IR 05000259/2022003
| ML22312A497 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 11/09/2022 |
| From: | Wesley Deschaine NRC/RGN-II/DRP/RPB5 |
| To: | Jim Barstow Tennessee Valley Authority |
| References | |
| IR 2022003 | |
| Download: ML22312A497 (17) | |
Text
SUBJECT:
BROWNS FERRY NUCLEAR PLANT - INTEGRATED INSPECTION REPORT 05000259/2022003, 05000260/2022003 AND 05000296/2022003
Dear Mr. Barstow:
On September 30, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Browns Ferry Nuclear Plant. On November 3, 2022, the NRC inspectors discussed the results of this inspection with Mr. Manu Sivaraman and other members of your staff. The results of this inspection are documented in the enclosed report.
No findings or violations of more than minor significance were identified during this inspection.
This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely, Wesley D. Deschaine, Chief Reactor Projects Branch 5 Division of Reactor Projects Docket Nos. 05000259, 05000260 and 05000296 License Nos. DPR-33, DPR-52, and DPR-68
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000259, 05000260 and 05000296
License Numbers:
Report Numbers:
05000259/2022003, 05000260/2022003 and 05000296/2022003
Enterprise Identifier:
I-2022-003-0013
Licensee:
Tennessee Valley Authority
Facility:
Browns Ferry Nuclear Plant
Location:
Athens, Alabama
Inspection Dates:
July 01, 2022 to September 30, 2022
Inspectors:
N. Karlovich, Resident Inspector
M. Kirk, Resident Inspector
M. Meeks, Senior Operations Engineer
N. Peterka, Fuel Facility Inspector
K. Pfeil, Resident Inspector
J. Steward, Senior Resident Inspector
J. Viera, Senior Operations Engineer
Approved By:
Wesley D. Deschaine, Chief
Reactor Projects Branch 5
Division of Reactor Projects
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Browns Ferry Nuclear Plant, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.
List of Findings and Violations
No findings or violations of more than minor significance were identified.
Additional Tracking Items
Type Issue Number Title Report Section Status URI 05000259/2022003-01 Browns Ferry Unit 1 High Pressure Coolant Injection (HPCI) Inoperable on July 12, 2022 71152S Open
PLANT STATUS
Unit 1 began the inspection period in Mode 1, 100 percent (full) rated thermal power (RTP). On July 6, 2022, the Unit down powered to 77 percent RTP in order to comply with the State of Alabama National Pollutant Discharge Elimination (NPDES) Permit which limits the temperature of heated effluent from the plant such that the 24-hour average downstream plant-induced water temperature should not exceed 90 degrees F. On July 7, 2022, downstream plant-induced water temperature was maintained such that Unit 1 returned to 100 percent RTP. On July 8, 2022, Unit 1 down powered to 51 percent RTP in order to comply with NPDES 24-hour average downstream plant-induced water temperature requirements and returned to full RTP on July 10, 2022. On July 11, 2022, Unit 1 down powered to 70 percent RTP for a control rod pattern adjustment and returned to full RTP on July 12, 2022. On August 22, 2022, Unit 1 commenced coast down in power in anticipation of a planned refueling outage (1R14). On September 1, 2022, reactor recirculation pump 1A tripped due to multiple power cells being bypassed on the 1A variable frequency drive (VFD) which lowered power to 38 percent RTP. On September 5, 2022, following repairs to the VFD power was raised to 95 percent RTP. Unit 1 continued to coast down in power until reactor recirculation pump 1B tripped due to multiple power cells being bypassed on the 1B VFD on September 28, 2022, which lowered power from 83 percent RTP to approximately 40 percent RTP. Unit 1 remained at 40 percent power until the unit was shutdown on September 30, 2022, at 2100 for the 1R14 refueling outage, where it remained through the end of the inspection period.
Unit 2 began the inspection period at full RTP. On September 15, 2022, Unit 2 performed a planned down power to 62 percent RTP for testing of the turbine control valve and then returned to full RTP where it remained through the end of the inspection period.
