IR 05000440/2020004
| ML21043A176 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 02/12/2021 |
| From: | Billy Dickson NRC/RGN-III |
| To: | Penfield R Energy Harbor Nuclear Corp |
| References | |
| IR 2020004 | |
| Download: ML21043A176 (28) | |
Text
February 12, 2021
SUBJECT:
PERRY NUCLEAR POWER PLANT - INTEGRATED INSPECTION REPORT 05000440/2020004
Dear Mr. Penfield:
On December 31, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Perry Nuclear Power Plant. On January 28, 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 III; the Director, Office of Enforcement; and the NRC Resident Inspector at Perry Nuclear Power Plant.
If you disagree with a cross-cutting aspect assignment in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region III; and the NRC Resident Inspector at Perry 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/
Billy C. Dickson, Jr., Chief Branch 2 Division of Reactor Projects
Docket No. 05000440 License No. NPF-58
Enclosure:
As stated
Inspection Report
Docket Number:
05000440
License Number:
Report Number:
Enterprise Identifier: I-2020-004-0031
Licensee:
Energy Harbor Nuclear Corp.
Facility:
Perry Nuclear Power Plant
Location:
Perry, OH
Inspection Dates:
October 01, 2020 to December 31, 2020
Inspectors:
S. Bell, Health Physicist
J. Nance, Operations Engineer
T. Ospino, Resident Inspector
G. Roach, Senior Operations Engineer
J. Steffes, Senior Resident Inspector
Approved By:
Billy C. Dickson, Jr., Chief
Branch 2
Division of Reactor Projects
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Perry 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
Failure to Close Valve During Surveillance Procedure Causes Inoperability and Unavailability of the Standby Liquid Control System Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000440/2020004-01 Open
[H.12] - Avoid Complacency 71152 A finding of very low safety significance (Green) and associated non-cited violation of Title 10 CFR Part 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings, was self-revealed for the licensees failure to perform activities affecting quality in accordance with an approved procedure appropriate for the circumstances. Specifically, during performance of PTI-C41-P0001, Standby Liquid Control Transfer System Pump and Valve Operability Test,
Revision 10, operators failed to shut transfer line isolation valve, 1C41-F522, causing an unplanned eight-hour limiting condition for operation (LCO) entry and unavailability of both trains of the standby liquid control system.
Additional Tracking Items
None.
PLANT STATUS
The plant began the inspection period at rated thermal power. On October 31, 2020, reactor power was lowered to 66 percent to perform a rod sequence exchange and control rod scram time testing. The unit was returned to rated thermal power on November 11, 2020. On November 14, 2020, reactor power was lowered to 65 percent to perform a rod pattern adjustment. The unit was returned to rated thermal power the same day. On December 14, 2020, reactor power was lowered to 69 percent to perform turbine control valve testing. The unit was returned to rated thermal power on December 15, 2020. The unit remained at, or near, rated thermal power until December 23, 2020, when the unit entered into coastdown operations to refueling outage 1R18. The plant was at 97 percent power on December 31,
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
External Flooding Sample (IP Section 03.03) (1 Sample)
- (1) External flooding walk down inspection Service Building on December 2, 2020
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Emergency closed cooling system (ECCS) valve alignment October 18, 2020
- (2) Low pressure core spray venting and valve lineup October 22, 2020
- (3) A residual heat removal (RHR) system lineup verification on November 18, 2020 (4)
"A" standby liquid control (SLC) system alignment verification on December 3, 2020
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated system configurations during a complete walkdown of the high-pressure core spray system on November 10 to 20, 2020.
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (6 Samples)
The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:
- (1) Intermediate building, elevation 620-foot, fire zone (FZ) 0IB-3 on November 7, 2020
- (2) Fuel handling building, elevation 620-foot, FZ 0FH-3 on November 7, 2020
- (3) Diesel generator building, 620- and 646-foot elevations, FZs 1DG-1C and DG-1D on November 7, 2020
- (4) Auxiliary building, 620- and 599-foot elevations on November 7 to 10, 2020
- (5) Unit 1 Division 3 Switchgear 620-6 FZ 1CC-3c on November 9, 2020
- (6) Emergency Service Water pumphouse FZ 0EW on November 10, 2020
71111.06 - Flood Protection Measures
Inspection Activities - Internal Flooding (IP Section 03.01) (2 Samples)
The inspectors evaluated internal flooding mitigation protections in the:
(1) "C" RHR system room on December 29, 2020
- (2) ECCS system on December 30, 2020
71111.07A - Heat Sink Performance
Annual Review (IP Section 03.01) (1 Sample)
The inspectors evaluated readiness and performance of:
- (1) Division 1 emergency diesel generator (EDG) jacket water heat exchanger review on December 7 to 17, 2020
71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance
Requalification Examination Results (IP Section 03.03) (1 Sample)
- (1) The inspectors reviewed and evaluated the licensed operator examination failure rates for the requalification program biennial written examination and annual operating test administered between October 26 and December 7, 2020.
71111.11B - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Requalification Program (IP Section 03.04) (1 Partial)
(1)
(Partial)
Biennial Requalification Written Examinations
The inspectors evaluated the quality of the licensed operator biennial requalification written examination administered on December 10, 2020.
Annual Requalification Operating Tests
The inspectors evaluated the adequacy of the facility licensees annual requalification operating test.
Administration of an Annual Requalification Operating Test
Due to the COVID-19 PHE, the inspectors could not by direct observation, evaluate the effectiveness of the facility licensee in administering requalification operating tests required by 10 CFR 55.59(a)(2) and that the facility licensee is effectively evaluating their licensed operators for mastery of training objectives. Specifically, the inspectors did not observe the administration of simulator scenarios and Job Performance Measures (JPM) during the conduct of an annual requalification operating test required by 10 CFR 55.59(a)(2).
