IR 05000390/2021001

Integrated Inspection Report 05000390/2021001 and 05000391/2021001

ML21125A204
Person / Time
Site:	Watts Bar
Issue date:	05/05/2021
From:	Tom Stephen NRC/RGN-II/DRP/RPB5
To:	Jim Barstow Tennessee Valley Authority
References
IR 2021001
Download: ML21125A204 (16)

Text

May 5, 2021

SUBJECT:

WATTS BAR - INTEGRATED INSPECTION REPORT 05000390/2021001 AND 05000391/2021001

Dear Mr. Barstow:

On March 31, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Watts Bar. On April 28, 2021, the NRC inspectors discussed the results of this inspection with Mr. Anthony Williams and other members of your staff. The results of this inspection are documented in the enclosed report.

One self-revealed Severity Level IV violation without an associated finding is documented in this report. 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 Watts Bar. 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/

Thomas A. Stephen, Chief Reactor Projects Branch 5 Division of Reactor Projects Docket Nos. 05000390 and 05000391 License Nos. NPF-90 and NPF-96

Enclosure:

As stated

Inspection Report

Docket Numbers: 05000390 and 05000391 License Numbers: NPF-90 and NPF-96 Report Numbers: 05000390/2021001 and 05000391/2021001 Enterprise Identifier: I-2021-001-0056 Licensee: Tennessee Valley Authority Facility: Watts Bar Location: Spring City, TN 37381 Inspection Dates: January 01, 2021 to March 31, 2021 Inspectors: W. Deschaine, Senior Resident Inspector K. Miller, Resident Inspector Approved By: Thomas A. Stephen, Chief Reactor Projects Branch 5 Division of Reactor Projects Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Watts Bar, 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

Pressurizer Safety Valves Outside of Technical Specification (TS) Limits Due to Set Point Drift Cornerstone Severity Cross-Cutting Report Aspect Section Not Applicable Severity Level IV Not Applicable 71153 NCV 05000391/2021001-01 Closed A self-revealed Severity Level (SL) IV NCV of TS 3.4.10, Pressurizer Safety Valves, was identified when routine as-found lift pressure tests of pressurizer safety valves WBN-2-RFV-068-0563 and WBN-2-RFV-068-0565 revealed that the valves lifted at a pressure lower than allowed by TS Surveillance Requirement 3.4.10.1 for a duration that was longer than the conditions TS required action completion time.

Additional Tracking Items

Type Issue Number Title Report Section Status LER 05000390,05000391/20 LER 2020-002-00 for Watts 71153 Closed 20-002-00 Bar Nuclear Plant, Units 1 and 2, Automatic Start of the Emergency Diesel Generators due to an Equipment Failure During Transfer of Power Source for the 1B-B Shutdown Board LER 05000391/2020-002-00 LER 391/2020-002-00, Two 71153 Closed Pressurizer Safety Valves Outside of Technical Specification Limits Due to Set Point Drift LER 05000390,05000391/20 LER 2020-005-00 for Watts 71153 Closed 20-005-00 Bar Nuclear Plant, Units 1 and 2, Automatic Start of the Emergency Diesel Generators Due to an Equipment Failure During Transfer of Power Source for the 2A-A Shutdown Board LER 05000390/2018-002-00 Licensee Event Report 71153 Closed 390/2018-002-00, 01, Shield Building Inoperability Due to Annulus Vacuum Transient

PLANT STATUS

Unit 1 operated at or near rated thermal power (RTP) from the beginning of the inspection period until March 26, when it was reduced to 85 percent RTP for turbine inlet valve testing. The unit was returned to 100 percent RTP on March 27, where it remained for the remainder of the inspection period.

Unit 2 operated at or near 90 percent RTP from the beginning of the inspection period until March 17, when the reactor automatically tripped following a main turbine trip due to loss of the 6.9 kV 2C unit board. The unit was returned to 90 percent RTP on March 20, where it remained for the remainder of the inspection period.

INSPECTION SCOPES

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 tele-work 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 inspection procedures (IP). 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 as well as on-site. The inspections documented below met the objectives and requirements for completion of the IP.

