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Category:Inspection Report
MONTHYEARIR 05000390/20243012024-12-16016 December 2024 NRC Operator License Examination Report 05000390/2024301 and 05000391/2024301 IR 05000390/20240032024-11-13013 November 2024 Integrated Inspection Report 05000390/2024003, 05000391/2024003 & 07201048/2024001 IR 05000390/20250102024-11-0404 November 2024 Notification of an NRC (FPTI) (NRC Inspection Report 05000390/2025010 0500039/ 2025010) (RFI) IR 05000390/20240052024-08-28028 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390-2024005 and 05000391-2024005 IR 05000390/20244022024-08-20020 August 2024 – Security Baseline Inspection Report 05000390-2024402 and 05000391/2024402 - Public IR 05000390/20240022024-08-0707 August 2024 Integrated Inspection Report 05000390/2024002 and 05000391/2024002 Rev IR 05000390/20244402024-07-12012 July 2024 95001 Supplemental Inspection Supplemental Report 05000390-2024440 and 05000391-2024440 and Follow-Up Assessment Letter IR 05000390/20240012024-05-14014 May 2024 Integrated Inspection Report 05000390/2024001 and 05000391/2024001 IR 05000391/20240072024-04-30030 April 2024 Assessment Follow-up Letter for Watts Bar Nuclear Plant, Unit 2 – Report 05000391/2024007 IR 05000390/20244012024-04-0202 April 2024 – Security Baseline Inspection Report 05000390/2024401 and 05000391/2024401 - (Public) IR 05000390/20240102024-03-0808 March 2024 Age-Related Degradation Inspection Report 05000390/2024010 and 05000391/2024010 IR 05000390/20230062024-02-28028 February 2024 Annual Assessment Letter for Watts Bar Nuclear Plant Units 1 and 2 - Report 05000390/2023006 and 05000391/2023006 IR 05000390/20230042024-02-13013 February 2024 Integrated Inspection Report 05000390/2023004 and 05000391/2023004 and Apparent Violation IR 05000390/20234412023-12-21021 December 2023 Plant–Final Significance Determination for a Security-Related Greater than Green Finding, Nov, and Assessment Follow-up, 05000390-2023441 and 05000391-2023441-Public IR 05000390/20234042023-12-14014 December 2023 – Security Baseline Inspection Report 05000390/2023404 and 05000391/2023404 IR 05000390/20230102023-11-30030 November 2023 RE-Issue Watts Bar Nuclear Plant - Biennial Problem Identification and Resolution Inspection Report 050000390/2023010 and 05000391/2023010 and Apparent Violation IR 05000390/20230032023-11-13013 November 2023 Integrated Inspection Report 05000390/2023003 and 05000391/2023003 and Apparent Violation ML23296A0242023-10-24024 October 2023 Biennial Problem Identification and Resolution Inspection Report and Preliminary Greater than Green Finding and Apparent Violation IR 05000390/20230052023-08-30030 August 2023 Updated Inspection Plan for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390/2023005 and 05000391/2023005 IR 05000390/20230022023-08-16016 August 2023 Reissue - Watts Bar Nuclear Plant - Integrated Inspection Report 05000390/2023002 and 05000391/2023002 ML23220A1582023-08-0909 August 2023 Integrated Inspection Report 05000390/2023002 and 05000391/2023002 IR 05000390/20230112023-07-24024 July 2023 Quadrennial Focused Engineering Inspection (FEI) Commercial Grade Dedication Report 05000390 2023011 and 05000391 2023011 IR 05000390/20234032023-05-30030 May 2023 Cyber Security Inspection Report 05000390/2023403 and 05000391/2023403 IR 05000390/20220032023-05-0909 May 2023 Reissue Watts Bar Nuclear Plant - Integrated Inspection Report 05000390/2022003 and 05000391/2022003 IR 05000390/20230012023-05-0404 May 2023 Integrated Inspection Report 05000390/2023001 and 05000391/2023001 IR 05000390/20234012023-03-13013 March 2023 – Security Baseline Inspection Report 05000390 2023401 and 05000391 2023401 IR 05000390/20220062023-03-0101 March 2023 Annual Assessment Letter for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390/2022006 and 05000391/2022006 IR 05000390/20220042023-02-10010 February 2023 – Integrated Inspection Report 05000390/2022004 and 05000391/2022004 IR 05000390/20224202022-12-0101 December 2022 Security Baseline Inspection 05000390/2022420 