Requalification Examination Security
The inspectors evaluated the ability of the facility licensee to safeguard examination material, such that the examination is not compromised.
Remedial Training and Re-examinations
The inspectors evaluated the effectiveness of remedial training conducted by the licensee and reviewed the adequacy of re-examinations for licensed operators who did not pass a required requalification examination.
Operator License Conditions
The inspectors evaluated the licensees program for ensuring that licensed operators meet the conditions of their licenses.
Control Room Simulator
The inspectors evaluated the adequacy of the facility licensees Control Room simulator in modeling the actual plant, and for meeting the requirements contained in 10 CFR 55.46.
Problem Identification and Resolution
The inspectors evaluated the licensees ability to identify and resolve problems associated with licensed operator performance.
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (1 Sample)
- (1) The inspectors observed and evaluated licensed operator performance in the Control Room during down power for rod sequence exchange and scram time testing on October 31, 2020.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (2 Samples)
- (1) The inspectors observed and evaluated licensed operator performance in the simulator on October 28, 2020.
- (2) The inspectors observed and evaluated licensed operator performance in the simulator on November 4, 2020.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (6 Samples)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:
- (1) SLC system unavailability due to dilution event on August 20, 2020
- (2) Emergency service water (ESW) radiation monitoring spiking on October 19 to 22, 2020
- (3) Work associated with "A" reactor protection system motor generator on November 12, 2020
- (4) Meteorological tower work after Quincy lane was down for weather-related event on November 17, 2020
- (5) Combustible gas mixing compressor "A" failure on December 22, 2020
- (6) Unit 2 startup transformer modification issues on December 22, 2020
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (4 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) Plant risk evaluation and assessment while "A" ESW, "A" ECCS system, and "A" RHR inoperable and unavailable for maintenance work window on October 20 to 22, 2020
- (2) Emergent work evaluation and risk assessment associated with reactor vessel level perturbation due to reactor feed pump "A" speed oscillations on November 5, 2020
- (4) Emergent activities associated to the reactor protection system motor generator "A" work on November 12, 2020
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (5 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Division 1 EDG operability determination associated with CR 2020-08482 on November 9, 2020
- (2) Meteorological tower operability check following weather-related event on November 17, 2020
- (3) Functional test of the FLEX emergency service water pump B based on CR 2020-09317 on December 9, 2020
- (4) Unit 2 startup transformer disconnect failure on December 16 to 17, 2020
- (5) Division 1 EDG jacket water circulating pump failure due to a blown fuse on December 31, 2020
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (2 Samples)
The inspectors evaluated the following permanent modification:
- (1) Main steam line isolation valve nuclear steam supply shutoff system isolation logic "C" test jack modification on October 6, 2020
- (2) Unit 1 startup transformer modification implementation 19-0203-001 on November 12, 2020
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (8 Samples)
The inspectors evaluated the following post-maintenance test activities to verify system operability and functionality:
- (1) The replacement of filters on "A" hydraulic power unit recirculation system on September 17 to 21, 2020
- (2) The replacement of the cable on the A ESW radiation monitor on October 7, 2020
- (3) The replacement of "A" electro-hydraulic control pump discharge filter on October 8, 2020
- (4) The replacement of the ECCS pump room cooler AGASTAT E7000 TD relay on October 18, 2020 (5)
"A" ESW system loop flow and differential pressure test following maintenance work window on October 26, 2020 (6)
"A" low pressure core spray room cooler time delay relay replacement October 21, 2020 (7)
"A" RHR room cooler time delay relay replacement on October 28, 2020 (8)
"A" RHR surveillance following motor operated valve test and adjustment on October 29, 2020
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Surveillance Tests (other) (IP Section 03.01)
- (1) Main steam line high flow C functional test on October 6, 2020
- (2) Main steam line low condenser vacuum channel A calibration on October 19, 2020 (3)
"A" ESW flow and differential pressure test on October 24, 2020
- (4) Channel "A" drywell high-pressure calibration for 1C71-N050A on September 21, 2020
Inservice Testing (IP Section 03.01) (1 Sample)
- (1) High-pressure core spray pump and valve operability test, work order 200771908
FLEX Testing (IP Section 03.02) (1 Sample)
- (1) Test of the FLEX lake water pumps on June 6, 2020
71114.04 - Emergency Action Level and Emergency Plan Changes
Inspection Review (IP Section 02.01-02.03) (1 Sample)
- (1) The inspectors completed an evaluation of submitted Emergency Action Level and Emergency Plan changes on December 11, 2020. This evaluation does not constitute NRC approval.
71114.06 - Drill Evaluation
Drill/Training Evolution Observation (IP Section 03.02) (2 Samples)
The inspectors evaluated:
- (1) Inspectors observed and evaluated the emergency response organization tabletop drill on October 29, 2020.
