IR 05000261/2020004

Integration Inspection Report 05000261/2020004 and Independent Spent Fuel Storage Fuel Storage Installation Inspection (ISFSI) Report 0720060/2020002

ML21040A474
Person / Time
Site:	Robinson, 07200060
Issue date:	02/09/2021
From:	Booma Venkataraman NRC/RGN-II/DRP/RPB3
To:	Kapopoulos E Duke Energy Progress
References
IR 2020002, IR 2020004
Download: ML21040A474 (18)

Text

February 9, 2021

SUBJECT:

H. B. ROBINSON STEAM ELECTRIC PLANT - INTEGRATED INSPECTION REPORT 05000261/2020004 AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION INSPECTION (ISFSI) REPORT 0720060/2020002

Dear Mr. Kapopoulos:

On December 31, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at H. B. Robinson Steam Electric Plant. On January 13, 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/

Booma Venkataraman, Acting Chief Reactor Projects Branch 3 Division of Reactor Projects Docket Nos. 05000261 and 0720060 License No. DPR-23

Enclosure:

As stated

Inspection Report

Docket Numbers: 05000261 and 0720060 License Number: DPR-23 Report Numbers: 05000261/2020004 and 0720060/2020002 Enterprise Identifiers: I-2020-004-0049 and I-2020-002-0074 Licensee: Duke Energy Progress, LLC Facility: H. B. Robinson Steam Electric Plant Location: Hartsville, South Carolina Inspection Dates: October 01, 2020 to December 31, 2020 Inspectors: M. Bates, Senior Operations Engineer A. Beasten, PhD, Resident Inspector A. Butcavage, Reactor Inspector B. Collins, Senior Reactor Inspector C. Dykes, Senior Health Physicist M. Fannon, Senior Resident Inspector A. Nielsen, Senior Health Physicist W. Pursley, Health Physicist Approved By: Booma Venkataraman, Acting Chief Reactor Projects Branch 3 Division of Reactor Projects Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at H. B. Robinson Steam Electric Plant, 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.

PLANT STATUS

Unit 2 began the inspection period at rated thermal power. On November 6 to 7, 2020, the unit was downpowered and shutdown for a planned refueling outage. The unit was restarted on December 7, 2020 and shutdown due to a rod control urgent failure alarm. Following repairs, the unit was restarted on December 9, 2020 and returned to rated thermal power on December 13, 2020. The unit remained at or near rated thermal power 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 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.

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.

71111.01 - Adverse Weather Protection

Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of seasonal cold temperatures for the following systems:

Auxiliary Feedwater System Diesel Fuel Oil System

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) 'B' and 'C' component cooling water (CCW) while 'A' CCW was out of service for motor replacement on October 26 and 28, 2020

(2) Spent fuel pool cooling system with the core fully offloaded, on November 17, 2020

(3) Dedicated shutdown diesel generator on December 22, 2020

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (IP Section 03.01) (5 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 20, main control room, on October 6, 2020

(2) Fire zone 24, containment vessel, on November 20, 2020

(3) Fire zone 28, spent fuel pit pumps and fuel handling areas, on November 16 and 18, 2020

(4) Fire zone 21, rod control room, on December 14, 2020

(5) Fire zone 25D, dedicated shutdown diesel generator, on December 22, 2020

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) A and B emergency diesel generator (EDG) rooms

71111.08P - Inservice Inspection Activities (PWR) PWR Inservice Inspection Activities Sample (IP Section 03.01)

The inspectors evaluated pressurized water reactor non-destructive testing by reviewing the following examinations from November 16 through December 9, 2020:

(1) 03.01.a - Nondestructive Examination and Welding Activities.

1. Ultrasonic Examination (UT)a. Augmented S/G A Nozzle To Elbow, Component ID 215/79-13-A, Weld 1R, 2R, & 4A, ASME Class 2 (reviewed)b. Pipe to Elbow Weld, Component ID: 1168/11, PZR Spray Piping, ASME Class 1 (reviewed)c. Latch Housing Top Weld, Control Rod Drive Mechanism (CRDM),

Head Penetration -63, P-10, Component ID: 101C/63(a), ASME Class 1 (reviewed)2. Visual Examination (VT)a. VT-1, ASME Cl. 2, SI Pump "B", Casing Studs b. Loop "C" Hot Leg Nozzle to Safe End, Component No. 107B/01DM, ASME Class 1 Visual Examination (reviewed)c. IWE Visual Examinations of Containment Moisture Barriers 3. Weld Package a. Work Order (WO) 20369683, ASME Class 3 Valve Replacement Spool Piece Fabrication 03.01.b - Pressurized-Water Reactor Vessel (LOWER) Head Penetration Examination Activities.