and 05000391/2022420 Cover Letter ML22318A0072022-11-14014 November 2022 Integrated Inspection Report 05000390/2022003 and 05000391/2022003 IR 05000390/20220102022-10-28028 October 2022 Design Basis Assurance Inspection (Teams) Inspection Report 05000390/2022010 and 05000391/2022010 IR 05000390/20223012022-09-30030 September 2022 NRC Operator License Examination Report 05000390/2022301 and 050000391/2022301 ML22256A2952022-09-14014 September 2022 Operation of an Independent Spent Fuel Storage Installation Report 07201048/2022001 IR 05000390/20220052022-08-31031 August 2022 Updated Inspection Plan for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390/2022005 and 05000391/2022005 - Final IR 05000390/20220022022-08-12012 August 2022 Integrated Inspection Report 05000390/2022002 and 05000391/2022002 and Exercise of Enforcement Discretion IR 05000390/20224012022-08-0303 August 2022 Security Baseline Inspection Report 05000390/2022401 and 05000391/2022401 IR 05000390/20220012022-05-11011 May 2022 Integrated Inspection Report 05000390/2022001 and 05000391/2022001 ML22123A2412022-05-11011 May 2022 Review of the Fall 2021 Mid-Cycle Steam Generator Tube Inspection Report IR 05000390/20210062022-03-0202 March 2022 Annual Assessment Letter for Watts Bar Nuclear Plant, Units 1 and 2 (Report No. 05000390/2021006 and 05000391/2021006) IR 05000390/20210042022-02-10010 February 2022 Integrated Inspection Report 05000390/2021004 and 05000391/2021004 IR 05000390/20210032021-11-10010 November 2021 Integrated Inspection Report 05000390/2021003 and 05000391/2021003 IR 05000390/20214022021-11-0202 November 2021 Security Baseline Inspection Report 05000390/2021402 and 05000391/2021402 IR 05000390/20214032021-10-26026 October 2021 Material Control and Accounting Program Inspection Report 05000390/2021403 and 05000391/2021403 (OUO Removed) ML21263A0042021-09-24024 September 2021 Review of the Fall 2020 Steam Generator Tube Inspection Report IR 05000390/20214012021-08-31031 August 2021 Security Baseline Inspection Report 05000390/2021401 and 05000391/2021401 IR 05000390/20210052021-08-24024 August 2021 Updated Inspection Plan for Watts Bar Nuclear Plant, Units 1 & 2 Report 05000390/2021005 and 05000391/2021005 IR 05000390/20210022021-08-0404 August 2021 Integrated Inspection Report 05000390/2021002 and 05000391/2021002 IR 05000390/20210122021-07-0101 July 2021 Biennial Problem Identification and Resolution Inspection Report 05000390/2021012 and 05000391/2021012 IR 05000390/20210102021-05-0606 May 2021 NRC Inspection Report 05000390/2021010 and 05000391/2021010 IR 05000390/20210012021-05-0505 May 2021 Integrated Inspection Report 05000390/2021001 and 05000391/2021001 2024-08-07
[Table view] Category:Letter
MONTHYEARCNL-24-082, Central Emergency Control Center Emergency Plan Implementing Procedure Revision2024-12-17017 December 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revision CNL-24-009, Brown Ferry Nuclear Plant, Units 1, 2 & 3; Sequoyah Nuclear Plant, Units 1 & 2 and Watts Bar Plant, Units 1 & 2 - Triennial Decommission Funding Plans for Independent Spent Fuel Storage Installations2024-12-17017 December 2024 Brown Ferry Nuclear Plant, Units 1, 2 & 3; Sequoyah Nuclear Plant, Units 1 & 2 and Watts Bar Plant, Units 1 & 2 - Triennial Decommission Funding Plans for Independent Spent Fuel Storage Installations ML24352A0092024-12-16016 December 2024 Investigation Summary, Office of Investigations Case Number 2-2023-007 IR 05000390/20243012024-12-16016 December 2024 NRC Operator License Examination Report 05000390/2024301 and 05000391/2024301 ML24346A3982024-12-16016 December 2024 NRC Examination Results Summary Examination Report 05000390/2024301 and 05000391/2024301 CNL-24-072, Request for Alternative to Extend First Containment Inservice Inspection Interval2024-12-12012 December 2024 Request for Alternative to Extend First Containment Inservice Inspection Interval CNL-24-075, Response to Request for Additional Information for Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah and Watts Bar (SQN-TSTS-23-02 