IR 05000390/2022004
| ML23041A079 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 02/10/2023 |
| From: | Louis Mckown NRC/RGN-II/DRP/RPB5 |
| To: | Jim Barstow Tennessee Valley Authority |
| References | |
| EA-19-092 IR 2022004 | |
| Download: ML23041A079 (1) | |
Text
February 10, 2023
SUBJECT:
WATTS BAR NUCLEAR PLANT - INTEGRATED INSPECTION REPORT 05000390/2022004 AND 05000391/2022004
Dear Mr. Barstow:
On December 31, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Watts Bar Nuclear Plant. On February 1, 2023, 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 finding of very low safety significance (Green) is documented in this report. This finding involved a violation of NRC requirements. We are treating this violation as a non-cited violation (NCV) consistent with Section 2.3.2 of the Enforcement Policy.
If you contest the violation or the significance or severity of the violation documented in this inspection report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN:
Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region II; the Director, Office of Enforcement; and the NRC Resident Inspector at Watts Bar Nuclear 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 II; and the NRC Resident Inspector at Watts Bar Nuclear Plant.
In addition, the Office of the Regional Administrator has authorized staff to use IP 92722 to perform a follow-up inspection of the escalated enforcement violations at Watts Bar Nuclear Plant because these traditional enforcement follow-up inspections are infrequent inspections and outside of the routine reactor oversight process (ROP) baseline inspections or supplemental inspection program elements. 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, Louis J. McKown, II, 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:
Report Numbers:
05000390/2022004 and 05000391/2022004
Enterprise Identifier:
I-2022-004-0020
Licensee:
Tennessee Valley Authority
Facility:
Watts Bar Nuclear Plant
Location:
Spring City, TN 37381
Inspection Dates:
October 01, 2022 to December 31, 2022
Inspectors:
W. Deschaine, Senior Resident Inspector
C. Fontana, Emergency Preparedness Inspector
A. Goldau, Operations Engineer
J. Hickey, Senior Project Engineer
N. Lacy, Operations Engineer
D. Lanyi, Senior Operations Engineer
T. McGowan, Resident Inspector
S. Ninh, Senior Project Engineer
C. Safouri, Senior Resident Inspector
S. Sanchez, Senior Emergency Preparedness Insp
D. Turpin, Resident Inspector
R. Wehrmann, Resident Inspector
Approved By:
Louis J. McKown, II, 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 Watts Bar 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
Inadequate procedure led to throttle valve misposition Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000390/2022004-01 Open/Closed
[P.2] -
Evaluation 71111.15 An NRC-identified, green finding and associated non-cited violation (NCV) of Watts Bar Unit 1 Technical Specifications (TS) 5.7.1.1, Procedures, Programs, and Manuals, was identified for the licensees failure to establish procedures for operation of the emergency core cooling system (ECCS). Specifically, 0-TI-31.08, Flow Balancing Valves Setpoint Positions, was found to be not adequately established to provide the actual valve position required for the operation of the residual heat removal (RHR) system which is part of ECCS.
Additional Tracking Items
Type Issue Number Title Report Section Status NOV 05000390/2020013-03 5. Violation D (AV 9 of the NRCs letter of March 9, 2020) Failure to provide complete and accurate information to OI 92722 Closed NOV 05000390/2020013-01 2. Violation A (AV 4 of the NRCs letter of March 9, 2020) Failure to follow TVA Procedure OPDP-1, Conduct of Operations 92722 Closed NOV 05000390/2020013-02 3. Violation C (AV 5 of the NRCs letter of March 9, 2020) Failure to Maintain Operating Logs 92722 Closed
PLANT STATUS
Unit 1 began the inspection period at rated thermal power (RTP). On October 11, 2022, the unit was down powered to 92 percent due to an issue with the 1B hotwell pump. The unit was returned to RTP on October 24, 2022 and remained at or near RTP for the remainder of the inspection period.
Unit 2 operated at or near RTP for the entire 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
71111.01 - Adverse Weather Protection
Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of seasonal cold temperatures for the following systems:
Vital battery room space heaters: 0-HTR-30-RM1; 0-HTR-30-RM2; 0-HTR-30-RM3; 0-HTR-30-RM4; 0-HTR-31-RM496
Diesel generator room space heaters: 1-HTR-30-471; 1-HTR-30-472; 1-HTR-30-473; 1-HTR-30-474; 2-HTR-30-475; 2-HTR-30-476; 2-HTR-30-477; 2-HTR-30-478 On the following dates: November 8, 2022, November 15, 2022, December 1, 2022, December 2, 2022, and December 22, 2022.
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; extreme winter weather, high winds, and sub-zero temperatures on December 22, 2022.
External Flooding Sample (IP Section 03.03) (1 Sample)
- (1) The inspectors evaluated that flood protection barriers, mitigation plans, procedures and equipment are consistent with the licensees design requirements and risk analysis assumptions for coping with external flooding on November 8, 2022.
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 turbine driven auxiliary feedwater system (AFWS) October 13, 2022.
(2)1A-A emergency diesel generator (EDG) subsystems (starting air and 125Vdc battery) on October 21, 2022.
- (3) Unit 1 centrifugal charging pump 1B-B on November 10, 2022.
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (4 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) Auxiliary Building Shutdown Board Rooms (Elevation 757') October 4, 2022
- (2) Auxiliary Building Corridor (Elevation 713') October 5, 2022
- (3) Unit-2 Control Rod Drive, Pressurizer Heater Transformer and Emergency Gas Treatment Filter Rooms (Elevation 772' and 757') October 5, 2022
- (4) EDG Board, Exhaust and Intake Rooms (Elevation 760.5) October 13, 2022
71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance
Requalification Examination Results (IP Section 03.03) (1 Sample)
- (1) The licensee completed the annual requalification operating examinations required to be administered to all licensed operators in accordance with Title 10 of the Code of Federal Regulations 55.59(a)(2), "Requalification Requirements," of the NRC's "Operator's Licenses." During the week of December 5, 2022, the inspector performed an in-office review of the overall pass/fail results of the individual operating examinations and the crew simulator operating examinations in accordance with Inspection Procedure (IP) 71111.11, "Licensed Operator Requalification Program." These results were compared to the thresholds established in Section 3.03, "Requalification Examination Results," of IP 71111.11.
The inspectors reviewed and evaluated the licensed operator examination failure rates for the requalification annual operating exam completed on December 2, 2022.
