IR 05000237/2022011

Design Basis Assurance Inspection (Programs) Inspection Report 05000237/2022011 and 05000249/2022011

ML22101A240
Person / Time
Site:	Dresden
Issue date:	04/12/2022
From:	Karla Stoedter NRC/RGN-III/DRS/EB2
To:	Rhoades D Constellation Energy Generation, Constellation Nuclear
References
IR 2022011
Download: ML22101A240 (10)

Text

April 12, 2022

SUBJECT:

DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3 - DESIGN BASIS ASSURANCE INSPECTION (PROGRAMS) INSPECTION REPORT 05000237/2022011 AND 05000249/2022011

Dear Mr. Rhoades:

On April 1, 2022, 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 Mr. 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.

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 Stoedter, Karla on 04/12/22 Karla K. Stoedter, Chief Engineering Branch 2 Division of 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: 05000237/2022011 and 05000249/2022011 Enterprise Identifier: I-2022-011-0037 Licensee: Constellation Energy Generation, LLC Facility: Dresden Nuclear Power Station, Units 2 and 3 Location: Morris, IL Inspection Dates: March 14, 2022 to April 01, 2022 Inspectors: J. Benjamin, Senior Reactor Inspector B. Jose, Senior Reactor Inspector A. Shaikh, Senior Reactor Inspector Approved By: Karla K. Stoedter, Chief Engineering Branch 2 Division of Reactor Safety Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a design basis assurance inspection (programs) 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.02 - Design-Basis Capability of Power-Operated Valves Under 10 CFR 50.55a Requirements POV Review (IP Section 03)

The inspectors reviewed the valves listed below to determine the following:

a. Whether the sampled power-operated valves (POVs) are being tested and maintained in accordance with NRC regulations along with the licensees commitments and/or licensing bases.

b. Whether the sampled POVs are capable of performing their design-basis functions.

c. Whether testing of the sampled POVs is adequate to demonstrate the capability of the POVs to perform their safety functions under design-basis conditions.

d. Material condition of the valve including a review of maintenance activities and a walkdown of the valve (if accessible).

(1) Air Operated Valve (AOV) 3-1601-60: Unit 3 Torus Vent Valve

(2) Squib 3-1106 A: Unit 3 Standby Liquid Control System Squib Valve

(3) Motor Operated Valve (MOV) 3-1501-10: Unit 3 High Pressure Coolant Injection (HPCI) System Test Return to Condensate Storage Tank

(4) MOV 2-1501-38A: Unit 2 Low Pressure Coolant Injection Test Injection Isolation Valve

(5) MOV 2-2301-3: Unit 2 HPCI Turbine Steam Supply Valve

(6) AOV 2-1599-61: Unit 2 Torus to Hotwell Containment Isolation Valve

(7) MOV 2-1201-1: Unit 2 Reactor Water Clean-Up System Inlet Isolation Valve

(8) Main Steam Isolation Valve 2-0302-1D: Unit 2 Inboard Main Steam Isolation Valve

(9) MOV 2-1301-3: Unit 2 Isolation Condenser Isolation Valve

(10) AOV 2-0302-158B: Unit 2 Scram Discharge Volume Drain Valve

(11) AOV-3 1601-23: Unit 3 Drywell Vent Valve

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

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

On April 1, 2022, the inspectors presented the design basis assurance inspection (programs) inspection results to Mr. P. Boyle, Site Vice President, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.21N.02 Calculations 2-1301-3 Midacalc Results DRE-2-1301-3 9

2-1501-38A MIDACALC Results MOV 2-1501-38A 3

AOV-MEDP- Inboard Main Steam Isolation Valve 0

DRE-02-001

DRE 02-0038 MOV Alternating Current (AC) Motor Terminal Voltage 1

Calculation

DRE 03-0015 HPCI MOV Design Basis Document and Differential 0A

Pressure Calculation

DRE 03-0100 Reactor Water Cleanup System Combined DBD and DP 000

Calculation

DRE 16-0040 Seismic Qualification of AVCO Air Pilot Valves 1

DRE-15-0046 Hardened Containment Vent System (HCVS) Vent Line 0

Sizing, Unit 3

DRE-3-2301-10 MIDACALC Results, DC MOV Generic Letter (GL) 96-05 7

Globe Valve 3-2301-10

DRE00-0061 Main Steam Isolation Valves Capability Margin Calculation 0A

DRE01-0066 Dresden Units 2 and 3 Standby Liquid Control (SLC) 2

Discharge Piping Pressure Drop

DRE03-0013 LPCI Differential Pressure (DP) Calculation 0

DRE98-0031 Unit 2 Reactor Building Motor Control Centers (MCCs), 4

Thermal Overload (TOL) Heater Sizing

Pratt Order # DD- 18" 2FII Dimensional Data for Commonwealth Edison 07/18/2000

664 (Pratty Dresden Plant PO 00013597

Original Order #

N-3410-2)

Corrective Action AR 03988159 2-2301-3 Unit 2 HPCI Turbine Steam Supply MOV Did Not 03/22/2017

