IR 05000254/2021010
| ML21328A052 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 11/24/2021 |
| From: | Karla Stoedter NRC/RGN-III/DRS/EB2 |
| To: | Rhoades D Exelon Generation Co, Exelon Nuclear |
| References | |
| IR 2021010 | |
| Download: ML21328A052 (10) | |
Text
SUBJECT:
QUAD CITIES NUCLEAR POWER STATION - DESIGN BASIS ASSURANCE INSPECTION (PROGRAMS) INSPECTION REPORT 05000254/2021010 AND 05000265/2021010
Dear Mr. Rhoades:
On November 18, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Quad Cities Nuclear Power Station and discussed the results of this inspection with Mr. B. Wake, 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 2 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:
05000254/2021010 and 05000265/2021010
Enterprise Identifier:
I-2021-010-0057
Licensee:
Exelon Generation Company, LLC
Facility:
Quad Cities Nuclear Power Station
Location:
Cordova, IL
Inspection Dates:
November 01, 2021 to November 18, 2021
Inspectors:
B. Daley, Senior Reactor Inspector
M. Jones, Reactor Inspector
B. Jose, Senior Reactor Inspector
Approved By:
Karla K. Stoedter, Chief
Engineering Branch 2
Division of Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a design basis assurance inspection (programs) 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.
Starting on March 20, 2020, in response to the National Emergency declared by the President of the United States on the public health risks of the coronavirus (COVID-19), inspectors were directed to begin telework. In addition, regional baseline inspections were evaluated to determine if all or a portion of the objectives and requirements stated in the IP could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable IP. In some cases, portions of an IP were completed remotely and on site. The inspections documented below met the objectives and requirements for completion of the IP.
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:
a.
Determined 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.
Determined whether the sampled POVs are capable of performing their design-basis functions.
c.
Determined 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.
Evaluated maintenance activities including a walkdown of the sampled POVs (if accessible).
(1)1-2301-004-MO; High Pressure Coolant Injection (HPCI) Inboard Steam Supply from Reactor Pressure Vessel (RPV) Primary Containment Isolation Valve (PCIV)
(2)2-1301-017-MO; Reactor Core Isolation Cooling (RCIC) Turbine Steam Supply from RPV PCIV (3)1-1001-026A-MO; Residual Heat Removal (RHR) A Loop Inboard Drywell Spray PCIV (4)2-0302-022A-AO; Control Rod Drive Scram Discharge Volume Drain Valve (5)2-0203-001A-AO; 1A Inboard Main Steam Isolation Valve (6)1-1201-005-MO; Reactor Water Cleanup Outboard PCIV (7)2-1001-005B-MO; RHR Service Water B Loop Flow Control Valve (8)2-1001-016A-MO; RHR A Loop Heat Exchanger Bypass Line Isolation Valve (9)2-2301-005-MO; HPCI Outboard Steam Supply from RPV PCIV (10)2-1001-034B-MO; RHR B Loop Torus Cooling and Spray Isolation 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 November 18, 2021, the inspectors presented the design basis assurance inspection (programs) inspection results to Mr. B. Wake, Site Vice President and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2N3585
Main Steam Isolation Valve (MSIV) Calculation Bases for
Minimum Air Supply Pressure
2/03/2014
04692920
C Residual Heat Removal (RHR) Service Water Pump
Comprehensive Test
06/18/2019
0591-544-03
Motor Operated Valve (MOV) Accumulator 1-220-82A
Capacity Check
27.02000.1100
MOV Structural Integrity Calculation
AOV-MEDP-
QDC-RX-002
Inboard Main Steam Isolation Valve - Design Basis
Calculation Report
AOV-MEDP-
QDC-RX-002
Inboard Main Steam Isolation Valve
MIDACALC QUA-
2-1001-5B
MIDACALC Results
NED-M-MSD-075
The Thrust Seismic Limits of the Quad Cities Non-Mark I
0A
QC-MISC-010
Quad Cities MOV Risk Ranking Input
003
QDC-0203-M-
0968
Main Steam Isolation Valves Sizing Calculation
QDC-0203-M-
0968
Main Steam Isolation Valve Sizing Calculation
QDC-1000-M-
1318
Residual Heat Removal System Combined Design Basis
Document and Differential Pressure Calculation
000
QDC-1000-S-
27
Review of Flowserve Seismic and Maximum Thrust
Analysis Report RAL-20588 for FLowserve 12" Class 300
Carbon Steel Globe Valve with SMB-0-25
QDC-1200-M-
1319
Reactor Water Cleanup (RWCU) System Combined
Design Basis Document and Differential Pressure
Calculation
000
QUA-1-1201-5
MIDACALC Results QUA-1-1201-5
QUA-2-1001-16A
MIDACALC Results QUA-1-1001-16A
71111.21N.02
Calculations