71111.11B - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Requalification Program (IP Section 03.04) (1 Sample)
- (1) Biennial Requalification Written Examinations The inspectors evaluated the quality of the licensed operator biennial requalification written examination administered during August 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 Unit 1 power ascension on October 2022.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated the following licensed operator requalification simulator scenarios (LOR training cycle 2205), which included tripping a condensate booster pump, circuit card failure in an instrumentation rack for reactor protection system, reactor coolant pump seal failure, and loss of coolant accident outside of containment:
Crew 1 on October 28, 2022
Crew 5 on November 04, 2022
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) Unit 1 centrifugal charging pump (CCP) 1B-B, specifically the CCP 1B-B component outage on October 11, 2022, under work orders 122573999, 122124785,122519239, and 122835302.
- (2) Auxiliary building exhaust ventilation, specifically WBN-0-FCO-0030-0169 (Fuel Handling Area Fan A-A Flow Control Damper), under work order 122760543 on November 16, 2022.
- (3) Vital inverter 1-INV-235-1-D, replacement of diodes and silicon controlled rectifier cards on November 30, 2022, under work order 122702916.
- (4) Unit 1 AFWS overall performance.
- (5) Unit 1 chemical volume control system overall performance on December 22, 2022.
- (6) Unit 2 residual heat removal system overall performance on December 28, 2022.
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (5 Samples)
The inspectors evaluated the accuracy and completeness of risk assessments for the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed:
- (1) Units 1 and 2, 6.9kV shutdown board maintenance supply breaker protective relay calibration and functional testing on October 17, 2022, under work order 123078635 (Unit 1) and work order 123078638 (Unit 2).
- (2) Unit 1 vital inverter 1-IV emergent troubleshooting and repair on November 18, 2022, under work order 122702983 and work order 123310867 (CR 1817755).
- (3) Main control room chiller A-A (WBN-0-CHR-031-0080-A) outage the week of November 28, 2022.
- (4) Risk assessment for (week of) December 5, 2022, with the 1B component cooling water pump out for maintenance.
- (5) Unit 1 response to loss of normal manual boration flow path emergent troubleshooting and repair on December 13, 2022.
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (16 Samples)
The inspectors evaluated, from October 26 - December 12, 2022, the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Engineering Work Request (EWR) 123200410 unit 2 2A-A thermal barrier booster pump low differential pressure.
- (2) Condition Reports (CR)s 1808913 and 1808914, Unit 1 emergency diesel generator 1B-1, engine 1B-2 cylinder temperature indications for cylinders #4 and #7 failed high.
- (3) EWR 22MEC015095 Unit 2 reflective metallic insulation not reinstalled for fuel cycle
5. (4)
CR 1809193 unit 2 2B-B containment spray pump seal leakage and boric acid buildup.
- (5) CR 1809152 Unit 1 emergency diesel generator 1B-1 room exhaust low flow pressure switch (1-FS-30-453) found out of tolerance.
- (6) CR 1808182 Unit 2 condenser circulating water pump 2A-A frequent oil additions to the upper motor bearing.
- (7) CR 1741493 Unit 1 pressurizer safety relief valve (WBN-1-RFV-68-565) leaking by.
- (8) CR 1808696 Unit 1 B train hydrogen analyzer heat trace system abnormal temperature annunciator.
- (9) CR 1815347 Unit 1 B RHR pump lower bearing needs oil added.
- (10) CR 1817555 Unit 2 essential raw cooling water piping floor penetration damaged.
- (11) CR 1817610 Unit 2 rod position indication for control bank A rod (K14) drifted high.
- (12) CR 1819730 Unit 2 component cooling system pump 2A-A particulates in motor oil sample.
- (13) CR 1809267 Unit 1 emergency raw cooling water strainer 1A-A leakage.
- (14) CR 1821694 B high pressure fire pump room rainwater accumulation (restricted floor drain).
- (15) CR 1822924 manual boration failed to actuate during start of planned down-power.
- (16) CR 1807268 RHR heat exchanger 1-A Component Cooling Water System (CCS)outlet flow control valve (1-FCV-70-156) failed full stroke test (1-SI-70-904-A) due to 1-THV-70-546A not being throttled in the correct position.
71111.18 - Plant Modifications
Severe Accident Management Guidelines (SAMG) Update (IP Section 03.03) (1 Sample)
- (1) The inspectors verified the site Severe Accident Management Guidelines (SAMGS)were updated in accordance with the Pressurized Water Reactor SAMGS and validated in accordance with NEI 14-01, Emergency Response Procedures and Guidelines for Beyond Design Basis Events and Severe Accidents, Revision 1, during the week December 12, 2022.
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (7 Samples)
The inspectors evaluated the following post-maintenance testing activities to verify system operability and/or functionality:
- (1) WO 122498825 - 480V molded case circuit breaker (1-BKR-082-B1) replacement at 1-MCC-215-B001-B for the 1B-1 lube oil circulating pump associated with the 1B-B emergency diesel generator on November 9, 2022.
- (2) Unit 2 penetration room, elevation 737', cooler 2-B-B motor and cooler clean, inspect, test on November 9, 2022, under WO 122519963.
- (3) Unit 2 penetration room, elevation 737', emergency raw cooling water safety valve inspection and testing on November 9, 2022, under WO 122520628.
- (4) Exhaust gas treatment system (EGTS) auxiliary building purge air modulating damper Bettis actuator rebuild (WBN-1-PCO-065-0049) and testing of B train EGTS on November 9, 2022, under WOs 12147747 and 122820683.
- (5) Unit 2 residual heat removal (RHR) pump 2A-A discharge isolation valve (2-ISV-074-0520-A) reach rod adjustment and position indication verification on November 14, 2022, under WO 122663412.
- (6) Unit 2 RHR heat exchanger 2A inlet isolation valve (2-ISV-074-0524-A) inspection and lubrication on November 14, 2022, under WO 122663418.
- (7) Unit 2 residual heat removal pump 2A-A room cooler (2-CLR-030-0175-A) and fan (2-FAN-030-0175-A) clean, inspect; and room cooler motor (2-MTR-030-0175-A) clean, inspect, and megger; and closed cooling system RHR pump 2A-A return relief valve (2-RFV-70-565-A-A) inspection and testing on November 14, 2022, under WOs
===12266336 and 12263428.
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) Unit 2 2A-A containment spray pump quarterly performance test on November 1, 2022, under WO 122821070.
FLEX Testing (IP Section 03.02) (1 Sample)
(1)6900V FLEX DG 3A standby alignment and start on October 31, 2022.
71114.02 - Alert and Notification System Testing
Inspection Review (IP Section 02.01-02.04) (1 Sample)
- (1) The inspectors evaluated the maintenance and testing of the alert and notification system during the week of November 14, 2022.