- (2) Inspectors observed and evaluated simulator-based licensed operator requal training on November 4,
RADIATION SAFETY
71124.05 - Radiation Monitoring Instrumentation
Calibration and Testing Program (IP Section 03.02) (11 Samples)
- (1) Thermo Scientific PCM-3 personnel contamination monitor, serial number L70L004E, calibrated on December 13, 2019
- (2) JL Shepherd Model 89 Irradiator calibrated on January 10, 2020
- (3) Canberra Fastscan Whole Body Counter calibrated on February 5, 2020
- (4) Mirion telepole survey instrument, serial number L70L074A, calibrated on February 11, 2020
- (5) Ludlum model 12 survey instrument, serial number L70L096D, calibrated on February 26, 2020
- (6) Eberline model RM20 survey instrument, serial number L70L020K calibrated on April 1, 2020
- (7) Eberline R02 survey instrument, serial number L70L030H, calibrated on May 15, 2020
- (8) Eberline model SAC-4 survey instrument, serial number L70L003E, calibrated on July 16, 2020
- (9) Bicron RSO-50 survey instrument, serial number L70L0045Z, calibrated on August 24, 2020
- (10) Thermo Scientific SAM9 small article monitor, serial number L70L504L, calibrated on September 9, 2020
- (11) Thermo Scientific SPM-906 portal monitor, serial number L702009L calibrated on September 25, 2020
Effluent Monitoring Calibration and Testing Program Sample (IP Sample 03.03) (2 Samples)
The inspectors evaluated the calibration and maintenance of the following radioactive effluent monitoring and measurement instrumentation:
- (1) Unit 1 Off-Gas Vent Pipe Noble Gas Calibration for 1D17-K836
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below:
BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10)===
- (1) October 1, 2019 through September 30, 2020
BI02: RCS Leak Rate Sample (IP Section 02.11) (1 Sample)
- (1) July 1, 2019 through September 30, 2020
OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)
- (1) October 1, 2019 through September 30, 2020
71152 - Problem Identification and Resolution
Semiannual Trend Review (IP Section 02.02) (1 Sample)
- (1) Human performance trend June through December 2020
Annual Follow-up of Selected Issues (IP Section 02.03) (3 Samples)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- (1) CR 2020-06561, Standby Liquid Control Hi/Lo Level Alarm During SLC Transfer Pump and Valve"
- (2) CR 2020-06471, "Timeliness of General Emergency Classification During August 8, 2020, Dry Run Drill"
- (3) Loss of Feedwater Heating Results in Loss of Safety Function
71153 - Follow-up of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02)
The inspectors evaluated the following licensee event reports (LERs):
- (1) LER 2019-004 and LER 2019-004-001, Loss of Feedwater Heating results in Loss of Safety Function on August 6, 2019.
The inspectors determined that the cause of the condition described in the LER was not reasonably within the licensees ability to foresee and correct, and, therefore, was not reasonably preventable. No performance deficiency nor violation of NRC requirements was identified.
INSPECTION RESULTS
Failure to Close Valve During Surveillance Procedure Causes Inoperability and Unavailability of the Standby Liquid Control System Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems
Green NCV 05000440/2020004-01 Open
[H.12] - Avoid Complacency 71152 A finding of very low safety significance (Green) and associated non-cited violation of Title 10 CFR Part 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings, was self-revealed for the licensees failure to perform activities affecting quality in accordance with an approved procedure appropriate for the circumstances. Specifically, during performance of PTI-C41-P0001, Standby Liquid Control Transfer System Pump and Valve Operability Test, Revision 10, operators failed to shut transfer line isolation valve, 1C41-F522 causing an unplanned eight-hour limiting condition for operation (LCO) entry and unavailability of both trains of the SLC system.
Description:
On August 20, 2020, during the performance of PTI-C41-P0001, Standby Liquid Control Transfer System Pump and Valve Operability Test, Revision 10, the licensee received the SLC storage tank level HI/LO alarm shortly after starting the SLC transfer pump. The evolution resulted in the unintended addition of approximately 226 gallons of water to the SLC storage tank. The licensee reviewed system response, interviewed personnel, and reviewed procedure PTI-C41-P0001 and determined that the normally locked open transfer line isolation valve, 1C41-F522, had not been shut.
The licensee completed Surveillance Requirement 3.1.7.5 to sample SLC storage tank concentration within 24-hours following the inadvertent water addition. Based on boron concentration, the licensee determined that both the SLC system trains were inoperable and entered LCO 3.1.7 Condition B to restore one train to operable status within eight hours. The licensee returned SLC storage tank concentration to the correct specification about three hours after the initial tank solution test.
Corrective Actions: Immediate corrective actions included determination and correction of SLC storage tank concentration and restoring the SLC system to operable. Additionally, the licensee made procedural changes to add an independent verification step to the closure of the transfer line isolation valve, 1C41-F522.
Corrective Action References: CR 2020-06561, Standby Liquid Control Hi/Lo Level Alarm During SLC Transfer Pump and Valve, 08/20/2020; CR 2020-06563, Leakby Observed Through SLC Transfer Line Isolation Valve, 08/20/2020; and CR 2020-07110, Misposition Plant Status Control Event During SLC Transfer System Pump and Valve Operability Test, 09/11/2020.
Performance Assessment:
Performance Deficiency: The inspectors determined that the licensees failure to implement Section 5.1.3, Step 3, of PTI-C41-P0001, Standby Liquid Control Transfer System Pump and Valve Operability Test, Revision 10, was a performance deficiency. Specifically, the failure to close the transfer line isolation valve 1C41-F522 in accordance with the procedure directly led to the inoperability and unavailability of the SLC system.
Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Human Performance attribute of the Mitigating Systems cornerstone and adversely affected the cornerstone objective to ensure the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences. The inspectors determined the performance deficiency was more than minor because it was associated with the Human Performance attribute of the Mitigating Systems cornerstone and adversely affected the cornerstone objective to ensure the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences. Specifically, an operator failed to close the transfer line isolation valve 1C41-F522, which allowed water to be added to the SLC storage tank, thus negatively impacting the availability of the SLC system.
Significance: The inspectors assessed the significance of the finding using Appendix A, The Significance Determination Process (SDP) for Findings At-Power. The inspector assessed the significance of the finding using Appendix A, The Significance Determination Process (SDP) for Findings At-Power. The inspectors screened the finding against the Mitigating Systems screening questions in Exhibit 2 and answered NO to all screening questions. Therefore, the finding screened to very low safety significance (Green).
