IR 05000413/2021003
| ML21301A063 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 10/28/2021 |
| From: | Eric Stamm NRC/RGN-II/DRP/RPB1 |
| To: | Simril T Duke Energy Carolinas |
| References | |
| IR 2021003 | |
| Download: ML21301A063 (12) | |
Text
October 28, 2021
SUBJECT:
CATAWBA NUCLEAR STATION - INTEGRATED INSPECTION REPORT 05000413/2021003 AND 05000414/2021003
Dear Mr. Simril:
On September 30, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Catawba Nuclear Station. On October 25, 2021, the NRC inspectors discussed the results of this inspection with you 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/
Eric J. Stamm, Chief Reactor Projects Branch 1 Division of Reactor Projects
Docket Nos. 05000413 and 05000414 License Nos. NPF-35 and NPF-52
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000413 and 05000414
License Numbers:
Report Numbers:
05000413/2021003 and 05000414/2021003
Enterprise Identifier: I-2021-003-0029
Licensee:
Duke Energy Carolinas, LLC
Facility:
Catawba Nuclear Station
Location:
York, South Carolina
Inspection Dates:
July 01, 2021 to September 30, 2021
Inspectors:
J. Austin, Senior Resident Inspector
D. Rivard, Acting Resident Inspector
C. Fontana, Emergency Preparedness Inspector
S. Sanchez, Senior Emergency Preparedness Inspector
J. Walker, Emergency Response Inspector
Approved By:
Eric J. Stamm, Chief
Reactor Projects 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 Catawba Nuclear 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
Valid Actuation of the Unit 2
System
Closed
PLANT STATUS
Unit 1 began the inspection period at or near 100 percent rated thermal power (RTP). It was
reduced to 15 percent RTP on August 27, 2021, to replace the main generator links. On
August 30, 2021, Unit 1 was returned to 100 percent RTP and remained at or near 100 percent
RTP for the remainder of the inspection period.
Unit 2 began the inspection period at or near 100 percent RTP. It was reduced to 18 percent
RTP on July 30, 2021, to stop a steam leak on steam generator shell side alternate sample
valve 2BB-1. Unit 2 was returned to 100 percent RTP on July 31, 2021, and remained at or
near 100 percent RTP for the remainder of the inspection period.
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), resident and
regional 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, increasing the amount of time on site as local COVID-19 conditions permitted.
As part of their onsite activities, resident inspectors conducted plant status activities as
described in IMC 2515, Appendix D; 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 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
71111.01 - Adverse Weather Protection
Impending Severe Weather Sample (IP Section 03.02) (1 Sample)
(1)
The inspectors evaluated the adequacy of the overall preparations to protect risk
significant systems from impending severe weather conditions associated with
Tropical Storm Elsa on July 8, 2021.
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (3 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following
systems/trains:
(1)
Unit 1 outside doghouse (main steam/feed penetration room) on July 19, 2021
(2)
1A and 2B emergency diesel generators on July 22, 2021
(3)
Units 1 and 2 service water pump house on July 23, 2021
Complete Walkdown Sample (IP Section 03.02) (2 Samples)
(1)
The inspectors evaluated system configuration during a complete walkdown of the
Unit 1A emergency diesel generator system on July 23, 2021.
(2)
The inspectors evaluated system configuration during a complete walkdown of the
safe shutdown facility (SSF) diesel generator and support systems on
September 21, 2021.
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (7 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)
Unit 1, Turbine Building, Elev. 568, Basement, SE Quadrant on September 21, 2021
(2)
Unit 1, Turbine Building, Elev. 568, Basement, NE Quadrant on September 21, 2021
(3)
Unit 1, Turbine Building, Elev. 568, Basement, NW Quadrant on September 21, 2021
(4)
Unit 1, Turbine Building, Elev. 568, Basement, SW Quadrant on September 21, 2021
(5)
Protected Area South, Standby Shutdown Facility, Elev. 594, Building 7748 on
September 21, 2021
(6)
Unit 2, Turbine Building, Elev. 568, Basement, NW Quadrant on September 23, 2021
(7)
Unit 2, Turbine Building, Elev. 568, Basement, SW Quadrant on September 23, 2021
71111.06 - Flood Protection Measures
Inspection Activities - Internal Flooding (IP Section 03.01) (1 Sample)
The inspectors evaluated internal flooding mitigation protections in the:
(1)
Work request (WR) 20209964, 2A emergency diesel generator (EDG) sequencer
hallway water leak above
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (1 Sample)
(1)
The inspectors observed the Unit 1 power increase on August 30, 2021, following
down power to repair main generator flexible links.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
(1)
The inspectors observed and evaluated simulator scenario recorded on
July 28, 2021, which contained failure of pressurizer spray valve, seal injection flow
control valve, control rod failure, reactor trip, loss of coolant accident (LOCA) from