71114.03 - Emergency Response Organization Staffing and Augmentation System
Inspection Review (IP Section 02.01-02.02) (1 Sample)
- (1) The inspectors evaluated the readiness of the Emergency Response Organization during the week of November 14, 2022.
71114.04 - Emergency Action Level and Emergency Plan Changes
Inspection Review (IP Section 02.01-02.03) (1 Sample)
- (1) The inspectors evaluated submitted Emergency Action Level, Emergency Plan, and Emergency Plan Implementing Procedure changes during the week of November 14, 2022. This evaluation does not constitute NRC approval.
71114.05 - Maintenance of Emergency Preparedness
Inspection Review (IP Section 02.01 - 02.11) (1 Sample)
- (1) The inspectors evaluated the maintenance of the emergency preparedness program during the week of November 14, 2022.
71114.06 - Drill Evaluation
Drill/Training Evolution Observation (IP Section 03.02) (2 Samples)
- (1) The inspectors observed and evaluated the following licensed operator examination simulator scenarios which included:
Crew 1A first scenario included: failure of pressurizer level instrumentation; failure of main feedwater pump (MFWP) differential pressure instrumentation; and a steam line break inside containment with an anticipated transient without a scram.
Crew 1A second scenario included: failure of volume control tank level instrumentation; heater drain tank pump motor overload resulting in a turbine runback; and a loss of coolant accident with a failure of containment phase B to actuate.
Crew 1B first scenario included: failure of pressurizer level instrumentation; failure of MFWP differential pressure instrumentation; and a steam line break inside containment with an anticipated transient without a scram; however, the scenario was terminated early due to simulator issues. Condition Report 1817592 was initiated documented the simulator issues.
Crew 1B second scenario included: failure of volume control tank level instrumentation; heater drain tank pump motor overload resulting in a turbine runback; and a loss of coolant accident with a failure of containment phase B to actuate.
These four observations on November 16, 2022, constitute one sample.
- (2) The inspectors observed and evaluated an after-hours emergency preparedness drill which had the following scenario:
Loss of spent fuel pool level resulting in a Notice of Unusual Event, followed by an anticipated transient without scram that resulted in an alert being declared based on emergency action level criteria SA5. This scenario was observed on November 2,
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
IE01: Unplanned Scrams per 7000 Critical Hours Sample (IP Section 02.01)===
- (1) Unit 1 (October 1, 2020, through March 31, 2022)
- (2) Unit 2 (October 1, 2020, through March 31, 2022)
IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02) (2 Samples)
- (1) Unit 1 (October 1, 2020, through March 31, 2022)
- (2) Unit 2 (October 1, 2020, through March 31, 2022)
IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03) (2 Samples)
- (1) Unit 1 (October 1, 2020, through March 31, 2022)
- (2) Unit 2 (October 1, 2020, through March 31, 2022)
MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04) (2 Samples)
- (1) Unit 1 (July 1, 2021, through June 30, 2022)
- (2) Unit 2 (July 1, 2021, through June 30, 2022)
MS07: High Pressure Injection Systems (IP Section 02.06) (2 Samples)
- (1) Unit 1 (July 1, 2021, through June 30, 2022)
- (2) Unit 2 (July 1, 2021, through June 30, 2022)
MS08: Heat Removal Systems (IP Section 02.07) (2 Samples)
- (1) Unit 1 (July 1, 2021, through June 30, 2022)
- (2) Unit 2 (July 1, 2021, through June 30, 2022)
MS09: Residual Heat Removal Systems (IP Section 02.08) (2 Samples)
- (1) Unit 1 (July 1, 2021, through June 30, 2022)
- (2) Unit 2 (July 1, 2021, through June 30, 2022)
MS10: Cooling Water Support Systems (IP Section 02.09) (2 Samples)
- (1) Unit 1 (July 1, 2021, through June 30, 2022)
- (2) Unit 2 (July 1, 2021, through June 30, 2022)
EP01: Drill/Exercise Performance (DEP) Sample (IP Section 02.12) (1 Sample)
- (1) October 1, 2021, through September 30, 2022 EP02: Emergency Response Organization (ERO) Drill Participation (IP Section 02.13) (1 Sample)
- (1) October 1, 2021, through September 30, 2022 EP03: Alert And Notification System (ANS) Reliability Sample (IP Section 02.14) (1 Sample)
- (1) October 1, 2021, through September 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) Pipe support base metal damaged during removal of old angles on RHR spray header pipe supports 47A437-4-73 & 47A437-4-70 (CR 1771430).
- (2) Linear indication discovered while performing a mag particle test in the annulus on the steel containment vessel (SCV) (CR 1749939).
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 ASME Section XI documentation that might be indicative of a more significant safety issue. None were identified during the past six months.
OTHER ACTIVITIES
- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL
===92722 - Follow-Up Inspection for Any Severity Level I or II Traditional Enforcement Violation or for Two or More Severity Level III Traditional Enforcement Violations in a 12-Month Period The Office of the Regional Administrator has authorized staff to use IP 92722 to perform a follow-up inspection of the escalated enforcement violations at Watts Bar Nuclear Plant because these traditional enforcement follow-up inspections are infrequent inspections and outside of the routine reactor oversight process (ROP) baseline inspections or supplemental inspection program elements.
Follow-Up Inspection for Any Severity Level I or II Traditional Enforcement Violation or for Two or More Severity Level III Traditional Enforcement Violations in a 12-Month Period===
- (1) Inspection Procedure (IP) 92722 - Follow Up Inspection For Any Severity Level I or II Traditional Enforcement Violation or For Two or More Severity Level III Traditional Enforcement Violation in A 12 month period.
On November 6, 2020, the NRC issued a Notice of Violation and Proposed Imposition of Civil Penalty (NOV) to TVAs Watts Bar Nuclear Plant (WBN) (ML20310A341). The NOV contained five separate violations (A - E) and related civil penalties, pertaining to events occurring at WBN Unit 1 in late 2015 to early 2016. In response to the NOV, TVA provided its written reply by letter dated December 7, 2020 (ML21027A394). After reviewing TVAs written reply, the NRC subsequently issued a revised NOV letter dated July 23, 2021 (ML21200A134). Within the revised letter, the NRC concluded that the five violations occurred as stated in the November 6, 2020 Notice of Violation. However, the NRC had reevaluated the violations, severity levels, and the associated civil penalties which included renaming Violations A, C, and D to Violations A, B, and C, respectively. Violations B and E, as originally written in the November 6, 2020 letter were dispositioned within the 3rd quarter 2021 Watts Bar Nuclear Plant Integrated Inspection Report (ML21314A547).