Unit 3 began the inspection period at full RTP. On July 8, 2022, Unit 3 down powered to 78 percent RTP in order to comply with NPDES 24-hour average downstream plant-induced water temperature requirements and returned to full RTP on July 9, 2022. On August 26, 2022, Unit 3 down powered to 65 percent RTP for a planned control rod pattern adjustment. On August 28, 2022, Unit 3 returned to full RTP. On September 6, 2022, Unit 3 down powered to 63 percent RTP for power suppression testing due to indications of damaged fuel. On September 10, 2022, Unit 3 returned to full RTP. On September 23, 2022, Unit 3 down powered to 70 percent for a planned control rod sequence exchange and returned to full RTP on September 24, 2022, where it remained through the end of the inspection period.
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors performed activities described in IMC 2515, Appendix D, Plant Status, observed risk significant activities, and completed on-site portions of IPs. 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.
REACTOR SAFETY
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (3 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Unit 2 Core Spray Loop 1 while Core Spray Loop 2 was under planned maintenance on July 13, 2022
- (2) Unit 2 Residual Heat Removal System (RHR) Loop 2 on September 09, 2022
- (3) Unit 0 "A" Control Bay Chiller pump and Chiller while B Chiller was under planned maintenance on September 15, 2022
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated system configurations during a complete walkdown of the Unit 1, 2 and 3 Containment Atmosphere and Dilution (CAD) system on August 17, 2022
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (3 Samples)
The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:
- (1) Fire Area 5, Electric board room 1A on August 9, 2022
- (2) Fire Area 18, Unit 2 Battery and battery board room on August 9, 2022
- (3) Fire Area 16, Units 2 and 3 Cable Spreading room B on September 16, 2022
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) Unit 3 Emergency Diesel Generator (EDG) Building on June 21-24, 2022, and August 10, 2022
71111.11B - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Requalification Program (IP Section 03.04) (1 Sample)
The inspectors reviewed the facility operating history and associated documents in preparation for this inspection. During the week of September 12, 2022, the inspectors reviewed documentation, interviewed licensee personnel, and observed the administration of operating tests associated with the licensees operator requalification program. Each of the activities performed by the inspectors was done to assess the effectiveness of the facility licensee in implementing requalification requirements identified in 10 CFR Part 55, Operators Licenses. The evaluations were also performed to determine if the licensee effectively implemented operator requalification guidelines established in NUREG-1021, Operator Licensing Examination Standards for Power Reactors, and Inspection Procedure (IP) 71111.11, Licensed Operator Requalification Program. The inspectors also evaluated the licensees simulation facility for adequacy for use in operator licensing examinations using ANSI/ANS-3.5-1985, American National Standard for Nuclear Power Plant Simulators for use in Operator Training and Examination. The inspectors observed three crews during the performance of the operating tests. Documentation reviewed included written examinations, Job Performance Measures (JPMs), simulator scenarios, licensee procedures, on-shift records, simulator modification request records, simulator performance test records, operator feedback records, licensed operator qualification records, remediation plans, watchstanding records, and medical records. The records were inspected using the criteria listed in IP 71111.11. Documents reviewed during the inspection are documented in the List of Documents Reviewed.
- (1) Biennial Requalification Written Examinations The inspectors evaluated the quality of the licensed operator biennial requalification written examination administered in 2021.
Annual Requalification Operating Tests The inspectors evaluated the adequacy of the facility licensees annual requalification operating test.
Administration of an Annual Requalification Operating Test The inspectors evaluated 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.