Cross-Cutting Aspect: H.12 - Avoid Complacency: Individuals recognize and plan for the possibility of mistakes, latent issues, and inherent risk, even while expecting successful outcomes. Individuals implement appropriate error reduction tools. H.12 - Avoid Complacency: Individuals recognize and plan for the possibility of mistakes, latent issues, and inherent risks, even while expecting successful outcomes. Individuals implement appropriate error reduction tools. Specifically, the operator failed to implement error reduction tools to ensure both actions contained with the step were performed in accordance with written procedures.
Enforcement:
Violation: Title 10 CFR 50 Appendix B, Part V, Instructions, Procedures, and Drawings, states, in part, that activities affecting quality shall be prescribed by documented instructions, procedures, or drawings of a type appropriate to the circumstances and shall be accomplished in accordance with these instructions, procedures, or drawings.
Contrary to the above, on August 20, 2020, while performing an activity affecting quality, operators did not accomplish a surveillance procedure in accordance with the procedure and incorrectly performed a step in surveillance procedure PTI-C41-P0001, and failed to close a valve. Specifically, operators failed to close the transfer line isolation valve 1C41-F522, resulting in an unplanned entry into Technical Specification 3.1.7, Condition B, and adversely affected the availability of the SLC system.
Enforcement Action: This violation is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
Observation: Human Performance Trend June to December 2020 71152 During the second half of 2020, while performing reviews associated with the daily corrective action program, the inspectors identified 17 corrective action documents with human performance-related issues. Examples of human performance issues were spread across different working groups and resulted in various consequential outcomes. These examples included, but were not limited to, a chemistry department individual loss of attention to detail and dropped a glass vial containing a source resulting in a spill, electrician personal not implementing human performance tools (peer check) resulting in the miswiring during modification to the Unit 2 startup transformer and an increase in the out of service time, and the failure to close a valve between the SLC and standby liquid control transfer systems resulting in the inoperability and unavailability of the SLC system. Following their review, the inspectors concluded that the Human Performance attributes associated with the issues were associated with a lack of attention to detail, supervisors' failure to challenge performance and enforce standards and requirements, and individuals not following their processes and procedures. The inspectors engaged the licensee and expressed their observations through meetings and other methods. The inspectors expressed their concern with the upward negative trend in licensee performance and its impacts to plant safety.
Due in part to previous inspector observations, the licensee developed a "critical coaching initiative" to analyze performance gaps and perform training for the site supervisors as documented in CR 2019-09164, "2019 INPO E&A AFI LF.1: Leadership." Following the critical coaching initiative institution, the inspectors observed a temporary reduction in human performance issues. However, considering the most recent human performance issues, the inspectors have concerns about the licensee's corrective actions' effectiveness and longevity.
Additionally, the inspectors noted as a consequence of the most recent supervisor coaching; the licensee wrote five condition reports for supervisors failing the "critical coaching lab in site supervisor training," as documented in CR 2020-08703, CR 2020-08696, CR 2020-08008, CR 2020-08007, and CR2020-07767. The inspectors concluded that while the licensee had begun to address human performance gaps site-wide, but as demonstrated by the most recent supervisor failures of the critical coaching lab, more work was required to ensure performance improvement.
The inspectors did not identify any findings or violations of NRC requirements in the course of their review.
Observation: Emergency Preparedness Drill General Emergency Classification Timeliness Review 71152 The inspectors performed a detailed review of CR 2020-06471, "ERO-Drill: Timeliness of General Emergency Classification During August 8, 2020, Dry Run Drill." The purpose of emergency preparedness drill performance and evaluation, in part, is to determine the licensee's ability to identify and classify events based on plant conditions and communicate emergency action level declarations promptly to state and local authorities. Title 10 CFR 50 Appendix E requires, in part, that "licensees shall establish and maintain the capability to assess, classify, and declare an emergency condition within 15-minutes after the availability of indications to plant operators that an emergency action level has been exceeded and shall promptly declare the emergency conditions as soon as possible following the identification of the appropriate emergency classification level." To assess the timeliness of licensee notification, a "time zero" is identified in drill scenarios when plant conditions change, which should be recognized by plant staff followed by event classification.
The inspectors noted that CR 2020-06471 documented a drill controller issue that the scenario "time zero" was different than what occurred during drill execution. Specifically, the scenario guide stated, "time zero" was 11:35 am, and "time zero" during drill debrief was determined to be 11:40 am. The inspectors noted this distinction to be important because event classification occurred at 11:54 am. The inspectors noted that "Perry Emergency Response Organization Integrated Drill Scenario Guide," Revision 1, stated that at 11:35 am a catastrophic body-to-bonnet failure of the "B" main steam line isolation valve occurred resulting in the rapid increase in steam tunnel temperatures, as well as turbine building/heater bay and Unit 1 plant vent radiation monitor readings. The Perry Emergency Response Organization Integrated Drill Scenario Guide controller notes stated that, "this is the indication for a General Emergency FG 1.1, loss of any two fission product barriers and the loss or potential loss of the third barrier." For this Problem Identification and Resolution sample, the inspectors focused on the licensee's evaluation and assessment of event classification timeliness and associated corrective actions.
The inspectors noted through review of licensee evaluation that upon insertion of the body-to-bonnet failure, the simulator errantly showed flow through the off-gas system.