and W2024-11-27027 November 2024 Response to Request for Additional Information for Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah and Watts Bar (SQN-TSTS-23-02 and WBN ML24297A4632024-11-21021 November 2024 – Environmental Assessment and Finding of No Significant Impact Related to Recapture of Low-Power Testing Time CNL-24-080, Response to Request for Additional Information Regarding Application to Revise Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis (WBN-19-011)2024-11-20020 November 2024 Response to Request for Additional Information Regarding Application to Revise Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis (WBN-19-011) IR 05000390/20240032024-11-13013 November 2024 Integrated Inspection Report 05000390/2024003, 05000391/2024003 & 07201048/2024001 CNL-24-021, Application to Revise Technical Specification Limiting Condition of Operation 3.5.2, ECCS – Operating, Note 1 to Include Residual Heat Removal Pump Flow Paths (SQN-TS-23-04 and WBN-TS-23-020)2024-11-12012 November 2024 Application to Revise Technical Specification Limiting Condition of Operation 3.5.2, ECCS – Operating, Note 1 to Include Residual Heat Removal Pump Flow Paths (SQN-TS-23-04 and WBN-TS-23-020) CNL-24-014, License Amendment Request to Revise the Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2 Technical Specifications to Use Online Monitoring Methodology (SQN-TS-24-02 and WBN-TS-23-22)2024-11-0404 November 2024 License Amendment Request to Revise the Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2 Technical Specifications to Use Online Monitoring Methodology (SQN-TS-24-02 and WBN-TS-23-22) CNL-24-064, Response to Request for Additional Information Regarding the Watts Bar Nuclear Plant, Unit 2 Steam Generator Tube Inspection Report for U2R52024-11-0404 November 2024 Response to Request for Additional Information Regarding the Watts Bar Nuclear Plant, Unit 2 Steam Generator Tube Inspection Report for U2R5 IR 05000390/20250102024-11-0404 November 2024 Notification of an NRC (FPTI) (NRC Inspection Report 05000390/2025010 0500039/ 2025010) (RFI) CNL-24-074, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-10-23023 October 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML24290A1202024-10-17017 October 2024 Operator Licensing Examination Approval 05000390/2024301 and 05000391/2024301 ML24282B0412024-10-15015 October 2024 Request for Withholding Information from Public Disclosure for Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2 ML24260A1682024-10-0404 October 2024 Regulatory Audit Summary Related to Request to Add and Revise Notes Related to Technical Specification Table 3.3.2-1, Function 5 ML24261C0062024-10-0404 October 2024 Correction to Amendment No. 134 to Facility Operating License No. NPF-90 and Amendment No. 38 to Facility Operating License No. NPF-96 ML24284A1072024-09-26026 September 2024 Affidavit for Request for Withholding Information from Public Disclosure for Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2 CNL-24-060, Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description2024-09-24024 September 2024 Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description CNL-24-047, Decommitment of Flood Mode Mitigation Improvement Systems2024-09-24024 September 2024 Decommitment of Flood Mode Mitigation Improvement Systems ML24262A0602024-09-23023 September 2024 Summary of August 19, 2024, Meeting with Tennessee Valley Authority Regarding a Proposed Supplement to the Tennessee Valley Authority Nuclear Quality Assurance Plan CNL-24-065, Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-09-18018 September 2024 Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions 05000390/LER-2024-002, Automatic Reactor Trip Due to Main Generator Protection Relay Actuation2024-09-0505 September 2024 Automatic Reactor Trip Due to Main Generator Protection Relay Actuation IR 05000390/20240052024-08-28028 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390-2024005 and 05000391-2024005 ML24218A1442024-08-27027 August 2024 Issuance of Amendment Nos. 169 and 