IR 05000400/2020004

Integrated Inspection Report 05000400/2020004

ML21027A108
Person / Time
Site:	Harris
Issue date:	01/27/2021
From:	Stewart Bailey NRC/RGN-II/DRP/RPB4
To:	Maza K Duke Energy Progress
References
IR 2020004
Download: ML21027A108 (30)

Text

January 27, 2021

SUBJECT:

SHEARON HARRIS NUCLEAR POWER PLANT - INTEGRATED INSPECTION REPORT 05000400/2020004

Dear Ms. Maza:

On December 31, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Shearon Harris Nuclear Power Plant. On January 20, 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.

One finding of very low safety significance (Green) is documented in this report. This finding involved a violation of NRC requirements. We are treating this violation as a non-cited violation (NCV) consistent with Section 2.3.2 of the Enforcement Policy.

If you contest the violation or the significance or severity of the violation documented in this inspection report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN:

Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region II; the Director, Office of Enforcement; and the NRC Resident Inspector at Shearon Harris Nuclear Power Plant. 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/

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: NPF-63 Report Number: 05000400/2020004 Enterprise Identifier: I-2020-004-0042 Licensee: Duke Energy Progress, LLC Facility: Shearon Harris Nuclear Power Plant Location: New Hill, NC 27562 Inspection Dates: October 1, 2020 to December 31, 2020 Inspectors: J. Zeiler, Senior Resident Inspector A. Patz, Resident Inspector J. Diaz-Velez, Senior Health Physicist B. Kellner, Senior Health Physicist J. Rivera, Health Physicist G. Smith, Senior Resident Inspector J. Steward, Resident Inspector Approved By: Stewart N. Bailey, Chief Reactor Projects Branch 4 Division of Reactor Projects Enclosure

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

Inadequate Surveillance Procedure for Control Rod Testing Resulted in Unnecessary Manual Reactor Trip in Response to a Dropped Control Rod Cornerstone Significance Cross-Cutting Report Aspect Section Initiating Events Green None (NPP) 71153 NCV 05000400/2020004-01 Open/Closed A self-revealing finding of very low safety significance (Green) and associated non-cited violation (NCV) of Technical Specification (TS) 6.8.1.a, Procedures and Programs, was identified for the licensees failure to maintain an adequate procedure for conducting control rod TS surveillance testing. Specifically, the procedure inappropriately directed operator action to manually trip the reactor for a dropped control rod that occurred during testing.

Additional Tracking Items

Type Issue Number Title Report Section Status LER 05000400/2020-002-00 Unit 1 Manual Reactor Trip 71153 Closed Due to Control Rod Drop During Surveillance Testing

PLANT STATUS

Unit 1 operated at or near rated thermal power until December 15, 2020, when the unit was down powered to 80 percent for a degraded lube oil problem on the 'A' condensate booster pump. On December 16, 2020, while preparing to make repairs on the condensate booster pump, an unrelated automatic reactor trip occurred due to a main generator lockout resulting from an electrical fault on the 'B' train non-safety electrical distribution system. Following a forced outage to address the electrical fault and 'B' condensate booster pump, as well as conduct other plant repair items, Unit 1 was restarted on December 21, 2020. The unit was returned to near rated thermal power on December 23, 2020 and 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 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 on December 1, 2020

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' emergency service water (ESW) train while 'A' ESW train was out of service for preventive maintenance on October 13, 2020

(2) 'B' emergency diesel generator (EDG) while 'A' EDG was out of service for emergent output breaker relay failure on October 15, 2020

(3) 'A' and 'B' motor driven auxiliary feedwater systems during startup from reactor trip and forced outage on December 20, 2020

Complete Walkdown Sample (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated system configurations during a complete walkdown of the alternate seal injection system on October 6, 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) Reactor Auxiliary Building (RAB) 261' elevation alternate seal injection and filter area (fire zone 1-A-4-COMC) on October 6, 2020

(2) 'A' and 'B' ESW pump intake structure (fire zones 12-I-ESWPA, 12-I-ESWPA-BAL, 12-I-ESWPB, 12-I-ESWPB-BAL, and 12-I-ESW-BAL) on October 13, 2020

(3) 'B' EDG room and support equipment areas (fire zones 1-D-1-DGB-RM, 1-D-3-DGB-ES, 1-D-DTB, 1-D-1-DGB-ASU, and 1-D-1-DGB-ER) on October 15, 2020

(4) RAB 236' elevation mechanical penetration room (fire zone 1-A-30MP) on December 3, 2020

(5) RAB 286' elevation 'B' train essential switchgear room, ventilation room, and battery room (fire zones 1-A-SWGRB, 1-A-HVB, and 1-A-BATB) on December 21, 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) Diesel fuel oil storage transfer building on October 13, 2020

71111.07A - Heat Sink Performance

Annual Review (IP Section 03.01) (1 Sample)

The inspectors evaluated readiness and performance of:

(1) * 'B' essential services chilled water (ESCW) condenser heat exchanger and service water valves

• 'B' train containment fan cooler units AH-1 and AH-4 heat exchangers and service water valves

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, the crew simulator operating examinations, and the biennial written examinations in accordance with 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 and biennial written examination completed on November 6, 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) The inspectors observed and evaluated licensed operator performance in the Control Room during control rod testing and select control rod drive mechanism coil current data acquisition on November 2, 2020

Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)

(1) The inspectors observed and evaluated a simulator scenario for an annual operator requalification examination involving a faulted steam generator tube rupture on October 28, 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) Failure of the 'A' EDG output breaker ability to automatically open on valid signal on

October 14, 2020 Quality Control (IP Section 03.02) (1 Sample)

The inspectors evaluated the effectiveness of maintenance and quality control activities to ensure the following SSC remains capable of performing its intended function:

(1) Electrical ground fault in 'B' EDG governor digital speed reference unit on October 28, 2020

