IR 05000254/2022012
| 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:
Report Numbers:
05000254/2022012 and 05000265/2022012
Enterprise Identifier:
I-2022-012-0017
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
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
Procedure
Type
Designation
Description or Title
Revision or
Date
GE-NE-A22-
00103-049-02
Task TO603: Fuel Pool Cooling and CleanUp System (Quad
Cities 1 & 2)
1A
GE-NE-A22-
00103-08-01
Task T0400: Containment System Response Dresden and
Quad Cities Extended Power Uprate (EPU)
1A
QDC-0000-N-
22
Dose and Dose Rate Scaling Factors to Evaluate Impact of
EPU on Radiological Equipment Qualification and Vital
Access
1A
QDC-0000-N-
2342
Quad Cities Units 1 and 2 Technical Support Center (TSC)
Post-Loss of Coolant Accident (LOCA) Alternate Source
Term (AST) Analysis
and 1
QDC-1000-M-
1019
Quad Cities Extended Power Uprate Evaluation of Residual
Heat Removal (RHR) / Core Spray (CS) Net Positive Suction
Head (NPSH) Analysis: Post-LOCA for Short and Long
Term Events
1A
Calculations
TSC-004
30-Day Post - LOCA Doses in TSC Building
Corrective Action
Documents
Resulting from
Inspection
NRC 50.59 Inspection Identified Completeness Issues with
50.59 Evaluation
06/02/2022
Evaluation of Procedure Changes to QCOP 0250-09 Making
Motor Operated Valves (MOVs) 1(2)-0220-2 Throttleable
Engineering
Changes
Wetwell Pressure Profile & RHR / CS NPSH at 3%
Containment Leakage
QC-E-2017-002
50.59 Evaluation for UFSAR Change that Eliminated the
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
404571, Off Gas Isolation Loss of Power/Air Vulnerability
Engineering
Evaluations
QC-E-2020-001
50.59 Evaluation for EC 632028, MO (1)2-0220-2 Setup with
Lower Closing Thrust at Torque Switch Trip than that
Required by the Sizing Calculation
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
QC-E-2020-002
50.59 Evaluation for EC 632119 and 632145 - Power
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
EntelliGuard Trip Units in Safety-Related Applications
QC-E-2021-002
50.59 Evaluation for ECs 629264 and 629265, Nuclear Fuels
Transition to GNF3 at Quad Cities (Dose Calculations Only)
QC-S-2018-0034
50.59 Screening for Off Gas Isolation Loss of Power/Air
Vulnerability
QC-S-2019-0004
50.59 Screening to Install/Remove Forced Signal for Main
Stop Valves' Linear Voltage Differential Transducer Nuisance
Alarms
QC-S-2019-0005
50.59 Screening to Install Close Torque Switch Bypass and
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
2-0220-2 to Increase Margin
QC-S-2019-0010
50.59 Screening for Standby Liquid Control Two Pump
Operation
QC-S-2019-0016
50.59 Screening for EC 627158 / Procedure Revision of
QCOP 0250-09 Making MOVs1(2)-0220-2 Throttleable
QC-S-2019-0021
50.59 Screening for EC 626084, Quad Cities Standby Gas
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
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 -
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
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 &
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
RHR / CS NPSH at 3% Containment Leakage
QC-S-2020-0056
50.59 Screening for EC 627226, Reactor Building Closed
Cooling Water (RBCCW) Temperature Control Valve Internal
Retrofit
QC-S-2021-0013
50.59 Screening to Permanently Remove Unit 1 Main
Turbine Bearing #8 Metal Temperature Indication
QC-S-2021-0021
50.59 Screening for Nuclear Fuels Transition to GNF3 at
Quad Cities (Dose Calculation Only)
QC-S-2021-0030
50.59 Screening to Adjust Setpoint for Bus 29 Cubicle 5C,
2B RBCCW Pump Motor Feed Breaker
QC-S-2022-0004
50.59 Screening for EC 636096 to Install Switchable Jumper
to Bypass 2-2002-97 Level Transmitter
QC-S-2022-008
50.59 Screening to Temporarily Cut and Cap the Half Inch
Reactor Head Vent Line
Exelon 50.59 Review Process
Exelon 50.59 Resource Manual
Procedures
QCOP 0250-09
Controlling the Reactor Cavity Level Using the Main Steam
Lines
1