IR 05000400/2021002
| ML21214A123 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 08/02/2021 |
| From: | Stewart Bailey NRC/RGN-II/DRP/RPB4 |
| To: | Maza K Duke Energy Progress |
| References | |
| IR 2021002 | |
| Download: ML21214A123 (25) | |
Text
August 2, 2021
SUBJECT:
SHEARON HARRIS NUCLEAR POWER PLANT - INTEGRATED INSPECTION REPORT 05000400/2021002
Dear Ms. Maza:
On June 30, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Shearon Harris Nuclear Power Plant. On July 19, 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 Margaret Tobin Acting for/
Stewart N. Bailey, Chief Reactor Projects Branch 4 Division of Reactor Projects
Docket No. 05000400 License No. NPF-63
Enclosure:
As stated
Inspection Report
Docket Number:
05000400
License Number:
Report Number:
Enterprise Identifier: I-2021-002-0009
Licensee:
Duke Energy Progress, LLC
Facility:
Shearon Harris Nuclear Power Plant
Location:
New Hill, NC 27562
Inspection Dates:
April 1, 2021 to June 30, 2021
Inspectors:
J. Zeiler, Senior Resident Inspector
C. Smith, Resident Inspector
B. Collins, Senior Reactor Inspector
J. Diaz-Velez, Senior Health Physicist
B. Kellner, Senior Health Physicist
A. Nielsen, Senior Health Physicist
W. Pursley, Health Physicist
J. Walker, Emergency Response Inspector
Approved By:
Stewart N. Bailey, Chief
Reactor Projects Branch 4
Division of Reactor Projects
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Shearon Harris Nuclear Power 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 1 operated at rated thermal power until April 6, 2021, when a coastdown was initiated in preparation for an upcoming refueling outage. On April 23, 2021, the unit was shut down from 90 percent power to begin refueling outage H1R23. The refueling outage was completed on May 14, 2021. That same day, with the unit operating at approximately 27 percent power, the unit was shut down to Mode 3 to address abnormal vibrations of an outage installed generator ground detection device frame support member in the generator exciter structure. The unit was restarted on May 15, 2021, and returned to rated thermal power on May 18, 2021. On June 4, 2021, the unit was shut down to Mode 3 to repair an oil leak on the 1B unit auxiliary transformer (UAT) X-winding electrical bushing connection. The unit was restarted on June 7, 2021, and was returned to rated thermal power on June 9, 2021. 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 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
71111.04 - 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' residual heat removal (RHR) system while 'A' RHR system was out of service for scheduled pump motor breaker maintenance on April 19, 2021 (2)
'B' emergency diesel generator (EDG) while 'A' EDG was out of service for refueling outage preventive maintenance on May 5, 2021 (3)
'B' essential services chilled water (ESCW) system while 'A' ESCW system was out of service for scheduled maintenance on June 22, 2021
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated system configurations during a complete walkdown of the auxiliary feedwater system, completed on June 14, 2021
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (6 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) Reactor Auxiliary Building (RAB) 261' elevation steam tunnel area (fire zone 1-A-46-ST) on April 13, 2021
- (2) Emergency service water (ESW) intake screening structure (fire zone 5-S-BAL) on April 22, 2021
- (3) Containment 221', 236', and 261' elevations (fire zones 1-C-1-BAL, 1-C-1-CHFA, 1-C-CHFB, 1-C-3-EPA, and 1-C-3-EPB) on April 25, 2021 (4)
'B' EDG room and support equipment areas (fire zones 1-D-1-DGB-ROM, 1-D-3-DGB-ES, 1-D-DTB, 1-D-1-DGB-ASU, and 1-D-1-DGB-ER) on May 8, 2021
- (5) RAB 190' elevation 'A' and 'B' RHR and containment spray pump rooms (fire zones 1-A-1-PA and 1-A-1-PB) on May 14, 2021
- (6) RAB 286' elevation 'B' train essential switchgear and battery rooms (fire zones 1-A-SWGRB and 1-A-BATB) on June 5, 2021
71111.06 - Flood Protection Measures
Cable Degradation (IP Section 03.02) (1 Sample)
The inspectors evaluated cable submergence protection in:
- (1) Cable vaults M70A, M70B, M71A, and M71B that contain 'A' train safety-related cables associated with the ESW system on May 18 and May 20, 2021
71111.07A - Heat Sink Performance
Annual Review (IP Section 03.01) (2 Samples)
The inspectors evaluated readiness and performance of:
(1)
'A' ESCW condenser heat exchanger during visual inspection, mechanical tube cleaning, and tube plugging maintenance activities on May 1-3, 2021 (2)
'A' component cooling water (CCW) heat exchanger during visual inspection, mechanical tube cleaning, and tube plugging maintenance activities on May 1-3, 2021
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 May 10 - 14, 2021:
(1)03.01.a - Nondestructive Examination and Welding Activities.