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 emergent alternate seal injection system non-functionality due to squib valves exceeding vendor assigned usage dates on October 6, 2020

(2) Elevated (Green) risk during planned unavailability of the 'A' ESW pump for preventive maintenance on October 13, 2020

(3) Elevated (Green) risk during unavailability of 'A' EDG and engineered safety features actuation system sequencer during emergent repair of failed 'A' EDG output breaker position status light and associated sequencer relay on October 15, 2020

(4) Elevated (Green) risk during planned unavailability of the 'B' EDG during corrective maintenance on October 27, 2020

(5) Elevated (Green) risk during startup from reactor trip on December 16, 2020

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) Alternate seal injection squib valves installed past their vendor recommended expiration date (Nuclear Condition Report (NCR) 02351994) on October 6, 2020

(2) 125 volt direct current (VDC) ground indication on 'B' EDG governor digital speed reference unit (NCRs 02355227 and 02352458) on October 28, 2020

(3) 'A' EDG output breaker position status circuitry sequencer relay failure (NCR 02353323) on October 17, 2020

(4) Scaffold clearance deviation on safety-related 'B' ESCW make-up tank service water inlet piping (NCR 02354131) on December 3, 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) Operations procedure (OP)-139, Service Water System, Section 5.2, Supplying ESW Headers with an ESW Pump, following scheduled cleaning of stuffing box and seal water piping of 'A' ESW pump on October 13, 2020

(2) OP-155, Diesel Generator Emergency Power System, Section 5.1 and 5.3, for starting 'A' EDG and synchronizing/paralleling to bus, following replacement of failed output breaker relay SN-SA on October 15, 2020

(3) OP-155, Diesel Generator Emergency Power System, Section 8.20 for resetting the governor electronic speed control on October 27, 2020

(4) Operations periodic test (OPT)-1546, TSC Emergency Ventilation System Performance Test Quarterly Interval at All Times, following emergent repair of failed air line to outside air intake damper on December 2, 2020

(5) PM-E0003, 6.9KV Bus and Cubicle, switchgear/bus inspections and testing following electrical fault repairs to 'B' Auxiliary Bus on December 17-19, 2020

(6) Post-modification functional testing under instructions in Engineering Change 418833 following cable repairs resulting from electrical fault on December 20, 2020

(7) OPT-1512, Essential Chilled Water Turbopak Units Quarterly Inspection/Checks Modes 1-6, following emergent repair of 'B' ESCW chiller hot gas bypass valve actuator on December 30, 2020

71111.20 - Refueling and Other Outage Activities

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

(1) The inspectors evaluated forced outage activities during recovery from an electrical fault in the busduct from the 'B' Unit Auxiliary Transformer to the 'B' Auxiliary Bus from December 16-22, 2020

71111.22 - Surveillance Testing

The inspectors evaluated the following surveillance tests:

Surveillance Tests (other) (IP Section 03.01)

(1) OST-1005, Control Rod and Rod Position Indicator Exercise Quarterly Interval Modes 1-3, on November 2, 2020

(2) OST-1010A, A Train Containment Cooling System Operability Test Monthly Interval Modes 1-4, on November 27, 2020

(3) OP-104, Rod Control System, Section 8.19, for exercising all control rods during forced outage using work order 20423639 on December 18-19, 2020

Inservice Testing (IP Section 03.01) (1 Sample)

(1) OST-1076, Auxiliary Feedwater Pump 1B-SB Operability Test Quarterly Interval Modes 1 - 4, on October 5, 2020

71114.06 - Drill Evaluation

Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)

The inspectors evaluated:

(1) A simulator-based licensed operator training evolution involving a faulted steam generator tube rupture on October 28,

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) (3 Samples)

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

(1) Observed licensee surveys of potentially contaminated material leaving the radiological controlled area (RCA) exit point

(2) Observed workers exiting the RCA exit point

(3) Observed licensee routine periodic radiological survey of the old reactor head storage facility High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (4 Samples)

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

(1) RAB - Spent Fuel Transfer Tube Hatch (Locked and Posted Grave Danger)

(2) Waste Processing Building (WPB) - Waste Holdup Tank (Locked and posted Locked High Radiation Area (LHRA))

(3) WPB Room 144A - Access Gate (LHRA key control and posted LHRA)

(4) WPB Room 144A Drum Crane - Crane controls Locked (LHRA lock/key and posted LHRA)

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.

71124.06 - Radioactive Gaseous and Liquid Effluent Treatment

Walkdowns and Observations (IP Section 03.01) (4 Samples)

The inspectors evaluated the following radioactive effluent systems during walkdowns:

(1) Turbine building wide range gaseous detection system to turbine vent stack

(2) Reactor auxiliary building wide range gaseous detection system to plant vent stack

(3) WPB wide range gaseous detection system to WPB vent stack

(4) Liquid effluent discharge and detection system

Sampling and Analysis (IP Section 03.02) (4 Samples)

Inspectors evaluated effluent samples reports and selective compensatory samples.

(1) Liquid Effluent Radiochemistry Surveillance Report #L-2020-0003 and L-2020-0029

(2) Liquid Effluent Radiochemistry Surveillance Report #L-2020-0031 and L-2020-0032

(3) Gaseous Effluent Radiochemistry Surveillance Reports #G-2020-0002, G-2020-0003, and G-2020-0181

(4) Gaseous Effluent Radiochemistry Surveillance Reports #G-2020-0182 and

G-2020-0183 Dose Calculations (IP Section 03.03) (2 Samples)

The inspectors evaluated the following dose calculations:

(1) Dose Calculations associated with Liquid Effluent Radiochemistry Surveillance Report

1. L-2020-0003, L-2020-0029, L-2020-0031, and L-2020-0032

(2) Dose Calculations associated with Gaseous Effluent Radiochemistry Surveillance Reports #G-2020-0182, G-2020-0183, G-2020-0002, G-2020-0003, and G-2020-0181

Abnormal Discharges (IP Section 03.04) (1 Sample)

The inspectors evaluated the following abnormal discharges:

(1) Sample completed in accordance with NRC IMC 306, Planning, Scheduling, Tracking and Reporting of the Reactor Oversight Process (ROP). The sample was not available because there were no unmonitored releases in 2018 and 2019.