1. Bare Metal Visual Examination a. ASME Class 1, Lower Reactor Vessel Head, Bottom Mounted Instrumentation, Penetrations, No's, 24, 38, 30,10, 15, 27, 36 and 23 (Photo's reviewed)03.01.c - Pressurized-Water Reactor Boric Acid Corrosion Control Activities.

The inspectors reviewed the licensee's boric acid corrosion control program performance, and sampled Condition Reports and Boric Acid evaluations.

03.01.d - Pressurized-Water Reactor Steam Generator Tube Examination Activities.

1. Eddy Current Testing (ECT)a. SG A, tubes R36C20, R25C62, R36C22, ASME Class 1 (observed via video)b. SG B, tubes R3C5, R11C91, R2C17, ASME Class 1 (observed via video)c. SG C, tubes R20C9, R6C23, R44C36, ASME Class 1 (observed via video)

71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance

Requalification Examination Results (IP Section 03.03) (1 Sample)

The licensee completed the annual requalification operating examinations required to be administered to all licensed operators in accordance with Title 10 of the Code of Federal Regulations 55.59(a)(2), Requalification Requirements, of the NRCs Operators Licenses. During the week of November 23, 2020, the inspector performed an in-office review of the overall pass/fail results of the individual operating examinations and the crew simulator operating examinations in accordance with Inspection Procedure (IP) 71111.11, Licensed Operator Requalification Program. These results were compared to the thresholds established in Section 3.02, Requalification Examination Results, of IP

===71111.11.

(1) The inspectors reviewed and evaluated the licensed operator examination failure rates for the requalification annual operating exam completed on April 30, 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) (1 Sample)

(1) The inspectors observed and evaluated licensed operator performance in the Control Room during a planned shutdown and cooldown on November 6 and 7, 2020.

Licensed Operator Requalification Training/Examinations (IP Section 03.02) ===

(1) The inspectors observed and evaluated licensed operator requalification training on October 14, 2020.

71111.12 - Maintenance Effectiveness

Maintenance Effectiveness (IP Section 03.01) (1 Sample)

The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:

(1) Nuclear condition report (NCR) 2350556, A CCW pump abnormal vibrations, noise, and temperatures

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) (6 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) A CCW abnormal vibrations and noise on October 1, 2020

(2) B CCW pump seal replacement on November 2 and 4, 2020

(3) Risk assessment for response time testing of the reactor coolant system resistance temperature detectors on November 6, 2020

(4) Multiple outage risk key safety functions as yellow risk conditions on November 9, 2020

(5) Reduced inventory during the refueling outage on November 13, 2020

(6) 'A' residual heat removal (RHR) valve work during the refueling outage on December 3, 2020

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (2 Samples)

The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:

(1) NCR 2350556, A CCW abnormal vibrations and noise on October 7, 2020

(2) NCR 2351146, B steam flow transmitter step change on October 9, 2020

71111.19 - Post-Maintenance Testing

Post-Maintenance Test Sample (IP Section 03.01) (7 Samples)

The inspectors evaluated the following post-maintenance test activities to verify system operability and functionality:

(1) Work Order (WO) 20288063, A RHR pump maintenance activities on October 8, 2020

(2) WO 20308389, B RHR pump breaker replacement on October 20, 2020

(3) WO 20414485, B CCW pump seal replacement on November 4, 2020

(4) WO 13391387, A RHR valve maintenance activities on November 24, 2020

(5) WO 20370941, OST-703-2 Primary side test for the RHR system, on November 25, 2020.

(6) WO 20358670, A EDG governor replacement on November 30, 2020

(7) WO 20438577, Power cabinet '2BD' urgent failure, on December 9, 2020.

