IR 05000413/2018004

NRC Integrated Inspection Report 05000413/2018004 and 05000414/2018004

ML19023A532
Person / Time
Site:	Catawba
Issue date:	01/23/2019
From:	Frank Ehrhardt NRC/RGN-II/DRP/RPB1
To:	Simril T Duke Energy Corp
Geanette D
References
IR 2018004
Download: ML19023A532 (13)

Text

ary 23, 2019

SUBJECT:

CATAWBA NUCLEAR STATION - NRC INTEGRATED INSPECTION REPORT 05000413/2018004 AND 05000414/2018004

Dear Mr. Simril:

On December 31, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Catawba Nuclear Station, Units 1 and 2. On January 15, 2019, 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.

NRC inspectors did not identify any findings or violations of more than minor significance.

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 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely,

/RA/

Frank J. Ehrhardt, Chief Reactor Projects Branch 1 Division of Reactor Projects Docket Nos.: 50-413, 50-414 License Nos.: NPF-35, NPF-52

Enclosure:

IR 05000413/2018004 and 05000414/2018004

Inspection Report

Docket Number(s): 50-413, 50-414 License Number(s): NPF-35, NPF-52 Report Number(s): 05000413/2018004 and 05000414/2018004 Enterprise Identifier: I-2018-004-0039 Licensee: Duke Energy Carolinas, LLC Facility: Catawba Nuclear Station, Units 1 and 2 Location: York, SC Inspection Dates: October 1, 2018 to December 31, 2018 Inspectors: J. Austin, Senior Resident Inspector C. Scott, Resident Inspector A. Butcavage, Reactor Inspector M. Meeks, Senior Operations Engineer R. Williams, Senior Reactor Inspector Approved By: Frank J. Ehrhardt, Chief Reactor Projects Branch 1 Division of Reactor Projects Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring licensees performance by conducting a quarterly baseline inspection at Catawba, Units 1 and 2 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. No findings were identified during this inspection period.

PLANT STATUS

Unit 1 operated at or near 100 percent rated thermal power (RTP) through November 16. On November 17, the unit commenced refueling outage 1RFO24 and returned to 100 percent RTP on December 14.

Unit 2 operated at or near 100 percent RTP for the entire 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 performed plant status activities described in IMC 2515 Appendix D, Plant Status and conducted routine reviews using IP 71152, Problem Identification and Resolution. 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.

71111.01 - Adverse Weather Protection Seasonal Extreme Weather

The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of seasonal cold temperatures, expecting snow and freezing rain on December 9, 2018.

71111.04 - Equipment Alignment Partial Walkdown

The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:

(1) standby shutdown facility (SSF) ventilation system on October 25, 2018

(2) Unit 1 and Unit 2 service water structure on November 13, 2018

(3) station blackout bus work on December 9, 2018

Complete Walkdown (1 Sample)

The inspectors evaluated system configurations during a complete walkdown of the diesel generator sump pump system on December 26, 2018.

71111.05AQ - Fire Protection Annual/Quarterly Quarterly Inspection

The inspectors evaluated fire protection program implementation in the following selected areas:

(1) Unit 1 B emergency diesel generator, Fire Area 26 on November 6, 2018

(2) Unit 2 B emergency diesel generator, Fire Area 28 on November 7, 2018

(3) standby shutdown facility elevation 612, Fire Area SSF on November 13, 2018

(4) Unit 1 reactor building elevation 565 lower containment, Fire Area RB1 on November 30, 2018

(5) Unit 1 turbine building elevation 568, Fire Area TB1 on December 26, 2018

Annual Inspection (1 Sample)

The inspectors evaluated fire brigade performance on October 5, 2018.

71111.06 - Flood Protection Measures Internal Flooding

The inspectors evaluated internal flooding mitigation protections in the Unit 1 and Unit 2 turbine buildings on October 11, 2018.

71111.08 - Inservice Inspection Activities

The inspectors evaluated pressurized water reactor non-destructive testing by reviewing the following examinations from November 26, 2018 to November 30, 2018:

(1) Ultrasonic Examination (UT)a) UT of 1SM-4B-A, 34 pipe-to-elbow weld, ASME Class 2 (observed)b) UT of 1SM28-3, 34 elbow-to-pipe weld, ASME Class 2 (observed)

(2) Liquid Penetrant Examination (PT)a) PT of SA5-2, 4 pipe valve weld, ASME Class 2 (reviewed) - This review included a pressure boundary welding activity

(3) Visual Examination (VE)a) VE of 1RPV-HEAD-SURFACE, reactor pressure vessel upper head; ASME Code Class 1 (reviewed)

(4) Radiographic Examination (RT)a) RT of SA5-2, 4 pipe valve weld, ASME Class 2 (reviewed) - This review included a pressure boundary welding activity

