|
---|
Category:Inspection Report
MONTHYEARIR 05000327/20234422024-01-11011 January 2024 95001 Supplemental Inspection Report 05000327/2023442 and 05000328/2023442 and Follow-Up Assessment Letter IR 05000327/20234202023-11-28028 November 2023 Security Baseline Inspection Report 05000327/2023420 and 05000328/2023420 IR 05000327/20230032023-11-0303 November 2023 Integrated Inspection Report 05000327/2023003 and 05000328/2023003 IR 05000327/20230112023-10-16016 October 2023 Triennial Fire Protection Inspection Report 05000327/2023011 and 05000328/2023011 IR 05000327/20234032023-09-14014 September 2023 Cyber Security Inspection Report 05000327/2023403 and 05000328/2023403 (Cover Letter) IR 05000327/20230052023-08-29029 August 2023 Updated Inspection Plan for Sequoyah Nuclear Plant, Units 1 and 2 - Report 05000327/2023005 and 05000328/2023005 IR 05000327/20230022023-07-31031 July 2023 Integrated Inspection Report 05000327/2023002 and 05000328/2023002 IR 05000327/20230102023-07-20020 July 2023 Biennial Problem Identification and Resolution Inspection Report 05000327/2023010 and 05000328/2023010 ML23163A0392023-06-13013 June 2023 Notification of an NRC Fire Protection Team Inspection (FPTI) (NRC Inspection Report 05000327/2023011, 05000328/2023011) and Request for Information (RFI) IR 05000327/20233012023-05-15015 May 2023 NRC Operator License Examination Report 05000327/2023301 and 05000328/2023301 IR 05000327/20230012023-05-0202 May 2023 Integrated Inspection Report 05000327/2023001 and 05000328/2023001 and Exercise of Enforcement Discretion IR 05000327/20234412023-04-20020 April 2023 Final Significance Determination for a Security-Related Greater than Green Finding, Nov & Assessment Followup Letter, 05000327/2023441 & 05000328/2023441 IR 05000327/20234022023-04-13013 April 2023 Security Baseline Inspection Report 05000327/2023402 and 05000328/2023402 IR 05000327/20220062023-03-0101 March 2023 Annual Assessment Letter for Sequoyah Nuclear Plant, Units 1 and 2 Report 05000327/2022006 and 05000328/2022006 IR 05000327/20234402023-02-13013 February 2023 NRC Inspection Report 05000327/2023440 and 05000328/2023440; Preliminary Greater than Green and Apparent Violation Cover Letter IR 05000327/20220042023-02-10010 February 2023 Integrated Inspection Report 05000327/2022004 and 05000328/2022004 IR 05000327/20234012023-02-0606 February 2023 Security Baseline Inspection Report 05000327/2023401 and 05000328/2023401 IR 05000327/20224402023-01-17017 January 2023 Special Inspection Report 05000327/2022440 and 05000328/2022440 and Apparent Violation - Cover IR 05000327/20220032022-11-0707 November 2022 Integrated Inspection Report 05000327/2022003 and 05000328/2022003 IR 05000327/20224012022-10-18018 October 2022 Material Control and Accounting Program Inspection Report 05000327/2022401 and 05000328/2022401 IR 05000327/20220052022-08-30030 August 2022 Updated Inspection Plan for Sequoyah Nuclear Plant, Units 1 and 2 - Report 05000327 2022005 and 05000328 2022005 - Final IR 05000327/20220022022-08-0101 August 2022 Integrated Inspection Report 05000327 2022002 and 05000328 2022002 IR 05000327/20223012022-07-21021 July 2022 Operator License Examination Report 05000327/2022301 and 05000328/2022301 IR 05000327/20220012022-05-11011 May 2022 Integrated Inspection Report 05000327/2022001, 05000328/2022001 and 07200034/2010002 IR 05000327/20220102022-04-25025 April 2022 Design Basis Assurance Inspection (Teams) Inspection Report 05000327/2022010 and 05000328/2022010 IR 05000327/20224022022-03-28028 March 2022 Security Baseline Inspection Report 05000327/2022402 and 05000328/2022402 IR 05000327/20210062022-03-0202 March 2022 Annual Assessment Letter for Sequoyah Nuclear Plant, Units 1 and 2 - (Report No. 05000327/2021006 and 05000328/2021006) IR 05000327/20210042022-02-0707 February 2022 Integrated Inspection Report 05000327/2021004 and 05000328/2021004 IR 05000327/20210032021-11-10010 November 2021 Integrated Inspection Report 05000327/2021003 and 05000328/2021003 and Apparent Violation and Exercise of Enforcement Discretion IR 05000327/20210052021-08-18018 August 2021 Updated Inspection Plan for Sequoyah Nuclear Plant, Units 1 and 2 Report 05000327/2021005 and 05000328/2021005 IR 05000327/20210022021-07-27027 July 2021 Integrated Inspection Report 05000327/2021002 and 05000328/2021002 IR 05000327/20210112021-07-19019 July 2021 Biennial Problem Identification and Resolution Inspection Report 05000327/2021011 and 05000328/2021011 IR 05000327/20210012021-04-27027 April 2021 Integrated Inspection Report 05000327/2021001 and 05000328/2021001 IR 05000327/20210102021-04-21021 April 2021 NRC Inspection Report 05000327/2021010 and 05000328/2021010 IR 05000327/20214012021-04-21021 April 2021 NRC Inspection Report 05000327/2021401 and 05000328/2021401 (U) IR 05000327/20200062021-03-0303 March 2021 Annual Assessment Letter for Sequoyah Nuclear Plant, Units 1 and 2 - Report 05000327/2020006 and 05000328/2020006 IR 05000327/20200042021-01-29029 January 2021 Integrated Inspection Report 05000327/2020004 and 05000328/2020004 ML20321A2102020-11-20020 November 2020 Security Inspection Report 05000327/2020420 and 05000328/2020420 - Cover Letter IR 05000327/20204202020-11-20020 November 2020 Security Inspection Report 05000327/2020420 and 05000328/2020420 IR 05000327/20200032020-11-10010 November 2020 Integrated Inspection Report 05000327/2020003, 05000328/2020003 and 07200034/2020002 IR 05000327/20200122020-10-20020 October 2020 Plants - Triennial Fire Protection Inspection Report 05000327/2020012 and 05000328/2020012 IR 05000327/20204012020-09-21021 September 2020 Cyber Security Inspection Report 05000327-2020401 and 05000328-2020401 IR 05000327/20204022020-09-18018 September 2020 Regulatory Commission Security Baseline Inspection Report 05000327/2020402 and 05000328/2020402 IR 05000237/20203012020-08-27027 August 2020 NRC Initial License Examination Report 05000237/2020301; 05000249/2020301 IR 05000327/20200052020-08-18018 August 2020 Updated Inspection Plan for Sequoyah Nuclear Plant, Units 1 and 2 - Report 05000327/2020005 and 05000328/2020005 IR 05000327/20200022020-07-23023 July 2020 Integrated Inspection Report 05000327/2020002 and 05000328/2020002 IR 05000327/20200012020-05-0505 May 2020 Integrated Inspection Report 05000327/2020001 and 05000328/2020001 IR 05000327/20203012020-04-24024 April 2020 NRC Operator License Examination Report 05000327/2020301 and 05000328/2020301 IR 05000327/20200102020-04-21021 April 2020 Design Basis Assurance Inspection (Programs) Inspection Report 05000327/2020010 and 05000328/2020010 ML20086M0062020-03-26026 March 2020 Information Request for the Cyber Security Inspection and Notification to Perform Inspection 05000327/2020401 and 05000328/2020401 2024-01-11
[Table view] Category:Letter