71111.20 - Refueling and Other Outage Activities

Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated refueling outage (R2R32) activities from November 7 to December 11, 2020.

71111.22 - Surveillance Testing

The inspectors evaluated the following surveillance tests:

Surveillance Tests (other) (IP Section 03.01)

(1) OST-053, inspection for reactor coolant system leakage (refueling interval) on

November 7, 2020 Containment Isolation Valve Testing (IP Section 03.01) (1 Sample)

(1) EST-064, containment isolation valve local leakage rate survey on December 4,

71124.01 - Radiological Hazard Assessment and Exposure Controls

Radiological Hazard Assessment (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated how the licensee identifies the magnitude and extent of radiation levels and the concentrations and quantities of radioactive materials and how the licensee assesses radiological hazards.

Instructions to Workers (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated radiological protection-related instructions to plant workers.

Contamination and Radioactive Material Control (IP Section 03.03) (2 Samples)

The inspectors evaluated licensee processes for monitoring and controlling contamination and radioactive material.

(1) Observed licensee personnel using detection instruments to exit the radiologically controlled area (RCA).

(2) Observed physical controls for contaminated items stored in the spent fuel pool.

Radiological Hazards Control and Work Coverage (IP Section 03.04) (3 Samples)

The inspectors evaluated in-plant radiological conditions during facility walkdowns and observation of radiological work activities.

(1) Steam generator eddy current testing activities in high contamination areas and high radiation areas.

(2) Valve work inside a high radiation area.

(3) Refuel floor work inside containment building.

High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (2 Samples)

The inspectors evaluated licensee controls of the following High Radiation Areas and Very High Radiation Areas:

(1) Containment building under-vessel sump (Very High Radiation Area).

(2) Waste hold up tank room (Locked High Radiation Area).

Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 03.06) (1 Sample)

(1) The inspectors evaluated radiation worker and radiation protection technician performance as it pertains to radiation protection requirements.

71124.03 - In-Plant Airborne Radioactivity Control and Mitigation

Permanent Ventilation Systems (IP Section 03.01) (2 Samples)

The inspectors evaluated the configuration of the following permanently installed ventilation systems:

(1) Control Room Air Conditioning and Filter System Unit 2

(2) Spent Fuel Ventilation System Unit 2

Temporary Ventilation Systems (IP Section 03.02) (2 Samples)

The inspectors evaluated the configuration of the following temporary ventilation systems:

(1) Kelly Building in the Unit 2 Radwaste Building

(2) High Efficiency Particulate Air Units on the steam generators in Unit 2 containment

Use of Respiratory Protection Devices (IP Section 03.03) (1 Sample)

(1) The inspectors evaluated the licensees use of respiratory protection devices.

Self-Contained Breathing Apparatus for Emergency Use (IP Section 03.04) (1 Sample)

(1) The inspectors evaluated the licensees use and maintenance of self-contained breathing apparatuses.

71124.04 - Occupational Dose Assessment

Source Term Characterization (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated licensee performance as it pertains to radioactive source term characterization.

External Dosimetry (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated licensee performance as it pertains to external dosimetry that is used to assign occupational dose.

Internal Dosimetry (IP Section 03.03) (2 Samples)

The inspectors evaluated the following internal dose assessments for actual internal exposures:

(1) Invivo bioassay result for individual evaluated for exposure to airborne radioactivity for facial contamination during a valve lineup evolution in Unit 2 containment on November 14, 2020 (Employee Identification (EID) #366611).

(2) Dose assessment for an individual evaluated for exposure to airborne radioactivity for facial contamination while installing scaffolding in Unit 2 containment on November 14, 2020 (EID #270168).

Special Dosimetric Situations (IP Section 03.04) (2 Samples)

The inspectors evaluated the following special dosimetric situations:

(1) Dose assessment for a declared pregnant worker (Employee ID# 704317)10/21/2020

(2) Gradient Radiation Field Task Evaluation for A, B and C steam generator primary manway removal, Radiation Work Permit (RWP)#2525, 11/17/2020

71124.05 - Radiation Monitoring Instrumentation

Walkdowns and Observations (IP Section 03.01) (10 Samples)

The inspectors evaluated the following radiation detection instrumentation during plant walkdowns:

(1) Area Radiation Monitors in the auxiliary building, Main Control Room and Spent Fuel Pool

(2) Portable ion chambers stored ready for use and/or during use in Unit 2 containment

(3) Portable friskers used at the exit to the Unit 2 radiologically controlled area and inside the Unit 2 radiologically controlled area.