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 the following evolutions:
Unit 1 downpower due to river temperature on July 6, 2022
Unit 1 removal of extraction steam from feedwater heaters 1A1, 1B1 and 1C1 to implement final feedwater temperature reduction on August 20, 2022
Unit 3 downpower to 70 percent RTP and removal of 3A Reactor Feed Pump Turbine from service on August 26, 2022
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated two separate licensed operator requalification training sessions which included a control rod drift, loss of Emergency Equipment Cooling Water (EECW), Safety Relief Valve (SRV) lift, Electro Hydraulic Control (EHC) system leak, high power Anticipatory Transient Without Scram (ATWS), high suppression chamber pressure caused by SRV tailpipe break on the Unit 2 simulator on August 15, 2022, which required the crew to enter various abnormal operating instructions (AOI), emergency operating instructions (EOI) and emergency plan Implementing procedures (EPIP) to control the plant and appropriately classify the emergency.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (3 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) RHR 1A Heat Exchanger Outlet Valve, 1-FCV-23-34 loss if indication during closure stroke from the main control room and subsequent actuator replacement maintenance activity on August 18, 2022
- (2) Maintenance Rule Periodic Evaluation, 50.65(a)(3) for January 2020 through December 2021 completed on September 21, 2022
- (3) Diesel Exhaust Board 3EB Room Exhaust Fan found tripped, work order 123060605 written and documented maintenance rule functional failure on September 28, 2022
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (1 Sample)
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) Evaluated risk of various Unit 1, Unit 3 and common protected equipment while EDG A removed from service during planned maintenance on August 2, 2022
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) Unit 2, System 2 Minimum Flow Isolation Valve Operator, 2-MVOP-075-0037 as found close stem factor exceeded acceptance criteria on September 22, 2022
- (2) Unit 1, RHR Loop 1 LPCI outboard injection valve,1-FCV-074-0052, having a worn bearing found in the gear train on September 23, 2022
- (3) Unit 1, 2, and 3 nitrogen storage tank A fill line safety valve, 0-RFV-084-0503, experiencing excessive leakage during relief valve testing on September 16, 2022
- (4) Unit 1 reactor building equipment access inner door leak failure of 0-TI-408 per CR
===1700900 on September 28, 2022
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01)===
The inspectors evaluated the following post-maintenance testing activities to verify system operability and/or functionality:
- (1) Unit 1, HPCI turbine control valve, 1-FCV-73-19, after replacement on the electronic governor (EG-R) actuator on July 16, 2022
- (2) Units 1 and 2, A diesel generator (DG) following generator replacement on August 4, 2022
- (3) Unit 0, a battery charger after replacement of the Shutdown Board D 250 V DC Battery Charger on September 22, 2022
- (4) Unit 0, breaker 0-BKR-031-2201A, for the 480V Supply for control bay chilled water pump B, after the breaker was returned from cleaning on September 22, 2022
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance testing activities to verify system operability and/or functionality:
Surveillance Tests (other) (IP Section 03.01) (1 Sample)
- (1) Unit 3 Control Rod Coupling Integrity Check during power suppression testing on September 08, 2022
Inservice Testing (IP Section 03.01) (2 Samples)
- (1) Unit 0 (Common) Residual Heat Removal Service Water (RHRSW) C3 IST Group A Quarterly Pump Test on August 31, 2022
- (2) Unit 0 (Common) Residual Heat Removal Service Water (RHRSW) Pump C1 IST Group A Quarterly Pump Test on September 26, 2022
RCS Leakage Detection Testing (IP Section 03.01) (1 Sample)
- (1) Unit 3, Drywell Floor Drain Leakage Rate rise documented under CR 1795731 which triggered entry on August 9, 2022, into Action Level 3 of Inspection Manual Chapter 2515, Appendix D, Attachment 1
FLEX Testing (IP Section 03.02) (1 Sample)
- (1) Flex Equipment Storage Building (FESB) Inspection and Maintenance on August 30, 2022
71114.06 - Drill Evaluation
Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)
The inspectors evaluated:
- (1) The inspectors reviewed and evaluated the emergency response organization drill response during a Unit 2 shutdown Mode 4 scenario that required the facilities to correctly classify the event and notify the required outside organizations within the required timeframes on July 27,
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