1. Ultrasonic Examination (UT)
a. 6" reactor coolant system weld (1-RC6-47SB), ASME Class 1 (reviewed) b. 6" safety injection system weld (II-SI-024SI-FW-587), ASME Class 1 (reviewed)
2. Liquid Penetrant Examination (PT)
a. 10" service water system spoolpiece 3SW10-938SA-1 weld (WO-1),
ASME Class 3 (reviewed, including weld documentation)b. 6" safety injection system component welded attachment (SI-H-0960-ATT), ASME Class 1 (reviewed)
3. Magnetic Particle Testing (MT)
a. 12" service water system spoolpiece 3SW12-938SA-1 welds (1-SW-427-1-VW-11, FW-1, FW-2, FW-3), ASME Class 3 (reviewed, including weld documentation)b. 36" steam generator nozzle-to-shell weld (II-SG-001SGB-FWNTSW-05-1), ASME Class 2 (reviewed)
03.01.b - Pressurized-Water Reactor Vessel Upper Head Penetration Examination Activities.
No activities performed this outage. Licensee replaced this unit's head during the previous outage (Fall 2019), and the new head is made of PWSCC-resistant materials.
03.01.c - Pressurized-Water Reactor Boric Acid Corrosion Control Activities.
The inspectors reviewed the licensee's boric acid corrosion control program performance.
03.01.d - Pressurized-Water Reactor Steam Generator Tube Examination Activities.
The inspectors reviewed the licensee's justification for skip-cycle approach on steam generator inservice inspection activities.
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 the following activities:
- Reactor shutdown for refueling outage H1R23 on April 24-25, 2021
- Initial reactor criticality following refueling outage H1R23 on May 13, 2021
- Reactor shutdown for maintenance outage to repair oil leak on the 1B UAT on June 4-5, 2021
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated a simulator scenario for operator training involving a complete loss of feedwater on June 16, 2021
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (2 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) Water leakage from fire protection piping failure into EDG building common entrance hallway (NCR 02372140) on March 2, 2021 (2)
'B' RHR pump failed to start during surveillance testing (NCR 02376252) on March 29, 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) Elevated (Green) risk during scheduled 'A' RHR pump motor breaker maintenance activities on April 19, 2021
- (2) Elevated (Yellow) risk during refueling outage H1R23 for initial reactor coolant system (RCS) draindown to below the reactor vessel flange elevation in preparation for removing the reactor vessel head on April 26, 2021
- (3) Elevated (Yellow) risk during refueling outage H1R23 with single train of RHR and spent fuel pool cooling available while 'A' train essential safety equipment was out of service for outage maintenance with defueling operations in progress on April 29, 2021
- (4) Elevated (Yellow) risk during scheduled annual dedicated shutdown diesel generator (DSDG) annual maintenance outage on June 9-10, 2021
- (5) Elevated (Green) risk during scheduled 'A' ESCW system preventive maintenance on June 22, 2021
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (4 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Evaluation of 10 CFR 21 notification from Ametek Solidstate Controls identifying potential seismic design concerns with selected power supplies used at Harris Nuclear Plant (NCRs 02361578 and 02376350) on March 30, 2021
- (2) Turbine auto-stop trip Quadvoter solenoid valve 1EH-159B unable to be surveillance tested weekly due to slow test reset of solenoid valve 1EH-159A (NCR 023764510)on April 9, 2021
- (3) Indentation/crack identified in container jar for 'A' train 125 volt-dc safety-related battery cells 37 and 41 (NCR 02381707) on May 8, 2021
- (4) Plant vent stack wide range gas monitor RM-21AV-3509-1SA degraded due to loss of output communication resulting in NRC special report (NCR 02384956) on June 14, 2021
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (2 Samples)
The inspectors evaluated the following temporary or permanent modifications:
- (1) Permanent modification engineering change (EC) 416783, Replacement of valve 1CC-252, CCW reactor coolant pump thermal barrier heat exchanger return isolation, implemented during refueling outage H1R23
- (2) Temporary modification EC 419555, Bypass locked in Data A rod position indication non-urgent alarm ALB-13/6-2, implemented on May 16, 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) Operations Surveillance Test (OST)-1008, 1A-SA RHR Pump Operability Quarterly Interval Modes 1-2-3, following 'A' RHR pump motor breaker maintenance on April 19, 2021
- (2) Maintenance Surveillance Test (MST)-E0027, 1E Battery Cell Connection Resistance and Service Test, following replacement of 'A' 125 volt-dc safety-related battery 1A-
-SA on May 5-8, 2021
- (3) OST-1823, 1A-SA Emergency Diesel Generator Operability Test Modes 1 Through 6 and Defueled, following 'A' EDG refueling outage preventive maintenance on May 8-
-9, 2021
- (4) Operating Procedure (OP)-186, Dedicated Shutdown Diesel Generator, Section 8.3, Manually Starting the Dedicated Shutdown Diesel Generator, following DSDG scheduled annual maintenance on June 9, 2021
- (5) Operations Periodic Test (OPT)-1512, Essential Chilled Water Turbopak Units Quarterly Inspection/Checks Modes 1-6, following 'A' ESCW chiller scheduled preventive maintenance on June 22, 2021
- (6) OST-1215, Emergency Service Water System Operability Train B Quarterly Interval Modes 1 2 3 4 5 6 Defueled, following 'B' ESW system preventive maintenance outage on June 29, 2021
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated refueling outage H1R23 activities from April 24, 2021, to May 14, 2021
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Surveillance Tests (other) (IP Section 03.01)
- (1) OST-1086, 1B-SB Diesel Generator Operability Test Semiannual Interval Modes 1-6, on April 11, 2021
- (2) OST-1087, Motor Driven Auxiliary Feedwater Pumps Full Flow Test Quarterly Interval Mode 1, on April 14, 2021
- (3) OST-1826, Safety Injection ESF Response Time, Train B Staggered Test Basis Mode 5 - 6, on May 6, 2021
Inservice Testing (IP Section 03.01) (1 Sample)
- (1) Engineering Surveillance Test (EST)-223, Insitu Main Steam Safety Valve Test Using Assist Device, on April 13, 2021
Containment Isolation Valve Testing (IP Section 03.01) (1 Sample)
- (1) EST-212, Type C Local Leak Rate Tests, Attachment 31, Penetration M-78A (RCS Hot Leg Sample) LLRT for 1SP-948 and 1SP-949, on April 28,
RADIATION SAFETY
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)
The inspectors evaluated instructions to workers including radiation work permits used to access high radiation areas.
