IR 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:
Report Number:
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
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 Aspect Report Section Initiating Events Green NCV 05000400/2020004-01 Open/Closed None (NPP)71153 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 Due to Control Rod Drop During Surveillance Testing 71153 Closed
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.
REACTOR SAFETY
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,
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)
- (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))
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
- 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 Aspect Report Section Initiating Events
Green NCV 05000400/2020004-01 Open/Closed
None (NPP)71153 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
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
Action Request
(AR) 02038102
Winter Readiness
10/08/2020
Procedures
AD-WC-ALL-0230
Seasonal Readiness
Rev. 0
AP-301
Seasonal Weather Preparations and Monitoring
Rev. 86
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
Alternate Seal Injection System (ASI-System 2007)
Rev. 4
Procedures
Auxiliary Feedwater System
Rev. 46
Service Water System
Rev. 138
Diesel Generator Emergency Power System
Rev. 91
Alternate Seal Injection
Rev. 12
Dedicated Shutdown Diesel Generator
Rev. 9
Fire Plans
CSD-HNP-PFP-
RAB-261
Reactor Auxiliary Building Elevation 261 Pre-Fire Plan
Rev. 1
CSD-HNP-PFP-
DGB
Diesel Generator Building Pre-Fire Plan
Rev. 1
CSD-HNP-PFP-
RAB-236
Reactor Auxiliary Building Elevation 236 Pre-Fire Plan
Rev. 2
CSD-HNP-PFP-
RAB-286
Reactor Auxiliary Building Elevation 286 Pre-Fire Plan
Rev. 1
CSD-HNP-PFP-
SEC
Out Building Pre-Fire Plan
Rev. 5
Procedures
AD-EG-ALL-1520
Transient Combustible Control
Rev. 13
Fire Protection Program Manual
Rev. 44
Fire Protection - Minimum Requirements, Mitigating Actions
and Surveillance Requirements
Rev. 105
FPT-3220A
Incipient Fire Detection Alarm Notification Functional Test -
Monthly Interval
Rev. 2
Calculations
CALC-HNP -
PRA F-E-0010
Diesel Fuel Oil Storage Transfer Building Internal Flooding
Evaluation
Rev. 3
Procedures
AD-EG-ALL-1312
Raw Water Program Implementation
Rev. 0
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
EPT-163
Generic Letter 89-13 Inspections (Raw Water Systems and
Local Area Air Handler Inspection and Documentation)
Rev. 19
MPT-M0091
Heat Exchanger Opening/Closure for NRC Generic Letter 89-
Inspections
Rev. 18
PLP-620
Service Water Program (Generic Letter 89-13)
Rev. 21
Work Orders
Inspect and replace AH-4 service water return header isolation
valve
10/16/2016
Inspect and replace 1SW-98, AH-1 containment fan cooler
service water outlet valve
10/17/2016
Inspection of AH-1 and AH-4 service water return valve
4/8/2015
Inspect and replace containment air handler heat exchanger
for AH-4
10/17/2010
Inspect 'B' ESCW chiller condenser
10/18/2019
Inspection and cleaning of 'B" ESCW chiller condenser heat
exchanger
7/17/2019
WOs 1563658
and 1527037
Inspect containment air handler AH-1 and AH-4
10/17/2010
71111.11Q Procedures
AD-OP-ALL-1000
Conduct of Operations
Rev. 17
AD-OP-ALL-1001
Conduct of Abnormal Operations
Rev. 3
Malfunction of Rod Control and Indication System
Rev. 55
Excessive Primary Plant Leakage
Rev. 58
Malfunction of RCS Pressure Control
Rev. 25
Secondary Steam Leak/Efficiency Loss
Rev. 8
APP-ALB-007
Annunciator Panel Procedure
Rev. 16
Steam Generator Tube Rupture
Rev. 7
OMM-001
Operations Administrative Requirements
Rev. 121
OST-1005
Control Rod and Rod Position Indicator Exercise Quarterly
Interval Modes 1-3
Rev. 28
Work Orders
CRDM coil current during control rod movement testing
11/02/2020
Corrective Action
Documents
Breaker 106 Amber Light Not Lit
10/14/2020
Technical Specification Documentation on Common Mode
Failures
10/20/2020
Replace EDG 'B' digital reference unit due to ground fault