(4) Portable neutron radiation detectors stored ready for use in the RP instrument laboratory

(5) Containment High Radiation Monitors in Unit 2 containment.

(6) Personnel contamination monitoring equipment at the RCA exit including personnel contamination monitors and tool monitors.

(7) Continuous air monitors inside Unit 2 containment and the auxiliary building.

(8) Extendable Geiger-Mueller radiation survey instrument stored 'ready for use' in the RP instrument laboratory.

(9) Air sampling equipment in the Unit 2 auxiliary, radwaste and containment building,

(10) Hand and Foot automated contamination monitors in the auxiliary and radwaste buildings.

Calibration and Testing Program (IP Section 03.02) (10 Samples)

The inspectors evaluated the calibration and testing of the following radiation detection instruments:

(1) Apex- Invivo Fastscan Counting System, RNPFS1 2019 Recalibration, 04/26/2019; 04/23/2020 Apex- Invivo Fastscan Counting System, RNPFS2 2019 Recalibration, 04/19/2019

(2) RST-020 Verification of Electronic Calibration of Radiation Monitoring System Monitors R-32A&B (Containment High Range Monitor- Victoreen), 03/05/2017 &

03/07/2018 RST-020 Verification of Electronic Calibration of Radiation Monitoring System Monitors R-32A&B (Containment High Range Monitor- Victoreen), 10/14/2017 &

10/21/2018

(3) RCP-109 Calibration of the Tennelec LB5100-Series IIIW And Series 5-XLB Proportional Counters; Tennelec 01, 04/19/2020

(4) Enrad Laboratories Central Calibration Certificate of Calibration Ludlum Model 12-4 (Remball), Serial # 315051, Enrad # 12710, 01/09/2018; 01/27/2020

(5) Enrad Laboratories Central Calibration Certificate of Calibration Telepole, # 6605-004, Enrad # 02151, 08/14/2019; 08/17/2020

(6) Enrad Laboratories Central Calibration Certificate of Calibration Canberra Argos-5AB, Serial # 1611-267-AR050AB, Enrad # 07854, 01/18/2018; 08/17/2020

(7) Enrad Laboratories Central Calibration Certificate of Canberra Cronos-4; TB RCA Exit, Serial # 1103-035, Enrad # 10346. 11/18/2019; 08/07/2020

(8) Enrad Laboratories Central Calibration Certificate of Calibration Ludlum Model 9-3, Serial # 288741, Enrad # 13000, 07/22/2019; 08/12/2020

(9) Enrad Laboratories Central Calibration Certificate of Canberra iCam, SERIAL # 6188, Enrad # 13245, 03/15/2019; 03/05/2020

(10) RST-008 Calibration of Radiation Monitor System, Monitors R-1 through R-9, and R-33, Monitor R-4 Canberra GP100C2/13000167, WO # 20305405-01, 07/23/2019 Effluent Monitoring Calibration and Testing Program Sample (IP Sample 03.03) (2 Samples)

The inspectors evaluated the calibration and maintenance of the following radioactive effluent monitoring and measurement instrumentation:

(1) R-18, CP-RST-918 Calibration of Radiation Monitoring System Liquid Effluent Radiation Monitor R-18 Channel, Work Order Package 20365656 01, 06/15/2020

(2) RST-012 Calibration of Radiation Monitor System, Monitor R-14 Channels C, D & E Plant Vent Continuous & Noble Gas Monitor, Work Order Package 20309498 01, 6/11/2020

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) October 1, 2019 to September 30, 2020

OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)

(1) July 1, 2019 to October 31, 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) July 1, 2019 to October 31, 2020

71152 - Problem Identification and Resolution

Semiannual Trend Review (IP Section 02.02) (1 Sample)

(1) The inspectors reviewed the licensees corrective action program (CAP) for potential adverse trends that might be indicative of a more significant safety issue.