RWP 1015, Radiography Labels on containers in the auxiliary building
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 surveys of potentially contaminated materials leaving the radiologically controlled area (RCA)
- (2) Observed the status of non-fuel 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) Seal table maintenance work
- (2) Reactor vessel head lift
- (3) Irradiated fuel movement
High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (3 Samples)
The inspectors evaluated licensee controls of the following High Radiation Areas and Very High Radiation Areas:
- (1) Auxiliary building areas
- (2) Containment building areas
- (3) Nuclear instrument (N42) detector and cable replacement
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.
71124.02 - Occupational ALARA Planning and Controls
Radiological Work Planning (IP Section 03.01) (5 Samples)
The inspectors evaluated the licensees radiological work planning.
- (1) ALARA Plan #: 2021HNPH123R1-003-Seal Table Activities, Rev. 0
- (2) ALARA Plan #: 2021HNPH123R1-004-Cavity Decon (Medium & High Risk), Rev. 0
- (3) ALARA Plan #: 2021HNPH123-005-Refueling Activities-HRRSA, Rev. 0
- (4) ALARA Plan #: 2021HNPH123R1-001-N42Detector Replacement (M-RRSA),Rev. 0
- (5) ALARA Plan #: 2021HNPH123R1-002-Radiography, Rev. 0
Verification of Dose Estimates and Exposure Tracking Systems (IP Section 03.02) (5 Samples)
The inspectors evaluated dose estimates and exposure tracking. The inspectors reviewed the following as low as reasonably achievable planning and radiological outcome evaluation documents:
- (1) ALARA Plan #: 2021HNPH123R1-003-Seal Table Activities, Rev. 0
- (2) ALARA Plan #: 2021HNPH123R1-004-Cavity Decon (Medium & High Risk), Rev. 0
- (3) ALARA Plan #: 2021HNPH123-005-Refueling Activities-HRRSA, Rev. 0
- (4) ALARA Plan #: 2021HNPH123R1-001-N42Detector Replacement (M-RRSA),Rev. 0
- (5) ALARA Plan #: 2021HNPH123R1-002-Radiography, Rev. 0
Implementation of ALARA and Radiological Work Controls (IP Section 03.03) (2 Samples)
The inspectors reviewed as low as reasonably achievable practices and radiological work controls.
The inspectors reviewed the following activities:
- (1) ALARA In-Progress Review at 50% - ALARA Plan 2021HNPH123R1-003, Seal Table Activities, 05/01/2021
Radiation Worker Performance (IP Section 03.04) (2 Samples)
The inspectors evaluated radiation worker and radiation protection technician performance during:
- (1) Reactor head Lift
- (2) Seal table maintenance work
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) Unit 1 reactor building purge ventilation system.
- (2) Main control room and emergency switchgear room emergency ventilation system
Temporary Ventilation Systems (IP Section 03.02) (2 Samples)
The inspectors evaluated the configuration of the following temporary ventilation systems:
- (1) Seal Table HEPA unit installed in Unit 1 containment.
- (2) Unit 1 pressurizer HEPA and charcoal unit
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's external dosimetry program.
Internal Dosimetry (IP Section 03.03) (1 Sample)
The inspectors evaluated the internal dosimetry program implementation.
- (1) The inspectors reviewed the following:
- There were no whole-body counts (WBCs), in vitro analysis, or air sampling analyses which resulted in a committed effective dose equivalent (CEDE)assignment equal to or exceeding 10 millirem during the period covered by the inspection.
- The inspectors reviewed 3 positive WBCs which had positive activity but did not result in CEDE assignments exceeding 10 mrem and evaluated the licensee's procedures for assessing internal dose.