(5) Eddy Current Examination (ET)a) Steam Generator B - ET for tubes R10C91, R97C70, R93C116, R111C72, R119C72, ASME Class 1 (observed)b) Steam Generator C - ET for tubes R24C5, R25C5, R25C4, R43C12, R46C7, ASME Class 1 (observed)

(6) Visual Examination (VT-1)a) VT-1 of 1SGB-MW-Y1-X2, Steam Generator Manway Nuts; ASME Code Class 1 (observed)b) VT-1 of 1SGB-MW-X2-Y2, Steam Generator Manway Nuts; ASME Code Class 1 (observed)c) VT-1 of 1SGC-MW-X1-Y1, Steam Generator Manway Nuts; ASME Code Class 1 (observed)d) VT-1 of 1SGC-MW-X1-Y2, Steam Generator Manway Nuts; ASME Code Class 1 (observed)

The inspectors evaluated the licensees boric acid corrosion control program performance.

71111.11 - Licensed Operator Requalification Program and Licensed Operator Performance Operator Requalification

The inspectors observed and evaluated a reactor operator simulator evaluation on October 4, 2018. The scenario consisted of a component cooling pump failure, loss of feedwater, and a faulted steam generator.

Operator Exams (1 Sample)

The inspectors reviewed and evaluated requalification examination results during the week of December 17, 2018.

Operator Performance (1 Sample)

The inspectors observed operator performance during the Unit 1 reactor startup on December 11, 2018.

71111.13 - Maintenance Risk Assessments and Emergent Work Control

The inspectors evaluated the risk assessments for the following planned and emergent work activities:

(1) Protected equipment plan with the 1B auxiliary feedwater pump out of service for pre-planned maintenance on November 1, 2018

(2) Yellow Risk condition for Unit 1 while at reduced inventory during refueling outage 1RFO24 to remove reactor vessel head on November 21, 2018

(3) Yellow Risk condition for Unit 1 to remove steam generator nozzle dams on December 3, 2018

(4) Green Risk condition for Unit 1 while reactor start-up was in progress on December 8, 2018

71111.15 - Operability Determinations and Functionality Assessments

The inspectors evaluated the following operability determinations and functionality assessments:

(1) Condition Report (CR) 2230546, Unit 1 Standby make up pump suction damper on October 16, 2018

(2) CR 2240817, Technical basis for standby shutdown facility without heating and ventilation on November 1, 2018

(3) CR 2247778, Unit 1 C steam generator PORV SV-7 inoperable during mode change to Mode 4 on December 8, 2018

(4) CR 2247892, 1A Motor generator breaker tripped on December 10, 2018

(5) CR 2249561, Investigate 1 delta cold leg accumulator inleakage on December 19, 2018

71111.19 - Post Maintenance Testing

The inspectors evaluated the following post maintenance tests:

(1) Work Request (WR) 20126420, Functional testing following repair of 1EMF-74, D SG N-16 leakage monitor on November 15, 2018

(2) PT/1/A/4350/002 A, Diesel operability test following 1A diesel governor modification on November 26, 2018

(3) TN/1/A/108756/01E, Post modification testing of 120 VAC power panelboard 1ERPA, following replacement on November 28, 2018

(4) PT/0/A/4400/002 A, Nuclear service water train A performance test following 1A service water pump replacement on November 29, 2018

(5) PT/1/A/4200/007 A, Centrifugal charging pump 1A test following mechanical seal rebuild on November 30, 2018

(6) Work Order (WO) 20189225, Functional verification following overheating of flex link connection adapter plates in main generator bushing box on December 16, 2018

71111.20 - Refueling and Other Outage Activities

The inspectors evaluated refueling outage 1RFO24 activities from November 16, 2018 to December 12, 2018.

71111.22 - Surveillance Testing The inspectors evaluated the following surveillance tests: Routine

(1) PT/0/A/4200/086, Ice bed analysis periodic test on November 24, 2018

Reactor Coolant System Leak Detection (1 Sample)

(1) PT/2/A/4150/001 D, Reactor coolant leakage calculation on December 12, 2018

Containment Isolation Valve (1 Sample)

(1) PT/1/A/4200/001 I, As Found Containment Isolation Valve Leak Rate Test, on November 27, 2018

71114.06 - Drill Evaluation Drill/Training Evolution

The inspectors evaluated a simulator based licensed operator requalification training evolution on November 1, 2018.

The inspectors observed emergency response organization focus area training on November 6,

OTHER ACTIVITIES - BASELINE

71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below for the period from October 2017 through September 2018.

(1) unplanned scrams per 7000 critical hours

(2) reactor coolant leakage

(3) safety system functional failure

71152 - Problem Identification and Resolution Semiannual Trend Review

The inspectors reviewed the licensees corrective action program for trends that might be indicative of a more significant safety issue.

