IR 05000254/2022012

Triennial Inspection of Evaluation of Changes, Tests and Experiments Baseline Inspection Report 05000254/2022012 and 05000265/2022012

ML22189A108
Person / Time
Site:	Quad Cities
Issue date:	07/11/2022
From:	Richard Skokowski Engineering Branch 3
To:	Rhoades D Constellation Energy Company
References
IR 2022012
Download: ML22189A108 (9)

Text

SUBJECT:

QUAD CITIES NUCLEAR POWER STATION - TRIENNIAL INSPECTION OF EVALUATION OF CHANGES, TESTS AND EXPERIMENTS BASELINE INSPECTION REPORT 05000254/2022012 AND 05000265/2022012

Dear Mr. Rhoades:

On May 27, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Quad Cities Nuclear Power Station and discussed the results of this inspection with Drew Griffiths 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, Richard A. Skokowski, Chief Engineering Branch 3 Division of Reactor Safety Docket Nos. 05000254 and 05000265 License Nos. DPR-29 and DPR-30

Enclosure:

As stated

Inspection Report

Docket Numbers: 05000254 and 05000265

License Numbers: DPR-29 and DPR-30

Report Numbers: 05000254/2022012 and 05000265/2022012

Licensee: Constellation Nuclear

Facility: Quad Cities Nuclear Power Station

Location: Cordova, IL

Inspection Dates: May 23, 2022 to May 27, 2022

Inspectors: J. Benjamin, Senior Reactor Inspector B. Jose, Senior Reactor Inspector J. Park, Reactor Inspector

Approved By: Richard A. Skokowski, Chief Engineering Branch 3 Division of Reactor Safety

Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a triennial inspection of evaluation of changes, tests and experiments baseline inspection at Quad Cities Nuclear Power Station, 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

71111.17T - Evaluations of Changes, Tests, and Experiments Sample Selection (IP Section 02.01)

The inspectors reviewed the following evaluations, screenings, and/or applicability determinations for Title 10 of the Code of Federal Regulations 50.59 from January 2019.

(1) QC-E-2018-001, Revision 2 - EC 404570 and 404571, ERVR - Off Gas Isolation Loss of Power/Air Vulnerability

(2) QC-E-2020-001 Revision 1 - EC 632028-MO 2-0220-2 Setup with Lower Closing Thrust at Torque Switch

(3) QC-E-2020-003, Revision 0 - Document Change Request (DCR) 632901 - Revise Maintenance Specification CC-QC-409 for Safety-Related Entelliguard Trip Units

(4) QC-E-2021-002, Revision 0 - EC 629264 and 629265 - Nuclear Fuels Transition to GNF3 at Quad Cities

(5) QC-E-2017-002, Revision 0 - Updated Final Safety Analysis Report (UFSAR)

Eliminated the Need for On-Site Rainbow Pumps

(6) QC-S-2021-0021, Revision 0 - Nuclear Fuels Transition to GNF3 at Quad Cities (Dose Calculations Only)

(7) QC-S-2021-0013, Revision 0 - Permanently Remove Unit 1 Main Turbine Bearing Number 8 Metal Temperature Indication

(8) QC-S-2021-0030, Revision 0 - Setpoint Change 2B Reactor Building Closed Cooling Water (RBCCW) Pump

(9) QC-S-2020-0002, Revision 0 - Unit 2 Install 5 Isolation Valves in Safety-Related Service Water Piping on Each Emergency Core Cooling System (ECCS) Room Cooler Supply Piping

(10) QC-S-2019-0010, Revision 0 - Injection of Standby Liquid Control

(11) QC-S-2019-0006, Revision 0 - Change Gearing in Motor Operated Valves (MOVs)2-0220-1 and 2-0220-2 to Increase Margin

(12) QC-S-2019-0005, Revision 0 - Install Close Torque Switch Bypass and Change Gearing to Improve Margin in MOV-2-1001-26A