MONTHYEARML24032A0202024-01-31031 January 2024 NPDES Biocide/Corrosion Treatment Plan Annual Report, Cy 2023 ML23319A2452024-01-29029 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 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 ML24018A0142024-01-17017 January 2024 Engine Systems, Inc., Report No. 10CFR21-0137, Rev. 1, 56913-EN 56913 ML24011A3182024-01-11011 January 2024 Submittal of Discharge Monitoring Report (Dmr), October 2023 ML24011A3172024-01-11011 January 2024 Submittal of Discharge Monitoring Report (Dmr), September 2023 ML24011A3202024-01-11011 January 2024 Submittal of Discharge Monitoring Report (Dmr), December 2023 ML24011A3162024-01-11011 January 2024 Submittal of Discharge Monitoring Report (Dmr), August 2023 ML24011A3192024-01-11011 January 2024 Submittal of Discharge Monitoring Report (Dmr), November 2023 IR 05000327/20234422024-01-11011 January 2024 95001 Supplemental Inspection Report 05000327/2023442 and 05000328/2023442 and Follow-Up Assessment Letter ML24010A2132024-01-10010 January 2024 CFR 21.21 Final Report Regarding Siemens Medium Voltage Circuit Breakers ML24018A0952024-01-0404 January 2024 Engine Systems, Inc., 10CFR21 Reporting of Defects and Non-Compliance Report No. 10CFR21-0137, Rev. 0 ML24004A0332024-01-0303 January 2024 Interim Report of a Deviation or Failure to Comply Crompton Instruments Type 077 Ammeter ML24004A0402024-01-0303 January 2024 Response to NRCs November 8, 2023, Request for Additional Information - Related to Independent Spent Fuel Storage Installation CNL-23-068, 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 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) ML23346A1222023-12-12012 December 2023 Annual Non-Radiological Environmental Operating Report - 2023 IR 05000327/20234202023-11-28028 November 2023 Security Baseline Inspection Report 05000327/2023420 and 05000328/2023420 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 ML23324A4362023-11-0909 November 2023 Exam Corporate Notification Letter Aka 210-day Letter ML23307A0822023-11-0808 November 2023 Request for Additional Information August 4, 2022, Exemption Request for Deviating from the Conditions of Certificate of Compliance No. 1032, Amendment No. 3, Related to Sequoyah Nuclear Plant Independent Spent Fuel Storage Installation IR 05000327/20230032023-11-0303 November 2023 Integrated Inspection Report 05000327/2023003 and 05000328/2023003 ML23306A1592023-11-0202 November 2023 Enforcement Action EA-22-129 Inspection Readiness Notification ML23292A0792023-10-19019 October 2023 Tennessee Valley Authority - Emergency Plan Implementing Procedure Revision, Includes EPIP-5, Revision 58, General Emergency IR 05000327/20230112023-10-16016 October 2023 Triennial Fire Protection Inspection Report 05000327/2023011 and 05000328/2023011 ML23285A0882023-10-12012 October 2023 Submittal of Sequoyah Nuclear Plant, Units 1 and 2, Submittal of Updated Final Safety Analysis Report Amendment 31 ML23284A4252023-10-11011 October 2023 10 CFR 50.59 and 10 CFR 72.48 Changes, Tests, and Experiments Summary Report; Commitment Summary Report; and Update to the Fire Protection Report ML23283A2792023-10-10010 October 2023 Revisions to the Sequoyah Nuclear Plant Units 1 and 2 Technical Requirements Manual ML23279A0612023-10-0505 October 2023 Paragon Energy Solutions LLC, Part 21 Final Report Re Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs) ML23277A0462023-10-0404 October 2023 Revisions to the Sequoyah Nuclear Plant Units 1 and 2 Technical Specification Bases ML23275A0272023-09-29029 September 2023 Submittal of Discharge Monitoring Report (DMR) Quality Assurance Study 43 Final Report 2023 ML23271A1662023-09-28028 September 2023 Registration of Spent Fuel Storage Cask Pursuant to 10 CFR 72.212(b)(2) 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 IR 05000327/20234032023-09-14014 September 2023 Cyber Security Inspection Report 05000327/2023403 and 05000328/2023403 (Cover Letter) ML23257A0062023-09-14014 September 2023 Enforcement Action EA-22-129 Inspection Postponement Request ML23254A2192023-09-11011 September 2023 Emergency Plan Implementing Procedure Revisions ML23254A0652023-09-0707 September 2023 Registration of Spent Fuel Storage Cask Pursuant to 10 CFR 72.212(b)(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 05000327/20230052023-08-29029 August 2023 Updated Inspection Plan for Sequoyah Nuclear Plant, Units 1 and 2 - Report 05000327/2023005 and 05000328/2023005 ML23233A0122023-08-17017 August 2023 Unit 1 Cycle 25 Refueling Outage - 90-Day Inservice Inspection Summary Report - Supplement ML23233A0142023-08-15015 August 2023 Discharge Monitoring Report (Dmr), July 2023 ML23215A1212023-08-0303 August 2023 301 Exam Administrative Items (2B) Normal Release ML23215A1572023-08-0303 August 2023 Enforcement Action EA-22-129 Inspection Readiness Notification 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 2024-01-04
[Table view] |
Text
{{#Wiki_filter:uly 23, 2020
SUBJECT:
SEQUOYAH, UNITS 1 AND 2 - INTEGRATED INSPECTION REPORT 05000327/2020002 AND 05000328/2020002
Dear Mr. Barstow:
On June 30, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Sequoyah, Units 1 and 2. On July 6, 2020, the NRC inspectors discussed the results of this inspection with Mr. Matt Rasmussen 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/
Thomas A. Stephen, Chief Reactor Projects Branch 5 Division of Reactor Projects Docket Nos. 05000327 and 05000328 License Nos. DPR-77 and DPR-79
Enclosure:
As stated
Inspection Report
Docket Numbers: 05000327 and 05000328 License Numbers: DPR-77 and DPR-79 Report Numbers: 05000327/2020002 and 05000328/2020002 Enterprise Identifier: I-2020-002-0064 Licensee: Tennessee Valley Authority Facility: Sequoyah, Units 1 and 2 Location: Soddy Daisy, TN 37379 Inspection Dates: April 1, 2020 to June 30, 2020 Inspectors: N. Childs, Resident Inspector P. Cooper, Reactor Inspector J. Diaz-Velez, Senior Health Physicist D. Hardage, Senior Resident Inspector J. Rivera, Health Physicist Approved By: Thomas A. Stephen, Chief Reactor Projects Branch 5 Division of Reactor Projects Enclosure
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Sequoyah, 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 Type Issue Number Title Report Section Status LER 05000327,05000328/20 LER 2019-004-00 for 71153 Closed 19-004-00 Sequoyah, Unit 1, Automatic Actuation of Emergency Diesel Generators Due to Loss of Power to 6.9kV Shutdown Board
PLANT STATUS
Unit 1 began the inspection period at 100 percent rated thermal power (RTP). On May 13, a turbine governor control system malfunction caused lowering main steam header pressure which initiated an automatic safety injection and reactor trip. The unit was returned to 100 percent RTP on May 17 and remained at or near 100 percent RTP for the remainder of the inspection period.
