IR 05000413/2021003

Integrated Inspection Report 05000413/2021003 and 05000414/2021003

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, th e NRC inspectors discussed the results of this inspection with you and other members of yo ur 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: NPF-35 and NPF-52

Report Numbers: 05000413/2021003 and 05000414/2021003

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 ReactorProjectsBranch1 Division of Reactor Projects

Enclosure SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitori ng the licensees performance by conducting an integrated inspection at Catawba N uclear Station, in accordance with the Reactor Oversight Process. The Reactor Oversight Proc ess is the NRCs program for overseeing the safe operation of commercial nuclear power react ors. 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 05000414/2021-002-00 Valid Actuation of the Unit 2 71153 Closed Reactor Protection System and Auxiliary Feedwater System

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 ma in generator links. On August 30, 2021, Unit 1 was returned to 100 percent RTP and rem ained 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 s hell 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 th e inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise note d. Currently approved IPs with their attached revision histories are located on the public web site 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 inspe ction activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Wa ter Reactor Inspection Program - Operations Phase. The inspectors reviewed selected p rocedures and records, observed activities, and interviewed personnel to assess licens ee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.

Starting on March 20, 2020, in response to the National Emergen cy declared by the President of the United States on the public health risks of the coronavi rus (COVID-19), resident and regional inspectors were directed to begin telework and to remo tely access licensee information using available technology. During this time, the resident insp ectors performed periodic site visits each week, increasing the amount of time on site as loca l COVID-19 conditions permitted.

As part of their onsite activities, resident inspectors conduct ed plant status activities as described in IMC 2515, Appendix D; observed risk significant ac tivities; and completed on site portions of IPs. In addition, resident and regional baseline in spections were evaluated to determine if all or a portion of the objectives and requirement s stated in the IP could be performed remotely. If the inspections could be performed remot ely, they were conducted per the applicable IP. In some cases, portions of an IP were comple ted remotely and on site. The inspections documented below met the objectives and requirement s 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 prepar ations to protect risk significant systems from impending severe weather conditions as sociated 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 w alkdowns 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 comp lete walkdown of the Unit 1A emergency diesel generator system on July 23, 2021.

(2) The inspectors evaluated system configuration during a comp lete walkdown of the safe shutdown facility (SSF) diesel generator and support syste ms 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 protect ion 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 protectio ns in the:

(1) Work request (WR) 20209964, 2A emergency diesel generator ( EDG) sequencer hallway water leak above

71111.11Q - Licensed Operator Requalification Program and Licen sed 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 Sec tion 03.02) (1 Sample)

(1) The inspectors observed and evaluated simulator scenario re corded on July 28, 2021, which contained failure of pressurizer spray val ve, seal injection flow control valve, control rod failure, reactor trip, loss of coola nt 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 en sure the following structures, systems, and components (SSCs) remain capable of pe rforming their intended function:

(1) WR 20204373, water dripping from overhead in 2A EDG sequenc er 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 Contr ol

Risk Assessment and Management Sample (IP Section 03.01) (5 Sam ples)

The inspectors evaluated the accuracy and completeness of risk assessments for the following planned and emergent work activities to ensure config uration 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 li nks, on August 26, 2021 (5) SSF diesel generator OOS for unscheduled maintenance, on Se ptember 13, 2021

71111.15 - Operability Determinations and Functionality Assessm ents

Operability Determination or Functionality Assessment (IP Secti on 03.01) (6 Samples)

The inspectors evaluated the licensee's justifications and acti ons associated with the following operability determinations and functionality assessme nts:

(1) NCR 2384415, B train component cooling miniflow valve fai led low, on June 1, 2021 (2) NCR 2388448, 2B EDG lube oil inlet/outlet low temperature a larm, 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 Sect ion 03.01 and/or 03.02) (1 Sample)

The inspectors evaluated the following temporary or permanent m odifications:

(1) Engineering change (EC) 419999, single piece flat washer fo r 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 ac tivities to verify system operability and functionality:

