IR 05000254/2020004
| ML21036A002 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 02/04/2021 |
| From: | Kenneth Riemer Division Reactor Projects III |
| To: | Rhoades D Exelon Generation Co |
| References | |
| IR 2020004 | |
| Download: ML21036A002 (15) | |
Text
February 4, 2021
SUBJECT:
QUAD CITIES NUCLEAR POWER STATION - INTEGRATED INSPECTION REPORT 05000254/2020004 AND 05000265/2020004
Dear Mr. Rhoades:
On December 31, 2020, 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. K. Ohr, 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,
/RA/
Kenneth R. Riemer, Chief Branch 1 Division of Reactor Projects
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:
05000254/2020004 and 05000265/2020004
Enterprise Identifier: I-2020-004-0065
Licensee:
Exelon Generation Company, LLC
Facility:
Quad Cities Nuclear Power Station
Location:
Cordova, IL
Inspection Dates:
October 1, 2020 to December 31, 2020
Inspectors:
J. Cassidy, Senior Health Physicist
M. Garza, Emergency Preparedness Inspector
R. Murray, Project Engineer
D. Tesar, Senior Resident Inspector
C. Mathews, Illinois Emergency Management Agency
Approved By:
Kenneth R. Riemer, Chief
Branch 1
Division of Reactor Projects
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated 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
Type Issue Number Title Report Section Status LER 05000254,05000265/20 20-002-00 LER 2020-002-00 for Quad Cities Nuclear Power Station, Unit 1, Main Steam Line Drain Valve Declared Inoperable Due to Improper Torque Switch Setting 71153 Closed
PLANT STATUS
Unit 1
The unit began the inspection period at full-rated thermal power, where it remained for the entire inspection period, with the exception of planned power reductions for turbine testing, scram timing testing, control rod pattern adjustments, and other short-term power reductions as requested by the transmission system operator.
Unit 2
The unit began the inspection period at full-rated thermal power, where it remained for the entire inspection period, with the exception of planned power reductions for turbine testing, scram timing testing, control rod pattern adjustments, and other short-term power reductions as requested by the transmission system operator.
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 Disease 2019 (COVID-19), resident inspectors were directed to begin telework and to remotely access licensee information using available technology. During this time, the resident inspectors performed periodic site visits each week; conducted plant status activities as described in IMC 2515, Appendix D, Plant Status; observed risk-significant activities; and completed on-site portions of IPs. In addition, resident and regional baseline inspections were evaluated to determine if all or portions 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
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (2 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Unit 2 reactor core isolation cooling on October 26, 2020
- (2) Turbine building closed cooling water on October 26, 2020
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated system configurations during a complete walkdown of the control rod drive system on October 26, 2020.
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:
- (1) Fire Zone 8.2.2.A, Unit 2 turbine building, elevation 572'-6", control rod drive pumps on October 19, 2020
- (2) Fire Zone 8.2.7.C, Unit 1/2 turbine building, elevation 611'-6", turbine building closed cooling water area on October 19, 2020
- (3) Fire Zone 11.2.3, Unit 1 reactor building, elevation 554'-0", northwest corner room - 1A core spray on October 26, 2020
- (4) Fire Zone 11.3.1, Unit 2 reactor building, elevation 554'-0", southwest corner room - 2B core spray on October 26, 2020
71111.07A - Heat Sink Performance
Annual Review (IP Section 03.01) (1 Sample)
The inspectors evaluated readiness and performance of:
- (1) 1A residual heat removal thermal performance test on November 30, 2020
71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance
Requalification Examination Results (IP Section 03.03) (1 Sample)
- (1) The inspectors reviewed and evaluated the licensed operator examination failure rates for the requalification annual operating test which was administered between October 13 and November 17, 2020.
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (2 Samples)
- (1) The inspectors observed and evaluated licensed operator performance in the control room during downpower, rod pattern adjustment, and scram timing tests on October 20, 2020.