Special Dosimetric Situations (IP Section 03.04) (1 Sample)
The inspectors evaluated the following special dosimetric situation:
- (1) Licensees implementation of requirements to manage radiation protection of one declared pregnant worker in 2020.
71124.05 - Radiation Monitoring Instrumentation
Walkdowns and Observations (IP Section 03.01) (9 Samples)
The inspectors evaluated the following radiation detection instrumentation during plant walkdowns:
- (1) Canberra iCAM Alpha/Beta Air Monitor EnRad ID: 13203 located in the technical support center and EnRad ID: 07894 located in the waste processing building
[Observed weekly source check]
- (2) Area radiation monitors located in the auxiliary building and waste processing building (WPB)
- (3) Portable survey instruments available for use: Telepole II EnRad ID: 13425/16055; Telepole EnRad ID: 07581; Ludlum Model 9-3 EnRad ID: 12067 and 10288
[Observed weekly source checks]
- (4) Canberra Argos beta/gamma personnel contamination monitor located at the RCA exit. EnRad ID: 12268 [Observed weekly source check]
- (5) Canberra Cronos tool & equipment monitors located in dosimetry and at several RCA exit points. EnRad IDs: 12473, 12950, and 13456 [Observed weekly source check]
- (6) Canberra GEM-5 (gamma) portal monitors located at the protected area exit. EnRad IDs: 13457 [Observed weekly source check]
- (7) Canberra GEM-5 (gamma) portal monitors located in dosimetry and at the RCA exit.
EnRad IDs: 10800 and 13450 [Observed weekly source check]
- (8) Portable friskers located at various locations in the auxiliary building and at the RCA exit
- (9) Ludlum Model 3030P alpha/beta scaler located at the main RCA exit
Calibration and Testing Program (IP Section 03.02) (15 Samples)
The inspectors evaluated the calibration and testing of the following radiation detection instruments:
- (1) Ludlum Model 9-3 Ion Chamber, SN:279916 (EnRad ID:10228), Cal. Date:
08/26/2020
- (2) Canberra iCAM Alpha/Beta Air Monitors, SN:6050 (EnRad ID:13217), Cal. Date:
12/08/2020; SN:6185 (EnRad ID:13483), Cal. Date: 11/12/2020
- (3) Canberra Sirius-5PB Hand/Foot Monitor, SN:2006-151 (EnRad:13453), Cal. Date:
10/10/2020
- (4) Rotem Ind. AMP-100 Area Monitor, SN:5013-056 (EnRad ID:12404), Cal. Date:
06/18/2020
- (5) Canberra Argos-5AB, SN:1111-166 (EnRad ID:10244), Cal. Dates: 07/24/2019 and 07/17/2020
- (6) Canberra Cronos-1, SN:1312-359 (EnRad ID:12473), Cal. Dates: 08/28/2019 and 07/14/2020
- (7) Canberra GEM-5 Whole Body Counter, SN:1409-172 (EnRad ID:10798), Cal. Dates:
01/15/2020 and 12/08/2020
- (8) RM-3589SA, High Range Containment Post Accident Monitor, Cal. Dates:
10/20/2019 and 05/08/2021
- (9) Ludlum Model 9-3 Ion Chamber, SN: 308350 (EnRad ID: 07650), Cal. Dates:
02/18/2019 and 06/08/2020
- (10) HNPFS1/Fastscan 1, 11/13/2020
- (11) HNPFS2/Fastscan 2, 11/13/2020
- (12) Gamma Spectroscopy System Detector # 4, SN: 54-P51384A, Cal. Dates:
09/16/2019 and 08/05/2020
- (13) Gas Flow Proportional counter, Tennelec 1, SN: 0614521-1, Cal Date: 06/24/2019 and 07/30/20
- (14) RM-3590SB High Range Containment Post Accident Monitor, Work Order (WO)
===2039494001, 05/08/2021
- (15) RM-3566B, Spent Fuel Building North, Cal Dates: WO 2028881601, 06/13/2019 and WO 2039609601, 03/03/2021
Effluent Monitoring Calibration and Testing Program Sample (IP Sample 03.03)===
The inspectors evaluated the calibration and maintenance of the following radioactive effluent monitoring and measurement instrumentation:
- (1) RM-3541, Waste Monitor Tank (liquid radwaste effluent release) Radiation Monitor - WO 2028079101, 05/02/2019 and WO 20389250 01, 12/02/2020
- (2) RM-3509-1SA, Plant Vent Stack Accident Monitor - WO 2022379401, 01/14/2019 and WO 2035144401, 11/11/2020
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below:
MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 03.04)===
- (1) April 2020 through March 2021
BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 03.10) (1 Sample)
- (1) April 2020 through March 2021
BI02: RCS Leak Rate Sample (IP Section 03.11) (1 Sample)
- (1) April 2020 through March 2021
OR01: Occupational Exposure Control Effectiveness Sample (IP Section 03.15) (1 Sample)
- (1) November 2020 through March 2021
PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent Occurrences Sample (IP Section 03.16) (1 Sample)
- (1) November 2020 through February 2021
71152 - Problem Identification and Resolution
Semiannual Trend Review (IP Section 02.02) (1 Sample)
- (1) The inspectors reviewed the licensees corrective action program for potential adverse trends in equipment and human performance that might be indicative of a more significant safety issue.