Unit 2 began the inspection period at 87 percent RTP due to end of life coastdown conditions.
On April 11, the unit was shutdown for refueling. The unit was returned to 100 percent RTP on May 5 and remained at or near 100 percent RTP for the remainder of the inspection period.
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors 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), resident inspectors were directed to begin telework and to remotely access licensee information using available technology. During this time the resident inspectors performed periodic site visits each week and during that time conducted plant status activities as described in IMC 2515, Appendix D; observed risk significant activities; and completed on site portions of IPs. In addition, resident and 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
71111.04 - Equipment Alignment Partial Walkdown Sample (IP Section 03.01)
Main article: IP 71111.04
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Unit 2 residual heat removal system with both trains in service for cooldown in Mode 5 with reactor coolant system level below the flange on April 13, 2020.
- (2) 2A emergency diesel generator following station blackout testing on April 20, 2020.
- (3) Unit 2 residual heat removal system after realignment for low head injection following refueling outage on May 4, 2020.
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated system configurations during a complete walkdown of the Unit 1 and Unit 2 Motor Driven Auxiliary Feedwater (AFW) on June 18 and June 25, 2020.
71111.05 - Fire Protection Fire Area Walkdown and Inspection Sample (IP Section 03.01)
Main article: IP 71111.05
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) Emergency Raw Cooling Water Building on April 6, 2020
- (2) Diesel Generator Building, Elevation 740.5 on April 20, 2020
- (3) Unit 1 and Unit 2 Auxiliary Building, Elevation 653 on May 4, 2020
- (4) Unit 1 and Unit 2 Control Building, Elevation 706 on May 21, 2020
- (5) Unit 2 Auxiliary Building (Non-RCA), Elevation 734 on May 21, 2020 Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated fire brigade performance on June 11, 2020.
71111.08P - Inservice Inspection Activities (PWR) PWR Inservice Inspection Activities Sample (IP Section 03.01)
Main article: IP 71111.08
- (1) The inspectors verified that the reactor coolant system boundary, steam generator tubes, reactor vessel internals, risk-significant piping system boundaries, and containment boundary are appropriately monitored for degradation and that repairs and replacements were appropriately fabricated, examined and accepted by reviewing the following activities:
03.01.a - Nondestructive Examination and Welding Activities.
- Ultrasonic Examination (UT), 3" Valve to Elbow, CVCF-213 , ASME Class 1, WO#119449412 (reviewed)
- Liquid Penetrant Examination (PT), 1" Pipe to Branch Connection, 2-FD-1609C4R0, ASME Class 2, weld package, WO#118769371 (reviewed)
- Enhanced Remote Visual (VE), RPV Closure Head and CRDM Penetration, WO#119809141. (reviewed)03.01.c - Pressurized-Water Reactor Boric Acid Corrosion Control Activities.
- Evaluation of 2-FCV-063-0158
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance Licensed Operator Requalification Training/Examinations (IP Section 03.02)
Main article: IP 71111.11Q
- (1) The inspectors observed and evaluated a simulator training scenario on June 8, 2020.
71111.12 - Maintenance Effectiveness Maintenance Effectiveness (IP Section 03.01)
Main article: IP 71111.12
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:
- (1) Part 21 Eval KCR-07 Battery Container Failure SQN Named (CR 1589441) .
- (2) 2-FCV-007-0003 Turbine Startup Drain Line Steam Break Failures (CR 1303568).
Quality Control (IP Section 03.02) (1 Sample)
The inspectors evaluated maintenance and quality control activities associated with the following equipment performance activity:
- (1) Quality critical maintenance to replace volume control tank (VCT) pressure transmitter 2-PT-62-122 (WO 120428331).
71111.13 - Maintenance Risk Assessments and Emergent Work Control Risk Assessment and Management Sample (IP Section 03.01)
Main article: IP 71111.13
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) Unit 1 and 2, week of April 5 - April 10 including protected equipment status reviews for scheduled maintenance on Unit 2 steam driven Auxiliary Feed Water (AFW) turbine trip and throttle valve and the 1A2 component cooling system heat exchanger.
- (2) Unit 2 Yellow shutdown risk week of April12-18 while reactor coolant system (RCS)level was below Reactor flange level and during Reactor core offload, including review of defense in depth protected equipment for U2R23.
- (3) Unit 2 Yellow shutdown risk week of April 19-24 while reactor coolant system (RCS)level was below Reactor flange level following core onload, including review of defense in depth protected equipment for U2R23.
71111.15 - Operability Determinations and Functionality Assessments Operability Determination or Functionality Assessment (IP Section 03.01)
Main article: IP 71111.15
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) MSIV 2-FCV-1-22, Steam Generator #3 Main Steam Header Isolation Valve, high friction after adjustment.
- (2) Foreign material found in Unit 2 Reactor Vessel Level Indication System (RVLIS) Line (CR 1600942).
- (3) 2-FCV-63-22 leaks by when indicating closed (CR 1603527).
- (4) Perform evaluation of 2-FSV-68-397, Reactor Head Vent Throttle Valve (CR
===1605225).
- (5) Centrifugal Charging Pump (CCP) Room Cooler Potential Design Basis Heat Load Issue (CR 1609392).
==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) Design Change Package 22703, Upgrade of the Turbine Driven Auxiliary Feedwater Speed Governor and Flow Controller.
71111.19 - Post-Maintenance Testing Post-Maintenance Test Sample (IP Section 03.01)
Main article: [[=
=IP 71111.18|count=4}}
The inspectors evaluated the following post maintenance test activities to verify system operability and functionality:
- (1) WO 120164119, repair 2-FCV-62-72-A, Regen Heat Exchanger Letdown Isolation Valve, due to local leak rate test failure, on April 12, 2020.
- (2) WO 115152446, Replace Power Operated Relief Valve (PORV) SQN-2- 068-0334B, on April 29, 2020.
- (3) WO 118769371, Replace SQN-2-VLV-002-0282A, on May 3, 2020.
- (4) WO 120418929, Replace TE-68-25A-E, RCS Loop 2 Hot Leg Resistance Temperature Detector (RTD), on May 4, 2020.
71111.20 - Refueling and Other Outage Activities Refueling/Other Outage Sample (IP Section 03.01)
Main article: IP 71111.20
- (1) The inspectors evaluated refueling outage U2R23 activities from April 10, 2020 to May 4, 2020.
71111.22 - Surveillance Testing The inspectors evaluated the following surveillance tests: Surveillance Tests (other) (IP Section 03.01)
Main article: IP 71111.22
- (1) 0-SI-OPS-082-026.A, Loss of Offsite Power With Safety Injection - D/G 2A-A Test on April 12, 2020.
- (2) 0-SI-SXV-068-201.0, Pressurizer PORV Operability Test performed prior to being required for LTOP on April 24, 2020.
Containment Isolation Valve Testing (IP Section 03.01) ===
- (1) 0-SI-SLT-062-258.1, Unit 2 - Containment Isolation Valve - Local Leak Rate Test Chemical and Volume Control System, on April 12, 2020.