71124.07 - Radiological Environmental Monitoring Program

Environmental Monitoring Equipment and Sampling (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated environmental monitoring equipment and observed collection of environmental samples.

Radiological Environmental Monitoring Program (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated the implementation of the licensees radiological environmental monitoring program.

GPI Implementation (IP Section 03.03) (1 Sample)

(1) The inspectors evaluated the licensees implementation of the Groundwater Protection Initiative program to identify incomplete or discontinued program elements.

71124.08 - Radioactive Solid Waste Processing & Radioactive Material Handling, Storage, &

Transportation

Radioactive Material Storage (IP Section 03.01)

(1) Inspectors evaluated the licensees performance in controlling, labeling and securing radioactive materials.

Radioactive Waste System Walkdown (IP Section 03.02) (1 Sample)

(1) Inspectors walked down accessible portions of the solid radioactive waste systems and evaluated system configuration and functionality.

Waste Characterization and Classification (IP Section 03.03) (3 Samples)

(1) The inspectors evaluated the licensees characterization and classification of radioactive waste associated with shipments19-124 and 20-270.

(2) The inspectors evaluated the licensees characterization and classification of radioactive waste associated with shipments19-008 and 19-109.

(3) The inspectors evaluated the licensees characterization and classification of radioactive waste.

Shipping Records (IP Section 03.05) (5 Samples)

The inspectors evaluated the following non-excepted radioactive material shipments through a record review:

(1) Shipping records for shipment 19-008

(2) Shipping records for shipment 19-124

(3) Shipping records for shipment 19-109

(4) Shipping records for shipments20-270

(5) Shipping records for shipment 18-067

OTHER ACTIVITIES - BASELINE

===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:

MS08: Heat Removal Systems (IP Section 02.07) ===

(1) Unit 1 (October 1, 2019 - September 30, 2020)

MS10: Cooling Water Support Systems (IP Section 02.09) (1 Sample)

(1) Unit 1 (October 1, 2019 - September 30, 2020)

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

(1) Unit 1 (November 1, 2019 through 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) Unit 1 (November 01, 2019 through 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 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 issues:

(1) Control rod F-2 in control bank A dropped into the core during routine quarterly control rod surveillance testing on August 13, 2020 (NCRs 02343834 and 02347492)

71153 - Followup of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02)

The inspectors evaluated the following licensee event report (LER):

(1) LER 05000400/2020-002-00, Manual Reactor Trip Due to Control Rod Drop During Surveillance Testing (ADAMS Accession No. ML20286A166). The inspection conclusions associated with this LER are documented in this report under Inspection Results Section 71153. This LER is closed.

Personnel Performance (IP Section 03.03) (1 Sample)

(1) The inspectors evaluated an automatic reactor trip due to an electrical fault in the bus duct for the electrical feeder from the 'B' Unit Auxiliary Transformer (UAT) to the 'B' Auxiliary Bus and licensees performance on December 16,

INSPECTION RESULTS

Inadequate Surveillance Procedure for Control Rod Testing Resulted in Unnecessary Manual Reactor Trip in Response to a Dropped Control Rod Cornerstone Significance Cross-Cutting Report Aspect Section Initiating Events Green None (NPP) 71153 NCV 05000400/2020004-01 Open/Closed A self-revealing finding of very low safety significance (Green) and associated non-cited violation (NCV) of Technical Specification (TS) 6.8.1.a, Procedures and Programs, was identified for the licensees failure to maintain an adequate procedure for conducting control rod TS surveillance testing. Specifically, the procedure inappropriately directed operator action to manually trip the reactor for a dropped control rod that occurred during testing.

Description:

On August 13, 2020, with the unit operating at full power, a single control rod in control bank A, (i.e., rod F-2), dropped into the reactor core during ongoing control rod quarterly TS surveillance testing using procedure OST-1005, Control Rod and Rod Position Indicator Exercise Quarterly Interval Modes 1-3. At the time of the dropped rod, control bank A was being withdrawn from step 225 back to its pre-test position at step 228. Guidance in the procedure via Precaution and Limitations item 11, stated that a dropped rod with any control rods inserted into the core other than the controlling bank is an unanalyzed condition and the reactor must be tripped. In accordance with this instruction, the operators inserted a manual reactor trip in response to the dropped rod. All plant safety systems operated as designed during the reactor trip and the operators successfully placed the plant in a safe configuration.

The licensee determined the cause of the dropped control rod was due to the accumulation of corrosion products in the dashpot region of the control rod drive mechanism (CRDM) for rod F-2 movable gripper latch support assembly. This corrosion prevented the stationary gripper from latching onto the control rod drive shaft when the movable gripper was released. With both the movable and stationary grippers not engaged on the drive shaft, the control rod dropped into the fuel assembly. Corrosion buildup in the CRDM dashpot region was a known industry issue periodically experienced after new CRDMs are installed as part of reactor vessel head replacement projects such as that implemented by Shearon Harris Unit 1 during the Fall 2019 refueling outage. This corrosion buildup continues until a tightly adhered oxide (passivation) layer develops on the CRDM latch assemblies, at which time the accumulation of new corrosion is significantly reduced.

The guidance in OST-1005 to manually trip the reactor for a dropped rod during testing was added to the procedure in May 2008; however, there was no technical basis for the statement that the condition was an unanalyzed condition. Based on a review of the plant licensing basis and safety analysis for a dropped control rod event, the licensee determined that a single dropped control rod that occurs during control rod testing was not an unanalyzed plant condition. Therefore, the operator actions to manually trip the unit on August 13, 2020, was unnecessary.