- (2) The inspectors observed and evaluated licensed operator performance in the control room during downpower, rod pattern adjustment, and turbine testing on November 7, 2020.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated observation of licensed operator requalification training on October 5, 2020.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (3 Samples)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components remain capable of performing their intended function:
- (1) High pressure coolant injection on November 30, 2020
- (2) Core spray on December 1, 2020
- (3) Turbine building closed cooling water on December 7, 2020
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (1 Sample)
The inspectors evaluated the accuracy and completeness of risk assessments for the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed:
- (1) Work week risk reviews and PARAGON updates on November 2, 2020
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (1 Sample)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Issue Report 4386700, "Pin-Hole Leaks 'B' HVAC [heating, ventilation, and air conditioning] System Operability," on November 30, 2020
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (3 Samples)
The inspectors evaluated the following temporary or permanent modifications:
- (1) Engineering Change 626394, "Install Bypass Switches for GRP 1 MSIV [main steam isolation valve] Isolation"
- (2) Engineering Change 395100, "Replace HPCI [high pressure coolant injection]
Obsolete Temperature Indicating Switches and Thermowells"
- (3) Engineering Change 621167, "RCIC [reactor core isolation cooling] Flow Controllers FIC 1(2)-1304-1 Upgrade"
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated the following post-maintenance test activities to verify system operability and functionality:
- (1) Standby gas treatment post-maintenance testing QCOS-7500-05, -06, -07 on October 22, 2020
- (2) Station blackout diesel quarterly on October 29, 2020
- (3) Unit 2 emergency diesel generator following 12-year preventive maintenance on November 5, 2020
- (4) QCOS 1400-1, "'B' Core Spray Pump Flow Rate Test," on November 16, 2020
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Surveillance Tests (other) (IP Section 03.01)
- (1) QCOS 1000-04, "RHR [residual heat removal] Service Water Pump 'B' Flow (IST),"
on October 22, 2020
FLEX Testing (IP Section 03.02) (1 Sample)
- (1) Emergency portable pump (B.5.B/FLEX) on November 7, 2020
71114.04 - Emergency Action Level and Emergency Plan Changes
Inspection Review (IP Section 02.01-02.03) (1 Sample)
- (1) The inspectors completed an evaluation of submitted emergency action level and emergency plan changes on December 2, 2020. This evaluation does not constitute NRC approval.
71114.06 - Drill Evaluation
Drill/Training Evolution Observation (IP Section 03.02) (2 Samples)
The inspectors evaluated:
- (2) Emergency preparedness drill - contaminated injured man on December 9,
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below:
MS07: High Pressure Injection Systems (IP Section 02.06)===
- (1) Unit 1 (10/01/2019-09/30/2020)
- (2) Unit 2 (10/01/2019-09/30/2020)
MS08: Heat Removal Systems (IP Section 02.07) (2 Samples)
- (1) Unit 1 (10/01/2019-09/30/2020)
- (2) Unit 2 (10/01/2019-09/30/2020)
MS09: Residual Heat Removal Systems (IP Section 02.08) (2 Samples)
- (1) Unit 1 (10/01/2019-09/30/2020)
- (2) Unit 2 (10/01/2019-09/30/2020)
MS10: Cooling Water Support Systems (IP Section 02.09) (2 Samples)
- (1) Unit 1 (10/01/2019-09/30/2020)
- (2) Unit 2 (10/01/2019-09/30/2020)
BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10) (2 Samples)
- (1) Unit 1 (10/01/2019-09/30/2020)
- (2) Unit 2 (10/01/2019-09/30/2020)
OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)
(1)
(10/01/2019-09/30/2020)
PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent Occurrences Sample (IP Section 02.16) (1 Sample)
(1)
(04/01/2019-09/30/2020)
71152 - Problem Identification and Resolution
Semiannual Trend Review (IP Section 02.02) (2 Samples)
The inspectors reviewed the licensees corrective action program for potential adverse trends in:
- (1) Elevated offgas flow and radiation monitor adjustments on November 9, 2020, that might be indicative of a more significant safety issue.
- (2) Control rod drive hydraulic accumulator unit trend review on December 14, 2020, that might be indicative of a more significant safety issue.
Annual Follow-up of Selected Issues (IP Section 02.03) (1 Partial)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
(1)
(Partial)
Issue Report 4371385, "[Unit] 1C RHRSW [residual heat removal service water] Seal Cooling Line Break," follow-up on December 9, 2020
71153 - Follow-up of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02)
The inspectors evaluated the following licensee event reports (LERs): LER 2020-002-00 for Quad Cities Nuclear Power Station, Unit 1, Main Steam Line Drain Valve Declared Inoperable Due to Improper Torque Switch Setting
- (1) LER 2020-002-00, Quad Cities Nuclear Power Station, Unit 1, Main Steam Line Drain Valve Declared Inoperable Due to Improper Torque Switch Setting (ADAMS Accession No. ML20315A447). The inspection conclusions associated with this LER are documented in NRC Integrated Inspection Report 05000254; 05000265/2020003 under Inspection Results Section
INSPECTION RESULTS
Observation: Follow-Up of Residual Heat Removal Service Water Low Pressure Pump Seal Line Break 71152 As documented in NRC Integrated Inspection Report 05000254; 05000265/2020003, the inspectors noted that on September 23, 2020, the licensee generated Issue Report 4371385, "Documenting a Seal Cooling Line Leak from the Unit 1C RHRSW Pump." The inspectors walked down the pump on the same day and noted that the seal cooling line had sheared at a union elbow joint. Additionally, the inspectors noted the piping at the elbow was completely blocked with debris and/or corrosion products and discussed with the licensee. The licensee documented the as found conditions in Issue Report 4371588, "As Found Condition of 1C RHRSW Pump Seal Cooling Line Leak," on September 23, 2020. The inspectors performed additional inspection activities to review the licensee's causal evaluation, and corrective actions associated with this issue during this inspection period as indicated in NRC Integrated Inspection Report 05000254; 05000265/2020003.