Additionally, as documented in the revised letter on July 23, 2021, the NRC concluded that the information regarding the reason for the violations and steps taken to prevent recurrence, and the date when full compliance was achieved, was adequately addressed in TVAs December 7, 2020 written response.
(Closed) VIO 05000390/2020013-01, Violation A (AV 4 of the NRC's letter of March 9, 2020) Failure to follow TVA Procedure OPDP-1, Conduct of Operations The NRC's revised NOV letter on July 23, 2021 documented a Severity Level III violation involving 10 CFR Part 50, Appendix B, Criterion V, "Instructions, Procedures, and Drawings", and TVA Procedure NPG-OPDP-1, "Conduct of Operations". The inspectors evaluated the corrective actions implemented by TVA to determine whether they were adequate to address the violation and to prevent recurrence. Based on the results of this review, no additional violations of NRC requirements were identified and violation 05000390/2020013-01 is closed.
(Closed) VIO 05000390/2020013-02, Violation C (AV 5 of the NRC's letter of March 9, 2020) Failure to Maintain Operating Logs The NRC's revised NOV letter on July 23 2021 renamed this violation to Violation B, and documented a Severity Level III violation involving 10 CFR Part 50, Appendix B, Criterion XVII, "Quality Assurance Records", and TVA Procedure NPG-OPDP-1, "Conduct of Operations", as it relates to Operations log keeping. The inspectors evaluated the corrective actions implemented by TVA to determine whether they were adequate to address the violation and to prevent recurrence. Based on the results of this review, no additional violations of NRC requirements were identified and violation 05000390/202013-02 is closed.
(Closed) VIO 05000390/2020013-03, Violation D (AV 9 of the NRC's letter of March 9, 2020) Failure to provide complete and accurate information to OI)
The NRC's revised NOV letter on July 23, 2021 renamed this violation to Violation C, and documented a Severity Level II violation involving 10 CFR 50.9(a) as it relates to information provided by a TVA WBN employee (Shift Manager) to Office of Investigations. The inspection conclusions associated with this violation are documented in this report under the Inspection Results section.
INSPECTION RESULTS
Inadequate procedure led to throttle valve misposition Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000390/2022004-01
[P.2] -
Evaluation 71111.15 Open/Closed An NRC-identified, green finding and associated non-cited violation (NCV) of Watts Bar Unit 1 Technical Specifications (TS) 5.7.1.1, Procedures, Programs, and Manuals, was identified for the licensees failure to establish procedures for operation of the emergency core cooling system (ECCS). Specifically, 0-TI-31.08, Flow Balancing Valves Setpoint Positions, lacked a means to position the valve, 1-THV-70-546A, obturator to the required throttled position for the ECCS function of the residual heat removal (RHR) system when operated from open due to failure to provide reliable valve position indication.
Description:
On October 5, 2022, while performing 1-SI-70-904-A, Valve Full Stroke Exercising During Plant Operation Component Cooling Water (Train A) attachment 2 for 1-FCV-70-156, the RHR heat exchanger 1-A Component Cooling Water System (CCS) outlet flow control valve, the licensee identified that the 1A RHR heat exchanger only had 1,000 gpm of indicated CCS flowing through it. The expected flow rate during this test was > 5,000 gpm.
The licensee declared the A train of ECCS inoperable and entered Unit 1 Technical Specification 3.5.2 required action statement for one or more trains inoperable which required them to restore the train to operable within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. While troubleshooting the low flow condition, the licensee discovered that the local valve position indicator for 1-THV-70-546A, the throttle valve associated with the 1-FCV-70-156, was loose and not tracking with valve obturator movement. Thus, it had been throttled to the wrong position because operators had positioned the valve from an unreliable open indication.
The inspectors performed a valve alignment walkdown and verified the physical attributes of the valve. This valve (1-THV-70-546A) is a butterfly valve and has physical stops at the closed position on both sides, but not for the open position. After verifying the physical attributes of the valve, the inspectors determined that since the open position cannot be verified by a physical stop, 0-TI-31.08 should not allow 1-THV-70-546A to be throttled using open as a starting point. The inspectors made the licensee aware of this condition and they entered it into their Corrective Action Program (CAP).
Throttle valve 1-THV-70-546A is required to be in its throttled position to ensure adequate CCS flow to the 1A RHR HX. With the throttle valve being closed too far, degraded flow was available to the 1A-A RHR HX, potentially rendering it incapable of meeting the heat removal requirements for the RHR system.
Corrective Actions: After discovering that the 1A RHR heat exchanger had inadequate CCS flow, a condition report (CR) was entered into the CAP and troubleshooting took place. The licensee corrected the inadequate CCS flow condition by throttling the valve from the closed position verifying that flow was restored to 5300 gpm. After the inspectors brought the inadequate procedure to the attention of the licensee a CR was entered into the CAP and is being evaluated by the site.
Corrective Action References: CRs 1807268 and 1832934
Performance Assessment:
Performance Deficiency: Failure to establish procedures for operation of the ECCS was a performance deficiency (PD). Specifically, 0-TI-31.08, Flow Balancing Valves Setpoint Positions, lacked a means to position the valve, 1-THV-70-546A, obturator to the required throttled position when operated from open due to failure to provide reliable valve position indication.
Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Configuration Control 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, failure to establish an adequate step in 0-TI-31.08 for throttling 1-THV-70-546A resulted in the inoperability of one train of ECCS.
Significance: The inspectors assessed the significance of the finding using IMC 0609 Appendix A, The Significance Determination Process (SDP) for Findings At-Power. The inspectors reviewed the licensees evaluation on if the condition discovered would have led to the inoperability of the train for greater than allowed by Technical Specification. The conclusion of the engineering evaluation was the 1A RHR heat exchanger would have been able to reject the post-accident heat load from the RHR to CCS during the recirculation phase following a lost-of-coolant accident (LOCA) for both short term and long-term cooling, which was the most limiting accident scenario. Based on the inspector's review of the licensees evaluation the finding was determined to be very low safety significance (Green) because all screening questions found in exhibit 2 were answered No.
Cross-Cutting Aspect: P.2 - Evaluation: The organization thoroughly evaluates issues to ensure that resolutions address causes and extent of conditions commensurate with their safety significance. Specifically, the licensee identified the condition in their corrective action program but failed to adequately evaluate the condition to ensure that resolutions address causes and extent of conditions commensurate with their safety significance. The licensee entered the inadequate CCS flow condition into their corrective action program but failed to identify that the procedure was inadequate and that caused the operator to throttle the valve from a false indication.