MS06: Emergency AC Power Systems (IP Section 02.05)===
- (1) Unit 1 (July 1, 2021 - June 30, 2022)
- (2) Unit 2 (July 1, 2021 - June 30, 2022)
- (3) Unit 3 (July 1, 2021 - June 30, 2022)
MS09: Residual Heat Removal Systems (IP Section 02.08) (3 Samples)
- (1) Unit 1 (July 1, 2021 - June 30, 2022)
- (2) Unit 2 (July 1, 2021 - June 30, 2022)
- (3) Unit 3 (July 1, 2021 - June 30, 2022)
MS10: Cooling Water Support Systems (IP Section 02.09) (3 Samples)
- (1) Unit 1 (July 1, 2021 - June 30, 2022)
- (2) Unit 2 (July 1, 2021 - June 30, 2022)
- (3) Unit 3 (July 1, 2021 - June 30, 2022)
71152A - Annual Follow-up Problem Identification and Resolution Annual Follow-up of Selected Issues (Section 03.03)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- (1) Corrective actions associated with relay contacts for the Unit 3 3C RHR pump 4kV shutdown board breaker not responding as expected while performing preventative maintenance on August 26, 2022
- (2) Repairs and corrective actions associated with Unit 3 Drywell Pressure High indicator reading high and indicating trip condition due to water intrusion in the pressure transmitter on June 22, 2022
71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02)
- (1) The inspectors reviewed the licensees corrective action program for potential adverse trends in increasing trend in moisture content in the Unit 1 HPCI turbine oil samples that might be indicative of a more significant safety issue on September 30, 2022
71153 - Follow Up of Events and Notices of Enforcement Discretion Event Followup (IP Section 03.01)
- (1) The inspectors evaluated unplanned inoperability of Unit 1 HPCI due to the failure of the turbine control valve to open during a surveillance and licensees response on July 12,
INSPECTION RESULTS
Unresolved Item (Open)
Browns Ferry Unit 1 High Pressure Coolant Injection (HPCI) Inoperable on July 12, 2022 URI 05000259/2022003-01 71152S
Description:
On July 12, 2022, during the performance of the Browns Ferry (BF) Unit 1 HPCI quarterly flow test, operators started the auxiliary oil pump, but the HPCI governor valve failed to open. The governor valve controls flow of steam to the HPCI pump turbine. With the governor valve closed the HPCI system cannot perform its safety function. The licensee subsequently declared Unit 1 HPCI inoperable at 0954 central time. The Automatic Depressurization System (ADS) and Reactor Core Isolation Cooling (RCIC) systems remained operable. This condition placed the unit into Technical Specification action statement LCO 3.5.1.C, which provides the licensee 14 days to restore HPCI to operation. Following replacement of the EGR (Electronic Governor Remote), remote servo and post maintenance testing, HPCI was restored to operable at 0915 on July 15, 2022.
The licensee reported the event to the NRC on July 12, 2022, under event number 55992 as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(v) and submitted a written report as Licensee Event Report (LER) 50-259/2022-002-00, HPCI Inoperable Due to Corroded Actuator on September 12, 2022. The licensee completed a Level 2 Evaluation Report titled, Unit 1 HPCI Turbine Control Valve Failed to Open documented under Condition Report (CR) 1789217 on August 17, 2022. HPCI Failure Analysis of the Woodward EGR Actuator, Rev.0 was performed by third party vendor Engine Systems Inc., on August 17, 2022. Revision 1 to the Failure Analysis of the Woodward EGR Actuator was issued on October 3, 2022. The licensee approved a Management Review Committee (MRC) endorsed version of a revision to the Level 2 Evaluation Report titled, Unit 1 HPCI Turbine Control Valve Failed to Open on October 17, 2022. Issuance of revision 2 to the Failure Analysis of the Woodward EGR Actuator is pending.
An unresolved item (URI) is opened to review the MRC endorsed version of the Level 2 Evaluation and the pending revision 2 of the failure analysis of the Woodward EGR Actuator to determine if there is a performance deficiency and when BF Unit 1 HPCI was inoperable.
Planned Closure Actions: NRC subject matter experts (SMEs) will review the licensees evaluation of the issue and will document the results in the BF fourth quarter integrated inspection report.
Licensee Actions: On July 21, 2022, scope add 1372 and WO 114560684, "Unit 1 HPCI Gland Seal Leak-off lines need to be routed downward, were added to the outage scope for the 1R14 refueling outage commencing October 1, 2022.
Corrective Action References: CRs 1552443, 1729940, 1789217, 1790363 and WO
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On November 3, 2022, the inspectors presented the integrated inspection results to Mr.
