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Category:Inspection Report
MONTHYEARIR 05000390/20234412023-12-21021 December 2023 Plantfinal 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 IR 05000390/20210112021-04-13013 April 2021 Triennial Fire Protection Inspection Report 05000390/2021011 and 05000391/2021011 IR 05000390/20200062021-03-0303 March 2021 Annual Assessment Letter for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390/2020006 and 05000391/2020006 IR 05000390/20200042021-02-11011 February 2021 Integrated Inspection Report 05000390/2020004, 05000391/2020004, 07201048/2020002, and Exercise of Enforcement Discretion IR 05000390/20203012021-01-19019 January 2021 Reissue - Watts Bar Nuclear Plant - NRC Operator License Examination Report 05000390/2020301 and 05000391/2020301 IR 05000390/20204032020-12-15015 December 2020 Security Baseline Inspection Report 05000390/2020403 and 05000391/2020403 IR 05000390/20204012020-11-30030 November 2020 Security Baseline Inspection Report 05000390/2020401 and 05000391/2020401 IR 05000390/20200032020-11-10010 November 2020 Integrated Inspection Report 05000390/2020003 and 05000391/2020003 IR 05000390/20200112020-10-20020 October 2020 Design Basis Assurance Inspection (Programs) Inspection Report 05000390/2020011 and 05000391/2020011 IR 05000390/20200052020-08-31031 August 2020 Assessment Followup Letter and Updated Inspection Plan for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390/2020005 and 05000391/2020005 IR 05000390/20200022020-08-11011 August 2020 Nuclear Regulatory Commission Integrated Inspection Report 05000390/2020002, 05000391/2020002, and 07201048/2020001 IR 05000390/20200012020-05-0505 May 2020 Integrated Inspection Report 05000390/2020001 and 05000391/2020001 IR 05000390/20204102020-03-31031 March 2020 Security Baseline Inspection Report 05000390/2020410 and 05000391/2020410 IR 05000390/20190062020-03-0303 March 2020 Annual Assessment Letter for Watts Bar Nuclear Plant Units 1 and 2 - NRC Report 05000390/2019006 and 05000391/2019006 2023-08-09
[Table view] Category:Letter
MONTHYEARML23319A2452024-01-29029 January 2024 Issuance of Amendment Nos. 366 and 360; 164 and 71 Regarding the Adoption of TSTF-567, Revision 1, Add Containment Sump TS to Address GSI-191 Issues ML24008A2462024-01-18018 January 2024 Revision to the Reactor Vessel Material Surveillance Capsule Withdrawal Schedule CNL-24-017, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions2024-01-17017 January 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions CNL-24-016, Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)2024-01-10010 January 2024 Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14) CNL-23-052, Application to Adopt TSTF-427-A, Revision 2, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability2024-01-0909 January 2024 Application to Adopt TSTF-427-A, Revision 2, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability CNL-23-062, Application to Revise the Technical Specifications Section 3.8.2, AC Sources-Shutdown, to Remove Reference to the C-S Diesel Generator (WBN-TS-23-018)2024-01-0808 January 2024 Application to Revise the Technical Specifications Section 3.8.2, AC Sources-Shutdown, to Remove Reference to the C-S Diesel Generator (WBN-TS-23-018) ML23346A1382024-01-0303 January 2024 Regulatory Audit Summary Related to Request to Increase the Number of Tritium Producing Burnable Absorber Rods CNL-23-069, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-21021 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000390/20234412023-12-21021 December 2023 Plantfinal Significance Determination for a Security-Related Greater than Green Finding, Nov, and Assessment Follow-up, 05000390-2023441 and 05000391-2023441-Public CNL-23-036, Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08)2023-12-18018 December 2023 Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08) IR 05000390/20234042023-12-14014 December 2023 Security Baseline Inspection Report 05000390/2023404 and 05000391/2023404 CNL-23-001, Rebaseline of Sections 3.1 and 3.2 of the Technical Specifications (WBN-TS-23-01)2023-12-13013 December 2023 Rebaseline of Sections 3.1 and 3.2 of the Technical Specifications (WBN-TS-23-01) ML23293A0572023-12-0606 December 2023 Issuance of Amendment Nos. 163 and 70 Regarding Adoption of TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control 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 CNL-23-067, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-11-27027 November 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000390/20230032023-11-13013 November 2023 Integrated Inspection Report 05000390/2023003 and 05000391/2023003 and Apparent Violation ML23312A1432023-11-0808 November 2023 Submittal of Dual Unit Updated Final Safety Analysis Report (UFSAR) Amendment 5 CNL-23-059, Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-2023-09-20020 September 2023 Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 CNL-23-061, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-09-20020 September 2023 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision ML23251A2002023-09-11011 September 2023 Request for Withholding Information from Public Disclosure for Watts Bar Nuclear Plant, Units 1 and 2 CNL-23-057, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 