75 Regarding Technical Specification Surveillance Requirement 3.9.5.1 to Reduce the Residual Heat Removal Flow Rate IR 05000390/20244022024-08-20020 August 2024 – Security Baseline Inspection Report 05000390-2024402 and 05000391/2024402 - Public CNL-24-061, Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08),2024-08-19019 August 2024 Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08), ML24219A0262024-08-12012 August 2024 Request for Withholding Information from Public Disclosure IR 05000390/20240022024-08-0707 August 2024 Integrated Inspection Report 05000390/2024002 and 05000391/2024002 Rev ML24204A2652024-07-25025 July 2024 Regulatory Audit Summary Related to Request to Revise Technical Specification Surveillance Requirement 3.9.5.1 to Reduce the Residual Heat Removal Flow Rate ML24199A0012024-07-22022 July 2024 Clarification and Correction to Exemption from Requirement of 10 CFR 37.11(c)(2) ML24170A8002024-07-15015 July 2024 Issuance of Amendment Nos. 168 and 74 Regarding Revision to Technical Specification Table 1.1-1 for Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts ML24172A1342024-07-15015 July 2024 Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter IR 05000390/20244402024-07-12012 July 2024 95001 Supplemental Inspection Supplemental Report 05000390-2024440 and 05000391-2024440 and Follow-Up Assessment Letter 05000391/LER-2024-003, Inoperability of Both Trains of Unit 2 Low Head Safety Injection2024-07-11011 July 2024 Inoperability of Both Trains of Unit 2 Low Head Safety Injection ML24131A0012024-07-0202 July 2024 Issuance of Amendment Nos. 167 and 73 Regarding Adoption of Technical Specification Task Force Traveler TSTF-427-A, Revision 2 CNL-24-052, Response to Request for Additional Information Regarding Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)2024-06-27027 June 2024 Response to Request for Additional Information Regarding Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14) CNL-24-018, License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A, Revision 2, Regarding TS 3.8.1 AC Sources – Operating to Clarify Requirements for Diesel Generator Testing (WBN-TS2024-06-25025 June 2024 License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A, Revision 2, Regarding TS 3.8.1 AC Sources – Operating to Clarify Requirements for Diesel Generator Testing (WBN-TS ML24089A1152024-06-21021 June 2024 Transmittal Letter, Environmental Assessments and Findings of No Significant Impact Related to Exemption Requests from 10 CFR 37.11(c)(2) ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24100A7642024-05-16016 May 2024 Issuance of Amendment No. 166 Regarding Revision to Technical Specification 3.8.2, AC Sources-Shutdown, to Remove Reference to C-S Diesel Generator (CNL-23-062) IR 05000390/20240012024-05-14014 May 2024 Integrated Inspection Report 05000390/2024001 and 05000391/2024001 CNL-24-040, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-05-0808 May 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions 05000391/LER-2024-002, Re Automatic Reactor Trip Due to Steam Generator 3 Level LO-LO2024-05-0606 May 2024 Re Automatic Reactor Trip Due to Steam Generator 3 Level LO-LO IR 05000391/20240072024-04-30030 April 2024 Assessment Follow-up Letter for Watts Bar Nuclear Plant, Unit 2 – Report 05000391/2024007 ML24120A1182024-04-29029 April 2024 – Notification of NRC Supplemental Inspection (95001) and Request for Information CNL-24-037, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 422024-04-22022 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 42 ML24087A1912024-04-18018 April 2024 Exemption from Select Requirements of 10 CFR Part 73, Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting 2024-09-05
[Table view] |
Text
October 30, 2019
SUBJECT:
WATTS BAR NUCLEAR PLANT, UNITS 1 AND 2 - INTEGRATED INSPECTION REPORT 05000390/2019003 AND 05000391/2019003
Dear Mr. Barstow:
On September 30, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Watts Bar, Units 1 and 2. On October 17, 2019, 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.