residual heat removal (RHR) and LOCA outside containment.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (4 Samples)
The inspectors evaluated the effectiveness of maintenance to ensure the following
structures, systems, and components (SSCs) remain capable of performing their intended
function:
(1)
WR 20204373, water dripping from overhead in 2A EDG sequencer hallway, on
June 29, 2021
(2)
WR 20204789, seismic alarm will not clear for control room indications, on
July 4, 2021
(3)
Nuclear condition report (NCR) 2392855, sump pump conditions, on August 9, 2021
(4)
NCR 2393943, longstanding equipment issue for Unit 1 steam dumps, on
August 16, 2021
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (5 Samples)
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)
2A service water pump out of service (OOS) for maintenance, on July 6, 2021
(2)
2A service water pump OOS for maintenance, on July 7, 2021
(3)
2A EDG OOS for scheduled maintenance, on August 5, 2021
(4)
Unit 1 power reduction to repair main generator flexible links, on August 26, 2021
(5)
SSF diesel generator OOS for unscheduled maintenance, on September 13, 2021
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (6 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the
following operability determinations and functionality assessments:
(1)
NCR 2384415, B train component cooling miniflow valve failed low, on June 1, 2021
(2)
NCR 2388448, 2B EDG lube oil inlet/outlet low temperature alarm, on July 5, 2021
(3)
NCR 2388798, 2A service water motor offline electrical test incomplete, on
July 7, 2021
(4)
NCR 2390752, repair pinhole leaks on downstream weld of 2RN-190B, on
July 22, 2021
(5)
NCR 2393733, 1A EDG sensor fault, on August 14, 2021
(6)
NCR 2393733, 1A EDG sensor fault indication for engine lube oil channel on,
August 16, 2021
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (1
Sample)
The inspectors evaluated the following temporary or permanent modifications:
(1)
Engineering change (EC) 419999, single piece flat washer for main generator flexible
link connection, on August 27, 2021
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (6 Samples)
The inspectors evaluated the following post-maintenance test activities to verify system
operability and functionality:
(1)
WR 20205613, flushed sample line following EMF52 loss of flow alarms, on
July 16, 2021
(2)
Work Order (WO) 20402161, electronic software reset to reset/resolve 1A reactor
vessel level instrument inoperability, on July 29, 2021
(3)
WO 20484700, repaired leak on 2A EDG cylinder head jumper pipe and verified the
leak was repaired, on August 7, 2021
(4)
WR 20208313, replaced relay following the 2YV containment chilled water chiller to
start, on August 28, 2021
(5)
WO 20487506, performed thermography following repair/replacement of U1 main
generator flex links and load placed on main generator, on August 30, 2021
(6)
WO 20491701, retest SSF frequency control following troubleshooting of non-
responsiveness, on September 13, 2021
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Surveillance Tests (other) (IP Section 03.01) (2 Samples)
(1)
PT/2/A/4350/002B, 2B EDG operability test, on July 24, 2021
(2)
PT/1A/4600/002A, Mode 1 periodic surveillance items performed, on August 17, 2021
Inservice Testing (IP Section 03.01) (1 Sample)
(1)
PT/1/A/4250/003C, turbine driven auxiliary feedwater pump #1 performance test, on
September 10, 2021
RCS Leakage Detection Testing (IP Section 03.01) (1 Sample)
(1)
PT/1/A/4150/001D, reactor coolant system leakage calculation performed, on
August 9, 2021
FLEX Testing (IP Section 03.02) (1 Sample)
(1)
WO 20470816, reviewed results of Catawba Nuclear Station quarterly FLEX
equipment inspection conducted, on August 9, 2021
71114.02 - Alert and Notification System Testing
Inspection Review (IP Section 02.01-02.04) (1 Sample)
(1)
The inspectors evaluated the maintenance and testing of the alert and notification
system during the week of August 23, 2021.
71114.03 - Emergency Response Organization Staffing and Augmentation System
Inspection Review (IP Section 02.01-02.02) (1 Sample)
(1)
The inspectors evaluated the readiness of the Emergency Response Organization
during the week of August 23, 2021.
71114.04 - Emergency Action Level and Emergency Plan Changes
Inspection Review (IP Section 02.01-02.03) (1 Sample)
(1)
The inspectors evaluated submitted Emergency Action Level, Emergency Plan, and
Emergency Plan Implementing Procedure changes during the week of
August 23, 2021. This evaluation does not constitute NRC approval.
71114.05 - Maintenance of Emergency Preparedness
Inspection Review (IP Section 02.01 - 02.11) (1 Sample)
(1)
The inspectors evaluated the maintenance of the emergency preparedness program
during the week of August 23, 2021.
71114.06 - Drill Evaluation
Select Emergency Preparedness Drills and/or Training for Observation (IP Section 03.01) (1
Sample)
(1)
The inspectors evaluated a drill scenario which simulated loss of component cooling,
loss of charging, turbine load rejection, tornado on site, safety injection actuation, and
reactor trip, on September 27, 2021.