Ice Condenser Testing (IP Section 03.01) (1 Sample)
- (1) 0-SI-MIN-061-105.0, Ice Condenser - Ice Weighing on April 22,
RADIATION SAFETY
71124.05 April 2020 - April 2020 Radiation Monitoring Instrumentation April 2020 Calibration and Testing Program (IP Section 03.02)
Main article: IP 71124.05
The inspectors evaluated the calibration and testing of the following radiation detection instruments:
- (1) Unit 1 Containment High Range Monitor 1-RE-90-271 (Upper Containment)
- (2) Unit 1 Containment High Range Monitor 1-RE-90-274 (Lower Containment)
- (3) Whole Body Counter, TVA No. 2
- (4) Perkin-Elmer Tri Carb Liquid Scintillation Counter No. 2203
- (5) Count Room Gamma Detector No. 2
- (6) ARGOS Personnel Contamination Monitor, TVA No. 951453
- (7) CRONOS Small Article Monitor, TVA No. 951456
- (8) GEM-5 Portal Monitor, TVA No. 18pm
- (9) Mirion Telepole, TVA No. 860096
- (10) Ludlum 12-4, TVA No. 860290
- (11) Thermo Radeye GX, TVA No. 951143
- (12) Mirion AMP-100, TVA No. 951485
- (13) DMC-3000 ED, TVA No. A0B724
- (14) AMS-4 Continuous Air Monitor, TVA No. 860272 April 2020 Effluent Monitoring Calibration and Testing Program Sample (IP Sample 03.03) (3 Samples)
The inspectors evaluated the calibration and maintenance of the following radioactive effluent monitoring and measurement instrumentation:
- (1) Auxiliary Building Vent Gaseous Radiation Monitor, 0-R-90-101B
- (2) Waste Disposal System Liquid Effluent Radiation Monitor, 0-R-90-122
- (3) Auxiliary Building Gas Treatment System Filter, Train A
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 (April 2019 - March 2020)
- (2) Unit 2 (April 2019 - March 2020)
IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02) (2 Samples)
- (1) Unit 1 (April 2019 - March 2020)
- (2) Unit 2 (April 2019 - March 2020)
IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03) (2 Samples)
- (1) Unit 1 (April 2019 - March 2020)
- (2) Unit 2 (April 2019 - March 2020)
71152 - Problem Identification and Resolution Semiannual Trend Review (IP Section 02.02)
- (1) The inspectors reviewed the licensees corrective action program for potential adverse trends in operationally impactful equipment failures that might be indicative of a more significant safety issue (CR 1573093).
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) Steam leak on turbine drain line results in reactor downpower (CR 1605906).
71153 - Followup of Events and Notices of Enforcement Discretion Event Followup (IP Section 03.01)
- (1) The inspectors evaluated Unit 1 reactor trip and safety injection and licensees response on May 13, 2020.
Event Report (IP Section 03.02) (1 Sample)
The inspectors evaluated the following licensee event reports (LERs):
- (1) LER 05000327/2019-004-00, Automatic Actuation of Emergency Diesel Generators Due to Loss of Power to 6.9kV Shutdown Board (ADAMS accession:
ML20044D623). The inspectors determined that it was not reasonable to foresee or correct the cause discussed in the LER therefore no performance deficiency was identified. The inspectors also concluded that no violation of NRC requirements occurred.
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On July 6, 2020, the inspectors presented the integrated inspection results to Mr. Matt Rasmussen and other members of the licensee staff.
- On April 29, 2020, the inspectors presented the Informal debrief with RP and Licensing for the completion of 2 out of 3 samples in IP 71124.05 (Covid-19 remote inspection).
Formal RP exit meeting with senior site management to be conducted when the last sample of the IP can be completed onsite. Inspection results were presented to Lee Baxley (Radiation Protection Manager) and Andrew McNeil (Licensing) and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection Type Designation Description or Title Revision or
Procedure Date
71111.04 Procedures 0- SI-OPS-082- Diesel Generator Operability Verification Revision 20
007.0
0-SO-74-1 Residual Heat Removal System Revision 107
0-SO-82-3 Diesel Generator 2A-A Revision 67
1,2-SO-3-2 Auxiliary Feedwater System Power Checklist
1,2-SO-3-2 Auxiliary Feedwater System Valve Checklist
71111.05 Corrective Action CR 1615936 Observations from the 6/11/20 SQN Fire Drill 06/11/2020
Documents CR 1617501 Fire Drills Lessons Learned 2nd Quarter 06/18/2020
Fire Plans AUX-0-653-00 Pre-Fire Plan Auxiliary Building, Elevation 653 Revision 9
AUX-0-734-01 Pre-Fire Plan Auxiliary Building, Elevation 734 (Unit 1 Non- Revision 8
RCA Side)
AUX-0-734-02 Pre-Fire Plan Auxiliary Building, Elevation 734 (Unit 2 Non- Revision 7
RCA Side)
CON-0-706-00 Pre-Fire Plan Control Building, Elevation 706 Revision 6
DGB-0-740.5-00 Pre-Fire Plan Diesel Generator Building, Elevation 740.5 Revision 6
ERCW-0-688-00 Pre-Fire Plan Essential Raw Cooling Water Pump Station, Revision 2
Elevation 688
ERCW-0-704-00 Pre-Fire Plan Essential Raw Cooling Water Pump Station, Revision 2
Elevation 704
ERCW-0-720-00 Pre-Fire Plan Essential Raw Cooling Water Pump Station, Revision 3
Elevation 720
Miscellaneous Fire Drill Evaluation Report - Yard Near Solar Building 05/07/2020
Procedures 0-PI-FPU-317- Fire Extinguisher Annual Inspection Revision 9
531.Y
71111.11Q Miscellaneous SEG Steam Generator Tube Rupture with loss of C-9 Interlock Revision 0
OPL273S2007
71111.12 Corrective Action CR 1303568 Unit 2 Turbine and Reactor Shutdown due main turbine drain 08/04/2017
Documents Equipment line steam break
Failure
Investigation
Inspection Type Designation Description or Title Revision or
Procedure Date
CR 1585280 Seven DG B Battery Cells Have Jar Cracks 02/07/2020
CR 1585746 Extent of Condition for BFN DG Battery Jar Cracking 02/10/2020
Miscellaneous CDE 2897 June 4, 2017 Failure of Turbine Startup Drain No. 3 Revision 1
CDE 2986 June 2, 2017 Failure of Turbine Startup Drain No. 3 Revision 1
TVA Central Lab Sequoyah Unit 2 Main Steam Drain Failures 06/20/2017
Technical Report
Procedures NPG-SPP- Quality Critical Maintenance Identification and Oversight Revision 6
07.2.16
TVA-NQA- Nuclear Quality Assurance Plan (NQAP) Quality Assurance Revision 38
PLN89-A Program Description
71111.13 Procedures 0-GO-16 System Operability Checklist Revision 25
71111.15 Drawings 2-47A595-3 Set-Up Parameters for Air Operated Valves, Setup Box for Revision 3
2-FCV-1-22
Engineering EWR-20-DEM- U2R23 MSIV 2-FCV-1-22 High Friction after Adjustment 04/26/2020
Evaluations 001069 Accept As Is Evaluation for CR 1603849
Operability Prompt Determination of Operability for CR 1609392, CCP 05/29/2020
Evaluations Room Cooler Design Basis Heat Load Issue
Procedures 2-PI-ICC-068-397 Channel Calibration of Reactor Vessel Vent Throttle Valve Revision 10
Loop 2-F-68-397 and Vent Valve 2-FSV-68-397
MMTP-154 Air Operated Valve Diagnostic Testing Revision 0
Work Orders WO 121314149 2-FSV-068-397 not operating properly 05/20/2020