Corrective Actions: Prior to restarting the unit, the licensee conducted multiple full length exercising all control rods in order to flush corrosion products from the dashpot region of the CRDMs and obtain CRDM coil current traces to detect the presence of corrosion. A preventive maintenance program was developed to routinely exercise the rods while taking coil current traces to break up any further corrosion and monitor performance of the gripper mechanisms to ensure continued CRDM proper operation. The licensee revised OST-1005, to remove the guidance to manually trip the reactor during surveillance testing for a dropped control rod and added direction that the existing guidance for a dropped control rod contained in Abnormal Operating Procedure (AOP)-001, Malfunction of Rod Control and Indication System, should be implemented, which required a controlled plant shutdown if more than two control rods dropped.

Corrective Action References: NCRs 02343834 and 02347492

Performance Assessment:

Performance Deficiency: The licensees failure to maintain an adequate control rod surveillance test procedure that resulted in an unnecessary manual reactor trip when a control rod drop occurred during testing was a performance deficiency.

Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Procedure Quality attribute of the Initiating Events cornerstone and adversely affected the cornerstone objective to limit the likelihood of events that upset plant stability and challenge critical safety functions during shutdown as well as power operations. Specifically, the failure to maintain adequate instructions for addressing a control rod drop transient during testing resulted in an unnecessary manual reactor trip.

Significance: The inspectors assessed the significance of the finding using Appendix A, The Significance Determination Process (SDP) for Findings At-Power. The finding was determined to be of very low safety significance (Green) because when screened as a transient initiator using Exhibit 1, "Initiating Events Screening Questions," it did not cause both a reactor trip AND the loss of mitigation equipment relied upon to transition the plant from the onset of the trip to a stable shutdown condition (e.g., loss of condenser or loss of feedwater).

Cross-Cutting Aspect: Not Present Performance. No cross-cutting aspect was assigned to this finding because the inspectors determined the finding did not reflect present licensee performance. The inadequate direction to manually trip the reactor if a dropped control rod occurred in any control bank other than the controlling bank was added to OST-1005 in 2008.

Enforcement:

Violation: TS 6.8.1.a, Programs and Procedures, requires, in part, that written procedures shall be established, implemented, and maintained covering the activities described in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978. Section 8.b of Appendix A includes surveillance procedures for control rod testing. The licensees procedure for control rod surveillance testing is OST-1005, Quarterly Rod Exercise Testing.

Contrary to the above, from May 2008 to August 13, 2020, the licensee failed to establish, implement, and maintain an adequate surveillance procedure for conducting quarterly control rod testing. Specifically, OST-1005 incorrectly stated that a dropped control rod with any control rods inserted into the core other than the controlling bank was an unanalyzed plant condition and directed the operators to manually trip the reactor. As a result, an unnecessary manual reactor trip was initiated during surveillance testing when a control rod dropped in control bank A during testing on August 13, 2020.

Enforcement Action: This violation is being treated as an non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.

The disposition of this violation closes LER 05000400/2020-002-00, Manual Reactor Trip Due to Control Rod Drop During Surveillance Testing.

EXIT MEETINGS AND DEBRIEFS

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

• On January 20, 2021, the inspectors presented the integrated inspection results to Kim Maza, Site Vice President (Site VP) and other members of the licensee staff.

• On November 23, 2020, the inspectors presented the RP Occupational and Public Radiation Safety Inspection results to Kim Maza, Site VP and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.01 Corrective Action Action Request Winter Readiness 10/08/2020

Documents (AR) 02038102

Procedures AD-WC-ALL-0230 Seasonal Readiness Rev. 0

AP-301 Seasonal Weather Preparations and Monitoring Rev. 86

71111.04 Drawings 2165-G-0871 Flow Diagram Alternate Seal Injection System Unit 1 Rev. 1

2165-S-1371 Simplified Flow Diagram Alternate Seal Injection System Unit Rev. 1

Miscellaneous DBD-320 Alternate Seal Injection System (ASI-System 2007) Rev. 4

Procedures OP-137 Auxiliary Feedwater System Rev. 46

OP-139 Service Water System Rev. 138

OP-155 Diesel Generator Emergency Power System Rev. 91

OP-185 Alternate Seal Injection Rev. 12

OP-186 Dedicated Shutdown Diesel Generator Rev. 9

71111.05 Fire Plans CSD-HNP-PFP- Reactor Auxiliary Building Elevation 261 Pre-Fire Plan Rev. 1

RAB-261

CSD-HNP-PFP- Diesel Generator Building Pre-Fire Plan Rev. 1

DGB

CSD-HNP-PFP- Reactor Auxiliary Building Elevation 236 Pre-Fire Plan Rev. 2

RAB-236

CSD-HNP-PFP- Reactor Auxiliary Building Elevation 286 Pre-Fire Plan Rev. 1

RAB-286

CSD-HNP-PFP- Out Building Pre-Fire Plan Rev. 5

SEC

Procedures AD-EG-ALL-1520 Transient Combustible Control Rev. 13

FPP-001 Fire Protection Program Manual Rev. 44

FPP-013 Fire Protection - Minimum Requirements, Mitigating Actions Rev. 105

and Surveillance Requirements

FPT-3220A Incipient Fire Detection Alarm Notification Functional Test - Rev. 2

Monthly Interval

71111.06 Calculations CALC- HNP - Diesel Fuel Oil Storage Transfer Building Internal Flooding Rev. 3

PRA F-E-0010 Evaluation

71111.07A Procedures AD-EG-ALL-1312 Raw Water Program Implementation Rev. 0

Inspection Type Designation Description or Title Revision or

Procedure Date

EPT-163 Generic Letter 89-13 Inspections (Raw Water Systems and Rev. 19

Local Area Air Handler Inspection and Documentation)