Annual Follow-up of Selected Issues (1 Sample)

The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:

(1) CR 2242621, 1B emergency diesel generator unstable voltage during testing

EXIT MEETINGS AND DEBRIEFS

The inspectors verified no proprietary information was retained or documented in this report.

The inspectors confirmed that proprietary information was controlled to protect from public disclosure.

• On January 15, 2019, the inspector presented the quarterly resident inspector inspection results to Mr. Tom Simril, and other members of the licensee staff.

LIST OF

DOCUMENTS REVIEWED

71111.04 - Equipment Alignment

CR 2245787, SSF-AHS-1 damage

CR 2238064, Capability of WN sump pumps

CR 2238070, WN and NS/ND sump pumps added to the IST program

71111.05AQ - Fire Protection Annual/Quarterly

RP/0/B/5000/029, Fire Brigade Response

71111.08 - Inservice Inspection Activities

Procedures

03-6016219, Field Procedure for In-Situ Pressure Testing RSG Tubes Using the Triplex Pump,

Rev. 012

03-9289742, Secondary Side Visual Inspection Plan and Procedure for Duke Energy, Catawba

1, EOC24, Rev. 0

54-ISI-400-022, Non-Destructive Examination Procedure, Multi-Frequency Eddy Current

Examination of Tubing, 6/27/17

AD-EG-PWR-1611, Boric Acid Corrosion Control Program - Implementation, Rev. 2

AD-MN-ALL-0006, Fluid Leak Management, Rev. 1

NDE-NE-ALL-4101, Liquid Penetrant Examination, Rev. 1

NDE-NE-ALL-6102, Utilization of PDI-UT-2 Generic Procedure for the Ultrasonic Examination of

Austenitic Pipe Welds, Rev. 2

NDE-NE-ALL-6111, Utilization of PDI-UT-1, Generic Procedure for the Ultrasonic Examination

of Ferritic Pipe Welds, Rev. 1

NDE-NE-ALL-7101, VT-1 Visual Examination, Rev. 0

NDE-NE-ALL-7202, Visual Examination of PWR Reactor Pressure Vessel Upper Head

Penetrations, Rev. 3

PD-EG-PWR-1611, Boric Acid Corrosion Control Program, Rev. 1

Calculations

CNC-1201.01-00-0009, Appendix F, Catawba 1EOC21 Steam Generator Condition Monitoring

and Operational Assessment (CMOA), 7/31/14

CNC-1201.01-00-0022, Determination of Periodic Inspection Requirements for the Reactor

Vessel Head and Reactor Vessel Head Inspection Documentation, Rev. 27

Drawings

7693E001, B&W Canada, Duke Power Company, Steam Generator Arrangement, Right Hand

Vessel, Rev. 7

7693E002, B&W Canada, Duke Power Company, Steam Generator Arrangement, Left Hand

Vessel, Rev. 3

CN-1680-182, Catawba Nuclear Station, Steam Generator Tube Repair and Plugging Listing,

Steam Generator 1A,1B,1C and 1D, Rev. 2

Other Documents

03-1246524, Instructions for Plug Visual Inspection Level III, Enclosure 1, Plug Inspection

Report, S/G-1D Cold Leg, 11/26/18

03-1246524, Instructions for Plug Visual Inspection Level III, Rev. 14

Areva, Certificate of Calibration, Eddy Current Tester MIZ-80, S/N 042, Expiration Date 7/19/19

Areva, Certificate of Conformance, Data Package No. 23-5061192-02, 4/22/05

Areva, Certificate of Personnel Qualification (ET), ID Code B3720, Level-III-QDA, Expires

8/17/21

ASME Boiler & Pressure Vessel Code, 2007 w/2008 Addenda, July 1, 2008

BWXT, Catawba Unit-1 Foreign Object Assessment, 12/4/18

Catawba 1R24, Steam Generator Degradation Assessment, Rev.0, 11/8/18

Catawba C1R24, Independent Quality Data Analyst (IQDA) Log, Sparky Data Observation,

11/23/2018

Catawba Unit-1, Model CFR 80 Tri-Pitch Steam Generators, Secondary Side Integrity Plan,

Rev. 1

Catawba Unit-1, Primary to Secondary Leak-rate, 5 minute Average Trend Plot, 2/1/18 through

11/1/18

Catawba Unit-1, SG1A, SG1B, SG1C and SG1D, Narrow Range Level Trend Plots, 2/1/18

through 11/1/18

Certificate of Method Qualification for Examiners:

D. Hill,

M. Freeman, 465817, 268757,

430648, 288663

C-ISISG-0169.030.0040, Duke Energy, Fourth Interval Steam Generator Tube In-service