OTHER ACTIVITIES

- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL

60855.1 - Operation of an Independent Spent Fuel Storage Installation at Operating Plants

(1) The inspectors evaluated the licensees activities related to long-term operation and monitoring of their independent spent fuel storage installation.

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

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

• On January 13, 2021, the inspectors presented the integrated inspection results to Mr.

E. Kapopoulos Jr. and other members of the licensee staff.

• On December 10, 2020, the inspectors presented the inservice inspection activities inspection results to Mr. E. Kapopoulos Jr. and other members of the licensee staff.

• On November 20, 2020, the inspectors presented the RP baseline inspection results to Mr. E. Kapopoulos Jr. and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.08P Corrective Action AR 02227944 Deferred Corrective Action Process Effectiveness Review 8/30/18

Documents for NCR 01905753

AR 02278082 Document Results and Recommendations from Combined 06/19/2019

Harris and McGuire INPO Materials Review Visit

NCR 01966533 Casing Leak on SI Pump "B" 10/21/15

Drawings 02-9198805B AREVA NP Inc. .875 Array Probe Flaw Calibration Rev. 000

Standard As Built Drawing

10015179 ZETEC, Inc. ASME Standard 2/TSR and Lexan Cover Rev. 0

Engineering EC 415408, Design Replace Carbon Steel Service Water Booster Pump Rev. 3

Changes Equivalent Change Discharge Valves with Stainless Steel

Package

Engineering H.B. Robinson Unit 2 RO32 Steam Generator Degradation Rev. 1

Evaluations Assessment

44F Steam Generators Site Technique Validation for Rev. 0

Robinson Nuclear Station Unit 2

H.B. Robinson Unit 2 RO32 Steam Generator Condition Rev. 0

Monitoring and Final Operational Assessment

218-AST-101129 BWXT Technologies, Inc. Condition Monitoring and Rev. 001

Operational Assessment for Robinson Unit 2 RO30 Outage

NCR No. Valve CVC-347, Boric Acid Filter Inlet Diaphragm Valve 9/10/20

2348023, Boric

Acid Evaluation

NCR No. CVC-349F Boric Acid Pump B, Discharge Press PI-110, 10/13/20

2353096, Boric Root Isolation Valve Stem Boric Acid Seep

Acid Evaluation

NCR: 02347664 Containment Vessel, Spray-PMP-B 7/1/18

Boric Acid

Evaluation

Miscellaneous Framatome Certificate of Personnel Qualification: ET II June

(Munsterman) 18,2020

Framatome Certificate of Vision Examination (Munsterman) June 16,

20

Inspection Type Designation Description or Title Revision or

Procedure Date

Curtiss-Wright Personnel Certification Summary Record: August

ET III (Shutler) 16,2020

Curtiss-Wright Vision Examination Certification (Shutler) July 21,

20

MoreTech Certificate of Personnel Qualification: ET III-QDA 07/14/20

(Mingus)

MoreTech Certificate of Vision Examination (Mingus) 07/13/20

Examiner ID No NDE Examiner Certification Review 9/9/20

280000

Examiner ID No. Level III, VT-2, Certificate of Method Qualification 09/21/2017

2699

Examiner ID No. Vision Acuity Examination Record 6/3/20

366449

ID No. 222699 AD-NE-ALL-1101 Revision 4, "Training, Qualification, and 3/3/2019

Certification of Nondestructive Examination Personnel",

Penetrant testing

ID No. 222699 AD-NE-ALL-1101 Revision 4, Training, Qualification, and 7/10/19

Certification of Nondestructive Examination Personnel,

Ultrasonic Testing, Level III

NDE Examiner ID NDE UT, PDI Level II Certification 2/19/20

No. 287789

NDE Examiner ID VT-II Examiner Certification 9//9/20

No. 288663

Test Block S/N 16- Certificate of Compliance 10/26/16

4119

Inspection Type Designation Description or Title Revision or

Procedure Date

NDE Reports NDE Report No. Visual Inspection, Loop "A" Hot leg Nozzle to Safe End, 11/12/20