Enforcement:
Violation: Unit 1 TS 5.7.1, Procedures, Programs, and Manuals, requires, in part, that written procedures shall be established, implemented, and maintained covering the applicable procedures recommended in Regulatory Guide 1.33, Revision 2, Appendix A, February 1978.
Regulatory Guide 1.33, Revision 2, Appendix A, February 1978, section 3 lists, in part, Procedures for Startup, Operation, and Shutdown of Safety-Related PWR systems such as the Emergency Core Cooling System.
0-TI-31.08, Flow Balancing Valves Setpoint Positions, is a procedure that provides the current position requirements for the operation of the Emergency Core Cooling System.
Contrary to the above, from January 29, 2016 to the present, the licensee failed to establish a written procedure covering the applicable procedures recommended in Regulatory Guide 1.33, Revision 2, Appendix A, February 1978, which includes 0-TI-31.08, Flow Balancing Valves Setpoint Positions. Specifically, 0-TI-31.08 lacked a means to position the valve, 1-THV-70-546A, obturator to the required throttled position when operated from open due to failure to provide reliable valve position indication.
Enforcement Action: This violation is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
Minor Violation 92722 Minor Violation: On March 9, 2020, inspection report 2020-012, Watts Bar Nuclear Plant - Office of Investigations Report No. 2-2016-042 and Apparent Violations, was issued to capture several apparent violations (AVs) related to the November 11, 2015, Unit 1 pressurizer water level excursion event occurring during a plant startup (ML20065M374). AV No. 9 documented a 10 CFR 50.9(a) violation related to the licensee providing information to the Commission (specifically the NRC Office of Investigations) that was not complete and accurate in all material respects. On July 19, 2020, the licensee initiated condition report (CR)1624009 to document acceptance, in part, of AV No. 9. The condition report stated that it is being initiated to conduct a Significant Condition Gap Analysis in response to AV No. 9. In addition, TVA submitted a response to the Notice of Violation (ML21027A394) and stated the following under Section I.D.2:
In July 2020, TVA entered into the corrective action program Condition Report 1624009 regarding the violation of 10 CFR 50.9(a) on December 18, 2015. Corrective actions associated with this CR include performing a gap analysis.
10 CFR 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings requires, in part, that Activities affecting quality shall be accomplished in accordance with these instructions, procedures, or drawings.
Quality-related procedure NPG-SPP-22.300, Corrective Action Program, Section 3.9.3 provides requirements/conditions for closing a corrective action to no actions taken. Contrary to the above, the inspectors observed that the licensees closure of CR 1624009 on May 17, 2021 without meeting the requirements of NPG-SPP-22.300 was a performance deficiency reasonably within the licensees ability to foresee and prevent.
The NRC identified this issue while performing follow-up inspection for Violation C (related to AV No. 9). This issue was captured and addressed under condition report 1814488.
Screening: The inspectors determined the performance deficiency was minor. In accordance with IMC 0612, Appendix B, "Issue Screening Directions," this performance deficiency was determined to be minor because it did not have the potential to lead to a more significant safety concern. Although a significant issues gap analysis was not originally performed by the licensee, there were several other corrective action products (root cause analyses, causal analyses, etc.) that, in totality, resulted in the condition adverse to quality being addressed.
Enforcement:
This failure to comply with 10 CFR 50, Appendix B, Criterion V, constitutes a minor violation that is not subject to enforcement action in accordance with the NRCs Enforcement Policy.
EXIT MEETINGS AND DEBRIEFS
The inspectors confirmed that proprietary information was controlled to protect from public disclosure.
On February 1, 2023, the inspectors presented the integrated inspection results to Mr.
Anthony Williams and other members of the licensee staff.
On October 27, 2022, the inspectors presented the Exit for Licensed Operator Requal Inspection 71111.11 (Biennial Section 3.04) inspection results to Beth Jenkins, WBN Plant Manager and other members of the licensee staff.
On October 27, 2022, the inspectors presented the IP 92722 Violation A and B inspection results to Beth Jenkins, WBN Plant Manager, and other members of the licensee staff.
On November 18, 2022, the inspectors presented the Emergency Preparedness Program inspection results to Mr. Anthony Williams and other members of the licensee staff.
On December 5, 2022, the inspectors presented the IP 92722 Violation C inspection results to Randy Staggs, Plant Support Director, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
0-AOI-7.01
Maximum Probable Flood (Watts Bar Nuclear Plant Unit 0,
& 2, Abnormal Operating Instruction)
0-MI-17.004
Movement of Equipment, Flood Mode Preparation
Procedures
0-PI-OPS-1-FP
Freeze Protection
0035
Work Orders
2820005
0-IP-OPS-1-FP
11/02/2022
1-47W809-1-ISI
Flow Diagram Chemical & Volume Control System
08/10/2021
2-47W803-1-ISI
Flow Diagram Feedwater
08/09/2021
Drawings
2-47W803-3
Flow Diagram
2/11/2008
0-SOI-82.01
1-SOI-62.01
CVCS Charging and Letdown
24
1-SOI-62.01 ATT
1V
CVCS Charging and Letdown Valve Checklist 1-62.01-1V
0000
Procedures
2-SOI-3.02
Auxiliary Feedwater System
Rev 0015
Fire Plans
Pre-Fire Plan
Pre-Fire Plan
AUX-0-757-
Rev 4/6,
AUX-0-757-
Rev 4/9,
AUX-713-02
Rev 3/3,
AUX-0-713-
Rev 4/3,
AUX-0-757-
Rev 6/4,
AUX-0-772-
Rev 5/4,
DGB-0-760-
Rev 3/2
Exam simulator scenarios and JPMs administered the
weeks of 10/17/22 and 1/24/22
Medical records for 10 licensed operators
Miscellaneous
Licensed Operators training attendance records, 2020-
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
22, since previous 71111.11B inspection
Licensed Operators remediation records, 2020-2022, since
previous 71111.11B inspection
License maintenance records, 2020-2022, since previous
71111.11B inspection
Simulator fidelity testing records, 2020-2022
NPG-SPP-17.1.0
Systematic Approach to Training Process
Rev 009
NPG-SPP-17.8.1
Licensed Operator Requalification Examination
Development and Implementation
Rev 0019
NPG-SPP-17.8.2
Job Performance Measures Development, Administration,
and Evaluation
Rev 0008
NPG-SPP-17.8.3
Simulator Exercise Guide Development and Revision
Rev 0015
Procedures
NPG-SPP-17.8.4
Conduct of Simulator Operations
Rev 0013
Reactivity Management Plan for Power Ascension after 1B
Hot-well Pump returned to service.