10/30/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Drawings
CAR 2166-B-401,
Sheet 1101
Emergency Load Sequencer ESS Cabinet 1A-SA
Rev. 014
Procedures
AD-QC-ALL-0108
Nuclear Oversight Vendor QC Acceptance
Rev. 2
AD-QC-ALL-1000
Conduct of Nuclear Oversight Quality Control
Rev. 9
Diesel Generator Emergency Power System
Rev. 91
OST-1013
1A-SA Emergency Diesel Generator Operability Test Monthly
Interval, Modes 1-6
Rev. 043
Work Orders
Troubleshooting DC ground indication in 'B' EDG governor
10/29/2020
Breaker 106 Amber Light Not Lit
10/26/2020
Replace 'B' EDG digital reference unit
2/01/2020
Corrective Action
Documents
NCR 2355134
Work order 20283049-06 lost from T-0 workweek due to
cross-train work
10/27/2020
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
OPT-1532 ASI Squib Valves Fire Test 54 Month Interval
Modes
10/06/2020
'A' ESW pump stuffing box and seal water piping cleaning
10/13/2020
-52.5 VDC ground indicated on panel for B EDG
10/27/2020
'A' EDG troubleshooting and repair of output breaker position
status light not lit
10/15/2020
Engineering
Evaluations
Shelf Plus Service Life Extension of ASI Squib Valves 1ASI-21
and 1ASI-22
Rev. 0
Scaffold clearance deviation from safety-related 'B' ESCW
system
11/16/2020
Corrective Action
Documents
NCR 2339156
-52.5 VDC ground indicated on DP-1B-SB
07/20/2020
Drawings
CAR 2166-B-401,
Sheet 2007
Diesel Generator 1B-SB Engine Governor Control
Rev. 11
Engineering
Changes
Repair Cables in Cable Tray L1200 Damaged by Electrical
Fault
2/16/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
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
2/02/2020
'A' ESW pump stuffing box and seal water piping cleaning
10/13/2020
-52.5 VDC ground indicated on panel for B EDG
10/27/2020
Replacement of failed 'A' EDG output breaker relay SN-SA
10/15/2020
Inspection, repairs, and testing of Auxiliary Bus 1B following
electrical fault
2/16/2020
Repair cables in L1200 cable tray damaged by electrical fault
2/16/2020
Troubleshooting/repair of B ESCW chiller frequent cycling
2/28/2020
Miscellaneous
Startup Reactivity
Manipulation Plan
H1C23 Forced Outage Power Escalation (December 2020)
Rev. 0
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
Procedures
OST-1076
Auxiliary Feedwater Pump 1B-SB Operability Test Quarterly
Interval Modes 1 - 4
Rev. 31
Procedures
AD-EP-ALL-0101
Emergency Classification
Rev. 1
AD-EP-ALL-0111
Control Room Activation of the ERO
Rev. 1
CSD-EP-HNP-
0101-02
EAL Wallchart
Rev. 0
Corrective Action
Documents
OST-1112, Rod Position Indication Test 18 Month Interval
placed on hold to ensure fleet best practices are incorporated
regarding requirements to open the reactor trip breakers
following multiple dropped rods
08/18/2020
2330239,
2331220,
2331403,
2334551,
2341730, and
235394,
Sampling of Radiation Safety Related Corrective Action
Documents written by the Licensee during the inspection
period being reviewed.
Various
Drawings
Locked High Radiation Area (LHRA) and Very High Radiation
Area (VHRA) Maps and Location Information
09/14/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
HNP eSOMS Log - Operations 08/13/2020 @ 0600 through
08/16/2020 @ 2400
Various
HNP eSOMS Log - RP 08/13/2020 @ 0600 through
08/16/2020 @ 2400
Various
High Radiation Area / Locked High Radiation Area Key Control
Log - 1/1/2020 through 11/18/2020
Various
HNP eSOMS Log - Outage 08/13/2020 @ 1100 through
08/16/2020 @ 0924
Various
CSD-RP-HNP-
0002
Neutron Survey Comparison
Revision 1
(09/19/2018)
Dose Reports for
RWP 40
Individual dose results for RWP 40 used during multiple at
power containment entries made for leak detection walkdowns
between 9/9 through 10/10/2020.
11/18/2020
HPP-800-19-60
Fuel Handling Building Underwater Material Storage Log
09/24/2019
RWP 46 Dose
Report
Daily and individual dose results for RWP 46 used during the
forced outage, 8/13 through 8/14/2020. Multiple entries made
to troubleshoot dropped rod issues and leak detection
walkdowns.