OTHER ACTIVITIES - BASELINE
71151 - Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below:
IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02) (2
Samples)
(1)
Unit 1 (July 1, 2020 - June 30, 2021)
(2)
Unit 2 (July 1, 2020 - June 30, 2021)
MS09: Residual Heat Removal Systems (IP Section 02.08) (2 Samples)
(1)
Unit 1 (July 1, 2020 - June 30, 2021)
(2)
Unit 2 (July 1, 2020 - June 30, 2021)
EP01: Drill/Exercise Performance (DEP) Sample (IP Section 02.12) (1 Sample)
(1)
Unit 1 (July 1, 2020 - June 30, 2021)
Unit 2 (July 1, 2020 - June 30, 2021)
EP02: Emergency Response Organization (ERO) Drill Participation (IP Section 02.13) (1
Sample)
(1)
Unit 1 (July 1, 2020 - June 30, 2021)
Unit 2 (July 1, 2020 - June 30, 2021)
EP03: Alert And Notification System (ANS) Reliability Sample (IP Section 02.14) (1 Sample)
(1)
Unit 1 (July 1, 2020 - June 30, 2021)
Unit 2 (July 1, 2020 - June 30, 2021)
71152 - Problem Identification and Resolution
Annual Follow-up of Selected Issues (IP Section 02.03) (2 Samples)
The inspectors reviewed the licensees implementation of its corrective action program
related to the following issues:
(1)
NCR 2390811, 2B EDG inadvertent auto start signal
(2)
NCR 2388357, 1B EDG bearing rotated
71153 - Follow Up of Events and Notices of Enforcement Discretion
Event Report (IP Section 03.02) (1 Sample)
The inspectors evaluated the following licensee event report (LER):
(1)
LER 05000414/2021-002-00, Valid Actuation of the Unit 2 Reactor Protection System
and Auxiliary Feedwater System (ADAMS Accession No. ML21180A302). The
inspection conclusions associated with this LER are documented in this report under
Inspection Results Section 71153.
INSPECTION RESULTS
Minor Violation
Minor Violation: Technical Specification 5.4.1, Procedures, requires that written procedures
shall be established, implemented, and maintained, covering applicable procedures
recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978. Section
8.b.(1)(I) of Appendix A of Regulatory Guide 1.33, Revision 2, February 1978, states that
written procedures should be provided for reactor protection system tests and
calibrations. Licensee Procedure IP/2/A/3222/095/B, Procedure for RTD and Thermocouple
Cross Calibration with Reactor Trip Breakers Closed or Open, Revision 39, contains
instructions for connecting test equipment and performing RTD calibrations. Contrary to the
above, on May 1, 2021, the licensee did not maintain the procedure to prevent an actuation of
the reactor trip system during reactor protection system tests and calibrations. Specifically,
inadequacies in the procedure and new test equipment resulted in reactor trip breaker open
actuation.
Screening: The inspectors determined the performance deficiency was minor. The
performance deficiency was screened in accordance with Inspection Manual Chapter (IMC) 0612 Appendix B, Additional Screening Guidance, dated December 12, 2020, and was
determined to be of minor significance because the finding did not meet any of the more than
minor screening questions.
Enforcement: The licensee has taken actions to restore compliance under NCR 02380726
and CNS LER 414/2021-002-00, "Valid Actuation of the Unit 2 Reactor Protection System
and Auxiliary Feedwater System," which included utilization of the original test boxes and
subsequent revisions to licensee procedures. The failure to comply with TS 5.4.1 constitutes
a minor violation that is not subject to enforcement action in accordance with the NRCs
Minor Violation
Minor Violation: Technical Specification 5.4.1, Procedures, requires that written procedures
shall be established, implemented, and maintained, covering applicable procedures
recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978. Section
3.k of Appendix A of Regulatory Guide 1.33, Revision 2, February 1978, states that written
procedures should be provided for startup, operations, and shutdown of safety-related
equipment, including the feedwater system (feedwater pumps to steam generator). Licensee
Procedure OP/2/A/6250/001, "Condensate and Feedwater System," Enclosure 4.19,
Recovery from Feedwater Isolation, contains instructions for restoration of the feed system
alignment following a feedwater isolation. Contrary to the above, on May 1, 2021, the
licensee failed to adequately implement procedure OP/2/A/6250/001 during restoration of the
feed system alignment following the reactor trip. Specifically, the main feedwater bypass
isolation valves were maintained in manual. When the feedwater pump was placed in
automatic with a level error signal present and no automatic control of the main feedwater
bypass isolation valves, the main feed pump speed control subsequently increased the pump
speed to a trip condition which, by design, resulted in the auxiliary feedwater actuation.
Screening: The inspectors determined the performance deficiency was minor. The
performance deficiency was screened in accordance with Inspection Manual Chapter (IMC) 0612 Appendix B, Additional Screening Guidance, dated December 12, 2020, and was
determined to be of minor significance because the finding did not meet any of the more than
minor screening questions.
Enforcement: The licensee has taken actions to restore compliance under NCR 02380727,
including human performance corrective actions and training. This failure to comply with TS 5.4.1 constitutes a minor violation that is not subject to enforcement action in accordance with
the NRCs Enforcement Policy.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On August 26, 2021, the inspectors presented the Emergency Preparedness Program
inspection results to Tom Simril and other members of the licensee staff.
On October 25, 2021, the inspectors presented the integrated inspection results to
Tom Simril and other members of the licensee staff.