Documents Open

AR 03991760 2-2301-3 Weak Link Calculation Revision Required for 03/30/2017

Disc and Stem

AR 04074741 2-2301-3 Failed to Close During DIS 2300-05 11/14/2017

AR 04191433 3-1601-60 Failed Pressure Decay Test in DOS1600-28 11/04/2018

AR 04193082 3-1601-60-SV, Unit 3 Instrument Air Supply Solenoid 11/08/2018

Inspection Type Designation Description or Title Revision or

Procedure Date

Valve Leak

Drawings 12E-2441 Schematic Diagram Low Pressure Coolant Injection AG

(LPCI) / Containment Cooling System MOVs 2- 1501-18A,

18B, 38A and 38B

2E-3512 Schematic Diagram, Primary Containment Isolation X

System (PCIS) Drywell and Torus Vent and Purge

Isolation Control

2E-3512A Schematic Diagram Atmospheric Control Inboard and E

Outboard Valves

2E-3529 Schematic Diagram HPCI Steam Main Pumps and AL

Condensate Valves

2553-2 1 " Gate Valve Actuator Operated 09/15/2006

706-4069-007 Assembly (MT1) 3A Line 8.00 Bore (G) 1.38 Rod Dia. NC 12/20/2011

B-397 Checkered Steel Floor Plate Details 06/30/1967

CBO7805 Sub-Assembly of Anti-Rotation Pilot Valve for List 653 01/06/2017

MSIV Assembly

H-29529 900 LB 18-8 MO Stainless Steel Gate Valves Sheet 1 A

M-12 Diagram of Main Steam Piping F

M-28 Diagram of Isolation Condenser Piping LR

M-34 Sheet 1 Diagram of Control Rod Drive Hydraulic Piping AN

M-34 Sheet 2 Diagram of Control Rod Drive Hydraulic Piping Z

M-356 Diagram of Pressure Suppression Piping CZ

M-356 Diagram of Pressure Suppression Piping CZ

M-374 Diagram of High Pressure Coolant Injection (HPCI) Piping CY

Engineering 401069 Hardened Containment Vent System Modification as 54

Changes Required by NRC Order EA-13-109

Engineering IST-DRE-BDOC- Inservice Test (IST) Basis Document, Valve 2-1501-38A 03/01/2019

Evaluations V-18

IST-DRE-BDOC- IST Basis Document for Valve 3-1601-60 0

V-21

IST-DRE-BDOC- IST Basis Document Valve 3-1106A 03/01/2019

V-31

Miscellaneous MPR-2524-A Joint Owners Group Programs Summary Report 1

OTC-371 Vendor Thrust Analysis, Required and Maximum for 0

Inspection Type Designation Description or Title Revision or

Procedure Date

Valves 1501-38A and B

Procedures DOP 1100-02 Injection of SLC 19

DOP 1300-01 Standby Operation of the Isolation Condenser 56

DOP 1300-02 Automatic Operation of the Isolation Condenser 28

DOP 1300-03 Manual Operation of the Isolation Condenser 39

DOP 1600-01 Normal Pressure Control of the Drywell or Torus 24

DOP 1600-03 Unit 2 Quarterly Valve Timing 56

DOS 0040-07 Verification of Remote Position Indication for Valves 49

DOS 0040-07 Verification of Remote Position Indication for Valves 49

DOS 0250-02 Full Closure Timing and Exercising of Main Steam 39

Isolation Valves

DOS 1100-03 SLC Injection Test 48

DOS 12600-18 Cold Shutdown Valve Testing 51

DOS 1600-03 Unit 2 Quarterly Valve Timing 56

DOS 1600-18 Main Steam Isolation Valve-Safe Closure Test 24

DOS 2300-01 HPCI Valve Operability and Timing 57

DOS 7000-01 Local Leak Rate Testing of Main Steam Isolation Valves 10

DOS-1600-28 Air Operated Valve Fail Safe and Accumulator Integrity 49

Test

DOS-2300-01 High Pressure Coolant Injection Valve Operability and 57

Timing

ER-AA-116 Motor Operated Valve Program 8

ER-AA-302 Motor Operated Valve Program Engineering Procedure 8

ER-AA-302-1001 MOV Rising Stem Motor Operated Valve Thrust and 12

Torque Sizing and Setup

ER-AA-302-1009 Final Joint Owners Group MOV Periodic Verification 3

Program Implementation

ER-AA-410 Air Operated Valve Program Implementing Procedure 6

ER-AA-410-1000 Air Operated Valve Cattegorization 4

ER-AA-410-1002 Air Operated Valve Testing Requirements 4

MA-AA-743-310 Diagnostic Testing and Evaluation of Air Operated Valves 8

Work Orders 00339085 Dresden 2, 10 Year MOV Diagnostic and Limitorque 01/06/2011

Surveillance 2-1501-38A

Inspection Type Designation Description or Title Revision or

Procedure Date

00597794 4th Refuel Replace Actuator on Valve 3-1601-60 09/06/2006

00692782 10 Year Preventive Maintenance (PM) Lube/Inspection 06/16/2016

Limitorque Valve Actuator 3-2301-10

00743475 12 Year Standby Liquid Squib Valve A, Replace 12/12/2007

Connector

00769761 10 Year Motor Operated Valve (MOV) Diagnostic and 03/18/2018

Limitorque Surveillance 3-2301-10

00976072 Dresden 3, 48 Month Standby Liquid Control System 11/17/2010

Manually Initiate to Inject Demineralized Water

01312947 In-Body Seat Found Damaged During Inspection 10/29/2015

01422808 4 Year Valve Lube Stem Threads Only 3-2301-10 03/20/2016

01803711 Technical Specifications Local Leak Rate Test Valve 12/09/2016

3-1601-60

04710348 Reactor Water Cleanup System MOV Operability and IST 11/15/2019

Timing

04849925 3-1601-60 Failed Pressure Decay Test in DOS 1600-28 11/16/2018

04877777 24 Month Air Operated Valve(AOV) Accumulator Integrity 11/02/2020

Test 3-1601-60

04981359 Cold Shutdown Valve Testing Surveillance 05/13/2021

05131603 TS Unit 3 Quarterly Valve Stroke Timing 1601-60 06/04/2021

05135479 AOV 1599-61 QTR TS Valve Timing (IST) 06/12/2021

05161497 AOV 1599-61 QTR TS Valve Timing (IST) 09/24/2021

8