Annual Follow-up of Selected Issues (IP Section 02.03) (1 Sample)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issue:
(1)
'B' RHR pump motor breaker failed to operate due to loose wire in breaker charging spring motor mechanism on March 29, 2021 (NCR 02376252)
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On July 19, 2021, the inspectors presented the integrated inspection results to Ms. Kim Maza, Site Vice President and other members of the licensee staff.
- On May 18, 2021, the inspectors presented the radiation protection inspection results to Ms. Kim Maza, Site Vice President and other members of the licensee staff.
- On May 14, 2021, the inspectors presented the Unit 1 inservice inspection results to Mr. John Dills, Plant Manager and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Drawings
CPL-2165-S-0544
Simplified Flow Diagram Feedwater System Unit 1
Rev. 40
Procedures
Auxiliary Feedwater System
Rev. 046
Procedures
Essential Services Chilled Water System
Rev. 82
Procedures
OST-1411
Auxiliary Feedwater Pump 1X-SAB Operability Test Quarterly
Interval Mode 1, 2, 3
Rev. 052
Fire Plans
CSD-HNP-PFP-
Containment Building Pre-Fire Plan
Rev. 0
Fire Plans
CSD-HNP-PFP-
DGB
Diesel Generator Building Pre-Fire Plan
Rev. 1
Fire Plans
CSD-HNP-PFP-
RAB-190-216
Reactor Auxiliary Building Elevations 190 and 216 Pre-Fire
Plan
Rev. 1
Fire Plans
CSD-HNP-PFP-
RAB-261
Reactor Auxiliary Building Elevation 261 Pre-Fire Plan
Rev. 1
Fire Plans
CSD-HNP-PFP-
RAB-286
Reactor Auxiliary Building Elevation 286 Pre-Fire Plan
Rev. 1
Fire Plans
CSD-HNP-PFP-
SEC
Out Building Pre-Fire Plan
Rev. 8
Drawings
CAR 2166-B-058,
Index 1, Sheet 1
of 5
Manhole & Manhole Details
Rev. 27
Drawings
CAR 2166-G-
0055, Sheet S01
Yard Duct Runs Unit 1
Rev. 26
Procedures
AD-EG-ALL-1615
Cable Aging Management Program - Implementation
Rev. 3
Procedures
AP-046
Control of Environmental Protective Features
Rev. 9
Work Orders
Inspect manholes and cables associated with manholes
M70A-SA, M70B-SA, M71A-SA, and M71B-SA
5/18-20/2021
Work Orders
'A' ESCW condenser tube inspections, cleaning, and tube
plugging
5/1-3/2021
Work Orders
'A' CCW heat exchanger inspections, tube cleaning, and
plugging
5/1-3/2021
Calibration
Records
Parker Research Corporation Certification: MT Contour Probe
(SN 29738)
3/5/20
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Calibration
Records
Calibration Standard Inspection Log: UT Cal Block (No. UT-
20-2)
1/27/86
Calibration
Records
2581
Standards Laboratory Instrument Certification: Digital
Thermometer (SN G507831)
10/27/2020
Corrective Action
Documents
04/26/2021
Engineering
Evaluations
Harris Steam Generator H1R23 Skipped Inspection Cycle
Outage Review
Rev. 0
Miscellaneous
Certificate of Method Qualification: UT II-N (Jensen)
2/19/2020
Miscellaneous
Visual Acuity Record (Jensen)
6/2/2020
Miscellaneous
Visual Acuity Record (Regan)
2/4/21
Miscellaneous
Certificate of Method Qualification: UT II-N (Regan)
4/13/2020
Miscellaneous
Magnaflux Certification: Ultragel II Couplant (Batch 20G038)
07/24/2020
Miscellaneous
Visual Acuity Record (May)
2/3/2020
Miscellaneous
Certificate of Method Qualification: UT II-N (May)
8/5/2020
Miscellaneous
Curtiss-Wright Personnel Certification Statement: UT III
(Blechinger)
2/09/2020
Miscellaneous
Curtiss-Wright Certification of Visual Acuity and Color Vision
per LMT Procedure PVE-1 (Blechinger)
07/20/2020
Miscellaneous
Magnaflux Certification: Spotcheck Penetrant SKL-SP2 (Batch
17B04K)
2/08/2017
Miscellaneous
Certificate of Method Qualification: MT II-N (Ransom)
10/5/20
Miscellaneous
Curtiss-Wright Personnel Certification Statement: PT III
(Blechinger)
2/09/2020
Miscellaneous
Magnaflux Certification: Spotcheck Developer SKD-S2 (Batch
18A10K)
01/12/2018
Miscellaneous