Manu Sivaraman and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
0-47E866-9
Flow Diagram Chilled Water Circulating Pumps
Rev 14
1-47E862-1
Units 1 and 0 Flow Diagram Containment Atmosphere
Dilution System
Rev 27
1-OI-84-ATT-2A
Containment Atmosphere Dilution System Panel Lineup
Checklist
Rev 8
2-47E811-1
Flow Diagram Residual Heat Removal System
Rev 77
2-47E814-1
Flow Diagram Core Spray System
Rev 56
Drawings
3-47E862-1
Unit 3 Flow Diagram Containment Atmosphere Dilution
System
Rev 32
0-OI-31
Control Bay and Off-Gas Treatment Building Air
Conditioning System
Rev 172
0-OI-31/ATT-1
Valve Lineup Checklist
Rev 137
0-OI-31/ATT-2
Panel Lineup Checklist
Rev 136
0-OI-31/ATT-3
Electrical Lineup Checklist
Rev 137
0-OI-31/ATT-4
Instrument Inspection Checklist
Rev 137
1-OI-84/ATT-1A
Containment Atmosphere Dilution System Valve Lineup
Checklist
Rev 10
2-OI-75
Core Spray System
Rev 120
2-OI-75/ATT-1
Core Spray System Valve Lineup Checklist
Rev 106
2-OI-75/ATT-2
Panel Lineup Checklist Unit 2
Rev 107
2-OI-75/ATT-3
Cores Spray System Electrical Lineup Checklist
Rev 106
2-OI-75/ATT-4
Core Spray System Instrument Inspection Checklist
Rev 105
2-OI-84/ATT-1
Containment Atmosphere Dilution System Valve Lineup
Checklist
Rev 51
3-OI-84/ATT-1A
Containment Atmosphere Dilution System Valve Lineup
Checklist
Rev 31
Procedures
3-OI-84/ATT-2A
Containment Atmosphere Dilution System Panel Lineup
Checklist
Rev 29
0-47E216-106
Ignition Source Drawings Plan El. 606.0 and 621.25
Rev 3
Drawings
0-47E216-70
NFPA 805 Fire Areas Plan El. 617.0 and 621.25
Rev 1
Fire Plans
NFPA 805 Fire Protection Report - Appendix F, Fire
Safety Analysis
Rev 0
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
FPR-Volume 2
Fire Protection Report Volume 2
Rev 73
NFPA 805 Protection
Report
Appendix F Fire Area 16
Rev 5
MDQ00004020110008
Flow Capacity of the Diesel Generator Building
Emergency Drain Piping
Rev 1
Calculations
NDN00099920070031
BFN Probabilistic Risk Assessment - Internal Flooding
Analysis
Rev 3
Drawings
0-47E851-4
Flow Diagram Drainage
Rev 18
0-OI-40
Station Drainage System
Rev 37
Procedures
3-ARP-9-7C
Panel 9-7 3-XA-55-7C
Corrective Action
Documents
Condition Reports
28394; 1738904; 1759998; 1627098; 1683693;
1692069; 1694927
JPM 0AREP20APTC
Hazards - Hostile Action within the Protected Area (HS1)
without Vaporstream
Rev 0
JPM 0AREP22APTC
HAZARDS - HOSTILE ACTION within the OWNER
CONTROLLED AREA or airborne attack threat within 30
minutes - without Vaporstream
Rev 0
JPM 1IPAOI06AP
Actions outside Control Room to attempt to close Unit 1
MSRV 1-18 per 1-AOI-1-1
Rev 0
JPM 1IPEO108
EOI Appendix 16L - Bypassing High Temperature
Isolation
Rev 1
JPM 1IPFSS38
Perform 1-FSS-16.2, Attachment 10, Section 2, Step C
to align Panel 25-31 for RCIC Operation at the Backup
Control Panel
Rev 0
JPM 2IPEOI06
EOI Appendix 16H - Bypassing RCIC High RPV Water
Level Shutdown Interlocks
Rev 7
JPM 2SAOI10AP
Respond to Single Recirc Pump Trip in Mode 1
Rev 3
JPM 2SEOI20
Align Shutdown Cooling from Unit 3 in accordance with
2-EOI Appendix 17E
Rev 0
JPM 3IPFSS20
Align 4KV Shutdown Board 3EA to Diesel Generator 3A
per 3-FSS-16-2, Attachment 6, Section 3.0
Rev 0
JPM 3SEOI22AP
3-EOI Appendix 17F, RHR Fails, use Loop II Core Spray
Rev 0
Medical Records
Medical Records reviewed for twelve licensed operators
Miscellaneous
Remediation Records