(13) QC-S-2019-0016, Revision 0 - Evaluation of Engineering Change 627158 /

Procedure Revision of QCOP 0250-09 Making MOVs1(2)-0220-2 Throttleable

(14) QC-S-2019-0021, Revision 0 - Quad Cities Standby Gas Treatment (SBGT) System Drawdown Analysis and Increased Main Steam Isolation Valve (MSIV) Leakage Impact

(15) QC-S-2019-0045, Revision 0 - Updated Final Safety Analysis Report (UFSAR)

Update to Better Align with Spent Fuel Pool (SFP) Analysis for Nucleate Boiling

(16) QC-S-2020-0026, Revision 0 - Wetwell Pressure Profile and Residual Heat Removal System (RHR) / Core Spray (CS) Net Positive Suction Head (NSPH) at 3%

Containment

(17) QC-S-2020-0056, Revision 0 - RBCCW Temperature Control Valve Internal Retrofit

(18) QC-S-2022-0004, Revision 0 - Install Switchable Jumper to Bypass 2-2002-97 Level Transmitter

(19) QC-S-2018-0034, Revision 0 - Off Gas Isolation Loss of Power / Air Vulnerability

(20) QC-S-2019-0004, Revision 0 - Digital Electro Hydraulic Control (DEHC), Main Stop Valve (MSV) Linear Voltage Differential Transducers (LVDT) Alarm Bypass

(21) QC-S-2020-0009, Revision 0 - Implementation of New Quad Cities Units 1 and 2 ATRIUM 10 XM Loss of Coolant Accident (LOCA) Break Spectrum Analysis with Increased Automatic Depressurization System (ADS) Flow

(22) QC-S-2022-0008, Revision 0 - Cut and Cap the Half Inch Reactor Head Vent Line

(23) QC-E-2020-002, Revision 0 - Power Recovery Via BELSIM Data Validation and Reconciliation Methodology

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

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

On May 27, 2022, the inspectors presented the triennial inspection of evaluation of changes, tests and experiments baseline inspection results to Drew Griffiths, Plant Manager and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.17T Calculations GE-NE-A22-Task TO603: Fuel Pool Cooling and CleanUp System (Quad 1A

00103-049-02 Cities 1 & 2)

GE-NE-A22-Task T0400: Containment System Response Dresden and 1A

00103-08-01 Quad Cities Extended Power Uprate (EPU)

QDC-0000-N-Dose and Dose Rate Scaling Factors to Evaluate Impact of 1A

22 EPU on Radiological Equipment Qualification and Vital

Access

QDC-0000-N-Quad Cities Units 1 and 2 Technical Support Center (TSC) 0 and 1

2342 Post-Loss of Coolant Accident (LOCA) Alternate Source

Term (AST) Analysis

QDC-1000-M-Quad Cities Extended Power Uprate Evaluation of Residual 1A

1019 Heat Removal (RHR) / Core Spray (CS) Net Positive Suction

Head (NPSH) Analysis: Post-LOCA for Short and Long

Term Events

TSC-004 30-Day Post - LOCA Doses in TSC Building 1

Corrective Action AR 04503410 NRC 50.59 Inspection Identified Completeness Issues with 06/02/2022

Documents 50.59 Evaluation

Resulting from

Inspection

Engineering EC 627158 Evaluation of Procedure Changes to QCOP 0250-09 Making 0

Changes Motor Operated Valves (MOVs) 1(2)-0220-2 Throttleable

EC 630848 Wetwell Pressure Profile & RHR / CS NPSH at 3% 0

Containment Leakage

Engineering QC-E-2017-002 50.59 Evaluation for UFSAR Change that Eliminated the 0