RAL-70296
Weak Link Supplement to Report R89.124 Analysis of the
Stem-Wedge Threaded and Pinned Connection
03/05/2018
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
04116815
MO 2-1301-16 Reactor Core Isolation Cooling (RCIC)
Inboard Valve Local Leak Rate Exceeds Alert Limit
04/19/2018
04132420
Main Steam Isolation Valves 2-0203-1A and 2-0203-1C
Closure Times Exceeded the Maximum Technical
Specification Limit of 5 Seconds
03/19/2018
Corrective Action
Documents
04442618
Power Operated Valve Self-Assessment GAP Discovered
on 1-1001-26A MIDAS Calculation
11/01/2021
04458885
NRC POV DBAI QUA-2-2301-5, MIDAS Calculation
Revision
11/05/2021
Corrective Action
Documents
Resulting from
Inspection
04461879
NRC DBAI POV: SharePoint Issues for External Users
11/18/2021
DR-33834
18" - 300 Pound Cast Steel Globe Valve
09/27/1968
DR-34289
Inch Y Pattern Globe Valve
M-79
Diagram of RHR Service Water Piping
BJ
Drawings
M-81
Diagram of RHR Piping
BL
Application to Revise Technical Specifications to Adopt
Technical Specifications Task Force (TSTF)-545
07/26/2016
Miscellaneous
NA
Quad Cities Station 180-Day Response to Generic Letter
(GL) 95-07
11/09/1995
Preventive Maintenance Program
Equipment Classification
Maintenance Strategy Analysis
Final Joint Owners Group (JOG) MOV Periodic
Verification Program Implementation
Post Maintenance Testing
Predictive Maintenance Program
NES-EIC-10.02
Standard for Thermal Overload Relay Element Selection
for Motor Operated Valves
Procedures
NES-MS-06.6
MOV Valve Factors
00587694
Stem Needs Replacement 2-1301-17
01/20/2004
00979119
Perform Mechanical MOV Inspection Only 2-1001-16A
08/01/2011
01010549
Open and Inspect Valve for Corrosion/Erosion
03/05/2008
01126921
Replace MO 2-1001-5B IN Q2R20
2/10/2009
Work Orders
255655
Mechanical Inspection and Stem Lube (MOV) 1-1201-5
2/12/2011
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
01470514
Prog Diagnostic Test - MOV 2-1001-16A PMID 25505-01
10/07/2011
01547997
Perform Static Testing MO 2-1301-17
04/25/2014
01578831
Prog Mechanical Inspection and Stem Lube (MOV)
2/03/2014
01611462
MOV Grease Inspection and Stem Lube 2-1301-17
04/10/2014
01630656
High Pressure Coolant Injection Steam Supply Local Leak
Rate Test (LLRT)
03/02/2015
01722591
Perform Borescope Inspection on MOV 2-1001-16A
2/07/2015
01752229
1A MSIV Air/Hydraulic O/H
10/09/2015
01775693
Program Diagnostic Test
2/06/2016
01794491
RHR B Loop Valve Position Indication
06/12/2016
01819374
03/27/2017
01819403
Prog Mechanical Inspection and Stem Lube (MOV)
07/03/2017
01834738
Program Diagnostic Test
10/15/2016
01908235
RCIC Steam Supply LLRT In-Service Test (IST)
03/19/2018
01908692
MOV Grease Inspection and Stem Lube 2-1001-16A
2/06/2017
01916764
LLRT - Main Steam Isolation Valves (IST)
03/11/2018
01933785
Perform Diagnostic Test MO 2-1001-16A
10/16/2017
01955867
Drywell Valve Position Indication Verification (IST)
04/04/2018
04580778
RHR B Loop Valve Position Indication (IST)
06/12/2018
04620642
Mechanical Maintenance (MM) Part 21 Action Item for
MOV 1-1201-5 IN Q1R25
11/08/2018
0462944
HPCI Low-Medium Risk Power Operated Valve Test
03/22/2019
04682289
Drywell Valve Position Indication Verification (IST)
04/04/2019
04682302
Reactor Water Cleanup (RWCU) Valve Timing Test (IST)
03/21/2019
04687701
Replace Flexible Hose - 'A' Inboard Main Steam Isolation
Valve
04/02/2020
04690786
Electrical Maintenance Perform Diagnostic Test
MO 1-1201-5
03/19/2021
04712364
03/11/2019
0471941
MM Replace Q2R24 2-0203-1A MSIV Airpack Manifold
03/21/2018
04798515
03/23/2020
04800217
Drywell Valve Position Indication Verification Test (IST)
04/12/2020
04818043
LLRT - Main Steam Isolation Valves (IST)
03/30/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
04914708
03/08/2021
04918468-24
HPCI Preventive Maintenance Tests (PMTs) Required
Prior to Mode 2
04/12/2020
04918468-25
RCIC PMTs Required Prior to Mode 2
04/12/2020
04962559
HPCI Low-Medium Risk Power Operated Valve Test
03/19/2021
0497715
03/24/2021
05010921
Lube MO 1-1201-5 Valve Stem
03/15/2021
05073968
11/22/2020
05120452
Scram Discharge Volume (SDV) Vent and Drain Valve
Test
04/21/2021
05140184
Drywell Valve Position Indication Verification
03/29/2021
RHR Low Risk Power Operated Valve Test
2/12/2019
RCIC Low-Medium Risk Power Operated Valve Test
04/02/2020
RHR Low Risk Power Operated Valve Test
05/27/2020
RHR Low Risk Power Operated Valve Test
10/21/2020
Scram Discharge Volume (SDV) Vent and Drain Valve
Test
10/21/2020
SDV Vent and Drain Valve Test
01/19/2021
SDV Vent and Drain Valve Test
04/21/2021