Five (5) Remedial Training Records (Individual and
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Crews) from 2-year Training Cycle
SEG# LOR-EXAM-26
Simulator Scenario LOR-EXAM-26
Rev #07
SEG# LOR-EXAM-77
Simulator Scenario LOR-EXAM-77
Rev #3
SEG# LOR-EXAM-
78A
Simulator Scenario LOR-EXAM-78A
Rev #0
SEG# LOR-EXAM-84
Simulator Scenario LOR-EXAM-84
Rev #00
Simulator Testing
Steady State Test, 74%, 11-29-2021; Steady State Test,
50%, 7-11-2022; Malfunction Test, FW30, 7-7-2022;
Malfunction Test, RD06, 7-10-2022; Malfunction Test,
TC01, 7-10-2022; Transient Test, 2021 #2, 11-2-2021;
Transient Test, 2021 #5, 11-2-2021; Transient Test,
22 #3, 6-27-2022; Transient Test, 2022 #7, 6-2-2022;
Transient Test, 2022 #8, 6-2-2022
Written Examination
21 NRC Biennial Examinations, RO and SRO
Examination 3
Miscellaneous
OPL1755494
Control Rod Drift/Loss of EECW/SRV Lift/EHC
Leak/ATWS EOI-1A/ High SC Pressure/EOI-2
Rev 0
1-GOI-100-12
Power Maneuvering
Rev 20
Procedures
1-OI-6
Feedwater Heating and Misc Drains System
Rev 44
1794453
08/18/2022
Corrective Action
Documents
1794821, 1791930
09/28/2022
Self-
Assessments
R40 220224 179
Maintenance Rule 13th Periodic Report January 2020 to
December 2021
Rev 0
23060605
09/28/2022
Work Orders
23091734
08/18/2022
Calculations
MDQ2075910144
Rev 6
CR 1222334827
Corrective Action
Documents
CR 1790852, 1711939
Operability
Evaluations
CR 1789337
09/22/2022
0-TI-408
Equipment Air Lock Door Seal Pressure Decay Test
Rev 11
NEDP-22
Operability Determinations and Functional Evaluations
Rev 23
Procedures
OPDP-8
Operability Determination Process and Limiting
Conditions for Operation Tracking
Rev 29
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2245070
09/22/2022
Work Orders
21509559
1-47E812-1
Flow Diagram High Pressure Coolant Injection System
Rev 48
Drawings
1-47E812-2
Flow Diagram HPCI Oil System
Rev 5
Miscellaneous
BFN-VTD-W290-0030
Installation and Operation of Woodward EG-3C AND
EG-R Actuators
Rev 1
1-SR-3.5.1.7
HPCI Main and Booster Pump Set Developed Head and
Flow Rate Test at Rated Reactor Pressure
Rev 45
MCI-0-082-ENG014
Standby Diesel Engine Generator Removal and
Reinstallation
Rev 22
Procedures
MPI-0-073-TRB001
High Pressure Coolant Injection (HPCI) Turbine
Preventative Maintenance
Rev 58
2405721
Work Orders
23038729,
23038489,
2196374
1-GOI-100-12
Power Maneuvering
Rev 20
1-GOI-100-12A
Unit Shutdown from Power Operation to Cold Shutdown
and Reductions in Power During Power Operations
Rev 38
Procedures
1-OI-69
Reactor Water Cleanup System
Rev 86
79847
Preventive Maintenance Job Plan
Rev 2
Miscellaneous
Operational Decision Making Issue Evaluation
Document on increasing Unit 3 Drywell Unidentified
Leakage
08/19/2022
0-SI-4.5.C.1(C1)
RHRSW Pump C1 IST Group A Quarterly Pump Test
Rev 12
Procedures
0-SI-4.5.C.1(C3)
RHRSW Pump C3 IST Group A Quarterly Pump Test
Rev 19
Work Orders
2344501
08/30/2022
R40210928088
Unit 2 MSPI Basis Document
Rev 20
R40210928089
Unit 3 MSPI Basis Document
Rev 20
71151
Engineering
Evaluations
R4021098087
Unit 1 MSPI Basis Document
Rev 21
Corrective Action
CR 1785291,
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
1801867, 1785140
Documents
CR 1798886, 1799518
Work Orders
23001232
Corrective Action
Documents
2443, 1729940,
1789217 and 1790363
10/17/2022
Miscellaneous
1372
Scope add
10/17/2022
Work Orders
114560684
10/17/2022