642023-09-0505 September 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 64 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 ML23233A0042023-08-28028 August 2023 Proposed Alternative to the Requirements of the ASME Boiler and Pressure Vessel Code for Upper Head Injection Dissimilar Metal Butt Welds 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 CNL-23-045, License Amendment Request to Revise Technical Specification Table 1.1-1 Regarding the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts (WBN-TS-23-010)2023-08-0707 August 2023 License Amendment Request to Revise Technical Specification Table 1.1-1 Regarding the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts (WBN-TS-23-010) CNL-23-028, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 and WBN-TS-23-06)2023-08-0202 August 2023 Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 and WBN-TS-23-06) ML23192A4472023-07-31031 July 2023 Staff Assessment of Updated Seismic Hazards at TVA Sites Following the NRC Process for the Ongoing Assessment of Natural Hazards Information CNL-23-055, Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills2023-07-25025 July 2023 Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills IR 05000390/20230112023-07-24024 July 2023 Quadrennial Focused Engineering Inspection (FEI) Commercial Grade Dedication Report 05000390 2023011 and 05000391 2023011 CNL-23-053, Tennessee Valley Authority - Radiological Emergency Plan Revisions2023-07-18018 July 2023 Tennessee Valley Authority - Radiological Emergency Plan Revisions CNL-23-020, Application to Revise Technical Specifications to Adopt TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control (WBN-TS-22-06)2023-06-28028 June 2023 Application to Revise Technical Specifications to Adopt TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control (WBN-TS-22-06) CNL-23-049, Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan .2023-06-26026 June 2023 Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan . ML23122A2322023-06-0707 June 2023 Issuance of Amendment Nos. 162 and 69 Regarding Change to Date in Footnotes for Technical Specification 3.7.11, Control Room Emergency Air Temperature Control System (Creatcs) CNL-23-044, Transmittal of Revision 3 to WCAP-18774-P and WCAP-18774-NP, Addendum to the Rotterdam Dockyard Company Final Stress Report for 173 P.W.R. Vessels TVA III & IV (Report No. 30749-B-030, Rev. 3) - Evaluation of One Closure Stud Out2023-06-0101 June 2023 Transmittal of Revision 3 to WCAP-18774-P and WCAP-18774-NP, Addendum to the Rotterdam Dockyard Company Final Stress Report for 173 P.W.R. Vessels TVA III & IV (Report No. 30749-B-030, Rev. 3) - Evaluation of One Closure Stud Out IR 05000390/20234032023-05-30030 May 2023 Cyber Security Inspection Report 05000390/2023403 and 05000391/2023403 ML23131A1812023-05-23023 May 2023 Correction to Amendment No. 161 to Facility Operating License No. NPF-90 CNL-23-042, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-05-16016 May 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000390/20220032023-05-0909 May 2023 Reissue Watts Bar Nuclear Plant - Integrated Inspection Report 05000390/2022003 and 05000391/2022003 ML23125A2202023-05-0505 May 2023 Issuance of Amendment No. 161 Regarding a Change to Footnotes for Technical Specification Table 1.1-1 Modes (Emergency Circumstances) IR 05000390/20230012023-05-0404 May 2023 Integrated Inspection Report 05000390/2023001 and 05000391/2023001 CNL-23-043, Emergency License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical Specification Table 1.1-1, Modes (WBN-TS-23-09)2023-05-0404 May 2023 Emergency License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical Specification Table 1.1-1, Modes (WBN-TS-23-09) CNL-23-032, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 412023-04-27027 April 2023 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 41 CNL-23-030, Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update2023-04-27027 April 2023 Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-23-033, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-04-24024 April 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision CNL-23-029, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-04-11011 April 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML23072A0652023-04-0505 April 2023 Units 1 and 2 Issuance of Amendment Nos. 364 and 358; 160 and 68 Regarding a Revision to Technical Specification 3.4.12 ML23073A2762023-04-0303 April 2023 Individual Notice of Consideration of Issuance of Amendments to Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing (EPID L-2023-LLA-0029) (Letter) CNL-23-023, Annual Insurance Status Report2023-03-30030 March 2023 Annual Insurance Status Report CNL-23-024, TVA Guarantee of Payment of Deferred Premiums - 2022 Annual Report2023-03-29029 March 2023 TVA Guarantee of Payment of Deferred Premiums - 2022 Annual Report 2024-01-09
[Table view] |
Text
October 20, 2020
SUBJECT:
WATTS BAR NUCLEAR PLANT, UNITS 1 AND 2 - DESIGN BASIS ASSURANCE INSPECTION (PROGRAMS) INSPECTION REPORT 05000390/2020011 AND 05000391/2020011
Dear Mr. Barstow:
On September 24, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Watts Bar Nuclear Plant, Units 1 and 2 and 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.