Magnaflux Certification: Spotcheck Cleaner SKC-S (Batch
18G14K)
07/27/2018
Miscellaneous
Visual Acuity Record (Ransom)
7/30/2020
Miscellaneous
193A
Procedure Qualification Record
11/10/93
Miscellaneous
GTSM0101-01
ASME Section IX Welding Procedure Specification
Rev. 10
Miscellaneous
GTSM0101-01
Record of Welder Performance Qualification Test - ASME
Section IX Groove Weld (Patterson)
10/31/2016
Miscellaneous
L-102E
Procedure Qualification Record
9/30/98
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
Procedure Qualification Record
9/26/75
Miscellaneous
Procedure Qualification Record
7/9/75
Miscellaneous
L-146D
Procedure Qualification Record
7/9/97
NDE Reports
MT-21-001
Magnetic Particle Examination Report (II-SG-001SGB-
FWNTSW-05-1)
5/4/2021
NDE Reports
UT-21-011
UT Calibration/Examination Report (II-SI-024SI-FW-587)
4/30/2021
NDE Reports
UT-21-023
UT Calibration/Examination Report (1RC6-47SB)
4/30/2021
Procedures
AD-EG-PWR-
1611
Boric Acid Corrosion Control Program - Implementation
Rev. 4
Procedures
NDE-NE-ALL-
3101
Magnetic Particle Examination
Rev. 003
Procedures
NDE-NE-ALL-
4101
Liquid Penetrant Examination
Rev. 003
Procedures
NDE-NE-ALL-
6102
Utilization of PDI-UT-2 Generic Procedure for the Ultrasonic
Examination of Austenitic Pipe Welds
Rev. 003
Procedures
NDE-NE-ALL-
6106
Ultrasonic Examination of Mid or Large Diameter Piping Welds
and Base Materials for Thermal Fatigue Damage
Rev. 002
Procedures
NDE-NE-ALL-
6403
Straight Beam Ultrasonic Examination
Rev. 001
Procedures
PD-EG-PWR-
1611
Boric Acid Corrosion Control Program
Rev. 1
Procedures
PT-21-003
Liquid Penetrant Examination Report (SI-H-0960-ATT)
4/30/2021
Procedures
TE-MN-PWR-
0006
Inspection, Assessment, and Cleanup of Boric Acid on Plant
Materials
Rev. 1
Procedures
WLD-EG-ALL-
24
Filler Material Control and Issuance
Rev. 0
Work Orders
WO20330314 02
M,3SW12-84SA-1, Replace WC-2A Condenser SW Return
Spool Piece
03/30/21
71111.11Q Miscellaneous
Reactivity
Manipulation Plan
H1C23 Shutdown to Support RFO23
Rev. 0
71111.11Q Procedures
AD-OP-ALL-1000
Conduct of Operations
Rev. 17
71111.11Q Procedures
EOP-FR-H.1
Response to Loss of Secondary Heat Sink
Rev. 5
71111.11Q Procedures
GP-004
Reactor Startup (Mode 3 to Mode 2)
Rev. 67
71111.11Q Procedures
GP-006
Normal Plant Shutdown from Power Operation to Hot Standby
Rev. 93
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
(Mode 1 to Mode 3)
71111.11Q Procedures
GP-008
Draining the Reactor Coolant System
Rev. 49
71111.11Q Procedures
OMM-001
Operations Administrative Requirements
Rev. 121
Procedures
AD-NF-ALL-0501
Electronic Risk Assessment Tool (ERAT)
Rev. 5
Procedures
AD-OP-ALL-0201
Protected Equipment
Rev. 8
Procedures
AD-OP-ALL-0210
Operational Risk Management
Rev. 1
Procedures
AD-WC-ALL-0200
On-Line Work Management
Rev. 19
Procedures
AD-WC-ALL-0240
On-Line Risk Management Process
Rev. 19
Procedures
AD-WC-ALL-0410
Work Activity Integrated Risk Management
Rev. 11
Procedures
AD-WC-ALL-0420
Shutdown Risk Management
Rev. 7
Procedures
AD-WC-HNP-
20
HNP Shutdown Risk Management
Rev. 6
Corrective Action
Documents
Multiple control rods have Data A alarms
5/13/2021
Engineering
Evaluations
Action Request
2324970
CFR 50.59 screening for EC 416783
4/13/2020
Engineering
Evaluations
Action Request
2382090
CFR 50.59 screening for EC 419555
5/12/2021
Procedures
AD-EG-ALL-1110
Design Review Requirements
Rev. 9
Procedures
AD-EG-ALL-1133
Preparation and Control of Design Equivalent Change
Engineering Changes
Rev. 14
Procedures
AD-EG-ALL-1155
Post Modification Testing
Rev. 4
Work Orders
Replacement of valve 1CC-252 under EC 416783
5/11/2021
Work Orders
Install temporary modification EC 419555
5/20/2021
Procedures
PLP-400
Post Maintenance Testing
Rev. 64
Work Orders