71111.19 Procedures 0-SI-SXV-068- Pressurizer PORV Operability Test Revision 2
201.0
2-SI-ICC-068- Channel Calibration of Delta T/ Tave Channel II, Rack 6 Revision 25
25.2 Loop 2-T-68-25
2-SI-IFT-003- Functional Test of Environmental Allowance Monitor / Trip Revision 23
519.2 Time Delay Protection Set II
2-SI-IRT-099- Response Time Test of RTD's in Loops 2-T-68-2 and 2-T- Revision 11
13A.0 68-25 Using Analysis and Measurement Services
Techniques Cycle A
2-SI-SXI-068- Leakage Test of the Reactor Coolant Pressure Boundary Revision 16
201.0
Work Orders 121274792 Pen X-15 (Letdown) Failed As Found LLRT 04/20/2020
21282200 Troubleshoot and Increase Seating Load on 2-FCV-62-72-A 04/20/2020
Inspection Type Designation Description or Title Revision or
Procedure Date
71111.20 Miscellaneous Unit 2 Cycle 23 Outage Safety Plan Revision 0
SQN-2-130 Fuel Transfer Operation - U2R23 Core Offload Revision 0
SQN-2-134 Fuel Transfer Operation - Core Reload Revision 0
Procedures 0-GO-5 Normal Power Operation Revision 97
0-GO-6 Power Reduction from 30% Reactor Power to Hot Standby Revision 65
0-GO-7 Unit Shutdown from Hot Standby to Cold Shutdown Revision 88
0-SI-SXX-068- RCS and Pressurizer Temperature and Pressure Limits Revision 15
27.0
E-0 Reactor Trip or Safety Injection Revision 41
ES-0.1 Reactor Trip Response Revision 39
71111.22 Corrective Action CR 1600918 Pen X-15 (Letdown) Failed as found LLRT 04/12/2020
Documents CR 1605537 U2 Ice Condenser Frozen Basket Trend 05/03/2020
Miscellaneous 0-SI-SLT-062- Unit 2 - Containment Isolation Valve Local Leak Rate Test 04/30/2017
258.1 Chemical and Volume Control System, completed
performance
U2R23.OUT ICE, Computer Program Version SQ1.1 04/22/2020
NDE Reports 0-SI-SLT-0692- Unit 2 - Containment Isolation Valve Local Leak Rate Test 05/10/17
258.1 Chemical and Volume Control System, completed
performance
71124.05 Corrective Action CR 1554447 Upper Containment Rad Monitor drifting into alarm 10/03/2019
April 2020 Documents CR 1569547 FY19 Annual and 4th Quarter RP Instrument Performance 11/29/2019
Trend Review
CR 1580287 2-RE-90-130 failed to respond to source check 01/21/2020
Miscellaneous Sequoya Nuclear Offsite Dose Calculation Manual (ODCM) Rev. 0063
Plant
Procedures 0-TI-CEM-016- Shield Building Radiation Monitor Sampling Methods Rev. 0002
001.4
RCDP-8 Radiological Instrumentation/Equipment Controls Rev. 0008
RCI-05 Radiation Protection Instrumentation Program Rev. 0083
Self-Assessments SQN-RP-SA-18- Radiation Monitoring Instrumentation 10/12/2018
013
71152 Corrective Action CR 1605906 Steam Leak on Turbine Drain Line Results in Reactor 06/04/2020
Documents Level 2 Downpower
Evaluation Report
Inspection Type Designation Description or Title Revision or
Procedure Date
71153 Corrective Action CR 1115176 GR5 Relays from ABB have incorrect components 02/25/2016
Documents CR 1142038 Part 21 evaluation for ABB GR5 Relays 03/03/2016
CR 1573472 Loss of 1B-B Shutdown Board Offsite Power 12/16/2019
CR 1573726 250 VDC Station Battery system voltage excursion 12/16/2019
CR 1607726 Transient on Unit 1 Reactor Trip and Safety Injection 05/13/2020
13|=
=IP 71111.18|count=4}}
The inspectors evaluated the following post maintenance test activities to verify system operability and functionality:
- (1) WO 120164119, repair 2-FCV-62-72-A, Regen Heat Exchanger Letdown Isolation Valve, due to local leak rate test failure, on April 12, 2020.
- (2) WO 115152446, Replace Power Operated Relief Valve (PORV) SQN-2- 068-0334B, on April 29, 2020.
- (3) WO 118769371, Replace SQN-2-VLV-002-0282A, on May 3, 2020.
- (4) WO 120418929, Replace TE-68-25A-E, RCS Loop 2 Hot Leg Resistance Temperature Detector (RTD), on May 4, 2020.
71111.20 - Refueling and Other Outage Activities Refueling/Other Outage Sample (IP Section 03.01)
Main article: IP 71111.20
- (1) The inspectors evaluated refueling outage U2R23 activities from April 10, 2020 to May 4, 2020.
71111.22 - Surveillance Testing The inspectors evaluated the following surveillance tests: Surveillance Tests (other) (IP Section 03.01)
Main article: IP 71111.22
- (1) 0-SI-OPS-082-026.A, Loss of Offsite Power With Safety Injection - D/G 2A-A Test on April 12, 2020.
- (2) 0-SI-SXV-068-201.0, Pressurizer PORV Operability Test performed prior to being required for LTOP on April 24, 2020.
Containment Isolation Valve Testing (IP Section 03.01) ===
- (1) 0-SI-SLT-062-258.1, Unit 2 - Containment Isolation Valve - Local Leak Rate Test Chemical and Volume Control System, on April 12, 2020.
Ice Condenser Testing (IP Section 03.01) (1 Sample)
- (1) 0-SI-MIN-061-105.0, Ice Condenser - Ice Weighing on April 22,
RADIATION SAFETY
71124.05 April 2020 - April 2020 Radiation Monitoring Instrumentation April 2020 Calibration and Testing Program (IP Section 03.02)
Main article: IP 71124.05
The inspectors evaluated the calibration and testing of the following radiation detection instruments:
- (1) Unit 1 Containment High Range Monitor 1-RE-90-271 (Upper Containment)
- (2) Unit 1 Containment High Range Monitor 1-RE-90-274 (Lower Containment)
- (3) Whole Body Counter, TVA No. 2
- (4) Perkin-Elmer Tri Carb Liquid Scintillation Counter No. 2203
- (5) Count Room Gamma Detector No. 2
- (6) ARGOS Personnel Contamination Monitor, TVA No. 951453
- (7) CRONOS Small Article Monitor, TVA No. 951456
- (8) GEM-5 Portal Monitor, TVA No. 18pm
- (9) Mirion Telepole, TVA No. 860096
- (10) Ludlum 12-4, TVA No. 860290
- (11) Thermo Radeye GX, TVA No. 951143
- (12) Mirion AMP-100, TVA No. 951485
- (13) DMC-3000 ED, TVA No. A0B724
- (14) AMS-4 Continuous Air Monitor, TVA No. 860272 April 2020 Effluent Monitoring Calibration and Testing Program Sample (IP Sample 03.03) (3 Samples)
The inspectors evaluated the calibration and maintenance of the following radioactive effluent monitoring and measurement instrumentation:
- (1) Auxiliary Building Vent Gaseous Radiation Monitor, 0-R-90-101B
- (2) Waste Disposal System Liquid Effluent Radiation Monitor, 0-R-90-122
- (3) Auxiliary Building Gas Treatment System Filter, Train A
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 (April 2019 - March 2020)
- (2) Unit 2 (April 2019 - March 2020)
IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02) (2 Samples)
- (1) Unit 1 (April 2019 - March 2020)
- (2) Unit 2 (April 2019 - March 2020)
IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03) (2 Samples)
- (1) Unit 1 (April 2019 - March 2020)
- (2) Unit 2 (April 2019 - March 2020)
71152 - Problem Identification and Resolution Semiannual Trend Review (IP Section 02.02)
- (1) The inspectors reviewed the licensees corrective action program for potential adverse trends in operationally impactful equipment failures that might be indicative of a more significant safety issue (CR 1573093).