No findings or violations of more than minor significance were identified during this inspection.
This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely,
/RA/
James B. Baptist, Chief Engineering Branch 1 Division of Reactor Safety 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: 05000390/2020011 and 05000391/2020011 Enterprise Identifier: I-2020-011-0042 Licensee: Tennessee Valley Authority Facility: Watts Bar Nuclear Plant, Units 1 and 2 Location: Spring City, TN Inspection Dates: August 31, 2020 to September 24, 2020 Inspectors: P. Carman, Senior Reactor Inspector M. Greenleaf, Reactor Inspector N. Morgan, Reactor Inspector Approved By: James B. Baptist, Chief Engineering Branch 1 Division of Reactor Safety Enclosure
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a design basis assurance inspection (programs) inspection at Watts Bar Nuclear Plant, 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.
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards. Starting on March 20, 2020, in response to the National Emergency declared by the President of the United States on the public health risks of the coronavirus (COVID-19),inspectors were directed to begin telework. In addition, regional baseline inspections were evaluated to determine if all or portion of the objectives and requirements stated in the IP could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable IP. In some cases, portions of an IP were completed remotely and on site. The inspections documented below met the objectives and requirements for completion of the IP.
REACTOR SAFETY
71111.21N.02 - Design-Basis Capability of Power-Operated Valves Under 10 CFR 50.55a Requirements POV Review (IP Section 03)
Main article: IP 71111.21
The inspectors:
a. Evaluated whether the sampled POVs are being tested and maintained in accordance with NRC regulations along with the licensees commitments and/or licensing bases.
b. Evaluated whether the sampled POVs are capable of performing their design-basis functions.
c. Evaluated whether testing of the sampled POVs is adequate to demonstrate the capability of the POVs to perform their safety functions under design-basis conditions.
d. Evaluated maintenance activities including a walkdown of the sampled POVs (if accessible).
- (1) 1-FCV-1-51-S, Turbine-Driven Auxiliary Feedwater Pump Trip and Throttle Valve
- (2) 1-FCV-67-67-B, Diesel Generator Heat Exchanger 1B1/1B2 Essential Raw Cooling Water Supply Header 1B Isolation Valve
- (3) 1-FCV-72-2-B, Containment Spray Header (Train B) Isolation Valve
- (4) 2-FCV-63-93-A, Residual Heat Removal to Cold Leg 2 & 3 Injection Isolation Valve
- (5) 2-FCV-68-332-B, Pressurizer Power-Operated Relief Valve (PORV) Block Valve
- (6) 2-LCV-62-135-A, Refueling Water Storage Tank Chemical and Volume Control System Supply Header Isolation Valve
- (7) 1-FCV-1-22-T, Main Steam Loop 3 Isolation Valve
- (8) 1-PCV-1-5-T, Steam Generator Loop 1 PORV Valve
- (9) 2-FCV-1-25-B, Steam Generator 3 Blowdown Isolation Valve
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On September 24, 2020, the inspectors presented the design basis assurance inspection (programs) 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
71111.21N.02 Calculations 048-018-MSS System Level Review for Watts Bar Main Steam Rev. 1
Supply System Air Operated Valves
048-018-PIL Evaluation of Required Thrust for MSIVs and SG- Rev. 1
PORVs (Pilot-Operated Balanced Disk Globe
AOVs) at Watts Bar Nuclear Power Station
25402-011-V1E-SS00- EPRI MOV PPM Analysis for 4 Butterfly MOVs for Rev. 2
00001-002 Compliance with GL 89-10 MOV Program
Requirements for Units 1 and 2, Document No.