Annual Preventive Maintenance on the Dedicated Shutdown
Diesel Generator
6/9/2021
Work Orders
'A' RHR pump motor breaker maintenance
4/19/2021
Work Orders
WOs 13498345
and 20397258
B ESW pump stuffing box and cyclone separator cleaning and
replacement of solenoid associated with valve 1SW-118
6/29/2021
Work Orders
WOs 20384425
and 20394043
Replacement of 125 Volt DC battery 1A-SA
5/8/2021
Work Orders
WOs 20391648
Replace HGBV actuator and clean PRV motor potentiometer
6/22/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
and 20447017
on 'A' ESCW chiller
Procedures
AP-545
Containment Entries
Rev. 62
Procedures
FHP-010
Core Loading Verification
Rev. 22
Procedures
FHP-014
Fuel and Insert Shuffle Sequences
Rev. 66
Procedures
FHP-024
HNP Spent Fuel Handling Operations
Rev. 19
Procedures
GP-001
Reactor Coolant System Fill and Vent Mode 5
Rev. 44
Procedures
GP-002
Normal Plant Heatup from Cold Solid to Hot Subcritical Mode
to Mode 3
Rev. 77
Procedures
GP-004
Reactor Startup (Mode 3 to Mode 2)
Rev. 67
Procedures
GP-005
Power Operation (Mode 2 to Mode 1)
Rev. 113
Procedures
GP-006
Normal Plant Shutdown from Power Operation to Hot Standby
(Mode 1 to Mode 3)
Rev. 97
Procedures
GP-007
Normal Plant Cooldown Mode 3 to Mode 5
Rev. 74
Procedures
GP-008
Draining the Reactor Coolant System
Rev. 49
Procedures
GP-009
Refueling Cavity Fill, Refueling and Drain of the Refueling
Cavity Modes 5-6-5
Rev. 71
Procedures
OMM-031
Implementation of Containment Closure
Rev. 12
Procedures
OPT-1519
Containment Visual Inspection for Boron and Evaluation of
Containment Sump Inleakage Every Refueling Outage
Shutdown Mode 3
Rev. 13
Procedures
OST-1081
Containment Visual Inspection When Containment Integrity is
Required Mode 5
Rev. 22
Self-Assessments AR 02365680
Refueling Outage Independent Review Team (IRT) for H1R23
3/30/2021
Corrective Action
Documents
Harris Nuclear Plant Rapid Notification Message - Harris
Stand Down
05/11/2021
Corrective Action
Documents
Corrective Action
Documents
Resulting from
Inspection
2381888
05/10/2021
Radiation Surveys HNP-M-
210424-20
RCB 250 Upper & Lower Reactor Cavity
04/24/2021
Radiation Work
RWP 1009
Miscellaneous Maintenance RCB (HRA Access)
Rev. 12
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Permits (RWPs)
Radiation Work
Permits (RWPs)
RWP1032
N42 Detector and Cable Replacement
Rev. 0
ALARA Plans
Harris Nuclear Plant ALARA Long Range Plan 2020 - 2025
Rev. 9
ALARA Plans
Harris Nuclear Plant H1R22 Refueling Outage RP/ALARA
Report
ALARA Plans
Harris Nuclear Plant H1R21 Refueling Outage RP/ALARA
Report
08/02/2018
ALARA Plans
21HNP123R1-
003
Seal Table Activities
Revs. 0 and
ALARA Plans
21HNP123R1-
005
Refueling Activities
Rev. 0
ALARA Plans
21HNPH123-
005
N42 Detector Replacement
Rev. 0
Corrective Action
Documents
2366130, and
2370684
Corrective Action Reports
Various
Procedures
AD-CP-ALL-0012
Radiation Source Term
Rev. 1
Procedures
AD-MN-ALL-0005
Nuclear Planning
Rev. 21
Procedures
AD-RP-ALL-2000
PREPARATION AND MANAGEMENT OF RADIATION
WORK PERMITS (RWP)
Rev. 4
Procedures
AD-RP-ALL-2006
RADIATION PROTECTION RISK MANAGEMENT PROCESS
Rev. 6
Procedures
AD-RP-ALL-2019
TEDE-ALARA EVALUATIONS AND DAC-HOUR TRACKING
Rev. 3
Procedures
AD-RP-ALL-9000
ALARA Program
Rev. 9
Procedures
AD-RP-ALL-9001
ALARA Planning
Rev. 5
Procedures
AD-RP-ALL-9002
SENTINEL ALARA MANAGEMENT
Rev. 1
Procedures
AD-RP-ALL-9007
RADIATION PROTECTION SOURCE TERM REVIEW
Rev. 2
Procedures
AD-WC-ALL-0200
ON-LINE WORK MANAGEMENT
Rev. 14
Procedures
CSD-CP-HNP-
0001
Harris Primary Chemistry Strategic Plan
Rev. 5
Procedures
MNT-NGGC-0003
Radiation Shielding Use
Rev. 17
Radiation Surveys HNP-M-
210427-18
Retracting Flux Thimbles
04/27/2021
Radiation Surveys HNP-M-
H1R23 Flux Thimble Replacement/Seal Table