11/18/2020
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
Supplemental Access Controls for HRA and LHRA
Revision 7
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
Interval Modes 1 - 3
Revision 28
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
Procedure
Type
Designation
Description or Title
Revision or
Date
Radiation Surveys HNP-M-
20191117-4
Incore Sump OPs Walk Down for Leaks Survey
11/17/2020
HNP-M-
200526-1
WPB 261' Room 144A Travel Path
05/26/2020
HNP-M-
200813-4
RCB 221' South
08/13/2020
HNP-M-
200813-5
Reactor Control Building - First Entry
08/13/2020
HNP-M-
200909-3
RCB 261' Seal Table 10 Path Inspection
09/09/2020
HNP-M-
201104-4
Waste Gas Compressors - Semi-Annual
11/04/2020
HNP-M-
201105-7
236' Piping Penetration Room - Monthly
11/07/2020
HNP-M-
201110-5
Spent Resin Transfer Pump
11/10/2020
HNP-M-
201110-6
Spent Resin Transfer Pump - Post Flush
11/10/2020
HNP-M-
201113-3
Weekly Hot Chem Lab
11/13/2020
HNP-M-
201118-5
Semi-Annual ORVH Storage Facility
11/18/2020
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
Procedure
Type
Designation
Description or Title
Revision or
Date
HNP-M-2020915-
RCB 261' Seal table
09/15/2020
Radiation Work
Permits (RWPs)
List of 'Initiated' Outage RWPs
09/14/2020
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
Corrective Action
Documents
Corrective Actions
- 2257710,
267431,
269896,
276863,
287081,
294813,
2307733,
2339091 and
2342424
Corrective Actions #2257710, 2267431, 2269896, 2276863,
287081, 2294813, 2307733, 2339091 and 2342424
Various
Miscellaneous
ERC-009, Out of
Service Radiation
Monitor Reports
May 2019 to
August 2020.
ERC-009, Out of Service Radiation Monitor Reports May 2019
to August 2020.
Various
Results of
Radiochemistry
Cross Check
Program 1st QTR
2019, 2nd QTR
2019, 1st QTR
20, 2nd QTR
20 and 3rd
QTR 2020
Results of Radiochemistry Cross Check Program
Various
Procedures
CRC-240
Plant Vent Stack 1 Effluent Sampling
Rev. 20
Inspection
Procedure
Type
Designation
Description or Title
Revision or
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,
and RHT) Sampling
Rev. 41
CRC-265
Chemistry Control of the Laundry and Hot Shower, Chemical
Drains, and Floor Drains Waste Treatment System
Rev. 17
CRC-851
ODCM Software Instructions and Documentation
Rev. 39
Radiation Surveys Radiochemistry
Analysis Report
for Sample
- 191096
Radiochemistry Analysis Report for Sample #191096
07/08/2019
RST-210 - Liquid
Effluent
Radiochemistry
Surveillance
Liquid Effluent Radiochemistry Surveillance Reports #L-2020-
0003, L-2020-0029, L-2020-0031 and L-2020-0032
Various
RST-211 -
Gaseous Effluent
Radiochemistry
Surveillance
Gaseous Effluent Radiochemistry Surveillance Reports #G-
20-0002, G-2020-0003, G-2020-0181, G-2020-0182 and G-
20-0183
Various
Self-Assessments Self-Assessment
- 22826173-05
Verification of Maintenance Rule Classification of Plant
Installed Radiation Monitor
10/03/2019
Self-Assessment
- 2342172-05
Extent of Condition Assessment to SA 2229376
08/06/2020
Calculations
2019 Annual XOQDOQ Modeling and Meteorological
Evaluation for Shearon Harris Nuclear Station
03/20/2020
2018 Annual XOQDOQ Modeling and Meteorological
Evaluation for Shearon Harris Nuclear Station
03/04/2019
Calibration
Records
EnRad 03145
Calibration record for ISCO-Model 3710 water sampler
08/06/2018
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
Procedure
Type
Designation
Description or Title
Revision or
Date
and
03/31/2020
EnRad 09128
Calibration record for ISCO-Model 3710 water sampler
03/20/2020
Corrective Action
Documents
268125,
268808,
276866, and
2337157
Sampling of REMP Related Corrective Action Documents
written by the Licensee during the inspection period being
reviewed.