71111.01 - Adverse Weather Protection

Impending Severe Weather Sample (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated the adequacy of the overall preparations to protect risk-significant systems from impending severe weather (high winds and a tornado watch)on March 24, 2021.

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) Units 1 & 2 component cooling water system with the C-S pump (normal B-train) out of service (OOS) for a motor replacement on February 10, 2021.

(2) Unit 1 charging and letdown system (CVCS) with the 1A-A charging pump OOS for a 6.9kV breaker inspection on March 4, 2021.

(3) Unit 2 containment spray (CS) A-train with the B-train was OOS for planned maintenance activities on March 22, 2021.

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) Fire Impairment Permit (C21-0118) compensatory measure (hourly roving fire watch)which was required because block valve (2-FCV-68-322) was in the closed position due to leaking pressurizer power operated relief valve, 2-PCV-68-334, on March 1, 2021.

(2) Auxiliary building, elevation 713' on March 11, 2021.

(3) Auxiliary building, elevation 757' - auxiliary control room, auxiliary instrument rooms, and 125V vital battery board rooms on March 15 & 17, 2021.

(4) Auxiliary building, elevation 772' on March 29, 2021.

(5) Auxiliary building, elevation 737 on March 30, 2021.

Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated the onsite fire brigade training and performance during an announced fire drill on January 22, 2021.

71111.06 - Flood Protection Measures

Cable Degradation (IP Section 03.02) (1 Sample)

The inspectors evaluated cable submergence protection in:

(1) Manholes 2 and 20 on March 2, 2021

71111.07A - Heat Sink Performance

Annual Review (IP Section 03.01) (1 Sample)

The inspectors evaluated readiness and performance of:

(1) Essential raw cooling water pump motor D-A upper bearing cooling coil

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 Unit 2 reactor operator performance of surveillance testing while maintaining the power level at 90 percent RTP on March 8 and 16, 2021. The inspectors also observed and evaluated licensed operator performance following the Unit 2 reactor automatic trip on March 17, 2021. Together, these observations make up one sample.

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

(1) The inspectors observed and evaluated a licensed operator requalification simulator scenario for crew 3 group 3B on January 13, 2021. Additionally, the inspectors observed and evaluated a licensed operator requalification simulator scenario for crew 4 group 4B on January 27, 2021. Together, these observations make up one sample.

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 (SSC) remain capable of performing their intended function:

(1) System 030-A -Control Room Emergency Air Temperature Control System (CREATCS)

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) Service Level 1 Coatings that occurred during 2020 (Work Order 120618392)

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) Risk assessment for (week of) February 1, 2021, with the A-train main control room chiller, the 1A generator bus cooling fan, and the 1A component cooling water (CCW)pump OOS.

(2) Risk assessment for (week of) February 8, 2021, with the C-S CCS pump out for a motor replacement and the B spent fuel pool pump OOS.

(3) Risk assessment for (week of) March 15, 2021, with the 2A-A CCS pump out for planned maintenance and the B-B shutdown board room chiller out for emergent repairs.

(4) Risk assessment for (week of) March 22, 2021, with the B-B shutdown board room chiller out for emergent repairs and a 6.9kV breaker swap on the 480V shutdown board.

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (1 Sample)

The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:

(1) Unit 1 RCS Loop 3 Channel III low flow Condition Report 1666298, Prompt Determination Operability

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) WO 12170069, Replacement of Control Air filtration Unit Filters on WBN-0 FLT-032-0422, Essential Control Air Train B Control Building Rad Filter. An initial service leak check (using Snoop) was completed for the post maintenance testing (PMT) on January 14, 2021, with no issues.

(2) WO 121922757, Replacement of the ERCW A-A Motor Upper Bearing Oil Cooler (WBN-0-MTR-067-0-28-A). A pressure test (using 60-80 psig air) was completed for the PMT on February 11, 2021 with no issues.

(3) WO 121418907, Periodic Testing of CCS 2A-A Motor and Feeder Cables. Post maintenance testing was performance of WO 121467997, Surveillance Instruction 0-SI-70-914-A, Component Cooling System Pump 2A-A Comprehensive Pump Test, Revision 0007.