10/23/2022
Miscellaneous
SEG #3-OT-SRT-
205-SIM (Crews 1
and 5)
LOR Training Cycle 2205 Simulator Scenario
1-SOI-2&3.01
Condensate and Feedwater System
Rev. 0044
1-SOI-62.02
Boron Concentration Control
Rev. 0022
Procedures
OPDP-1
Conduct Of Operations
Rev. 0054
1693542
Oil Leaks coming from OB Bearing Housing
05/12/2021
1738929
Pressure indicator not reading correctly
11/30/2021
1746182
1-ISV-3-1002A missing handwheel shaft key
01/07/2022
1750810
Work Order to Replace diodes and SCRs in Vital Inverter
1-INV-235-1-D
01/27/2022
1753780
1A CCP needs oil added to inboard motor bearing
2/09/2022
1755092
Part 21 Final Report of a Potential Defect, Watts Bar
Named, Vishay Diodes
2/15/2022
1757907
Outage work order needed to obtain WBN MIG/FIN
support to make adjustments to setpoint for pressure
controllers.
2/28/2022
Corrective Action
Documents
1763795
the flow control damper for the 2A General exhaust fan
does not seem to respond to controller demand or
03/20/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
pressure.
1787510
Venting RHR Discharge Header Pressure on Unit 2 five to
seven times per shift.
07/04/2022
1791245
WBN Followup Actions for SQN CCP Issue
07/21/2022
1797005
Replace 1B CCP rotating element
08/17/2022
1798957
Flow control damper for 2A Gen Exh Fan does not appear
to control correctly.
08/27/2022
1799903
BM Strategy - 1B CCP Potential for Shaft Cracking
08/31/2022
1805057
BM Strategy-Vital Inverter Diodes (Heat Map WBN0-0040)
09/27/2022
1808878
oil leak OB bearing housing
10/12/2022
1818472
Recorder is dark and needs replaced.
11/21/2022
CR 1746182
1-ISV-3-1002A missing shaft key for handwheel
01/07/2022
CR 1747852
Trending 1-FCV-3-6386 failed to stroke
01/14/2022
CR 1749992
Failed stroke time open and closed for 1-LCV-3-148
01/25/2022
CR 1753327
No output from 1-FM-3-155BD
2/08/2022
CR 1756168
1-TANK-3-403C N2 bottle handwheel is broken
2/19/2022
CR 1757331
1-FT-3-170B noted wire pinched under transmitter cover
2/25/2022
CR 1759680
TS LCO 3.3.3 Post Accident Monitoring Instrumentation
not restored within 30 days report required.
03/06/2022
CR 1764743
1-LCV-3-175 failed to indicate full closed when stroked
closed
03/24/2022
CR 1764748
Post Accident Status for AFW LCV indications
03/24/2022
CR 1766000
QMS/EQ activities assigned to components not in
database.
03/29/2022
CR 1769316
Some insulation holding wire ties on the Unit 1 terry turbine
have come loose.
04/13/2022
CR 1780029
Unit 1 1A-A MDAFW Pump vibrations in Alert range
05/31/2022
CR 1789285
Stroke time evaluation for 1-LCV-3-175
07/12/2022
CR 1790277
Unit 1 1A-A Motor Driven Auxiliary Feedwater Pump
vibrations in the Alert range.
07/18/2022
CR 1799125
Evaluate and remove unnecessary local verification
actions from TDAFW Pump procedures.
08/29/2022
CR 1802839
Evaluate need to hold control switch in the closed position
09/16/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
for 30 seconds when resetting the Steam Driven Auxiliary
Feedwater Pump Trip and Throttle Valve.
2-47W810-1
Flow Diagram Residual Heat Removal System
R27
Drawings
2-47W811-1
Flow Diagram Safety Injection System
R56
Engineering
Evaluations
System Health
Report
Health Report Scorecard
10/20/2022
Miscellaneous
Heat Map Item
WBN0-0040
Vital Inverter Diode Failures Bridging and Mitigation
Strategy
01/27/2022
119205912
Troubleshoot/Repair Inverter 1-IV, Inverter failed.
2/19/2018
21711952
Received annunciator 20-C 120 AC Vital Inverter 1-IV/0-IV
abnormal.
04/16/2021
21988955
Vital Inverter 1-IV failure.
06/22/2022
2124785
Oil Leaks coming from OB Bearing Housing
10/11/2022
2519239
Speed Increaser Oil Change - PM M6204V
10/11/2022
2573999
Pressure indicator 1-PI-62-104 not reading correctly.
10/11/2022
2702916
Replace diodes and SCRs in Vital Inverter 1-INV-235-1-D
11/30/2022
2760543
Outage work order needed to adjust setpoints for pressure
controllers for ventilation exhaust fans.
06/22/2022
2835302
Dry Boric Acid Leak
10/11/2022
Work Orders
23156139
Flow control damper for 2A Gen Exh Fan dose not appear
to control correctly.
08/31/2022
1817755
MCR received 20-C alarm due to Inverter 1-IV transferring
to bypass.
11/18/2022
Corrective Action
Documents
CR 1822924
1-FCV-62-144 failed to open in P-Auto during manual
boration.
2/13/2022
WDR10172022
October 17, 2022 Plan of the Day
10/17/2022
Miscellaneous
Work Week
Summary Report for
11/28/2022
Week of 11/28/2022, including multiple Reactor Protection
Instrument Calibrations, 480v and 6.9Kv breaker
maintenance, and Main Control Room Chiller maintenance
11/28/2022
2702938
Troubleshoot 1-IV inverter failure, diode and silicone
controlled rectifier replacement
11/18/2022
Work Orders
23078635
1-TRI-211-7 Cal & Functional Tests on 6.9kV Shutdown
Board 1A-A Maintenance Supply Breaker Relays.
10/17/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
23078638
2TRI-211-9 Cal and Functional Tests on 6.9kV Shutdown
Bard 2A-A Maintenance Supply Breaker Protective Relays.
10/17/2022
23310867
MCR received 20-C alarm due to Inverter 1-IV transferring
to bypass.