The Perry Nuclear Power Plant construction is such that both outboard main steam isolation valves and main steam stops are contained in the steam tunnel. Therefore, an indication of off-gas flow in conjunction with the rise in steam tunnel temperatures and vent radiation monitor readings led the operations crew to believe the failure and steam leak had occurred downstream of the main steam stops. The operations crew shut the main steam stops and noted no change in steam tunnel temperature trend or turbine building/heater bay and Unit 1 plant vent radiation monitor readings. The operations crew determined that the leak was unisolable and constituted a loss of a fission product barrier. This information was not promptly communicated to the Emergency Director in the Emergency Operations Facility (EOF) due to conference bridge communications issues. The inspectors challenged the licensee as to why 11:40 am was "time zero" and not 11:35 am, as stated in the drill guide and when plant conditions first presented themselves. The inspectors reviewed PSI-0019, "Emergency Action Level (EAL) Bases Document," Revision 21, Attachment 2 fission product barrier loss/potential loss matrix and bases for an unisolable direct downstream pathway to the environment exists after containment isolation signal guidance. The inspectors noted that the threshold is considered met if the breach is not isolable from the Control Room or an attempt for isolation from the Control Room has been made and was unsuccessful. The licensee stated that based on the off-gas flow indications, even though erroneous and emergency action level basis guidance, it was reasonable for the operations crew to attempt to shut the main steam stops before declaring an unisolable leak.
The inspectors noted three contributors to the event classification almost exceeding the regulatory time frame:
1. Communication issues between the Control Room and EOF Emergency Director
delayed recognition of the leak in the final fission product barrier and a General Emergency declaration. The licensee changed its process to require the Control Room and Emergency Director to maintain an open communication line rather than connecting to the bridge to relay information.
2. The EOF Emergency Director had noted and focused solely on rising Unit 1 plant vent
radiation levels as the indicator to determine a General Emergency had occurred.
The Director was slow to recognize the unisolable leak condition in the Emergency Action Level matrix also applied until prompted by the Control Room.
3. Recent simulator software upgrades resulted in the unintended off-gas flow
indications encountered during the drill. The licensee had validated the scenario before the software upgrades going into effect and had not revalidated before the licensee performing the drill. The licensee changed its process to ensure simulator fidelity before drill execution following software upgrades.
The inspectors did not identify any findings or violations of NRC requirements in the course of their review.
Observation: Loss of Feedwater Heating results in Loss of Safety Function 71152 The inspectors reviewed the associated causal evaluation and corrective actions associated with loss of feedwater heating due to heater 5B isolation during heater alignment. The inspectors noted that the apparent cause was inadequate communication within the Perry organization associated with heater tuning strategies and implications to operating procedures. Specifically, the licensee tuned the heater normal controller for steady-state operations to dampen heater level oscillations at 100 percent power. This strategy restricts the ability to transfer level control from alternate to normal at power levels greater than 62 percent power. The inspectors noted that the operations procedure did not include mitigating actions to reduce power based on the tuning strategy and resulted in heater isolation. Corrective actions included, but were not limited to, revising IOI-0003, "Power Changes," to provide a caution note to operations about heater drain control based on power level, which would incorporate level control restrictions based on tuning strategy. The inspectors did not identify any findings or violations of NRC requirements in the course of their review.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On January 28, 2021, the inspectors presented the integrated inspection results to Mr. R. Penfield, Site Vice President, and other members of the licensee staff.
- On December 10, 2020, the inspectors presented the radiation protection baseline inspection results to Mr. R. Penfield, Site Vice President, and other members of the licensee staff.
- On December 11, 2020, the inspectors presented the Perry Biennial Licensed Operator Requalification Program Inspection Results inspection results to Mr. R. Penfield, Site Vice President, and other members of the licensee staff.
- On December 11, 2020, the inspectors presented the emergency action level and emergency plan changes inspection results to Mr. R. Penfield, Site Vice President, and other members of the licensee staff.