(4) WO 121418815, Safety Injection Pump 2B-B Cuno Filter Inspection, Pump Oil change, Oil Cooler Heat Exchanger Cleaning. Post maintenance testing was performance of Surveillance Instruction 2-SI-63-901-B, Safety Injection Pump 2B-B Quarterly Performance Test.

(5) WO 121988955, Vital Inverter 1-IV failure on March 10, 2021. Vital Inverter 1-IV failed and transferred to bypass (Ref. CR 1677899). An AUO placed static inverter 0-IV in service to satisfy TS LCO 3.8.7, Condition A. The cause of the failure was determined to be a failed diode and blown fuse (due to the failed diode). The problem was corrected by replacing the D2 diode and the F2 fuse and performing a load bank test (using 0-MI-235.002) was completed for the PMT on March 11, 2021.

(6) WO 121473239, Containment Spray Pump 2B-B - Perform Relay Functional Test. Post maintenance testing was performance of WO 121529515, Surveillance Instruction 2-SI-72-901-B, Containment Spray Pump 2B-B Quarterly Performance Test, Revision 8.

(7) WO 121133779, B-B Spent Fuel Pit Circulation Pump Discharge Check Valve Leaking, Causing the Idle Pump to Rotate in the Reverse Direction. Check valve inspection maintenance was performed per this work order. Post maintenance testing was accomplished by the performance of 0-TI-50.039, Spent Fuel Pit Circulation Pump B-B Performance Test Revision 0003.

71111.22 - Surveillance Testing

The inspectors evaluated the following surveillance tests:

Surveillance Tests (other) (IP Section 03.01)

(1) WOs 122034366 and 122034410 were performed following completion of a planned maintenance outage on the 1-B-B motor driven auxiliary feedwater pump and associated equipment on March 30, 2021.

(2) WO 121467560, Surveillance Instruction 2-SI-63-901-B, Safety Injection Pump 2B-B Quarterly Performance Test completed on March 9, 2021.

Inservice Testing (IP Section 03.01) (1 Sample)

(1) WO 121413875, Surveillance Instruction 0-SI-70-902-S, Component Cooling System Pump C-S Quarterly Performance Test, Revision 0030

71114.06 - Drill Evaluation

Select Emergency Preparedness Drills and/or Training for Observation (IP Section 03.01) (1 Sample)

(1) The residents observed the site emergency response to a training drill which involved a turbine trip, without an immediate reactor trip, followed by a steam generator tube rupture leading to a general emergency declaration on February 17,

OTHER ACTIVITIES - BASELINE

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) The inspector reviewed LER 390/2018-002-00 and supplement LER 390/2018-002-01, Shield Building Inoperability Due to Annulus Vacuum Transient (ADAMS accession: ML19219A219) and determined that the licensee complied with applicable requirements, Technical Specifications (TSs), and 50.73 reporting criteria. 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.

(2) The inspectors reviewed LER 390, 391/2020-005-00, Automatic Start of the Emergency Diesel Generators Due to an Equipment Failure During Transfer of Power Source for the 2A-A Shutdown Board LER 391/2020-005-00, Automatic start of the Emergency Diesel Generators due to an Equipment Failure During Transfer of Power Source for the 2A-A Shutdown Board (ADAMS accession: ML21004A098,) and determined that the licensee complied with applicable requirements, TS, and 50.73 reporting criteria. 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 on NRC requirements was identified.

(3) The inspectors reviewed LER 391/2020-002-00, Two Pressurizer Safety Valves Outside of Technical Specification Limits Due to Set Point Drift (ADAMS accession:

ML20352A005) and determined that the licensee complied with applicable requirements and 50.73 reporting criteria. A self-revealed SL IV NCV of TS 3.4.10, Pressurizer Safety Valves, was identified when routine as-found lift pressure tests of pressurizer safety valves WBN-2-RFV-068-0563 and WBN-2-RFV-068-0565 revealed that the valves lifted at a pressure lower than allowed by TS Surveillance Requirement 3.4.10.1 for a duration that was longer than the conditions TS required action completion time. The inspectors determined this violation was not reasonably foreseeable and preventable by the licensee and therefore is not a performance deficiency. Specifically, random setpoint drift is a recognized valid phenomenon that can occur despite routine testing and maintenance. The inspection conclusions associated with this LER are documented in this report under Inspection Results Section.