(1) WR 20205613, flushed sample line following EMF52 loss of fl ow alarms, on July 16, 2021 (2) Work Order (WO) 20402161, electronic software reset to rese t/resolve 1A reactor vessel level instrument inoperability, on July 29, 2021 (3) WO 20484700, repaired leak on 2A EDG cylinder head jumper p ipe and verified the leak was repaired, on August 7, 2021 (4) WR 20208313, replaced relay following the 2YV containment c hilled water chiller to start, on August 28, 2021 (5) WO 20487506, performed thermography following repair/replac ement of U1 main generator flex links and load placed on main generator, on Augu st 30, 2021 (6) WO 20491701, retest SSF frequency control following trouble shooting 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, 2 021

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 calculatio n performed, on August 9, 2021 FLEX Testing (IP Section 03.02) (1 Sample)

(1) WO 20470816, reviewed results of Catawba Nuclear Station qu arterly 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 Augment ation System

Inspection Review (IP Section 02.01-02.02) (1 Sample)

(1) The inspectors evaluated the readiness of the Emergency Res ponse 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 o f August 23, 2021. This evaluation does not constitute NRC approv al.

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 p reparedness program during the week of August 23, 2021.

71114.06 - Drill Evaluation

Select Emergency Preparedness Drills and/or Training for Observ ation (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated a drill scenario which simulated l oss of component cooling, loss of charging, turbine load rejection, tornado on site, safe ty injection actuation, and reactor trip, on September 27, 2021.

OTHER ACTIVITIES - BASELINE

71151 - Performance Indicator Verification

The inspectors verified licensee performance indicators submitt als listed below:

IE03: Unplanned Power Changes per 7000 Critical Hours Sample (I P 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 Sampl es)

(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 (I P 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 Sampl es)

The inspectors reviewed the licensees implementation of its co rrective 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 Discreti on

Event Report (IP Section 03.02) (1 Sample)

The inspectors evaluated the following licensee event report (L ER):

(1) LER 05000414/2021-002-00, Valid Actuation of the Unit 2 Rea ctor 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 71153 Minor Violation: Technical Specification 5.4.1, Procedures, requires that written procedures shall be established, implemented, and maintained, covering app licable 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 sy stem 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, R evision 39, contains instructions for connecting test equipment and performing RTD c alibrations. Contrary to the above, on May 1, 2021, the licensee did not maintain the proced ure 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 i n reactor trip breaker open actuation.

Screening: The inspectors determined the performance deficienc y was minor. The performance deficiency was screened in accordance with Inspecti on Manual Chapter (IMC)

0612 Appendix B, Additional Screening Guidance, dated Decembe r 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 complia nce under NCR 02380726 and CNS LER 414/2021-002-00, "Valid Actuation of the Unit 2 Rea ctor Protection System and Auxiliary Feedwater System," which included utilization of the original test boxes and subsequent revisions to licensee procedures. The failure to com ply with TS 5.4.1 constitutes a minor violation that is not subject to enforcement action in accordance with the NRCs Enforcement Policy.

Minor Violation 71153 Minor Violation: Technical Specification 5.4.1, Procedures, requires that written procedures shall be established, implemented, and maintained, covering app licable 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, Februar y 1978, states that written procedures should be provided for startup, operations, and shut down of safety-related equipment, including the feedwater system (feedwater pumps to s team generator). Licensee Procedure OP/2/A/6250/001, "Condensate and Feedwater System," E nclosure 4.19, Recovery from Feedwater Isolati on, contains instructions for restoration of the feed system alignment following a feedwater isolation. Contrary to the abov e, on May 1, 2021, the licensee failed to adequately implement procedure OP/2/A/6250/0 01 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 co ntrol of the main feedwater bypass isolation valves, the main feed pump speed control subse quently increased the pump speed to a trip condition which, by design, resulted in the aux iliary feedwater actuation.

Screening: The inspectors determined the performance deficienc y was minor. The performance deficiency was screened in accordance with Inspecti on Manual Chapter (IMC)

0612 Appendix B, Additional Screening Guidance, dated Decembe r 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 complia nce under NCR 02380727, including human performance corrective actions and training. Th is failure to comply with TS 5.4.1 constitutes a minor violation that is not subject to enfo rcement 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 Pre paredness Program inspection results to Tom Simril and other members of the licen see staff.

• On October 25, 2021, the inspectors presented the integrated i nspection results to Tom Simril and other members of the licensee staff.

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