2914C
CGACQ1304 Weak Link Analysis for 8-150# Posi Seal Butterfly Rev. 1
Valves Mark# 17W586-1
EDQ00099920070002 AC Auxiliary Power System Analysis Rev. 73
EPMCPH060292 Documentation of MOV Design Basis Review and Rev. 6
Thrust/Torque Requirements and Valve and
Actuator Capability Assessment for Valve 1-FCV-
2-2
EPMDTN051192 Documentation of Design Basis Review, Required Rev. 6
Torque Calculations, and Valve and Actuator
Capability Assessment for Valve 1-FCV-67-67
EPMTSS117091 Generic Letter 89-10 MOV Population at Watts Bar Rev. 28
(Unit 1)
EPTMSS100292 Documentation of Design Basis Review, Required Rev. 7
Thrust/Torque Calculations, and Valve and Actuator
Capability Assessment for Valve 1-FCV-01-051
MDN-000-999-2011- WBN Probabilistic Risk Assessment - Risk Ranking Rev. 2
0178 of Motor Operated Valves
MDN-000-999-2011- WBN Probabilistic Risk Assessment - Risk Ranking Rev. 1
0179 of Air Operated Valves (AOV)
MDQ00099920010063 Categorization of the Air Operated Valves (AOVs) Rev. 7
MDQ00100120020072 Component Level Review Calculation for Watts Bar Rev. 5
Main Steam Supply (MSS) System Pilot-Operated
Balanced Disk Globe Air Operated Valves (AOVs)
Inspection Type Designation Description or Title Revision or
Procedure Date
MDQ00199920100167 Watts Bar Nuclear Plant JOG MOV Periodic Rev 5
Verification Classification
MDQ0020622008-0226 Documentation of Design Basis Review Required Rev. 5
Thrust/Torque Calculations and Valve and Actuator
Capability Assessment for Valve 2-LCV-62-135
MDQ0020632008-0244 Documentation of Design Basis Review, Required Rev. 9
Thrust/Torque Calculations and Actuator Capability
Assessment for Valve 2-FCV-63-093
MDQ0020682008-0274 Documentation of Design Review Basis Review, Rev. 4
Required Thrust/Torque Calculations and Valve and
Actuator Capability Assessment for Valve 2-FCV-
68-332
MDQ0029992009-0310 Generic Letter 89-10 MOV Population for Watts Bar Rev. 10
(Unit 2)
MDQ0029992015000687 Watts Bar Nuclear Plant Unit 2 JOG MOV Periodic Rev. 0
Verification Classification
QDC0029992014000504 Material Aging Calculation for Unit 1 and 2 Rev. 11
Mechanical Equipment Qualification (Binder WBN-
MEQ-001)
WAT-D-8584 Maximum Allowable Thrusts 06/25/1991
WBN-EM-59 Essentially Mild Calculation for Limitorque Actuators Rev. 9
WBNOSG4159 Thermal Transient of Target Rock Solenoid Valves Rev. 6
Located in the Valve Vaults During a MSLB
WBT-D-4037 Summary of Seismic Analysis of 8GM78FN Built to 08/29/2012
Drawing 115E012 at Watts Bar Unit 2
Corrective Action CRs 1093165, 1195979,
Documents 1601458, 1624132,
25963
Corrective Action CR 1639485 2020 NRC POV Inspection - PM frequency change 09/23/2020
Documents needed
Resulting from CR 1634592 2020 NRC POV Inspection - procedure typo in 09/03/2020
Inspection rev.log reference
CR 1634666 2020 NRC POV Inspection - Correct reference in 09/03/2020
Section 7.1.9 of calculation EPMDTN051192
Inspection Type Designation Description or Title Revision or
Procedure Date
CR 1634871 2020 NRC POV Inspection - Administrative Error in 09/03/2020
EDQ00099920070002 Appendix 10.9
CR 1635223 2020 NRC POV Inspection - Calculation 09/08/2020
EPMTSS100292 reference omission and input
clarification
CR 1636100 2020 POV NRC Inspection - Correct typographical 09/08/2020
error for Reference 3 on pdf page 730 (actual calcul
CR 1636444 2020 NRC POV Inspection - Document critical 09/14/2020
thinking associated with Section XI repairs
CR 1637673 2020 NRC POV Inspection - Additional 09/17/2020
Documentation of Critical Thinking for Section XI
Repairs.