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) Steam leak on turbine drain line results in reactor downpower (CR 1605906).
71153 - Followup of Events and Notices of Enforcement Discretion Event Followup (IP Section 03.01)
- (1) The inspectors evaluated Unit 1 reactor trip and safety injection and licensees response on May 13, 2020.
Event Report (IP Section 03.02) (1 Sample)
The inspectors evaluated the following licensee event reports (LERs):
- (1) LER 05000327/2019-004-00, Automatic Actuation of Emergency Diesel Generators Due to Loss of Power to 6.9kV Shutdown Board (ADAMS accession:
ML20044D623). The inspectors determined that it was not reasonable to foresee or correct the cause discussed in the LER therefore no performance deficiency was identified. The inspectors also concluded that no violation of NRC requirements occurred.
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On July 6, 2020, the inspectors presented the integrated inspection results to Mr. Matt Rasmussen and other members of the licensee staff.
- On April 29, 2020, the inspectors presented the Informal debrief with RP and Licensing for the completion of 2 out of 3 samples in IP 71124.05 (Covid-19 remote inspection).
Formal RP exit meeting with senior site management to be conducted when the last sample of the IP can be completed onsite. Inspection results were presented to Lee Baxley (Radiation Protection Manager) and Andrew McNeil (Licensing) and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection Type Designation Description or Title Revision or
Procedure Date
71111.04 Procedures 0- SI-OPS-082- Diesel Generator Operability Verification Revision 20
007.0
0-SO-74-1 Residual Heat Removal System Revision 107
0-SO-82-3 Diesel Generator 2A-A Revision 67
1,2-SO-3-2 Auxiliary Feedwater System Power Checklist
1,2-SO-3-2 Auxiliary Feedwater System Valve Checklist
71111.05 Corrective Action CR 1615936 Observations from the 6/11/20 SQN Fire Drill 06/11/2020
Documents CR 1617501 Fire Drills Lessons Learned 2nd Quarter 06/18/2020
Fire Plans AUX-0-653-00 Pre-Fire Plan Auxiliary Building, Elevation 653 Revision 9
AUX-0-734-01 Pre-Fire Plan Auxiliary Building, Elevation 734 (Unit 1 Non- Revision 8
RCA Side)
AUX-0-734-02 Pre-Fire Plan Auxiliary Building, Elevation 734 (Unit 2 Non- Revision 7
RCA Side)
CON-0-706-00 Pre-Fire Plan Control Building, Elevation 706 Revision 6
DGB-0-740.5-00 Pre-Fire Plan Diesel Generator Building, Elevation 740.5 Revision 6
ERCW-0-688-00 Pre-Fire Plan Essential Raw Cooling Water Pump Station, Revision 2
Elevation 688
ERCW-0-704-00 Pre-Fire Plan Essential Raw Cooling Water Pump Station, Revision 2
Elevation 704
ERCW-0-720-00 Pre-Fire Plan Essential Raw Cooling Water Pump Station, Revision 3
Elevation 720
Miscellaneous Fire Drill Evaluation Report - Yard Near Solar Building 05/07/2020
Procedures 0-PI-FPU-317- Fire Extinguisher Annual Inspection Revision 9
531.Y
71111.11Q Miscellaneous SEG Steam Generator Tube Rupture with loss of C-9 Interlock Revision 0
OPL273S2007
71111.12 Corrective Action CR 1303568 Unit 2 Turbine and Reactor Shutdown due main turbine drain 08/04/2017
Documents Equipment line steam break
Failure
Investigation
Inspection Type Designation Description or Title Revision or
Procedure Date
CR 1585280 Seven DG B Battery Cells Have Jar Cracks 02/07/2020
CR 1585746 Extent of Condition for BFN DG Battery Jar Cracking 02/10/2020
Miscellaneous CDE 2897 June 4, 2017 Failure of Turbine Startup Drain No. 3 Revision 1
CDE 2986 June 2, 2017 Failure of Turbine Startup Drain No. 3 Revision 1
TVA Central Lab Sequoyah Unit 2 Main Steam Drain Failures 06/20/2017
Technical Report
Procedures NPG-SPP- Quality Critical Maintenance Identification and Oversight Revision 6
07.2.16
TVA-NQA- Nuclear Quality Assurance Plan (NQAP) Quality Assurance Revision 38
PLN89-A Program Description
71111.13 Procedures 0-GO-16 System Operability Checklist Revision 25
71111.15 Drawings 2-47A595-3 Set-Up Parameters for Air Operated Valves, Setup Box for Revision 3
2-FCV-1-22
Engineering EWR-20-DEM- U2R23 MSIV 2-FCV-1-22 High Friction after Adjustment 04/26/2020
Evaluations 001069 Accept As Is Evaluation for CR 1603849
Operability Prompt Determination of Operability for CR 1609392, CCP 05/29/2020
Evaluations Room Cooler Design Basis Heat Load Issue
Procedures 2-PI-ICC-068-397 Channel Calibration of Reactor Vessel Vent Throttle Valve Revision 10
Loop 2-F-68-397 and Vent Valve 2-FSV-68-397
MMTP-154 Air Operated Valve Diagnostic Testing Revision 0
Work Orders WO 121314149 2-FSV-068-397 not operating properly 05/20/2020
71111.19 Procedures 0-SI-SXV-068- Pressurizer PORV Operability Test Revision 2
201.0
2-SI-ICC-068- Channel Calibration of Delta T/ Tave Channel II, Rack 6 Revision 25
25.2 Loop 2-T-68-25
2-SI-IFT-003- Functional Test of Environmental Allowance Monitor / Trip Revision 23
519.2 Time Delay Protection Set II
2-SI-IRT-099- Response Time Test of RTD's in Loops 2-T-68-2 and 2-T- Revision 11
13A.0 68-25 Using Analysis and Measurement Services
Techniques Cycle A
2-SI-SXI-068- Leakage Test of the Reactor Coolant Pressure Boundary Revision 16
201.0
Work Orders 121274792 Pen X-15 (Letdown) Failed As Found LLRT 04/20/2020
21282200 Troubleshoot and Increase Seating Load on 2-FCV-62-72-A 04/20/2020
Inspection Type Designation Description or Title Revision or
Procedure Date
71111.20 Miscellaneous Unit 2 Cycle 23 Outage Safety Plan Revision 0
SQN-2-130 Fuel Transfer Operation - U2R23 Core Offload Revision 0
SQN-2-134 Fuel Transfer Operation - Core Reload Revision 0
Procedures 0-GO-5 Normal Power Operation Revision 97
0-GO-6 Power Reduction from 30% Reactor Power to Hot Standby Revision 65
0-GO-7 Unit Shutdown from Hot Standby to Cold Shutdown Revision 88
0-SI-SXX-068- RCS and Pressurizer Temperature and Pressure Limits Revision 15
27.0
E-0 Reactor Trip or Safety Injection Revision 41
ES-0.1 Reactor Trip Response Revision 39
71111.22 Corrective Action CR 1600918 Pen X-15 (Letdown) Failed as found LLRT 04/12/2020
Documents CR 1605537 U2 Ice Condenser Frozen Basket Trend 05/03/2020
Miscellaneous 0-SI-SLT-062- Unit 2 - Containment Isolation Valve Local Leak Rate Test 04/30/2017
258.1 Chemical and Volume Control System, completed
performance
U2R23.OUT ICE, Computer Program Version SQ1.1 04/22/2020