(4) The inspectors reviewed LER 390, 391/2020-002-00, Automatic Start of the Emergency Diesel Generators due to an Equipment Failure During Transfer of Power Source for the 1B-B Shutdown Board390/2020-002-00, Automatic Start of the Emergency Diesel Generators due to an Equipment Failure During Transfer of Power Source for the 1B-B Shutdown Board (ADAMS accession: ML20196L832,) and determined that the licensee complied with applicable requirements, Technical Specifications and 50.73 reporting criteria. 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 on NRC requirements was identified.

Personnel Performance (IP Section 03.03) (1 Sample)

(1) The inspectors evaluated licensed operator performance following the Unit 2 reactor automatic trip on March 17,

INSPECTION RESULTS

Pressurizer Safety Valves Outside of TS Limits Due to Set Point Drift Cornerstone Severity Cross-Cutting Report Aspect Section Not Severity Level IV Not 71153 Applicable NCV 05000391/2021001-01 Applicable Closed A self-revealed Severity Level (SL) IV NCV of Technical Specifications (TS) 3.4.10, Pressurizer Safety Valves, was identified when routine as-found lift pressure tests of pressurizer safety valves WBN-2-RFV-068-0563 and WBN-2-RFV-068-0565 revealed that the valves lifted at a pressure lower than allowed by TS Surveillance Requirement 3.4.10.1 for a duration that was longer than the conditions TS required action completion time.

Description:

During the Watts Bar Nuclear Plant Unit 2 October 2020 refueling outage, pressurizer safety valves WBN-2-RFV-068-0563 and WBN-2-RFV-068-0565 were removed from service and sent to an off-site testing facility. On November 2, 2020, the site was notified that the as-found lift pressure testing determined that valve WBN-2-RFV-068-0563 opened at 2380 psig and valve WBN-2-RFV-068-0565 opened at 2398 psig, which for both valves was low outside the plant TS allowable lift setting range of >/= 2410 psig and </= 2560 psig. Both valves had been installed and placed in service at the Watts Bar Nuclear Plant Unit 2 during the 2017 fall outage and remained in service during two complete 18-month fuel cycles (December 6, 2017 to October 23, 2020). Pressurizer safety valves WBN-2-RFV-068-0563 and WBN-2-RFV-068-0565 were replaced with similar operable refurbished valves during the October 2020 refueling outage. Licensee Event Report (LER) 05000391/2020-002-00, Two Pressurizer Safety Valves Outside of TS Limits Due to Setpoint Drift, was submitted by the licensee for this event.

Corrective Actions: The two safety valves were replaced with similar operable refurbished valves during the refueling outage prior to plant startup.

Corrective Action References: CRs 1649435 and 1649440

Performance Assessment:

The NRC determined this violation was not reasonably foreseeable and preventable by the licensee and therefore is not a performance deficiency.

Enforcement:

Severity: Traditional Enforcement is being used to disposition this violation with no associated Reactor Oversight Process performance deficiency per section 3.10 of the Enforcement Manual. The inspector assessed the severity of the violation using Section 6.1 of the Enforcement Policy and determined the significance is appropriately characterized as Severity Level IV, due to the inappreciable potential safety consequences. The licensee determined that the safety valve low as-found lift set-point did not have an adverse impact on reactor coolant system over-pressurization protection, since the valve continued to perform its reactor coolant system over-pressure protection function to prevent the system from exceeding the design pressure of 2485 psig. Therefore, the plant remained bounded by the accident analysis in the FSAR, based on the as-found condition.

Violation: Watts Bar Nuclear Plant unit 2 TS LCO 3.4.10, Pressurizer Safety Valves, requires three operable pressurizer safety valves with lift settings of >/= 2410 psig and </=

2560 psig, while the Unit is in modes 1, 2, and 3. With one pressurizer safety valve inoperable, Action Statement, Condition A. Required Action A.1, requires restoration of the valve to operable status within 15 minutes. If the required action and associated completion time is not met OR with two or more pressurizer safety valves inoperable, Action Statement, Condition B.1, requires that the unit to be in mode 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Contrary to the above, the licensee determined that two of the pressurizer safety valves lift pressure settings were outside the TS limits longer than 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and 15 minutes during the last two operating cycles, between December 6, 2017 and October 23, 2020, while the unit was in modes 1 and 2.