VT-20-023 Component. ID, 107/01DM

NDE Report No. Visual Inspection, LOOP "B" Hot Leg Nozzle To Safe End, 11/12/20

VT-20-024 Component ID, 107A/010M

NDE Report No. Visual Inspection, Loop "C" Hot Leg Nozzle To Safe End, 11/12/20

VT-20-025 Component ID 107B/01DM

Report No. 2020- Liquid Penetrant Examination Report (PT), Weld 1, Weld 2, 11/2/20

60643 Line/Component, 12-CW-168

Report No. VT-20- Component I

D. No. L-MB-CWI, VT-1, Visual Examination, 12/2/20

140 Moisture Barrier - Inside Crane Wall

Report No: UT-VE- CRDM PEN TO ADAPTOR

20-005

Rpt. No. 2018- Visual Examination (VT-1) of Pressure Retaining Bolting, 7/16/18

28143 "B" SI Pump Casing Studs, No.s 2,4,6,10,14

UT-20-006 SG "A", Nozzle to Vessel Weld, Component ID, 215/79-13- 11/17/20

A

UT-20-023 Ultrasonic Test Report, Component ID: 116B/11 11/20/20

Pressurizer Spray Line, Pipe to Elbow Weld

UT-20-025 Ultrasonic Inspection Report, CRDM Assembly, Head 11/21/20

PEN-63, P-10, Component ID: 101C/63(a)

VT-20-137 Bottom Mounted Instrumentation Penetration No's 1 thru 12/1/20

Inspection Type Designation Description or Title Revision or

Procedure Date

VT-2 Examination Results

VT-20-139 Component I

D. No, L-MB-CWO, VT-1 Visual Examination 12/1/20

of Moisture Barrier - Outside Crane Wall

Procedures Eddy Current Guidelines for Duke Energys 44F Steam Rev. 2

Generators

NDE-NE-ALL- VT-2 Visual Examinations 6/2/20

201

NDE-NE-ALL-6111 Utilization of PDI-UT-1, Generic Procedure for the Rev. 1

Ultrasonic

Examination of Ferritic Pipe Welds

NDE-NE-ALL-7203 Visual Examination of PWR Reactor Pressure Vessel 6/2/20

Bottom Mounted Instrument

Penetrations

NDE-NE-ALL-7402 Visual Examination of IWE Components 11/9/20

NDE-NE-ALL-7701 VISUAL EXAMINATION OF WELDS AND BRAZED Rev.001

JOINTS

NOS-QC-ALL- Hold Point Instructions for Visual Examination (VT-W) of Rev. 000

1002-01 Welds and Brazed Joints

Self-Assessments AD-PI-ALL-0300, Welding Program Implementation at RNP 4/27/17

Number: 1993339

AD-PI-ALL-0300, 2020 Augmented Inservice Inspection Assessment 8/10/20

SA No. 02310727-

Work Orders WO 20194311-01 SI-Pump-B , Inspect SI Pump "B" Casing Studs 7/16/18

Inspection Type Designation Description or Title Revision or

Procedure Date

71124.01 Corrective Action NCR 02358213

Documents

Resulting from

Inspection

Procedures AD-RP-ALL-0004 Radiological Posting and Labeling Revision 4

AD-RP-ALL-0005 Access Controls for High and Locked High Radiation Areas Revision 1

Radiation RNP-M-20201115- Scaffold built at Rx head 11/15/2020

Surveys 19

RNP-M-20201118 "A" Steam Generator Survey 11/18/20

71124.03 Calibration Posi3 USB serial Posi3 USB Functional Test Results 09/18/2019

Records #115SO8005938

Posi3 USB serial Posi3 USB Functional Test 09/18/2019

1. 115SO818005931

Posi3 USB serial Posi3 USB Functional Test 09/08/2019

1. 115SO818005936

Work Orders WO 20407155-1 RST-023 Routine Respiratory Inspection/Inventory 10/7/2020;

RST-023 11/02/2020

WO 20397813-01

71124.04 Miscellaneous CSD-RP-ALL-4016 CSD-RP-ALL-4016 Prospective Determination for 01/30/2017

Occupational Exposure

Procedures AD-RP-ALL-0006 Personnel Contamination Monitoring Revision 1

AD-RP-ALL-4010 Internal Dose Assessment Revision 3

16