11/18/2022
1815347
1B RHR Pump lower bearing needs oil added
11/08/2022
CR 1741493
1-RFV-68-565 began simmering at 0313 on 12/11/21
2/11/2021
CR 1741785
This CR to track ACMP for U1 Simmering Pressurizer
Simmering Safety
2/14/2021
CR 1760352
Unit-1 Ice Condenser Bays 11 and 12 not fully serviced
during 1U17 refueling outage
03/08/2022
CR 1808182
Unit-2 2A CCW Pump Upper Bearing Oil Level Low
10/09/2022
CR 1808696
Hydrogen Analyzer Heat Trace System B Abnormal
Temperature Light is lit
10/12/2022
CR 1808913
Emergency Diesel Generator 1B-1 Engine 1B2 Cylinder #4
Temperature Indication Failed High
10/12/2022
CR 1808914
Emergency Diesel Generator 1B-1 Engine 1B2 Cylinder #7
Temperature Indication Failed High
10/12/2022
CR 1809152
1-FS-30-453 Found Out of Tolerance (OOT)
10/13/2022
CR 1809193
Unit-2 Containment Spray Pump 2B-B Boric Acid Around
Seal Area
10/13/2022
CR 1809267
ERCW Strainer 1A-1 leaking from top of strainer
10/18/2022
CR 1817555
Damaged Floor Penetration Seal for Essential Raw Water
Cooling (WBN-0-SLV-304-A0472BMA)
11/17/2022
CR 1817610
Unit 2 Control Bank A Rod Position Indicator K14 started
drifting high
11/17/2022
CR 1817704
Unit 2 Lower Containment Cooling Adjustment resulted in
Rod Position Indication Drift
11/17/2022
CR 1819730
Unit 2 Component Cooling Pump Motor Oil Sample
contained very small light-colored particulates.
11/29/2022
CR 1821694
B High Pressure Fire Pump Room water accumulation
following rain.
2/07/2022
CR 1822924
1-FCV-62-144 failed to open during manual boration
2/13/2022
Corrective Action
Documents
SR 378827
Hydrogen Analyzer Heat Tracing Function and
Performance
5/31/2011
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
EWR 12300410
2A-A Thermal Barrier Booster Pump Flow Evaluation
10/04/2022
Engineering
Evaluations
EWR22MEC015095
Evaluation for not reinstalling some reflective metallic
insulation in Unit-2 containment for Fuel Cycle-5
06/28/2022
0-SI-82-11-B
Monthly Diesel Generator Start And Load Test DG 1B-B
10/12/2022
Procedures
0-TI-78
Lubrication Program
0018
2519542
1-FS-30-453-B, Switch Calibration and Draining of
Condensate From Sense Line and Volume Chamber
10/13/2022
Work Orders
Unit-1 B Hydrogen Analyzer Abnormal Temperature
10/25/2022
DPG
Diagnostic Process Guideline
Revision
000003
Emergency Response Procedures and Guidelines for
Beyond Design Basis Events and Severe Accidents
Revision 1
NISP-IP-ENG-001
Standard Design Process
003
NPG-SPP-03.15
FSAR Management
0003
NPG-SPP-09.4
CFR 50.59 Evaluations of Changes, Tests, and
Experiments
0017
PWROG-15015-P
PWROG Severe Accident Management Guidelines
(Westinghouse Proprietary Class 2)
PA-PSC-
0932, Rev. 5
SAG-1
Main Control Room Severe Accident Guideline Initial
Response
Revision
0008
SAG-10
Spent Fuel Pool Level
Revision
0002
SAG-2
Main Control Room Severe Accident Guideline
TSC Recommending Strategies
Revision
0007
SAG-3
Technical Support Center Severe Accident Guideline Inject
into Steam Generators
Revision
0009
SAG-4
Technical Support Center Severe Accident Guideline
Depressurize RCS
Revision
0007
SAG-5
Technical Support Center Severe Accident Guideline
Inject into RCS
Revision
0010
SAG-6
Technical Support Center Severe Accident Guidelines
Inject Into Containment
Revision
0008
Procedures
SAG-7
Technical Support Center Severe Accident Guideline
Reduce Containment Hydrogen
Revision
0006
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
SAG-9
Technical Support Center Severe Accident Guideline
Mitigate Product Release
Revision
0002
Technical Support Guideline
Instrumentation
Revision
0003
Technical Support Guideline
Site Emergency Director
Revision
0000
Site Capabilities
Revision
0002
Benefit Consequence
Revision
0001
Computational Aids
Revision 001
0-47W859-4
Mechanical Flow Diagram Component Cooling Water
R3
1-47W866-1
Flow Diagram Heating and Ventilation Air Flow
R72
2-47W810-1
Flow Diagram Residual Heat Removal System
R27
Drawings
Mechanical Heating, Ventilating and Air Conditioning
R36
Procedures
2-SOI-74.01
Unit 2 System Operating Instruction Residual Heat
Removal System
22
21947747
1-PCO-065-0049, EGTS Aux Bldg. Purge Air modulating
damper, Bettis Actuator rebuild
11/09/2022
2498825
1-BKR-082-B1/1-B in Compartment 2D on 1-MCC-215-
B001-B, 480V DSL AUX BD 1B1-B
11/09/2022
2519963
PM 600112028 - Clean, Inspect, Test, Check T-Drain,
General Inspection both Motor and Cooler.