MPT-M0091 Heat Exchanger Opening/Closure for NRC Generic Letter 89- Rev. 18

Inspections

PLP-620 Service Water Program (Generic Letter 89-13) Rev. 21

Work Orders WO 12080977 Inspect and replace AH-4 service water return header isolation 10/16/2016

valve

WO 12080978 Inspect and replace 1SW-98, AH-1 containment fan cooler 10/17/2016

service water outlet valve

WO 13300529 Inspection of AH-1 and AH-4 service water return valve 4/8/2015

WO 1563658 Inspect and replace containment air handler heat exchanger 10/17/2010

for AH-4

WO 20269012 Inspect 'B' ESCW chiller condenser 10/18/2019

WO 20342496 Inspection and cleaning of 'B" ESCW chiller condenser heat 7/17/2019

exchanger

WOs 1563658 Inspect containment air handler AH-1 and AH-4 10/17/2010

and 1527037

71111.11Q Procedures AD-OP-ALL-1000 Conduct of Operations Rev. 17

AD-OP-ALL-1001 Conduct of Abnormal Operations Rev. 3

AOP-001 Malfunction of Rod Control and Indication System Rev. 55

AOP-016 Excessive Primary Plant Leakage Rev. 58

AOP-019 Malfunction of RCS Pressure Control Rev. 25

AOP-042 Secondary Steam Leak/Efficiency Loss Rev. 8

APP-ALB-007 Annunciator Panel Procedure Rev. 16

EOP-E-3 Steam Generator Tube Rupture Rev. 7

OMM-001 Operations Administrative Requirements Rev. 121

OST-1005 Control Rod and Rod Position Indicator Exercise Quarterly Rev. 28

Interval Modes 1-3

Work Orders WO 20424460 CRDM coil current during control rod movement testing 11/02/2020

71111.12 Corrective Action NCR 02353323 Breaker 106 Amber Light Not Lit 10/14/2020

Documents NCR 02354050 Technical Specification Documentation on Common Mode 10/20/2020

Failures

NCR 02355227 Replace EDG 'B' digital reference unit due to ground fault 10/30/2020

Inspection Type Designation Description or Title Revision or

Procedure Date

Drawings CAR 2166-B-401, Emergency Load Sequencer ESS Cabinet 1A-SA Rev. 014

Sheet 1101

Procedures AD-QC-ALL-0108 Nuclear Oversight Vendor QC Acceptance Rev. 2

AD-QC-ALL-1000 Conduct of Nuclear Oversight Quality Control Rev. 9

OP-155 Diesel Generator Emergency Power System Rev. 91

OST-1013 1A-SA Emergency Diesel Generator Operability Test Monthly Rev. 043

Interval, Modes 1-6

Work Orders WO 20412441 Troubleshooting DC ground indication in 'B' EDG governor 10/29/2020

DRU

WO 20429280 Breaker 106 Amber Light Not Lit 10/26/2020

WO 20431799 Replace 'B' EDG digital reference unit 12/01/2020

71111.13 Corrective Action NCR 2355134 Work order 20283049-06 lost from T-0 workweek due to 10/27/2020

Documents cross-train work

Procedures AD-NF-ALL-0501 Electronic Risk Assessment Tool (ERAT) Rev. 5

AD-OP-ALL-0201 Protected Equipment Rev. 7

AD-WC-ALL-0200 On-Line Work Management Rev. 17

AD-WC-ALL-0240 On-Line Risk Management Process Rev. 2

AD-WC-ALL-0410 Work Activity Integrated Risk Management Rev. 10

Work Orders WO 20238078 OPT-1532 ASI Squib Valves Fire Test 54 Month Interval 10/06/2020

Modes

WO 20379279 'A' ESW pump stuffing box and seal water piping cleaning 10/13/2020

WO 20412441 -52.5 VDC ground indicated on panel for B EDG 10/27/2020

WO 20429280 'A' EDG troubleshooting and repair of output breaker position 10/15/2020

status light not lit

71111.15 Engineering EC 418420 Shelf Plus Service Life Extension of ASI Squib Valves 1ASI-21 Rev. 0

Evaluations and 1ASI-22

EC 418533 Scaffold clearance deviation from safety-related 'B' ESCW 11/16/2020

system

71111.19 Corrective Action NCR 2339156 -52.5 VDC ground indicated on DP-1B-SB 07/20/2020

Documents

Drawings CAR 2166-B-401, Diesel Generator 1B-SB Engine Governor Control Rev. 11

Sheet 2007

Engineering EC 418833 Repair Cables in Cable Tray L1200 Damaged by Electrical 12/16/2020

Changes Fault

Inspection Type Designation Description or Title Revision or

Procedure Date

Procedures AD-EG-ALL-1155 Post Modification Testing Rev. 4

PLP-400 Post Maintenance Testing Rev. 64

Work Orders 20420667 TSC emergency ventilation testing failure and repairs 12/02/2020

WO 20379279 'A' ESW pump stuffing box and seal water piping cleaning 10/13/2020

WO 20412441 -52.5 VDC ground indicated on panel for B EDG 10/27/2020

WO 20429280 Replacement of failed 'A' EDG output breaker relay SN-SA 10/15/2020

WO 20440075 Inspection, repairs, and testing of Auxiliary Bus 1B following 12/16/2020

electrical fault

WO 20441385 Repair cables in L1200 cable tray damaged by electrical fault 12/16/2020

WO 20442682 Troubleshooting/repair of B ESCW chiller frequent cycling 12/28/2020

71111.20 Miscellaneous Startup Reactivity H1C23 Forced Outage Power Escalation (December 2020) Rev. 0

Manipulation Plan

Procedures GP-004 Reactor Startup (Mode 3 to Mode 2) Rev. 66

GP-005 Power Operation (Mode 2 to Mode 1) Rev. 110

GP-007 Normal Plant Cooldown Mode 3 to Mode 5 Rev. 72

71111.22 Procedures OST-1076 Auxiliary Feedwater Pump 1B-SB Operability Test Quarterly Rev. 31

Interval Modes 1 - 4

71114.06 Procedures AD-EP-ALL-0101 Emergency Classification Rev. 1

AD-EP-ALL-0111 Control Room Activation of the ERO Rev. 1

CSD-EP-HNP- EAL Wallchart Rev. 0

0101-02

71124.01 Corrective Action AR 2344247 OST-1112, Rod Position Indication Test 18 Month Interval 08/18/2020

Documents placed on hold to ensure fleet best practices are incorporated

regarding requirements to open the reactor trip breakers

following multiple dropped rods

NCR 02303724, Sampling of Radiation Safety Related Corrective Action Various

2330239, Documents written by the Licensee during the inspection

2331220, period being reviewed.