NDE Reports 0-SI-SLT-0692- Unit 2 - Containment Isolation Valve Local Leak Rate Test 05/10/17
258.1 Chemical and Volume Control System, completed
performance
71124.05 Corrective Action CR 1554447 Upper Containment Rad Monitor drifting into alarm 10/03/2019
April 2020 Documents CR 1569547 FY19 Annual and 4th Quarter RP Instrument Performance 11/29/2019
Trend Review
CR 1580287 2-RE-90-130 failed to respond to source check 01/21/2020
Miscellaneous Sequoya Nuclear Offsite Dose Calculation Manual (ODCM) Rev. 0063
Plant
Procedures 0-TI-CEM-016- Shield Building Radiation Monitor Sampling Methods Rev. 0002
001.4
RCDP-8 Radiological Instrumentation/Equipment Controls Rev. 0008
RCI-05 Radiation Protection Instrumentation Program Rev. 0083
Self-Assessments SQN-RP-SA-18- Radiation Monitoring Instrumentation 10/12/2018
013
71152 Corrective Action CR 1605906 Steam Leak on Turbine Drain Line Results in Reactor 06/04/2020
Documents Level 2 Downpower
Evaluation Report
Inspection Type Designation Description or Title Revision or
Procedure Date
71153 Corrective Action CR 1115176 GR5 Relays from ABB have incorrect components 02/25/2016
Documents CR 1142038 Part 21 evaluation for ABB GR5 Relays 03/03/2016
CR 1573472 Loss of 1B-B Shutdown Board Offsite Power 12/16/2019
CR 1573726 250 VDC Station Battery system voltage excursion 12/16/2019
CR 1607726 Transient on Unit 1 Reactor Trip and Safety Injection 05/13/2020
13]] [[IP sample::=
=IP 71111.18|count=4}}
The inspectors evaluated the following post maintenance test activities to verify system operability and functionality:
- (1) WO 120164119, repair 2-FCV-62-72-A, Regen Heat Exchanger Letdown Isolation Valve, due to local leak rate test failure, on April 12, 2020.
- (2) WO 115152446, Replace Power Operated Relief Valve (PORV) SQN-2- 068-0334B, on April 29, 2020.
- (3) WO 118769371, Replace SQN-2-VLV-002-0282A, on May 3, 2020.
- (4) WO 120418929, Replace TE-68-25A-E, RCS Loop 2 Hot Leg Resistance Temperature Detector (RTD), on May 4, 2020.
71111.20 - Refueling and Other Outage Activities Refueling/Other Outage Sample (IP Section 03.01)
Main article: IP 71111.20
- (1) The inspectors evaluated refueling outage U2R23 activities from April 10, 2020 to May 4, 2020.
71111.22 - Surveillance Testing The inspectors evaluated the following surveillance tests: Surveillance Tests (other) (IP Section 03.01)
Main article: IP 71111.22
- (1) 0-SI-OPS-082-026.A, Loss of Offsite Power With Safety Injection - D/G 2A-A Test on April 12, 2020.
- (2) 0-SI-SXV-068-201.0, Pressurizer PORV Operability Test performed prior to being required for LTOP on April 24, 2020.
Containment Isolation Valve Testing (IP Section 03.01) ===
- (1) 0-SI-SLT-062-258.1, Unit 2 - Containment Isolation Valve - Local Leak Rate Test Chemical and Volume Control System, on April 12, 2020.
Ice Condenser Testing (IP Section 03.01) (1 Sample)
- (1) 0-SI-MIN-061-105.0, Ice Condenser - Ice Weighing on April 22,
RADIATION SAFETY
71124.05 April 2020 - April 2020 Radiation Monitoring Instrumentation April 2020 Calibration and Testing Program (IP Section 03.02)
Main article: IP 71124.05
The inspectors evaluated the calibration and testing of the following radiation detection instruments:
- (1) Unit 1 Containment High Range Monitor 1-RE-90-271 (Upper Containment)
- (2) Unit 1 Containment High Range Monitor 1-RE-90-274 (Lower Containment)
- (3) Whole Body Counter, TVA No. 2
- (4) Perkin-Elmer Tri Carb Liquid Scintillation Counter No. 2203
- (5) Count Room Gamma Detector No. 2
- (6) ARGOS Personnel Contamination Monitor, TVA No. 951453
- (7) CRONOS Small Article Monitor, TVA No. 951456
- (8) GEM-5 Portal Monitor, TVA No. 18pm
- (9) Mirion Telepole, TVA No. 860096
- (10) Ludlum 12-4, TVA No. 860290
- (11) Thermo Radeye GX, TVA No. 951143
- (12) Mirion AMP-100, TVA No. 951485
- (13) DMC-3000 ED, TVA No. A0B724
- (14) AMS-4 Continuous Air Monitor, TVA No. 860272 April 2020 Effluent Monitoring Calibration and Testing Program Sample (IP Sample 03.03) (3 Samples)
The inspectors evaluated the calibration and maintenance of the following radioactive effluent monitoring and measurement instrumentation:
- (1) Auxiliary Building Vent Gaseous Radiation Monitor, 0-R-90-101B
- (2) Waste Disposal System Liquid Effluent Radiation Monitor, 0-R-90-122
- (3) Auxiliary Building Gas Treatment System Filter, Train A
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 (April 2019 - March 2020)
- (2) Unit 2 (April 2019 - March 2020)
IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02) (2 Samples)
- (1) Unit 1 (April 2019 - March 2020)
- (2) Unit 2 (April 2019 - March 2020)
IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03) (2 Samples)
- (1) Unit 1 (April 2019 - March 2020)
- (2) Unit 2 (April 2019 - March 2020)
71152 - Problem Identification and Resolution Semiannual Trend Review (IP Section 02.02)
- (1) The inspectors reviewed the licensees corrective action program for potential adverse trends in operationally impactful equipment failures that might be indicative of a more significant safety issue (CR 1573093).
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) Steam leak on turbine drain line results in reactor downpower (CR 1605906).
71153 - Followup of Events and Notices of Enforcement Discretion Event Followup (IP Section 03.01)
- (1) The inspectors evaluated Unit 1 reactor trip and safety injection and licensees response on May 13, 2020.
Event Report (IP Section 03.02) (1 Sample)
The inspectors evaluated the following licensee event reports (LERs):
- (1) LER 05000327/2019-004-00, Automatic Actuation of Emergency Diesel Generators Due to Loss of Power to 6.9kV Shutdown Board (ADAMS accession:
ML20044D623). The inspectors determined that it was not reasonable to foresee or correct the cause discussed in the LER therefore no performance deficiency was identified. The inspectors also concluded that no violation of NRC requirements occurred.
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On July 6, 2020, the inspectors presented the integrated inspection results to Mr. Matt Rasmussen and other members of the licensee staff.
- On April 29, 2020, the inspectors presented the Informal debrief with RP and Licensing for the completion of 2 out of 3 samples in IP 71124.05 (Covid-19 remote inspection).