The NRC inspectors did not identify any finding or violation of more than minor significance.
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 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely,
/RA/
Omar R. López-Santiago, 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:
05000390/2019003 and 05000391/2019003
Enterprise Identifier:
I-2019-003-0024
Licensee:
Tennessee Valley Authority
Facility:
Watts Bar, Units 1 and 2
Location:
Spring City, TN 37381
Inspection Dates:
July 01, 2019 to September 30, 2019
Inspectors:
N. Childs, Senior Resident Inspector
W. Deschaine, Senior Resident Inspector
J. Hamman, Resident Inspector
S. Janicki, Resident Inspector
R. Mathis, Test Inspector
J. Nadel, Senior Resident Inspector
Approved By:
Omar R. López-Santiago, 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, Units 1 and 2 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
None.
PLANT STATUS
Unit 1 began the inspection period at rated thermal power. On August 31, 2019, the unit was manually tripped due to a main feedwater regulating valve (MFRV) failure. Repairs were made to the MFRV and on September 3, 2019, the unit reached 12%. On September 5, 2019, the licensee noted some turbine repairs that were necessary and shutdown the unit. The unit remained offline for the remainder of the inspection period.
Unit 2 operated at or near rated thermal power 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 plant status activities described in IMC 2515 Appendix D, Plant Status and conducted routine reviews using IP 71152, Problem Identification and Resolution. 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
71111.04Q - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
(1)1B train charging system while 1A centrifugal charging pump (CCP) was out of service (OOS) for a component outage on July 8, 2019 (2)2B train of containment spray while 2A train was OOS for planned maintenance on July 9, 2019 (3)1A-A emergency diesel generator (EDG) while 1B-B EDG was OOS for planned maintenance (4)1A, 1B and 2A 480V electric board room (EBR) chillers while 2B EBR chiller was OOS for repairs on August 22, 2019
71111.05A - Fire Protection (Annual)
Annual Inspection (IP Section 03.02) (1 Sample)
- (1) Inspectors observed an announced fire drill for a fire in the 1B-B containment spray pump room on August 14, 2019.
Quarterly Inspection (IP Section 03.01) (1 Sample)
The inspectors evaluated fire protection program implementation in the following selected areas:
- (1) Control building elevation 741', Unit 1 and 2 cable spreading rooms on August 20, 2019.
71111.06 - Flood Protection Measures
Inspection Activities - Internal Flooding (IP Section 02.02a.) (1 Sample)
The inspectors evaluated internal flooding mitigation protections in the:
- (1) Unit 1 and 2 auxiliary building elevation 757', shutdown board rooms
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 a Unit 1 start-up following a forced outage due to the failure of the #2 main feedwater regulating valve on September 2, 2019.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed simulator scenario 3-OT-SRT-H1-6, Revision 2, for a loss of ultimate heat sink following a rapid load reduction due to high turbine bearing temperature on September 19, 2019.