2331403,

2334551,

2341730, and

235394,

Drawings Locked High Radiation Area (LHRA) and Very High Radiation 09/14/2020

Area (VHRA) Maps and Location Information

Inspection Type Designation Description or Title Revision or

Procedure Date

Miscellaneous HNP eSOMS Log - Operations 08/13/2020 @ 0600 through Various

08/16/2020 @ 2400

HNP eSOMS Log - RP 08/13/2020 @ 0600 through Various

08/16/2020 @ 2400

High Radiation Area / Locked High Radiation Area Key Control Various

Log - 1/1/2020 through 11/18/2020

HNP eSOMS Log - Outage 08/13/2020 @ 1100 through Various

08/16/2020 @ 0924

CSD-RP-HNP- Neutron Survey Comparison Revision 1

0002 (09/19/2018)

Dose Reports for Individual dose results for RWP 40 used during multiple at 11/18/2020

RWP 40 power containment entries made for leak detection walkdowns

between 9/9 through 10/10/2020.

HPP-800-19-60 Fuel Handling Building Underwater Material Storage Log 09/24/2019

RWP 46 Dose Daily and individual dose results for RWP 46 used during the 11/18/2020

Report forced outage, 8/13 through 8/14/2020. Multiple entries made

to troubleshoot dropped rod issues and leak detection

walkdowns.

Procedures AD-PI-ALL-0100 Corrective Action Program Revision 24

AD-RP-ALL-0002 Radiation And Contamination Surveys Revision 2

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

AD-RP-ALL-0010 Radiological Job Coverage Revision 0

AD-RP-ALL-2011 Radiation Protection Briefings Revision 5

AD-RP-ALL-2014 Work in Alpha Environments Revision 7

AD-RP-ALL-2017 Access Controls To Very High Radiation Areas And Revision 7

Supplemental Access Controls for HRA and LHRA

AP-545 Containment Entries Revision 61

AP-545 Containment Entries Revision 62

HPP-625 Performance of Radiological Surveys Revision 49

OST-1005 Control Rod and Rod Position Indicator Exercise Quarterly Revision 28

Interval Modes 1 - 3

OST-1112 Rod Position Indication Test 18 Month Interval Revision 16

PD-RP-ALL-0001 Radiation Worker Responsibilities Revision 13

PLP-511 Radiation Control and Protection Program Revision 37

Inspection Type Designation Description or Title Revision or

Procedure Date

Radiation Surveys HNP-M- Incore Sump OPs Walk Down for Leaks Survey 11/17/2020

20191117-4

HNP-M- WPB 261' Room 144A Travel Path 05/26/2020

200526-1

HNP-M- RCB 221' South 08/13/2020

200813-4

HNP-M- Reactor Control Building - First Entry 08/13/2020

200813-5

HNP-M- RCB 261' Seal Table 10 Path Inspection 09/09/2020

200909-3

HNP-M- Waste Gas Compressors - Semi-Annual 11/04/2020

201104-4

HNP-M- 236' Piping Penetration Room - Monthly 11/07/2020

201105-7

HNP-M- Spent Resin Transfer Pump 11/10/2020

201110-5

HNP-M- Spent Resin Transfer Pump - Post Flush 11/10/2020

201110-6

HNP-M- Weekly Hot Chem Lab 11/13/2020

201113-3

HNP-M- Semi-Annual ORVH Storage Facility 11/18/2020

201118-5

HNP-M-2020812- RCB Excess Letdown walkdown 08/12/2020

HNP-M-2020813- RCB Leak Inspection I/S Biowall 08/13/2020

HNP-M-2020814- RCB Cabling Inspection on Rx Head 08/14/2020

HNP-M-2020814- WPB Demin Skid 08/14/2020

HNP-M-2020814- RCB 305' - MS-13 Isolation valve reseat 08/14/2020

HNP-M-2020909- RCB 261' Seal Table 09/09/2020

Inspection Type Designation Description or Title Revision or

Procedure Date

HNP-M-2020915- RCB 261' Seal table 09/15/2020

Radiation Work List of 'Initiated' Outage RWPs 09/14/2020

Permits (RWPs) List of 'Active' online RWPs 09/14/2020

RWP 33 Emergency Conditions and Drills Revision 8

RWP 40 RCB Entries with the Rx Critical Revision 39

RWP 46 Forced Outage Revision 9

RWP 5000 Self Brief for Work Areas < 25 mr/hr Revision 1

Self-Assessments 02331483-05 Field Operations and Radiation Worker Practices 10/21/2020

71124.06 Corrective Action Corrective Actions Corrective Actions #2257710, 2267431, 2269896, 2276863, Various

Documents #2257710, 2287081, 2294813, 2307733, 2339091 and 2342424

267431,

269896,

276863,

287081,

294813,

2307733,

2339091 and

2342424

Miscellaneous ERC-009, Out of ERC-009, Out of Service Radiation Monitor Reports May 2019 Various

Service Radiation to August 2020.

Monitor Reports

May 2019 to

August 2020.