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

EXIT MEETINGS AND DEBRIEFS

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

• On April 28, 2021, the inspectors presented the integrated inspection results to Mr.

Anthony Williams and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.01 Procedures 0-AOI-8 Tornado Watch or Warning 25

71111.01 Procedures BP-128 Site Tornado Procedure 2

71111.04 Corrective Action Condition Report 1670544, 1671764

Documents

71111.04 Miscellaneous Flow Diagram 0- Component Cooling System 8

47W859-1

71111.04 Miscellaneous Flow Diagram 0- Component Cooling System 3

47W859-4

71111.04 Miscellaneous Flow Diagram 1- Chemical and Volume Control System 68

47W809-1

71111.04 Miscellaneous Flow Diagram 1- Component Cooling System 43

47W859-2

71111.04 Miscellaneous Flow Diagram 2- Component Cooling System 35

47W859-3

71111.04 Procedures 0-SOI-70.01 Component Cooling System 8

71111.04 Procedures 1-SOI-62.01 Charging and Letdown System (CMCS) 20

71111.04 Work Orders WO 120227822 Work Order

71111.04 Work Orders WO121938552 Perform Part 21 Inspection of WBN-1-BKR-062-0108-A for

CCP 1A-A (1-PMP-62-108)

71111.05 Corrective Action Condition Reports 1667589, 1678126, 1678104, 1678099, 1678967, 1678980,

Documents 1678983, 1678986

71111.05 Fire Plans Tur-0-729-01 Pre-Fire Plan

71111.05 Fire Plans TVA 41419 Fire Drill Evaluation Report - Unit 1 Turbine Building

Hydrogen Seal Oil Filter

71111.05 Miscellaneous WBN Fire Protection Report

71111.06 Drawings 15W810-1 As Constructed Conduit & Grounding General Plan Revision 27

71111.06 Work Orders 121405436 Clean, Inspect, and Restore 1E Manhole / Sumps 3/2/2021

71111.07A Miscellaneous 41343 TVA Form

71111.07A Procedures 0-TI-79.000 Program for Implementing NRC Generic Letter 89-13 6

71111.07A Procedures NPG-SPP-09.14 Generic Letter 89-13 Implementation 5

71111.07A Procedures NPG-SPP-09.7.3 Raw Water Corrosion Program 5

71111.07A Procedures TI-67.000 Raw Water Program 6

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.07A Work Orders 121276347 Replace ERCW Pump Motor Bearing Cooling Coil

71111.07A Work Orders 121418719 ERCW D-A Motor Inspection

71111.11Q Miscellaneous 55143 Event Notification 71111.11Q Miscellaneous SEG # 3-OT- Misaligned Control Rod and Break of Downstream Dam Revision 0

SRT-AOI-2+22

71111.11Q Procedures 2-AOI-39 Rapid Load Reduction 4

71111.11Q Procedures 2-GO-4 Normal Power Operation 18

71111.11Q Procedures 2-SI-63-901-B Safety Injection Pump 2B-B Quarterly Performance Test 9

71111.11Q Procedures 2-SI-70-914-A Component Cooling System Pump 2A-A Comprehensive 7