CR 1638837 2020 NRC POV Inspection - MOV PV thrust test 09/21/2020
data for 1-FCV-1-51 suspected unreliable
CR 1639066 2020 NRC POV Inspection - missing 09/21/2020
evaluation/justification of not obtaining AF torque
values
CR 1639626 2020 NRC POV Inspection - QMDS requirements 09/23/2020
do not match Vendor Manual
CR 1639697 2020 NRC POV Inspection Performance Deficiency 09/24/2020
CR 1639749 2020 NRC POV Inspection - Delete o-ring 09/24/2020
replacement
Drawings 0-47W845-1 Mechanical Flow Diagram-Essential Raw Cooling Rev. 19
Water System
1-47A595-3 Set-Up Parameters for Air Operated Valves Setup Rev. 2
Box for 1-FCV-001-0022-T
1-47A8910-72-01 Mechanical Table of Motor-Operated Valve Rev. 3
Requirements
1071240-7 Solenoid Operated Valve Energize to Open (FC) - Rev. G
ON/OFF 2 1/2 - 4 Inch
1167E80 Motor Op Gate Valve, MOD 10000GM82FBB00B Rev. 903
2-47W813-1 Flow Diagram Reactor Coolant System Rev. 39
2607 Electrical Assy Rev. E
O-47W803-2 Rev. 9
Inspection Type Designation Description or Title Revision or
Procedure Date
Miscellaneous ESBU/WOG-96-022 Summary of January 4 & 5, 1996 Pressure Locking 01/19/1996
& Thermal Binding (PLTB) Task Team Meeting
(MUHP-6050)
SDD-N3-1-4002 Main Steam System Rev. 22
SDD-N3-15-4002 Steam Generator Blowdown System Unit 1 / Unit 2 Rev. 19
SDD-N3-3B-4002 Auxiliary Feedwater System Rev. 30
SDD-N3-68-4001 Reactor Coolant System Rev. 43
WB-DC-30-15 Motor Operated Valve Thermal Overload and Rev. 6
Torque Switch Bypass
WBN-SDD-N3-63-4001 Safety Injection System (Unit 1 / Unit 2) Rev. 36
WBN-SDD-N3-67-4002 Essential Raw Cooling Water System, System 67 Rev. 38
WBN-VTD-C994-0010 Equipment Inaccuracy Summary for Motor Rev. 7
Operated Valves
WBN-VTD-T020-0520 Target Rock Technical Manual for Calve Models Rev. 1
2AB-001-4BB, 82AB-001-5BB
WBN-VTD-T401-0010 Teledyne Test Services Quiklook II Valve Rev. 1
Diagnostic Test Equipment Description, Safety
Related Status, Accuracy & Calibration Periodicity
Summary
WBNEQ-MOV-003 Limitorque Actuators with Class B Motors Rev. 37
WBNEQ-SOL-002 Target Rock Solenoid Valves Rev. 40
WBNMEQ-001-53006 Mechanical Equipment Qualification Package Rev. 2
WOG-05-87 Addendum to Verification of Pressure Locking 02/28/2005
Analysis Program - PRESLOK (CN-SEE-01-141)
Procedures 0-TI-100.006 Inservice Testing Program Rev. 9
1-SI-1-906-A Main Steam Valves Position Indication Verification - Rev. 13
Train A
1-SI-3-902 Turbine Driven Auxiliary Feedwater Pump 1A-S Rev. 59
Quarterly Performance Test
2-SI-68-901-B Valve Full Stroke Exercising During Plant Rev. 3
Operation: Reactor Coolant B-Train
2-TRI-0-4 18 Month B Train MOV Thermal Overload Relay Rev. 7
Bypass Circuit Functional Test
DS-M18.2.21 Motor Operated Valve Thrust and Torque Rev. 25
Inspection Type Designation Description or Title Revision or
Procedure Date
Calculations
G-50 Torque, Thrust and Control Switch Settings for Rev. 12
Motor-Operated Valves
NPG-SPP-09.26.13 Air Operated Valve Program Rev. 0
NPG-SPP-09.26.14 Motor Operated Valve Program Rev. 4
Work Orders 114900760, 115264274,
116646007, 116986101,
117325065, 117404329,
117758092, 117625369,
117943531, 118294730,
118720661, 119064218,
119064767, 119473916,
119475391, 119526855,
119528673, 120241095,
20241347, 120295031,
20295726, 120498998,
20555952, 120557231,
20850611, 120850804,
21027350
9