71111.12 - Maintenance Effectiveness
Routine Maintenance Effectiveness Inspection (IP Section 02.01) (1 Sample)
The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions:
- (1) Condition Report (CR) 1526540, A and B Emergency Gas Treatment System functional failure due to a tear in penetration seal 0-SLV-304-R2S065
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated the risk assessments for the following planned and emergent work activities:
- (1) Risk assessment for week of August 12, 2019 with 1B-B emergency diesel generator OOS for planned maintenance
- (2) Risk assessment for August 29, 2019, with the 2B-B emergency diesel generator OOS for planned maintenance
- (3) Risk assessment for September 9, 2019, with Unit 1 shutdown for a forced outage
- (4) Risk assessment for September 25, 2019 with 2B-B emergency diesel generator OOS due to load swings during a surveillance
Operability Determination or Functionality Assessment (IP Section 02.02) (2 Samples)
The inspectors evaluated the following operability determinations and functionality assessments:
- (1) Operability determination for CR 1539213, auxiliary building gas treatment system 1A-A fan motor high vibrations
- (2) Operability determination for CR 1534088, Engineering Work Request EWR-19-ELE-030-284, low margin to maximum limit for Unit 1 lower containment temperature.
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (1 Sample)
The inspectors evaluated the following temporary or permanent modifications:
- (1) Temporary Modification WBN-0-2019-031-004, temporary chillers installed to provide chilled water to the B-B shutdown board room chiller loads on August 22, 2019
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (2 Samples)
The inspectors evaluated the following post maintenance tests:
- (1) Post maintenance test of 1A-A auxiliary building gas treatment system exhaust fan motor after preventive maintenance on August 8, 2019
- (2) WO 120614655, 0-SI-82-12-B, Monthly Diesel Start and Load Test DG 2B-B, following 2B-B emergency diesel generator repairs on September 25, 2019
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Inservice Testing (IP Section 03.01)
Main article: IP 71111.22
- (1) Work Order (WO) 120163013, 1-SI-3-901-B, Motor Driven Auxiliary Feedwater Pump 1B-B Quarterly Performance Test on August 2,
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below:
MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04)===
- (1) Unit 1 (July 1, 2018 - June 30, 2019)
- (2) Unit 2 (July 1, 2018 - June 30, 2019)
MS07: High Pressure Injection Systems (IP Section 02.06) (2 Samples)
- (1) Unit 1 (July 1, 2018 - June 30, 2019)
- (2) Unit 2 (July 1, 2018 - June 30, 2019)
MS10: Cooling Water Support Systems (IP Section 02.09) (2 Samples)
- (1) Unit 1 (July 1, 2018 - June 30, 2019)
- (2) Unit 2 (July 1, 2018 - June 30, 2019)
BI02: RCS Leak Rate Sample (IP Section 02.11) (2 Samples)
- (1) Unit 1 (July 1, 2018 - June 30, 2019)
- (2) Unit 2 (July 1, 2018 - June 30, 2019)
71152 - Problem Identification and Resolution
Semiannual Trend Review (IP Section 02.02) (1 Sample)
- (1) The inspectors reviewed the licensees corrective action program for trends that might be indicative of a more safety significant issue.
Annual Follow-up of Selected Issues (IP Section 02.03) (1 Sample)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- (1) The inspectors conducted safety culture interviews in the Watts Bar Site Projects organization as a result of several safety culture related condition reports. The inspectors concluded that individuals in the Watts Bar Site Projects organization understood the various methods of reporting safety concerns and were willing to use them without fear of retaliation.
INSPECTION RESULTS
Observation: Review of Condition Reports Related to Tritium Production in Unit 1 Reactor 71152 During their regular review of the licensees corrective action program, the inspectors identified eleven condition reports written between February and September 2019 relating to tritium production using tritium producing burnable absorber rods (TPBAR) in the Unit 1 reactor. The inspectors evaluated this as a possible trend. The technical issues described in ten of the condition reports had insignificant impact on plant operations. Condition report 1521541, related to airborne tritium concentration in lower containment, received a detailed review by the inspectors. Specifically, increased tritium concentration in unit 1 reactor coolant sometimes resulted in increased airborne tritium in lower containment. This is because reactor coolant is collected in the reactor building equipment drain system, which is open to the lower containment atmosphere, and is present in the reactor coolant drain tank, which is vented to the lower containment atmosphere. The inspectors found that the licensee had procedures in place to monitor lower containment tritium concentrations and to ensure protection for personnel working in lower containment. Additionally, the licensee monitored gaseous releases from Unit 1 containment to ensure that those releases are below regulatory requirements. Overall, the inspectors concluded that none of the condition reports reviewed were indicative of a more significant safety issue.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On October 17, 2019, the inspectors presented the integrated inspection results to Mr.