Pump Test

71111.12 Miscellaneous CDE 1702 Main Control Room Chiller B failure 1/21/2021

71111.12 Miscellaneous G-55 General Engineering Specification - Technical and Revision 26

Programmatic Requirements for the Protective Coating

Program for TVA Nuclear Plants

71111.12 Procedures MAI-5.3 Protective Coatings Revision 20

71111.12 Work Orders 120618392 Protective Coating WO for 2020 12/31/2020

71111.13 Procedures NPG-SPP-07.3 Work Activity Risk Management Process 0032

71111.19 Corrective Action Condition Report 1589349, 1670699, 1677899

Documents

71111.19 Miscellaneous LER 390/2019- Loss of Control Room Emergency Air Temperature Control

2-00 System Due to Air Filter Failure

71111.19 Procedures 0-MI-235.002 120 VAC Vital Inverter Automatic Transfer Test 8

71111.19 Procedures 2-AOI-11 Loss of Condenser Vacuum 7

71111.19 Procedures 2-E-0 Reactor Trip or Safety Injection 8

71111.19 Procedures 2-ES-0.1 Reactor Trip Response 2

71111.19 Procedures 2-FR-0 Status Trees 1

71111.19 Procedures 2-GO-2 Reactor Startup 16

71111.19 Procedures 2-GO-3 Unit Startup From Less Than 4% Reactor Power to 30% 12

Reactor Power

71111.19 Procedures 2-GO-4 Normal Power Operation 18

71111.19 Procedures 2-GO-5 Unit Shutdown from 30% Reactor Power to Hot Standby 6

71111.19 Procedures 2-PMP-063-0015- Safety Injection Pump 2B-B Cuno Filter Inspection Pump Oil

Inspection Type Designation Description or Title Revision or

Procedure Date

B Change, HTX Cleaning (PM #620630055)

71111.19 Procedures 2-SI-63-901-B Safety Injection Pump 2B-B Quarterly Performance Test 9

71111.19 Work Orders 121270069 Replacement of Control Air filtration Unit Filters on WBN-0

FLT-032-0422, Essential Control Air Train B Control Building

Rad Filter

71111.19 Work Orders 121418907 Periodic Testing of CCS 2A-A Motor and Feeder Cables

71111.19 Work Orders 121467997 Surveillance Instruction 0-SI-70-914-A, Component Cooling 7

System Pump 2A-A Comprehensive Pump Test

71111.19 Work Orders 121473239 Containment Spray Pump 2B-B - Perform Relay Functional

Test

71111.19 Work Orders 121529515 Surveillance Instruction 2-SI-72-901-B, Containment Spray 8

Pump 2B-B Quarterly Performance Test

71111.19 Work Orders 121988955 Vital Inverter1-IV Failure

71111.19 Work Orders Work Orders 121927796, 121928989, 121133779

71111.22 Corrective Action 1682711 Condition Report

Documents

71111.22 Procedures 1-SOI-3.02 Auxiliary Feedwater System 25

71111.22 Procedures 2-SI-63-901-B Safety Injection Pump 2B-B Quarterly Performance Test 9

71111.22 Work Orders Work Orders 121227822, 122034366, 122034410, 1221413875

71114.06 Miscellaneous 2021 WBN February Training Drill 2/17/2021

71153 Corrective Action Condition Report 1378357,1387151, 1395914, 1397625, 1609672, 1610556,

Documents 1610956, 1649435, 1649440, 1652116, 1652363

71153 Miscellaneous 390/2020-002-00 Automatic Start of the Emergency Diesel Generators due to

an Equipment Failure During Transfer of Power Sources for

the 1B-B Shutdown Board

71153 Miscellaneous Event Number 53173

71153 Miscellaneous Event Number Automatic Start of the Emergency Diesel Generators due to

54997, LER an Equipment Failure During Transfer of Power Source for

391/2020-005-00 the 2A-A Shutdown Board

71153 Miscellaneous LERs LER 390/2018-002-00

LER 390/2018/002/01

LER 390/2017-008 and 390/2017-007 (similar previous

events)

Inspection Type Designation Description or Title Revision or

Procedure Date

71153 Miscellaneous Technical (TS) 3.4.10

Specification,

"Pressurizer

Safety Valves

71153 Procedures 1-SI-211-1-A 18 Month 6.9 KV Shutdown Board 2A-A Automatic and 8

Manual Tests

71153 Procedures 1-SI-211-1-B 18 Month 6.9 KV Shutdown Board 1B-B Automatic and 4

Manual Tests

71153 Work Orders Work Orders 121737335, 121737363, 119377644, 113413926

71153 Work Orders Work Orders For WBN-2-RFV-068-0563 (S/N N56964-10-0034)

20729610

(U2R3) and

117416658

(U2R1)

71153 Work Orders Work Orders For WBN-2-RFV-068-0565 (S/N N56964-10-0097)

20729621

(U2R3) and

118295338

(U2R1)

13