- On January 28, 2021, the inspectors presented the integrated inspection results to Mr. R. Penfield, Site Vice President, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Engineering
Evaluations
FENOC Perry Flood Hazard Reevaluation Report
2/4/2020
Drawings
2-0701-00000
High-Pressure Core Spray System
KK
Procedures
SVI-C41-T2001-A Standby Liquid Control
SVI-P42-T5326
Emergency Closed Cooling System Valve Position Check
VLI-E22A
High-Pressure Core Spray
Work Orders
200753720
SVI-E12-T1182A RHR A PLCI Vlv L/U (31D) RHR A LPCI
Valve Lineup Verification and System Venting
11/18/2020
200754601
SVI-P42-T5326 ECCS Vlv Position Check (31D) Emergency
Closed Cooling System Valve Position Check
10/18/2020
200754975
SVI-E21-T11 LPCS Venting and Vlv L/U (31D) LPCS
Venting and Valve Lineup Verification
10/22/2020
Fire Plans
FPI-0FH
Fuel Handling Building
FPI-0IB
Intermediate Building
FPI-1AB
Auxiliary Building Unit 1
FPI-1DG
Diesel Generator Building
Procedures
FPI-0CC
Unit 1-Division 3 Switchgear 620 - 6 Elevation Fire Zone
FPI-0EW
Emergency Service Water Pumphouse
Calculations
JL-083
Flooding Analysis of Control Complex Building, Intermediate
Building, and Fuel Handling Building - Floor Elevation 574
Feet - 10 Inches
Corrective Action
Documents
2013-05625
Corrective Action Generated to Track Closure of Prompt
Functionability Assessment for CR 2013-05625
10/23/2015
Calculations
R46-023
Division 1 Diesel Generator Jacket Water Heat Exchanger
Performance Testing Results
Miscellaneous
Perry Nuclear Power Plant Annual LORT Exam Information
2/14/2020
Corrective Action
Documents
CR 2019-08949
Recombiner A/B TEMP HI / LOW Alarm in the Control Room
Label Does Not Match the Alarm Response Instruction or
Simulator Alarm Window
10/26/2019
CR 2019-10283
Simulator Hardware Failure During Annual Exam Job
Performance Measures
2/10/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
CR 2020-02702
Simulator Hardware Issue Caused Short Training Delay
03/27/2020
Corrective Action
Documents
Resulting from
Inspection
CR 2020-09365
Inaccurate Information Provided to the NRC
2/07/2020
Miscellaneous
2019 LORT Attendance Records
20 LORT Attendance Records
100% Simulator Steady-State Test
08/28/2020
75% Simulator Steady-State Test
07/27/2019
75% Simulator Steady-State Test
08/28/2020
43% Simulator Steady-State Test
07/27/2019
43% Simulator Steady-State Test
08/28/2020
Operator Remediation Plan; Various Operators
2/31/2019
100% Simulator Steady-State Test
07/27/2019
2019 01-05
Requalification Training Schedule
2/31/2019
20 06-10
Requalification Training Schedule
2/01/2020
20-13
RO Written Exam
Week 7
20-14
SRO Written Exam
Week 7
B2.2.1.1
Transient Testing, Manual SCRAM
03/27/2019
B2.2.1.10
Transient Testing, Main Steam Isolation Valve Closure with
One Safety Relief Valve Stuck Open
07/24/2020
B2.2.1.2
Transient Testing, Trip All Reactor Feed Pump Turbines
03/27/2019
B2.2.1.3
Transient Testing, Main Steam Isolation Valve Closure
07/23/2020
B2.2.1.4
Transient Testing, Simultaneous Trip of All B33 Recirc
Pumps
03/27/2019
B2.2.1.5
Transient Testing, Trip Single B33 Recirc Pump
07/24/2020
B2.2.1.7
Transient Testing, Maximum Rate Power Ramp (100% to
75% to 100%) Using Flow Control Valves
07/24/2020
B2.2.1.9
Transient Testing, Main Steam Line Rupture in Drywell
03/27/2019
Credit for Position
Report
BOP Operator
2/31/2019
Credit for Position
Report
ATC Operator
2/31/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Credit for Position
Report
Shift Manager
2/31/2019
Credit for Position
Report
Unit Supervisor
2/31/2019
Credit for Position
Report
BOP Operator
2/01/2020
Credit for Position
Report
ATC Operator
2/01/2020
Credit for Position
Report
Unit Supervisor
2/01/2020
Credit for Position
Report
Shift Manager
2/01/2020
Cycle 18
Real Time Annual Testing
03/26/2019
OT-3070-PC1E
Simulator Scenario Guide PC1E
OT-3070-001-
PC5D
Simulator Scenario Guide PC5D
OT-3070-005-
RP2A
Simulator Scenario Guide RP2A
OT-3070-RP1D
Simulator Scenario Guide RP1D
OT-3701-ADM-
25SRO
Week 4
OT-3701-ADM-
24SRO
SRO Admin Job Performance Measure (JPM)
Week 2
OT-3701C11-
514RO
Simulator JPM
Week 7
OT-3701C41-
008RO
In Plant JPM
Week 7
OT-3701C61-
501RO
In Plant JPM
Week 7
OT-3701C71-
003RO
Simulator JPM
Week 7
OT-3701G43-
001RO
Week 7
Miscellaneous
OT-3701P57-
In Plant JPM
Week 4
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
001RO
OT-3701R10-
2RO
In Plant JPM
Week 4
OT-3701R43-
501RO
Simulator JPM
Week 6
OTLC-
3058202006-PY-
SGA
Scenario Based Testing
OTLC-
3058202006-PY-
SGB
Scenario Based Testing
OTLC-
3058202006-PY-
SGC1
Scenario Based Testing
OTLC-
3058202007-PY-
SGA
Scenario Based Testing
OTLC-
3058202008-PY-
SGA-HIT
Scenario Based Testing
Simulator Post
Event Testing
Turbine Valve Closure
05/28/2019
Simulator Post
Event Testing
Loss of Two Circulating Water Pumps
2/17/2020
Procedures
NOBP-TR-1271,
Inactive License Retraining Program Records; Various
Operators
NOP-OP-1013-04
Time Critical Operator Actions Tracking Sheet
NOP-TR-1240-06
Remediation Training
NOP-TR-1280
Simulator Configuration Management
Self-Assessments
20 Nuclear Oversight Quality Assessment of Operations
Department