Inspection Plan, Catawba Nuclear Station, Units 1&2, Rev. 0

CS-CP-CNS-0020, Catawba Nuclear Station Primary to Secondary Leak Rate Monitoring

Program, Rev. 1

Duke Energy, Catawba, Calibration Group SG1BHCAL00037, IQDA Equipment Used, Data

Display, 11/29/18

Duke Energy, Catawba, Calibration Group SG1CHCAL000011, QDA Equipment Used, Data

Display, 11/26/18

Duke Energy, Certificate of Method Qualification (ET), ID Code 224860, Level-III-N, Expires

7/11/21

Duke Energy, Eddy Current Guidelines for Duke Energy CFR80 Steam Generators, 11/7/18

Duke Energy, Visual Acuity Record, ID Code 224860, Expires 5/15/19

ETSS-11956.3, Performance Demonstration Database, X-Probe Array, Rev. 2

ETSS-11956.4, Performance Demonstration Database, X-Probe Array, Rev. 2

ETSS-2, Examination Technique Specification Sheet, Catawba C1R24, Rev. 0

ETSS-96004.3, Performance Demonstration Database, Bobbin Coil, Rev. 13

Framatome, Certificate of Visual Examination, ID Code B3720 Expires 6/13/19

More Tech, Certificate of Personnel Qualification (ET), ID Code M2655, Level-III, QDA, Expires

8/29/23

More Tech, Certificate of Visual Examination, ID Code M2655, Expires 8/30/19

NDE Report No. WE170294

NDE-NE-CFR-0112, Duke Energy CFR80 Steam Generator Site Technique Validation for

Catawba Nuclear Station, Unit-1 and McGuire Nuclear Station Units-1 & 2, Rev 2

Procedure Qualification Record: L-102E Rev. 0, L-104 Rev. 3, L-133 Rev. 1, L-146D Rev. 0

Radiographic Examination Report No. DEC1_SA5-1_2017-03-24

SF-040115,Rev.1, B&W Ltd. Canada, Operability Statement for B&W RSGs/ROTSGs Without

Documented NB-3000 Analysis of Tube to Tubesheet Welds, 4/14/15

SGMP-IL-15-01, Steam Generator ASME Code Pressure Boundary-Tubesheet Weld or Tube-to

Tubesheet Friction Joint, 7/9/15

UT Calibration/Examination Report No.: UT-18-99, UT-18-100

Visual Examination for Boric Acid Detection Report No. VT-18-212

Visual Examination of Pressure Retaining Bolting (VT-1) Report No.: VT-18-231, VT-18-232,

VT-18-233, VT-18-234

Weld Doc No. 170373

Weld Procedure Specification Technical Sheet: GTSM01010-01, Rev. 8

ZETEC, Certificate of Conformance, Eddy Current Probe, S/N 756440, 9/29/18

ZETEC, Certificate of Conformance, Eddy Current Probe, S/N 760981, 11/16/18

Condition Reports

AR 01898451, Fatigue Analysis of Replacement Steam Generator Tube to Tube Sheet Welds

AR 02123708, Engineering to perform boric acid corrosion evaluation

AR 02124726, (NRC Identified) Evaluate Enhancement to SGME Procedures (PD-EG-PWR-

1801, AD-EG-PWR-1814 and AD-EG-PWR-1815) for improved clarity in how Vendor

Condition Monitoring and Operational Assessments (CMOAs) and Degradation Assessments

(DAs), are Retained as Site Calculations

AR 02127992, Boric acid corrosion control evaluation

AR 02130581, Boric acid corrosion control evaluation 1-NS-VA-5

AR 02161998, Perform BACC evaluation - 1-NV-VA-313

AR 02189442, Perform BACC evaluation 1NM-27 pipe cap leak

AR 02190836, 1-NV-VA-A087 - BACC evaluation IAW AD-EG-PWR-1611

AR 02246790, C1R24 SG Condition Monitoring and Reports

Work Orders (WO)/Work Requests (WR)

WR 20127583

WR 20127584

WR 20127585

WR 20127586

WR 20127587

WO 2209610

71111.11 - Licensed Operator Requalification Program and Licensed Operator

Performance

CPE 1801 License Operator Requalification

71111.19 - Post Maintenance Testing

IP/1/A/3450/003, 1ERPA, B, C, D Low Voltage Relay Checkout Procedure, Rev.10

EC 108756, Replace 1ERPA Panel Board

71111.20 - Refueling and Other Outage Activities

CNJITT10-N, Unit 1/2/ EOC Shutdown to Mode 5 JITT

OP/1/A/6100/002, Controlling Procedure for Unit Shutdown, Rev. 193

C1R24 Risk Plans

71111.22 - Surveillance Testing

CR 2246695, Ice Condenser- light ice baskets

11