05/01/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
210501-1
Radiation Surveys HNP-M-
210501-13
Thimble Tube Cutting Tool
05/01/2021
Radiation Surveys HNP-M-
210503-27
Retracting Thimbles ~3" / Seal Table Room
05/03/2021
Radiation Surveys HNP-M-
210507-13
Tri-Nuke and Tri-Nuke Housing [underwater survey]
05/07/2021
Radiation Surveys HNP-M-
210509-36
Seal Table Room / Thimble Insertion
05/09/2021
Radiation Work
Permits (RWPs)
RWPs 1010,
1013,1015, 1016,
22, 1024, 1032,
1036, and 1040
Radiation Work Permits
Various
Work Orders
Work Orders
20394854-01,
20362767-02,
20362768-02,
20375246-01, and
20420372-01
Work Orders
Various
Corrective Action
Documents
Resulting from
Inspection
2380246
04/28/2021
Procedures
AD-RP-ALL-0008
Use and Control of HEPA Filtration and Vacuum Equipment
Rev. 0
Procedures
AD-RP-ALL-2014
Work in Alpha Environments
Rev. 7
Procedures
AD-RP-ALL-6001
Quantitative Fit Testing
Rev. 3
Procedures
AD-RP-ALL-6002
Inspections of Self-Contained Breathing Apparatus (SCBA and
Associated Equipment)
Rev. 2
Procedures
HPP-630
Respiratory Protection
Rev. 35
Procedures
AD-RP-ALL-4010
Internal Dose Assessment
Rev. 3
Procedures
AD-RP-ALL-4011
In Vitro Bioassay
Rev. 3
Procedures
CSD-RP-HNP-
0001
Alpha Radiation Characterization
Rev. 005
Corrective Action
Corrective Action Reports
Various
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Documents
2334551,
2358756, and
2363438
Engineering
Changes
Evaluate Area Radiation Monitor Calibration Reference Values Rev. 0
Engineering
Changes
Radiation Monitoring System (RMS) Migration to the
Distributed I&C System Platform (DICSP) / Abandonment of
Non-Critical Plant Radiation Monitors (RM-80s)
Rev. 147
Procedures
ENRAD 802, 808,
20, 823, 826,
28, 831, 839,
841, 842, 854,
855, 857, and 862
ENRAD 802, 808, 820, 823, 826, 828, 831, 839, 841, 842,
854, 855, 857, and 862
Various
Procedures
Waste Monitor Tanks and Waste Evaporator Condensate
Tanks Discharge Radiation Monitor REM-21WL-3541
Calibration
Rev. 15
Procedures
Plant Vent Stack Accident Monitor RM-21AV-3509-1SA
Calibration
Rev. 25
Procedures
Spent Fuel Pool North Area Radiation Monitor
RM-*1FR-3566ASA Calibration
Rev. 12
Procedures
Spent Fuel Pool North Area Radiation Monitor RM-*1FR-
3566BSB Calibration
Rev. 11
Procedures
Containment High Range Accident Monitor RM-01CR-3589SA
Calibration
Rev. 16
Procedures
Containment High Range Accident Monitor RM-01CR-3590SB
Calibration
Rev. 18
71151
Miscellaneous
21 Liquid and
Gaseous Effluents
Report (YTD-
March 10, 2021)
21 Liquid and Gaseous Effluents Report (YTD)
03/10/2021
71151
Miscellaneous
AR3749 Dose
Alarm Report
(November 2020 -
April 19, 2021)
AR3749 Dose Alarm Report (November 2020 - April 19, 2021)
04/19/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71151
Miscellaneous
AR3750 Dose
Rate Alarms
Report
(November 2020 -
April 19, 2021)
AR3750 Dose Rate Alarms Report (November 2020 -
April 19, 2021)
04/19/2021
71151
Miscellaneous
Licensee Event
Reports between
20 - 2021
71151
Miscellaneous
Operator Log
Entries between
20 - 2021
71151
Procedures
AD-PI-ALL-0700
Performance Indicators
Rev. 4
71151
Procedures
AD-PI-ALL-0700
PERFORMANCE INDICATORS
Rev. 4
71151
Procedures
AD-RP-ALL-1101
PERFORMANCE INDICATORS (PI) FOR THE
OCCUPATIONAL AND PUBLIC RADIATION SAFETY
CORNERSTONES
Rev. 0
71151
Procedures
OST-1026
Reactor Coolant System Leakage Evaluation, Computer
Calculation Daily Interval, Mode 1-2-3-4
Rev. 54
71151
Procedures
RCP-711
Dose Equivalent Iodine 131 Calculation
Rev. 9
71151
Procedures
RST-204
Reactor Coolant System Chemistry and Radiochemistry
Surveillance
Rev. 32
Procedures
AD-PI-ALL-0100
Corrective Action Program
Rev. 25
Procedures
AD-PI-ALL-0101
Root Cause Evaluation
Revs. 7 and
Procedures
AD-PI-ALL-0106
Cause Investigation Checklists
Revs. 5 and
6