The inspectors reviewed the work group evaluation associated with Issue Report 4371385 as well as the documented response from the vendor regarding the loss of seal water flow to the RHRSW pump low pressure seals. In addition, inspectors reviewed the actions from Issue Reports 4371385 and 4371588.
All actions from Issue Report 4371588 are documented as complete with no issues identified.
Actions from Issue Report 4371385 are in progress with extent-of-condition work orders generated and scheduled for completion during the next available work windows for each of the remaining RHRSW pumps. In addition, Action Item 02 to evaluate the need for scheduled preventive maintenance on the low-pressure pump seal lines is in progress and scheduled for completion on January 21, 2021.
The inspectors reviewed the work group evaluation and vendor response associated with Issue Report 4371385. The inspectors requested clarification of statements in the work group evaluation. All questions have been resolved with no additional concerns identified.
The inspectors did identify that the low-pressure seal water piping was not included in the aging management program, the preventive maintenance program, nor were there steps included in the scheduled scope of work to disassemble, clean or inspect the low-pressure seal water piping. The inspectors did not identify any violations of procedural or regulatory requirements during this review.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On December 31, 2020, the inspectors presented the integrated inspection results to Mr. K. Ohr, Site Vice President, and other members of the licensee staff.
- On December 16, 2020, the inspectors presented the licensed operator annual exam inspection results to Mr. R. Ramsay, Operations Training Manager, and other members of the licensee staff.
- On December 17, 2020, the inspectors presented the IP 71114.04 exit meeting inspection results to Mr. D. Moore, Senior Manager - Emergency Preparedness, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
QCOP 0300-01
CRD System Startup and Operation
QCOP 0300-02
CRD System Shutdown
QCOP 1300-01
RCIC System Preparation for Standby Operation
QCOP 3800-02
Unit 1 TBCCW System Operation
QCOP 3800-03
Unit 2 TBCCW System Operation
QOM 1-3800-01
Unit 1 TBCCW Valve Checklist
QOM 2-3800-01
Unit 2 TBCCW Valve Checklist
Fire Plans
FZ 11.2.3
Unit 1 RB 554'-0" Elev. NW Corner Room - 1A Core Spray
November
2011
FZ 11.3.1
Unit 2 RB 544'-0" Elev. SW Corner Room - 2B Core Spray
October
2013
FZ 8.2.2.A
Unit 2 Turbine Building, Elevation 572'-6", Control Rod Drive
Pumps
October
2019
FZ 8.2.7.C
Unit 1/2 Turbine Building, Elevation 611'-6", Turbine Building
Closed Cooling Water Area
October
2019
71111.07A Work Orders
1A RHR HX Thermal Performance Test
11/30/2020
Corrective Action
Documents
1B TBCCW Hx Requires Additional Maintenance
11/25/2019
1A TBCCW Hx Requires Additional Maintenance
2/17/2019
Abnormal Pressure on Keepfill During 2A Core Spray
Surveillance
2/30/2019
2-3 C-4 Core Spray Pump 'A' High Seal Leakage Alarm
Received
03/25/2020
Q2R25 As-Left LLRT on HPCI MO 2-2301-5 Exceeds Alert
04/09/2020
Light to Moderate Corrosion Observed During HPCI
Walkdown
04/22/2020
EO ID's Excessive No Flow Time During HPCI Venting
06/01/2020
U2 HPCI Check Valve Response During QCOS 2300-11
06/04/2020
Unexpected 2B Core Spray Header Low Pressure Alarm
06/11/2020
U2 HPCI Room Temp High
06/16/2020
Suspected Crack/Flange Leak in 2B Core Spray Floor Drain
07/30/2020
U2 HPCI TG MGU Signal Converter Display Not Functioning
08/15/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
U2 HPCI Check Valve Response During QCOS 2300-11
09/04/2020
EO ID: 2B TBCCW Pump Oil Leak
09/22/2020
Corrective Action
Documents
Pin-Hole Leaks Found at Weld for 0-5799-381 'B' HVAC
Train
11/27/2020
Engineering
Changes
N-513 Evaluation for Line 1/2-57479-2 1/2" Through-Wall
Leak
Operability
Evaluations
Op Eval 633095
CR HVAC 'B' Train Piping Line 0-57479-2 1/2" Through-Wall
Leak
Procedures
Operability Determinations (CM-1)
Engineering
Changes
EC 395100, Rev.