03/31/2020
2019 Nuclear Oversight Quality Assessment of Training
Department
2/27/2020
Simulator Review
Meeting Minutes
2/20/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Committee
Simulator Review
Committee
Meeting Minutes
04/17/2019
Simulator Review
Committee
Meeting Minutes
01/30/2020
Simulator Review
Committee
Meeting Minutes
04/16/2020
Simulator Review
Committee
Meeting Minutes
08/17/2020
Work Orders
19-0002
DFWCS Reactor Feed Pump Trip and Swap to Single
Element
05/02/2019
19-0003
ECP 04-0145 RFP Min Flow Controller Modification
2/21/2019
19-0004
ECP 18-0081 Implement Stroke Time Changes for
1G33F0039 & 1G33F0040
2/21/2019
19-0006
Implement Cycle 18 Core Files for All Three Exposures
(BOL, MOL, EOL)
03/05/2019
19-0007
Implement ECP 18-0274 to Eliminate Automatic High Shaft
Vibration Trip from Main Turbine Protection System
03/12/2019
19-0012
Div 2 EH12 Undervoltage ECP 16-0336-002
03/18/2019
19-0019
Install ECP 04-0113-001 Fire Computer in Control Room
08/28/2019
19-0030
Install ECP 12-0238 Diesel Fire Pump Switch on P970
10/01/2019
20-0015
Install Div 3 DG RM Vent CO2 Injection Bypass Switch on
P800
2/24/2020
20-0044
Implement ECP 17-0220 in the Simulator (MSIV Bypass
Jacks)
10/20/2020
20-0045
Implement ECP 15-0517 for Div 3 in the Simulator
08/17/2020
71111.11Q Miscellaneous
Evolution Specific
Reactivity Plan
Perry Nuclear Power Plant October 2020 Pattern Adjustment 0
OT-3070-003-
RP1C
Scenario Guide
OT-3070-PC1B
Scenario Guide
OT-3070-RP5A
Scenario Guide
Corrective Action
Documents
20-06482
Emergency Service Water Radiation Monitor Spiking
08/17/2020
20-08558
Reactor Protection System (RPS) MG SET a Tripped During
11/04/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
20-08868
MET Tower Instrumentation Not Restored Upon Restoration
of Quincy Power
11/17/2020
20-09476
Unit 2 Startup Transformer Manual Disconnect Stuck Open
2/15/2020
20-09635
Combustible Gas Mixing Compressor Suction Valve Would
Not Reopen Following Compressor Start
2/22/2020
Work Orders
200840084
Replace Power Supply CR 2020-08986
11/23/2020
Corrective Action
Documents
20-08567
Uncertainty of Proper Motor starter Overload Settings for
Reactor Protection System (RPS) Motor Generator (MG) Set
A
11/04/2020
20-08575
Feedback System Transient - Steamflow/Feedflow
Mismatch
11/05/2020
Procedures
NOP-ER-3001-03
Simple Troubleshooting Plan
NOP-OP-1007
Risk Management
PAP-1924
Risk-Informed Safety Assessment and Risk Management
Work Orders
200093606
Replace Relays in RPS "A" MG set
11/27/2020
200835639
ECP 20-0179-001 Disable LS6/7 Linkage TM
11/18/2020
Corrective Action
Documents
2008-50767
Less Than Adequate Documentation for USAR Technical
Basis
2/12/2008
2014-10996
60dpm Leak Shaft Div 2 Jacket Water Circ Pump Prompt
Operability Determination Test
06/27/2014
20-08868
MET Tower Instrumentation not Restored upon Restoration
of Quincy Power
11/17/2020
20-09317
Rheostat on FLEX Lake Pump for ESW "B" Doesnt Work
Correctly Acts as On Off Switch
2/09/2020
20-09535
As Found Condition of the Unit 2 Startup Transformer
Manual Disconnect 2S11-S290 Gearing
2/17/2020
20-09640
Division 1 Diesel Generator Jacket Water Circulation Pump
Blown Fuse
2/22/2020
Operability
Evaluations
20-07870
Plan for Actions for Operation Challenge, Degraded Division
D/G Circulating Jacket Water Pump/Motor
10/16/2020
Procedures
R45-025
Division 1 and 2 Emergency Diesel Generator Jacket Water
Available Net Positive Suction Head
03/09/2010
Work Orders
200841352
Unit 2 Main Transformer Troubleshooting for Unexpected
2/18/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Results Upon Installation of a Modification
Corrective Action
Documents
20-06562
During Development of the Open Phase Modification
ECP-19-203, an Engineer Walkdown of the Startup
Transformer Relay Panel (1H13P0809) was Not Performed
08/20/2020
20-08701
Failed PMT Unit 1 Startup OPPS Modification
11/10/2020
Engineering
Changes
ECP 17-0220-003 Main Steam Line Isolation Valve Nuclear Steam Supply
Shutoff System Isolation Logic C Test Jack Installation
ECP 17-0220-003 Main Steam Line Isolation Valve Nuclear Steam Supply
Shutoff System Isolation Logic C Test Jack Installation
Engineering
Evaluations
601293470
Engineering Evaluation Request
11/11/2020
Procedures
IP-ENG-001 Form
19-0203-000 Dedicated Open Phase Control Room
Annunciators - Unit-1
NOP-WM-1001-0
Addendum # A-4 TEST Functional WO 200803505
SVI-E31-T0074-C
MSL High Flow Channel "C" Functional for 1E31-N686C and
Work Orders
200737101
Implement ECP 17-0220-003
05/10/2020
200751207
SVI-E31-T0074C (92D) MSL High Flow Channel "C"
Functional for 1E31-N686C and 1E31-N688C
06/10/2020
Corrective Action
Documents
20-07809
Steam Bypass and Pressure Regulating Pump A
Discharge Filter Failed Post-Maintenance Testing
10/08/2020
Work Orders
200750868
Emergency Service Water Loop "A" Flow and Differential
Pressure Test
10/24/2020
200752301
Replace 3.0 Micron Filter
10/08/2020
200752959
Replace Fullers Earth Filters
09/12/2020
200762832
Replace High-Pressure Filter, HPU A
09/17/2020
200773294
SVI-D17-T8041 ESW Loop A Radiation Monitor Channel
Calibration For 1D17-K604
10/07/2020
