspectors presented the NRC inspection results to C. Joseph, Site Vice President and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Calculations

DRE98-0077

Dresden HPCI Room Thermal Response with Reduced

Room Cooler

001

AR 02645074

U2 HPCI Room Cooler Outboard Fan Vibe Reading in

Alert Range

10/14/2016

AR 02738296

Discolored Cables in Riser 325

11/07/2016

AR 04173707

U2 HPCI Room Cooler Abnormal Noise

10/16/2018

AR 04206210

U2 HPCI Room Cooler Leak Identified

04/08/2019

AR 04213082

U2 HPCI Room Cooler Noise Change

2/22/2019

AR 04356737

Packing Leak on AO 3-1301-17 Main Steam Line Inbd Iso

Vlv

07/14/2020

AR 04474980

3-1301-17 Iso Cond Vent Valve Solenoid Buzzing

01/31/2022

AR 04480839

Packing Leak on 3-1301-17

AR 04559790

Vibration Data Anomaly on the U2HPCI Room Cooler

04/05/2023

Corrective Action

Documents

AR 04780485

Light Corrosion on 2-1301-20 Valve Bolting

06/13/2024

AR 04780263

NRC ID: Identified Loose Fasteners Behind Bus 2B

06/12/2024

AR 04780269

NRC ID: Identified Loose Fasteners Behind Bus 3B

AR 04780581

Perform NDE Inspection of Piping for U3 HPCI Room

Cooler

06/13/2024

AR 04780780

NRC ID: Identified BCD Device Near Bus 39

06/14/2024

AR 04783603

NRC ID: NRC CONCERN CALC CHANGES/BASIS

06/27/2024

Corrective Action

Documents

Resulting from

Inspection

AR 0484352

ARDI NRC ID: NRC Question ERV Solenoid Conductor

Temperature

07/01/2024

Drawings

2E-2410

Schematic Diagram Reactor Manual Control Sheet 2

Rev. L

CDBI-DRE02-

066A

Emergency Diesel Generator & Auxiliaries License

Renewal

CDBI-DRE02-

66A

Emergency Diesel Generators & Auxiliaries License

Renewal

ER-DR-330-1001

ISI Program Plan Sixth Inspection Interval

LRTI-15

AMR Gas and Ventilation Air (M01)

71111.21N.04

Miscellaneous

MA-AB-725-110

Preventative Maintenance Inspection of GE Types AK-25

Circuit Breakers

Rev. 11

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

MA-AB-725-112

Preventative Maintenance Inspection of GE 480V Types

AK-50/75, AKS-50, & AKR-75/100 Circuit Breakers and

Cubicles

Rev. 13

PO# 12382

Certificate of Conformance HPCI Cooling Coil Material

10/18/2018

05142242

U3 Eddy Current Test HPCI CLR Coil

05/05/2023

05145356

U2 Eddy Current Test HPCI RM CLR Coil

05/08/2023

ER-AA-335-004

UT Thickness U2 Air Dryers

NDE Reports

ER-AA-336-004

UT Thickness Sheet U3 Air Dryers

04949809

Pressure Gauge Out of Tolerance During Power Labs

Calibration

Rev. 1

Procedures

MA-DR-EM-4-

200

Dresser Electromatic Solenoid Actuator Rebuild

Instructions

Rev. 13

00986900-01

Inspect/Replace HPCI Room Cooler Fan Bearings

03/18/2013

01490829

Replace HPCI Room Cooler Coiling Coil U2

01/09/2019

01804350

Unit 2/3 Internal UT Inspection of CST-B Tank Bottom

10/23/2023

01805284

Unit 2/3 Internal UT Inspection of CST-A Tank Bottom

09/24/2023

04589133

2A RBCCW HX Inspection and Eddy Current Testing

01/03/2022

04599405

3A RBCCW HX Inspection and Eddy Current Testing

2/05/2019

04601529

3B RBCCW HX Inspection and Eddy Current Testing

01/27/2020

04749723

2B RBCCW HX Inspection and Eddy Current Testing

01/02/2023

04949809

PRESSURE GAUGE OUT OF TOLERANCE DURING

POWER LABS CALBRATION

10/31/2020

05145356-01

Eddy Current HPCI Room Cooler

03/09/2023

05194571

Unit 2/3 Diesel Fire Pump Flow Capacity Test

03/23/2023

275017

Unit 1 Diesel Fire Pump Flow Capacity Test

01/31/2024

Work Orders

05397632-01

Eddy Current HPCI Room Cooler Coils

03/03/2023