001
Replace HPCI Obsolete Temperature Indicating Switches
and Thermowells
04/03/2019
EC 621167, Rev.
000
RCIC Flow Controllers FIC 1(2)-1340-1 Upgrade
01/08/2020
EC 626394, Rev.
000
U-2 Install Bypass Switches for -59" Group 1 MSIV Isolation
2/03/2019
Work Orders
Replace U2 HPCI TIS 2-2341-3B
09/02/2020
Failed Instrument, TIS 2-2341-2B
09/02/2020
Install Bypass Switches for GRP 1 MSIV Isolation 626394
04/16/2020
Procedures
QCOS 1400-01
Core Spray System Flow Rate Test
QCOS 1400-10
Core Spray Operability Verification
QCOS 6600-42
Unit 2 Emergency Diesel Generator Load Test
QCOS 6600-45
Unit 2 Diesel Generator Timed Start Test
QCOS 6620-01
SBO DG 1(2) Quarterly Load Test
QCOS 7500-05
SBGTS Monthly Operability Test
QCOS 7500-06
SBGTS Power Operated Valve Test
QCOS 7500-07
SBGT System 24-Month Operability Test
Procedures
OP-AA-201-010-
1001
Mitigating Strategies Equipment Expectations
QCOS 1000-04
RHR Service Water Pump Operability Test
Work Orders
(Flex) Emergency Portable Pump (B.5.B/Flex)
11/07/2020
Corrective Action
Documents
Perform an Impact Review of EAL Revisions for EOP/SAMG
Revision 4
03/10/2020
EP FAQ EAL Change License Amendment Implementation
03/20/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Actions
NOS ID: Revise Standardized Emergency Plan
03/26/2020
Emergency Plan: CDAM 50.54(q) Potential Deficiencies
04/09/2020
Miscellaneous
Eval No. 19-29
Exelon Nuclear Standardized Radiological Emergency Plan
09/04/2019
Eval No. 19-65
Exelon Nuclear Standardized Radiological Emergency Plan
09/06/2019
Eval No. 19-79
Various Station Emergency Plan Annexes
11/08/2019
Eval No. 19-80
On-Shift Staffing Assessments
11/08/2019
Eval No. 20-28
EALs for Quad Cities Station
03/24/2020
71151
Miscellaneous
CY-QC-120-720,
Actual Dose Data - Unit 1
April 2019 -
September
20
CY-QC-120-720,
Actual Dose Data - Unit 2
April 2019 -
September
20
Monthly Data Elements for NRC ROP Indicator - Reactor
Coolant System (RCS) Specific Activity
October
2019 -
September
20
A
Site Performance Indicator Information
October
2019 -
September
20
Corrective Action
Documents
U1 MCR Received Alarm 901-3 D2 Offgas High Radiation
2/13/2020
U1 MCR Received Alarm 901-3 D2 Offgas High Radiation
2/15/2020
Unexpected Receipt of 901-3 D-2 (Offgas High Rad)
06/30/2020
901-D2 Offgas High Radiation Alarm
07/14/2020
Offgas Rad Monitor Setpoint Need Adjusted
07/21/2020
Unexpected Offgas High Radiation Alarm
08/14/2020
U1C RHRSW Pump Seal Line Leak
09/23/2020
As Found Condition of 1C RHRSW Pump Seal Cooling Line
Leak
09/23/2020
Offgas Rad Monitor Setpoints Need Adjusted
11/08/2020
'B' CREV HVAC AHU Motor Overload
11/11/2020
2D RHR Pump Breaker Auxiliary Contracts High Resistance
2/09/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
CY-QC-170-301
Offsite Dose Calculation Manual (ODCM) Special
Distribution (Change SRRS ID Number to 2C.110 Before
Archiving)
14