Results of Results of Radiochemistry Cross Check Program Various

Radiochemistry

Cross Check

Program 1st QTR

2019, 2nd QTR

2019, 1st QTR

20, 2nd QTR

20 and 3rd

QTR 2020

Procedures CRC-240 Plant Vent Stack 1 Effluent Sampling Rev. 20

Inspection Type Designation Description or Title Revision or

Procedure Date

CRC-241 Turbine Building Vent Stack 3A Effluent Sampling Rev. 23

CRC-242 Waste Processing Building Vent Stack 5 Effluent Sampling Rev. 25

CRC-243 Waste Processing Building Vent Stack 5A Effluent Sampling Rev. 19

CRC-255 Waste Gas Decay Tank And Waste Gas (VCT, PRT, RCDT, Rev. 41

and RHT) Sampling

CRC-265 Chemistry Control of the Laundry and Hot Shower, Chemical Rev. 17

Drains, and Floor Drains Waste Treatment System

CRC-851 ODCM Software Instructions and Documentation Rev. 39

Radiation Surveys Radiochemistry Radiochemistry Analysis Report for Sample #191096 07/08/2019

Analysis Report

for Sample

1. 191096

RST-210 - Liquid Liquid Effluent Radiochemistry Surveillance Reports #L-2020- Various

Effluent 0003, L-2020-0029, L-2020-0031 and L-2020-0032

Radiochemistry

Surveillance

RST-211 - Gaseous Effluent Radiochemistry Surveillance Reports #G- Various

Gaseous Effluent 2020-0002, G-2020-0003, G-2020-0181, G-2020-0182 and G-

Radiochemistry 2020-0183

Surveillance

Self-Assessments Self-Assessment Verification of Maintenance Rule Classification of Plant 10/03/2019

1. 22826173-05 Installed Radiation Monitor

Self-Assessment Extent of Condition Assessment to SA 2229376 08/06/2020

1. 2342172-05

71124.07 Calculations 2019 Annual XOQDOQ Modeling and Meteorological 03/20/2020

Evaluation for Shearon Harris Nuclear Station

2018 Annual XOQDOQ Modeling and Meteorological 03/04/2019

Evaluation for Shearon Harris Nuclear Station

Calibration EnRad 03145 Calibration record for ISCO- Model 3710 water sampler 08/06/2018

Records and

07/08/2019

EnRad 09059 Calibration record for ISCO- Model 3710 water sampler 1/21/2019

EnRad 09072 Calibration record for environmental air sampler Model LV-1D 04/10/2019

EnRad 09083 Calibration record for environmental air sampler Model LV-1D 03/09/2018

Inspection Type Designation Description or Title Revision or

Procedure Date

and

03/31/2020

EnRad 09128 Calibration record for ISCO- Model 3710 water sampler 03/20/2020

Corrective Action NCR 02255956, Sampling of REMP Related Corrective Action Documents Various

Documents 02268125, written by the Licensee during the inspection period being

268808, reviewed.

276866, and

2337157

NCR 02354142 Met Tower Lower Wind Speed sensor not calibrated (WO 10/20/2020

20395270-01)

Corrective Action 02358620 NCR written for damaged MW-10 monitoring well pad 11/18/2020

Documents damage. Does not appear to have any damaged to the well

Resulting from casing. [NRC identified]

Inspection

Miscellaneous Shearon Harris Nuclear Power Plant 2019 Annual Radiological

Environmental Operating Report (AREOR)

Shearon Harris Nuclear Power Plant 2018 Annual Radiological

Environmental Operating Report (AREOR)

Harris REMP TLD Summary Report [Environmental TLD data] 11/03/2020

- First thru third quarter 2020

Shearon Harris Nuclear Power Plant Unit 1 2019 Annual

Radioactive Effluent Release Report

Harris Ground Water Protection Initiative and Tritium Sampling Various

Summaries and Reports [Individual Sampling Location Data

and 10 Year Trend] - 2019 and 2020

List of REMP Telemetry ALERT emails (Pump Failure, Utility 10/19/2020

Power Failure, etc)

Harris Nuclear Plant 2018 Annual Land Use Census 08/28/2018

Harris Nuclear Plant 2019 Annual Land Use Census 08/22/2019

Harris Nuclear Plant 2020 Annual Land Use Census 08/10/2020

Harris Nuclear Plant Meteorological Tower Data Recovery - Various

January 2018 to August 2020

HNP Environmental Risk Registry [List and risk ranking of 11/12/2020

Inspection Type Designation Description or Title Revision or

Procedure Date

Systems, Structures, and Components (SSCs) and buried

piping that could pose a risk to groundwater]

Harris Lake Tritium Concentration - 2010 thru June 2019 06/18/2019

Procedures AD-CP-ALL-0015 Radiological Environmental Monitoring Program Data Revision 3

Evaluation

AD-CP-ALL-0017 Radiological Groundwater Protection Revision 4

AD-EG-ALL-1613 Buried Piping Integrity Program Implementation Revision 5

EMP-012 Groundwater Monitoring Program Revision 11

EnRad 207 Configuration and Set Up of the ISCO 3710 Water Sampler Revision 6

EnRad 746 Transfer of Harris REMP Samples from Harris Nuclear Plant Revision 5

To EnRad Laboratories

EnRad 749 Airborne Radioiodine And Airborne Particulate Sampling At Revision 3

Harris Nuclear Plant

EnRad 753 Milk Sampling At Harris Nuclear Plant Revision 4

EnRad 767 Ground Water Sampling At Harris Nuclear Plant Revision 2

Enrad 850 Calibration of REMP Air Sampling Equipment Revision 2

MPT-I0129 Meteorology Tower Equipment Calibration Revision 16

PLP-504 Tritium Management Revision 4

Self-Assessments 02198443-05 Radiological Environmental Monitoring Program (REMP) Self- 04/16/2018