Evaluations Rainbow Pump from Onsite to a Leasing Facility to Respond

to a Lock and Dam Failure Down Stream of Quad Cities

Plant

QC-E-2018-001 50.59 Evaluation for Engineering Change (EC) 404570 and 2

404571, Off Gas Isolation Loss of Power/Air Vulnerability

QC-E-2020-001 50.59 Evaluation for EC 632028, MO (1)2-0220-2 Setup with 1

Lower Closing Thrust at Torque Switch Trip than that

Required by the Sizing Calculation

Inspection Type Designation Description or Title Revision or

Procedure Date

QC-E-2020-002 50.59 Evaluation for EC 632119 and 632145 - Power 0

Recovery via BESLIM Data Reconciliation and Validation

(DVR) Method

QC-E-2020-003 50.59 Evaluation to Revise Procedure CC-QC-409 for Use of 0

EntelliGuard Trip Units in Safety-Related Applications

QC-E-2021-002 50.59 Evaluation for ECs 629264 and 629265, Nuclear Fuels 0

Transition to GNF3 at Quad Cities (Dose Calculations Only)

QC-S-2018-0034 50.59 Screening for Off Gas Isolation Loss of Power/Air 0

Vulnerability

QC-S-2019-0004 50.59 Screening to Install/Remove Forced Signal for Main 0

Stop Valves' Linear Voltage Differential Transducer Nuisance

Alarms

QC-S-2019-0005 50.59 Screening to Install Close Torque Switch Bypass and 0

Change Gearing to Improve Margin in MOV 2-1001-26A

QC-S-2019-0006 50.59 Screening to Change Gearing in MOVs 2-0220-1 and 0

2-0220-2 to Increase Margin

QC-S-2019-0010 50.59 Screening for Standby Liquid Control Two Pump 13

Operation

QC-S-2019-0016 50.59 Screening for EC 627158 / Procedure Revision of 0

QCOP 0250-09 Making MOVs1(2)-0220-2 Throttleable

QC-S-2019-0021 50.59 Screening for EC 626084, Quad Cities Standby Gas 0

Treatment System Drawdown Analysis and Increased Main

Steam Isolation Valve (MSIV) Leakage Impact

QC-S-2019-0045 50.59 Screening for EC 628372, Updated Final Safety 0

Analysis Report (UFSAR) Update to Better Align with Spent

Fuel Pool (SFP) Analysis for Nucleate Boiling

QC-S-2020-0002 50.59 Screening to Install 5 Isolation Valves in Safety - 1

Related Service Water Piping on Each Emergency Core

Cooling System (ECCS) Room Cooler Supply Piping

QC-S-2020-0009 50.59 Screening for Quad Cities Units 1 and 2 ATRIUM 0

10XM Loss of Coolant Accident (LOCA) Break Spectrum

Analysis with Increased Automatic Depressurization System

(ADS) Flow

QC-S-2020-0026 50.59 Screening for EC 630848, Wetwell Pressure Profile & 0

Inspection Type Designation Description or Title Revision or

Procedure Date

RHR / CS NPSH at 3% Containment Leakage

QC-S-2020-0056 50.59 Screening for EC 627226, Reactor Building Closed 0

Cooling Water (RBCCW) Temperature Control Valve Internal

Retrofit

QC-S-2021-0013 50.59 Screening to Permanently Remove Unit 1 Main 0

Turbine Bearing #8 Metal Temperature Indication

QC-S-2021-0021 50.59 Screening for Nuclear Fuels Transition to GNF3 at 0

Quad Cities (Dose Calculation Only)

QC-S-2021-0030 50.59 Screening to Adjust Setpoint for Bus 29 Cubicle 5C, 0

2B RBCCW Pump Motor Feed Breaker

QC-S-2022-0004 50.59 Screening for EC 636096 to Install Switchable Jumper 0

to Bypass 2-2002-97 Level Transmitter

QC-S-2022-008 50.59 Screening to Temporarily Cut and Cap the Half Inch 0

Reactor Head Vent Line

Procedures LS-AA-104 Exelon 50.59 Review Process 12

LS-AA-104-1000 Exelon 50.59 Resource Manual 14

QCOP 0250-09 Controlling the Reactor Cavity Level Using the Main Steam 1

Lines

7