11/09/2022
2520628
Safety Valve Inspection and Testing in Support of 2-SI-0-
911. Perform 0-MI-0.011
11/09/2022
2663336
2-MTR-030-0175-A, RHR PUMP 2A-A RM CLR, INSP,
MEGGER, CLEAN MTR AND FAN/CLR INSP AND LUBE
11/04/2022
2663412
2-ISV-074-0520-A, Perform Reach-Rod
Adjustments/Verifications Per 0-MI-0.002 and 620740008
11/04/2022
2663418
2-ISV-074-0524-A, Perform Inspection and Lubrication per
M2230V
11/04/2022
2663428
CCS RHRS PUMP 2A-A RETURN RELIEF
11/04/2022
Work Orders
2820683
0-SI-65-6-B Emergency Gas Treatment System Train B
Operational Test
11/09/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
0-SOI-360.003
6900 FLEX Diesel Generator System
0-TI-446
Diverse and Flexible Coping Strategies (FLEX) Program
Bases
Procedures
0-TI-447
Diverse and Flexible Coping Strategies (FLEX) program
2517637
Fuel Oil Transfer Pump 3A
10/31/2022
Work Orders
2-SI-72-901-A Containment Spray Pump 2A-A Quarterly
Performance Test
11/01/2022
22 WBN November Off Hours QTD (Team C)
11/02/2022
Miscellaneous
22 WBN
November Off
Hours QT (Team C)
Report
11/02/2022
CR 1725400
Steam leak identified on walk down above #4 governor
valve on unit 2 turbine
CR 1726908
Failure analysis for steam leak on 2-PT-1-81
Corrective Action
Documents
CR 1751243
U1 East Condenser waterbox DP high
Mitigating System
Performance Index
(MSPI) Basis
Document, Revision
MSPI Derivation
Reports (UAI, URI,
PLE) - Unit 1 and
Unit 2 Cooling
Water Systems
(July 1, 2021 - June
30, 2022)
71151
Miscellaneous
MSPI Derivation
Reports (UAI, URI,
PLE) - Unit 1 and
Unit 2 Heat
Removal Systems
(July 1, 2021 - June
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
30, 2022)
MSPI Derivation
Reports (UAI, URI,
PLE) - Unit 1 and
Unit 2 High
Pressure Injection
System (July 1,
21 - June 30,
22)
MSPI Derivation
Reports (UAI, URI,
PLE) - Unit 1 and
Unit 2 Residual
Heat Removal
Systems ((July 1,
21 - June 30,
22)
Regulatory
Assessment
Performance
Indicator Guideline
Watts Bar Unit 1
Operations Log -
7/1/2021 through
6/30/2022
Watts Bar Unit 1 PI
Summary Report
Watts Bar Unit 2
Operations Log -
7/1/2021 through
6/30/2022
Watts Bar Unit 2 PI
Summary Report
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
NPG-SPP-02.2,
Rev. 0019
Performance Indicator Program,
Rev. 0019
SGT Non-Conformance Report 1130
Closed 5-22-
22
Corrective Action
Documents
SGT NCR-1053
SGT Non-Conformance Report 1053
Closed 3-29-
22
178130
Missed Section XI R/R Revision Review of WO 120927336
06/13/2022
1787788
U2R4 Mode 3 Walkdown Normal Operating Temperature
(NOT) Hold Time not Met
07/05/2022
Corrective Action
Documents
1791571
ANII Section Xi Issues Continue To Be Identified
07/23/2022
27691
Root Cause Analysis
27691
Root Cause Analysis
1155393
Root Cause Analysis
Condition Report(s)
1114975, 1116732, 1116741, 1116743, 1121520,
25569, 1127691, 1516431, 1624008, 1667128,
1670960, 1711441, 1711443, 1711445, 1736522,
1736528, 1670690, 1280168, 1464396, 1594403,
1816947, 1624009
Corrective Action
Documents
OPDP-1
Conduct of Operations
Revised NRC Finding/Violation Checklist - Violation C
09/29/2022
1814488
Significant Issues Gap Analysis
11/16/2022
Corrective Action
Documents
Resulting from
Inspection
Condition Report(s)
1812082, 1812353, 1812797
Nuclear Safety Culture Monitoring Panel Minutes
09/21/2017
Nuclear Safety Culture Monitoring Panel Minutes
10/19/2017
Nuclear Safety Culture Monitoring Panel Minutes
01/11/2018
Nuclear Safety Culture Monitoring Panel Minutes
01/12/2017
Guidelines for OCC Execution
CR Action 1127691-022 (CAPR) MRC Update for Sep.
2016
09/26/2016
MRC Meeting Minutes
2/14/2018
Site Clock Resets: 4-5-17 to 5-15-18
2722
Miscellaneous
NRC Docket No. EA 19-092, TVA Corrective Action
Statement
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Email - Access Termination after EA-19-092
03/17/2020
Operator Briefing following TVA/NRC PEC regarding AVs
07/29/2020
CNO Communication - Always Provide 'Complete and
Accurate' Information
07/17/2020
Cause Evaluation Training Manual
Nuclear Safety Culture Monitoring Panel Minutes
05/26/2017
50005715
CFR 50.9 LMS Training
GEN051C
SOER 10-2, Rec 1a Case Study - Vogtle/WBN Events
GEN051C.1
Salem Inadvertent PZR Draindown and WBN Events Case
Study
OPS-SM-LM2
Job Familiarization Guide - Maintaining a Broad View of
Plant Operations
OPS-SM-VP1
Job Familiarization Guide - Site Vice President Interview
WBN-2016-OTG-
007
Needs Analysis Worksheet
2/26/2016
Operability
Evaluations
1-SOI-74.01
Residual Heat Removal System
1-GO-1
Unit Startup from Cold Shutdown to Hot Standby
1-GO-1
Unit Startup from Cold Shutdown to Hot Standby
1-GO-2
Reactor Startup
1-GO-2
Reactor Startup
1-GO-3
Unit Startup from Less than 4% Reactor Power to 30%
Reactor Power
1-GO-3
Unit Startup from Less than 4% Reactor Power to 30%
Reactor Power
1-SOI-74.01
Residual Heat Removal System
2-GO-1
Unit Startup from Cold Shutdown to Hot Standby
2-GO-1
Unit Startup from Cold Shutdown to Hot Standby
2-GO-2
Reactor Startup
2-GO-2
Reactor Startup
2-GO-3
Unit Startup from Less than 4% Reactor Power to 30%
Reactor Power
Procedures
2-GO-3
Unit Startup from Less than 4% Reactor Power to 30%
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Reactor Power
2-SOI-74.01
Residual Heat Removal System
2-SOI-74.01
Residual Heat Removal System
NPG-SPP-01.18
Emergent Issue Response and Resolution
NPG-SPP-03.10
Managing TVA's Interface with NRC
NPG-SPP-07.2
Outage Management
NPG-SPP-07.2
Outage Management
NPG-SPP-07.2.11
Shutdown Risk Management
NPG-SPP-07.2.4
Forced Outage or Short Duration Planned Outage
Management
NPG-SPP-07.2.4
Forced Outage or Short Duration Planned Outage
Management
NPG-SPP-07.2.5
Outage Control Center
NPG-SPP-07.2.5
Outage Control Center
NPG-SPP-07.2.5
Outage Control Center
NPG-SPP-07.2.8
Outage Scope Control
NPG-SPP-07.2.8
Outage Scope Control
NPG-SPP-07.3
Work Activity Risk Management Process
NPG-SPP-07.3
Work Activity Risk Management Process
NPG-SPP-22.300
Corrective Action Program
ODM-15.0
Operations Work Control Process
ODM-15.0
Operations Work Control Process
Compliance with NPG-SPP-03.10, "Managing TVA's
Interface with NRC"
10/11/2018
27691
Effectiveness Review
05/15/2018
Self-
Assessments
1783675
Readiness Assessment for NRC Closeout on 2015 RHR
Event Violations (EA-19-092)
09/15/2022