Various
Met Tower Lower Wind Speed sensor not calibrated (WO 20395270-01)
10/20/2020
Corrective Action
Documents
Resulting from
Inspection
2358620
NCR written for damaged MW-10 monitoring well pad
damage. Does not appear to have any damaged to the well
casing. [NRC identified]
11/18/2020
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]
- First thru third quarter 2020
11/03/2020
Shearon Harris Nuclear Power Plant Unit 1 2019 Annual
Radioactive Effluent Release Report
Harris Ground Water Protection Initiative and Tritium Sampling
Summaries and Reports [Individual Sampling Location Data
and 10 Year Trend] - 2019 and 2020
Various
List of REMP Telemetry ALERT emails (Pump Failure, Utility
Power Failure, etc)
10/19/2020
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 -
January 2018 to August 2020
Various
HNP Environmental Risk Registry [List and risk ranking of
11/12/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
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
Evaluation
Revision 3
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
To EnRad Laboratories
Revision 5
EnRad 749
Airborne Radioiodine And Airborne Particulate Sampling At
Harris Nuclear Plant
Revision 3
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-
Assessment at Shearon Harris Nuclear Plant: Airborne
Particulate and Airborne Radioiodine, Drinking Water, and
Surface Water
04/16/2018
271393-05
Radiological Environmental Monitoring Program (REMP) Self-
Assessment at Shearon Harris Nuclear Plant: Airborne
Particulate and Airborne Radioiodine, Drinking Water, and
Surface Water
05/13/2019
240431
Optimization of HNP Radiological Environmental Monitoring
Program
11/15/2018
Self-Assessment
- 02020000
Quick Hit Self Assessment Radiological Environmental
Monitoring Program
04/25/2016
Self-Assessment
- 02133131
Radiological Environmental Monitoring Program (REMP) Self
Assessment
10/03/2017
Self-Assessment
- 2173466
NEI 07-07 Groundwater Protection Initiative Assessment
08/13/2018
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Self-Assessment
- 2236139
Possible trending in REMP air sampling equipment
10/09/2018
Self-Assessment
- 2240431
Optimization of HNP Radiological Environmental Monitoring
Program
11/05/2018
Work Orders
209742-01
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)
20395270-01
Replaced lower wind speed and direction sensor only
11/11/2020
Corrective Action
Documents
Corrective Actions
- 2312255,
2331522 and
2331608
Corrective Actions #2312255, 2331522 and 2331608
Various
Corrective Action
Documents
Resulting from
Inspection
2358615
Water found in ORVH storage building
11/18/2020
2359102
10CFR37 training not validated as complete
11/22/2020
Miscellaneous
HPP-800 - Semi-
Annual Source
Inventory
HPP-800 - Semi-Annual Source Inventory
10/26/2020
HPP-800 - Semi-
Annual Source
Inventory
HPP-800 - Semi-Annual Source Inventory
04/13/2020
Procedures
AD-RP-ALL-0007
Control of Radioactive Material
Rev. 2
AD-RP-ALL-3003
OUTSIDE RADIOACTIVE MATERIAL CONTAINER
INVENTORY AND CONTROL
Rev. 3
AD-RP-ALL-5000
PREPARATION AND SHIPMENT OF RADIOACTIVE
MATERIAL AND RADIOACTIVE WASTE
Rev. 4
AD-RP-ALL-5002
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
of Radioactive Material
Rev. 6
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
HPP-063
RESIN SAMPLE/SLUICE/TRANSFER AND FILTER
BACKWASH ACTIVITIES
Rev. 31
HPP-800
HANDLING RADIOACTIVE MATERIAL
Rev. 64
PLP-300
Rev. 14
Self-Assessments Self-Assessment
- 02186418-05
2018 NRC RP ORS Inspection, Inspection Manual Procedure
71124.08 - Radioactive Solid Waste Processing and
Radioactive Material Handling, Storage, and Transportation
03/15/2018
Self-Assessment
- 2345263-05
Extent of Condition Assessment to SA 02186418-05
08/26/2020
Shipping Records19-008, 19-109,19-124 and 20-
270
Shipping papers associated with shipments19-008, 19-109,19-124 and 20-270
Various
71151
Calculations
HNP-F/PSA-0068
NRC Mitigating System Performance Index (MSPI) PRA Input
Document
Rev. 11
HNP-M/MECH-
231
Mitigating System Performance Index Basis Document
Rev. 2
Corrective Action
Documents
and 02337154
Sampling of Radiation Safety Related Corrective Action
Documents written by the Licensee during the inspection
period being reviewed.
Various
Corrective Action
Documents
Resulting from
Inspection
March 2020 INPO IRIS Data Not Entered
11/12/2020
Miscellaneous
Electronic Dosimeter dose and dose rate log - 11/1/2019
through 9/12/2020
Various
2019 ARERR
Shearon Harris Nuclear Power Plant Unit 1 2019 Annual
Radioactive Effluent Release Report (ARERR)
April 2020
G-2020-0183
Radioactive Gaseous Release Permit
11/3/2020
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
Radiation Safety Cornerstones
Revision 0
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
Startup and Unit Auxiliary Transformer Trouble
Rev. 17
Reactor Trip or Safety Injection
Rev. 15
Reactor Trip Response
Rev. 4
Fire Emergency
Rev. 45
OMM-004
Post-Trip/Safeguards Actuation Review
Rev. 43
AC Electrical Distribution
Rev. 172