Anthony Williams and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71111.04Q Drawings
2-47W812-1
Miscellaneous
SDD-N3-30AB-
4001
Auxiliary Building Heating, Ventilation, Air Conditioning
System (30, 31, 44) Unit1/Unit 2
Procedures
0-SI-82-2
Hour Diesel Generator AC Power Source Operability
Verification
1-PI-OPS-PE
Protection Equipment
2-PI-OPS-1-PE
Protected Equipment
71111.05A
Fire Plans
AUX-0-676-01
WBN Prefire Plan
Miscellaneous
Watts Bar Nuclear Plant Fire Protection Report
71111.05Q Corrective Action
Documents
CR
1542582
Fire Plans
CON-0-729-01
Pre-Fire Plan
71111.06
Calculations
Flooding Calculation WBN0SG4009, Appendix J, Backflow
Through Floor Drains
09/25/1987
MDN-000-999-
2008-0146
WBN Probabilistic Risk Assessment - Internal Flooding
Analysis Notebook
WBN-DC-40-
31.51
Evaluating the Effects of Flooding due to Moderate Energy
Pipe Failures Inside and Outside of Containment
WBN-DC-40-61
Equipment and Floor Draining System
Corrective Action
Documents
CR
1542885, 1539120
71111.11Q Corrective Action
Documents
CR
26540
Miscellaneous
1-GO-2
Reactor Startup
1646, 1647
Cause Determination Evaluation
Procedures
0-TI-119
Maintenance Rule Performance Indicator Monitoring,
Trending, and Reporting - 10CFR50.65
Work Orders
20536836
71111.13
Miscellaneous
Operator's Risk Report
08/12/2019
WBN Defense in Depth Assessment
09/09/2019
Operator's Risk Report
09/25/2018
Procedures
0-SI-82-2
Hour Diesel Generator AC Power Source Operability
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Verification
71111.15
Corrective Action
Documents
CR
1534088, 1535612, 1536108, 1539213
Miscellaneous
EWR-19-ELE-
030-284
Evaluate the impact of one or more failed temperature
sensors on the determination of the average lower
containment temperature for WBN 1
07/23/2019
Procedures
0-TI-31.02
Plant Equipment Monitoring & Vibration Diagnostics
Program
1-T-30-210
Setpoint and Scaling Document
NEDP-10,
Site Engineering Setpoint and Scaling Documents
NEDP-2
Safety/Quality-Related Setpoint Establishment and
Validation Process
NEDP-4,
Quality-related Processes-Augmented QA
NPG-SPP-06.7
Instrumentation Setpoint, Scaling, and Calibration Program
NPG-SPP-09.0
Conduct of Engineering
Work Orders
119904284
71111.18
Miscellaneous
C19-0447, C19-
0454
Fire Protection Impairment Permit
WBN-0-2019-
031-004
Temporary Chiller to Support Replacement of B-Train
Shutdown Board Room (SDBR) Chiller
71111.19
Corrective Action
Documents
CR
1539213
Procedures
0-SI-82-12-B
Monthly Diesel Start and Load Test B2-B
0-TI-31.02
Plant Equipment Monitoring & Vibration Diagnostics
Program
Work Orders
119904284
71111.22
Procedures
1-SI-3-901-B
Motor Driven Auxiliary Feedwater Pump 1B-B Quarterly
Performance Test
71152
Corrective Action
Documents
1494503,
21541,
22992,
24508,
Condition Reports
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
26913,
29480,
1531261,
1533009,
1549445,
1549467,
1549912