200778768
Replace Time Delay Relay 1M39Q7004
10/21/2020
200778768
Replace Time Delay Relay 1M39Q7004
10/22/2020
200778769
Replace Time Delay Relay 1M39Q7008
10/22/2020
200791518
Inspect/Replacement Filters, LPCS Room A
10/21/2020
200794100
Perform Static Motor Operated Valve Test
10/22/2020
200832456
A Rad Monitor Cable Replacement
09/23/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
Diverse and Flexible Coping Strategies (FLEX)
Implementation Guide
Procedures
FSG 60.1
Supply ESW A Header from a FLEX Pump at the ESW
PTI-P45-P0001
ESW System Loop A Flow Differential Pressure Test
SVI-B21T0077A
MSL Low Condenser Vacuum Channel "A" Calibration For
SVI-C71-T0043-A
Drywell High-Pressure Channel A Calibration For
SVI-R43-T1317
Diesel Generator Start and Load Division 1
Work Orders
200737101
IMPLEMENT ECP 17-0220-003
10/05/2020
200750868
PTI-P45P0001 1 (92D) EWS System Loop A Flow and
Differential Pressure Test on
10/24/2020
200751027
SVI-E31T0074C-1 (92D) MSL High Flow Channel "C"
Functional for 1E31-N668C and 1E31-N688C
10/06/2020
200752684
FLEX Water Pump Functional Testing
06/15/2020
200770447
SVI-B21-T0077-A MSL Low Condenser Vacuum "A"
Calibration For 1B21-N0
10/19/2020
200773288
SVI-C71-T0043-A Drywell High-Pressure Channel A
Calibration
09/21/2020
Miscellaneous
Perry Station 10 CFR 50.54(q) Evaluator Qualification and
Training Records Spreadsheet
05/19/2020
NRC Letter
Subj: Perry Nuclear Power Plant, Unit No. 1 - Issuance of
Amendment No. 186 Concerning Changes to Emergency
Response Organization Staff
08/14/2019
PY-2019-017-00
CFR 50.54(q)2 Analysis for Perry Nuclear Power Plant
Emergency Plan Revision
08/07/2019
PY-2019-017-00
CFR 50.54(q)3 Evaluation for Perry Nuclear Power Plant
Emergency Plan Revision
09/06/2019
PY-2019-039-00
CFR 50.54(q)2 Analysis for Perry Nuclear Power Plant
Emergency Plan Revision
11/04/2019
PY-2019-039-00
CFR 50.54(q)3 Evaluation for Perry Nuclear Power Plant
Emergency Plan Revision
11/06/2019
PY-2019-044-00
CFR 50.54(q)2 Analysis for Perry Nuclear Power Plant
Emergency Plan Revision
2/17/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
PY-2019-044-00
CFR 50.54(q)3 Evaluation for Perry Nuclear Power Plant
Emergency Plan Revision
01/06/2020
Procedures
Emergency Plan for Perry Nuclear Power Plant
Emergency Plan for Perry Nuclear Power Plant
Emergency Plan for Perry Nuclear Power Plant
Emergency Plan for Perry Nuclear Power Plant
NOP-LP-5002
Evaluation of Changes to Emergency Plans and Supporting
Documents 10 CFR 50.54(q)
Miscellaneous
20 4th Quarter ERO Tabletop Drill TSC-EOF
Calibration
Records
Abacos 2000 Whole Body Counter Calibration
2/05/2020
JL Shepherd Irradiator Calibration and Verification
01/10/2020
L702009L
Thermo Scientific SPM-906 Portal Monitor
09/25/2020
L70L003E
Eberline SAC-4 Survey Instrument
07/16/2020
L70L0045Z
Bicron RSO-50 Survey Instrument
08/24/2020
L70L004E
Thermo Scientific PCM-2
2/13/2019
L70L020K
Eberline RM-20 Survey Instrument
04/01/2020
L70L030H
Eberline RO2 Survey Instrument
05/16/2020
L70L074A
Mirion Telepole Survey Instrument
2/11/2020
L70L096D
Ludlum Model 12 Survey Instrument
2/26/2020
L70L504L
Thermo Scientific Small Article Monitor
09/22/2020
ESW Loop A Radiation Monitor Channel Calibration for
10/07/2020
Corrective Action
Documents
CR-2020-05336
Procedure Adherence During WBC Calibration
06/29/2020
CR-2020-05337
Input Error in Creating WBC Calibration File
06/29/2020
CR-2020-05376
Pre NRC Assessment SA-BN-2020-1920 Identified
Deficiency: Incorrect Source Information Contained in
SVI-D19-T1356A
06/30/2020
Engineering
Evaluations
D19 Containment Hi Range Radiation Monitor Evaluation
Procedures
HPI-J0054
Calibration of the Abacos 2000 Whole Body Counting
System
4, 6
NOP-OP-4401
Radiation Protection Instrumentation Program
Work Orders
200767227
Off-Gas Vent Pipe Noble Gas Radiation Monitor Calibration
09/17/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
200773294
ESW Loop A Radiation Monitor Channel Calibration for
10/07/2020
71151
Corrective Action
Documents
CR-2020-06028
NRC ID: Door 1P54X0202A High-Pressure Core Spray
Pump Room Found Unsecured
07/29/2020
Miscellaneous
Reactor Coolant System Dose Equivalent Iodine
Determination Summary Data from 10/01/2019 Through
09/30/2020
Various
Procedures
TSR Modes
1,2&3-19
Technical Specification Rounds Modes 1, 2, and 3
10/01/2019 -
01/19/2020
TSR Modes
1,2&3-20
Technical Specification Rounds Modes 1, 2, and 3
01/20/2020 -
09/30/2020
Corrective Action
Documents
2019-06618
Entered ONI-N36 Loss of Feedwater Heating and ONI-C51
due to Heater 5B Isolation during Startup while Aligning
Heater Normal Drains Unplanned Limiting Condition of
Operation Entry
08/16/2019
Drawings
2-0691-00000
Standby Liquid Control System
2-0692-00000
Standby Liquid Control Transfer System
V
Miscellaneous
LER 2019-004
Loss of Feedwater Heating Results in Loss of Safety
Function
06/08/2019
Procedures
PTI-C41-P0001
Standby Liquid Control Transfer System Valve Test
Miscellaneous
LER 2019-004
Loss of Feedwater Heating Results in Loss of Safety
Function
06/08/2019
LER 2019-004-01 Loss of Feedwater Heating Results in Loss of Safety
Function
11/06/2019