Assessment at Shearon Harris Nuclear Plant: Airborne

Particulate and Airborne Radioiodine, Drinking Water, and

Surface Water

271393-05 Radiological Environmental Monitoring Program (REMP) Self- 05/13/2019

Assessment at Shearon Harris Nuclear Plant: Airborne

Particulate and Airborne Radioiodine, Drinking Water, and

Surface Water

240431 Optimization of HNP Radiological Environmental Monitoring 11/15/2018

Program

Self-Assessment Quick Hit Self Assessment Radiological Environmental 04/25/2016

1. 02020000 Monitoring Program

Self-Assessment Radiological Environmental Monitoring Program (REMP) Self 10/03/2017

1. 02133131 Assessment

Self-Assessment NEI 07-07 Groundwater Protection Initiative Assessment 08/13/2018

1. 2173466

Inspection Type Designation Description or Title Revision or

Procedure Date

Self-Assessment Possible trending in REMP air sampling equipment 10/09/2018

1. 2236139

Self-Assessment Optimization of HNP Radiological Environmental Monitoring 11/05/2018

1. 2240431 Program

Work Orders 20209742-01 MET TOWER EQUIP CAL (SEMIANNUAL PORTION) 03/06/2018

211627-01 MET TOWER EQUIPMENT CAL (ANNUAL PORTION) 11/01/2018

288663-01 MET TOWER EQUIP CAL (SEMIANNUAL) PORTION 04/25/2019

295719-01 MET TOWER EQUIPMENT CAL (ANNUAL PORTION) 09/23/2019

20358932-01 MET TOWER EQUIP CAL (SEMI-ANNUAL PORTION) 04/27/2020

Work Order (WO) Replaced lower wind speed and direction sensor only 11/11/2020

20395270-01

71124.08 Corrective Action Corrective Actions Corrective Actions #2312255, 2331522 and 2331608 Various

Documents #2312255,

2331522 and

2331608

Corrective Action 02358615 Water found in ORVH storage building 11/18/2020

Documents 02359102 10CFR37 training not validated as complete 11/22/2020

Resulting from

Inspection

Miscellaneous HPP-800 - Semi- HPP-800 - Semi-Annual Source Inventory 10/26/2020

Annual Source

Inventory

HPP-800 - Semi- HPP-800 - Semi-Annual Source Inventory 04/13/2020

Annual Source

Inventory

Procedures AD-RP-ALL-0007 Control of Radioactive Material Rev. 2

AD-RP-ALL-3003 OUTSIDE RADIOACTIVE MATERIAL CONTAINER Rev. 3

INVENTORY AND CONTROL

AD-RP-ALL-5000 PREPARATION AND SHIPMENT OF RADIOACTIVE Rev. 4

MATERIAL AND RADIOACTIVE WASTE

AD-RP-ALL-5002 10 CFR 61 RADIOACTIVE WASTE CLASSIFICATION Rev. 1

AD-RP-ALL-5003 RECEIPT OF RADIOACTIVE MATERIAL Rev. 2

AD-SY-ALL-0270 Physical Protection of Category 1 and Category 2 Quantities Rev. 6

of Radioactive Material

Inspection Type Designation Description or Title Revision or

Procedure Date

HPP-063 RESIN SAMPLE/SLUICE/TRANSFER AND FILTER Rev. 31

BACKWASH ACTIVITIES

HPP-800 HANDLING RADIOACTIVE MATERIAL Rev. 64

PLP-300 PROCESS CONTROL PROGRAM Rev. 14

Self-Assessments Self-Assessment 2018 NRC RP ORS Inspection, Inspection Manual Procedure 03/15/2018

1. 02186418-05 71124.08 - Radioactive Solid Waste Processing and

Radioactive Material Handling, Storage, and Transportation

Self-Assessment Extent of Condition Assessment to SA 02186418-05 08/26/2020

1. 2345263-05

Shipping Records19-008, 19-109, Shipping papers associated with shipments19-008, 19-109, Various19-124 and 20- 19-124 and 20-270

270

71151 Calculations HNP-F/PSA-0068 NRC Mitigating System Performance Index (MSPI) PRA Input Rev. 11

Document

HNP-M/MECH- Mitigating System Performance Index Basis Document Rev. 2

231

Corrective Action NCR 02312255 Sampling of Radiation Safety Related Corrective Action Various

Documents and 02337154 Documents written by the Licensee during the inspection

period being reviewed.

Corrective Action NCR 02357703 March 2020 INPO IRIS Data Not Entered 11/12/2020

Documents

Resulting from

Inspection

Miscellaneous Electronic Dosimeter dose and dose rate log - 11/1/2019 Various

through 9/12/2020

2019 ARERR Shearon Harris Nuclear Power Plant Unit 1 2019 Annual April 2020

Radioactive Effluent Release Report (ARERR)

G-2020-0183 Radioactive Gaseous Release Permit 11/3/2020

L-2020-0032 Radioactive Liquid Waste Release Permit - Monitor Tank B 09/19/2020

Procedures AD-EG-ALL-1217 Mitigating System Performance Index (MSPI) Rev. 1

AD-PI-ALL-0700 Performance Indicators Rev. 4

AD-PI-ALL-0700 Performance Indicators Revision 4

AD-RP-ALL-1101 Performance Indicators (PI) for the Occupational and Public Revision 0

Radiation Safety Cornerstones

Inspection Type Designation Description or Title Revision or

Procedure Date

71153 Procedures AOP-039 Startup and Unit Auxiliary Transformer Trouble Rev. 17

EOP-E-0 Reactor Trip or Safety Injection Rev. 15

EOP-ES-0.1 Reactor Trip Response Rev. 4

FPP-002 Fire Emergency Rev. 45

OMM-004 Post-Trip/Safeguards Actuation Review Rev. 43

OP-156 AC Electrical Distribution Rev. 172

27