Formal RP exit meeting with senior site management to be conducted when the last sample of the IP can be completed onsite. Inspection results were presented to Lee Baxley (Radiation Protection Manager) and Andrew McNeil (Licensing) and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection Type Designation Description or Title Revision or
Procedure Date
71111.04 Procedures 0- SI-OPS-082- Diesel Generator Operability Verification Revision 20
007.0
0-SO-74-1 Residual Heat Removal System Revision 107
0-SO-82-3 Diesel Generator 2A-A Revision 67
1,2-SO-3-2 Auxiliary Feedwater System Power Checklist
1,2-SO-3-2 Auxiliary Feedwater System Valve Checklist
71111.05 Corrective Action CR 1615936 Observations from the 6/11/20 SQN Fire Drill 06/11/2020
Documents CR 1617501 Fire Drills Lessons Learned 2nd Quarter 06/18/2020
Fire Plans AUX-0-653-00 Pre-Fire Plan Auxiliary Building, Elevation 653 Revision 9
AUX-0-734-01 Pre-Fire Plan Auxiliary Building, Elevation 734 (Unit 1 Non- Revision 8
RCA Side)
AUX-0-734-02 Pre-Fire Plan Auxiliary Building, Elevation 734 (Unit 2 Non- Revision 7
RCA Side)
CON-0-706-00 Pre-Fire Plan Control Building, Elevation 706 Revision 6
DGB-0-740.5-00 Pre-Fire Plan Diesel Generator Building, Elevation 740.5 Revision 6
ERCW-0-688-00 Pre-Fire Plan Essential Raw Cooling Water Pump Station, Revision 2
Elevation 688
ERCW-0-704-00 Pre-Fire Plan Essential Raw Cooling Water Pump Station, Revision 2
Elevation 704
ERCW-0-720-00 Pre-Fire Plan Essential Raw Cooling Water Pump Station, Revision 3
Elevation 720
Miscellaneous Fire Drill Evaluation Report - Yard Near Solar Building 05/07/2020
Procedures 0-PI-FPU-317- Fire Extinguisher Annual Inspection Revision 9
531.Y
71111.11Q Miscellaneous SEG Steam Generator Tube Rupture with loss of C-9 Interlock Revision 0
OPL273S2007
71111.12 Corrective Action CR 1303568 Unit 2 Turbine and Reactor Shutdown due main turbine drain 08/04/2017
Documents Equipment line steam break
Failure
Investigation
Inspection Type Designation Description or Title Revision or
Procedure Date
CR 1585280 Seven DG B Battery Cells Have Jar Cracks 02/07/2020
CR 1585746 Extent of Condition for BFN DG Battery Jar Cracking 02/10/2020
Miscellaneous CDE 2897 June 4, 2017 Failure of Turbine Startup Drain No. 3 Revision 1
CDE 2986 June 2, 2017 Failure of Turbine Startup Drain No. 3 Revision 1
TVA Central Lab Sequoyah Unit 2 Main Steam Drain Failures 06/20/2017
Technical Report
Procedures NPG-SPP- Quality Critical Maintenance Identification and Oversight Revision 6
07.2.16
TVA-NQA- Nuclear Quality Assurance Plan (NQAP) Quality Assurance Revision 38
PLN89-A Program Description
71111.13 Procedures 0-GO-16 System Operability Checklist Revision 25
71111.15 Drawings 2-47A595-3 Set-Up Parameters for Air Operated Valves, Setup Box for Revision 3
2-FCV-1-22
Engineering EWR-20-DEM- U2R23 MSIV 2-FCV-1-22 High Friction after Adjustment 04/26/2020
Evaluations 001069 Accept As Is Evaluation for CR 1603849
Operability Prompt Determination of Operability for CR 1609392, CCP 05/29/2020
Evaluations Room Cooler Design Basis Heat Load Issue
Procedures 2-PI-ICC-068-397 Channel Calibration of Reactor Vessel Vent Throttle Valve Revision 10
Loop 2-F-68-397 and Vent Valve 2-FSV-68-397
MMTP-154 Air Operated Valve Diagnostic Testing Revision 0
Work Orders WO 121314149 2-FSV-068-397 not operating properly 05/20/2020
71111.19 Procedures 0-SI-SXV-068- Pressurizer PORV Operability Test Revision 2
201.0
2-SI-ICC-068- Channel Calibration of Delta T/ Tave Channel II, Rack 6 Revision 25
25.2 Loop 2-T-68-25
2-SI-IFT-003- Functional Test of Environmental Allowance Monitor / Trip Revision 23
519.2 Time Delay Protection Set II
2-SI-IRT-099- Response Time Test of RTD's in Loops 2-T-68-2 and 2-T- Revision 11
13A.0 68-25 Using Analysis and Measurement Services
Techniques Cycle A
2-SI-SXI-068- Leakage Test of the Reactor Coolant Pressure Boundary Revision 16
201.0
Work Orders 121274792 Pen X-15 (Letdown) Failed As Found LLRT 04/20/2020
21282200 Troubleshoot and Increase Seating Load on 2-FCV-62-72-A 04/20/2020
Inspection Type Designation Description or Title Revision or
Procedure Date
71111.20 Miscellaneous Unit 2 Cycle 23 Outage Safety Plan Revision 0
SQN-2-130 Fuel Transfer Operation - U2R23 Core Offload Revision 0
SQN-2-134 Fuel Transfer Operation - Core Reload Revision 0
Procedures 0-GO-5 Normal Power Operation Revision 97
0-GO-6 Power Reduction from 30% Reactor Power to Hot Standby Revision 65
0-GO-7 Unit Shutdown from Hot Standby to Cold Shutdown Revision 88
0-SI-SXX-068- RCS and Pressurizer Temperature and Pressure Limits Revision 15
27.0
E-0 Reactor Trip or Safety Injection Revision 41
ES-0.1 Reactor Trip Response Revision 39
71111.22 Corrective Action CR 1600918 Pen X-15 (Letdown) Failed as found LLRT 04/12/2020
Documents CR 1605537 U2 Ice Condenser Frozen Basket Trend 05/03/2020
Miscellaneous 0-SI-SLT-062- Unit 2 - Containment Isolation Valve Local Leak Rate Test 04/30/2017
258.1 Chemical and Volume Control System, completed
performance
U2R23.OUT ICE, Computer Program Version SQ1.1 04/22/2020
NDE Reports 0-SI-SLT-0692- Unit 2 - Containment Isolation Valve Local Leak Rate Test 05/10/17
258.1 Chemical and Volume Control System, completed
performance
71124.05 Corrective Action CR 1554447 Upper Containment Rad Monitor drifting into alarm 10/03/2019
April 2020 Documents CR 1569547 FY19 Annual and 4th Quarter RP Instrument Performance 11/29/2019
Trend Review
CR 1580287 2-RE-90-130 failed to respond to source check 01/21/2020
Miscellaneous Sequoya Nuclear Offsite Dose Calculation Manual (ODCM) Rev. 0063
Plant
Procedures 0-TI-CEM-016- Shield Building Radiation Monitor Sampling Methods Rev. 0002
001.4
RCDP-8 Radiological Instrumentation/Equipment Controls Rev. 0008
RCI-05 Radiation Protection Instrumentation Program Rev. 0083
Self-Assessments SQN-RP-SA-18- Radiation Monitoring Instrumentation 10/12/2018
013
71152 Corrective Action CR 1605906 Steam Leak on Turbine Drain Line Results in Reactor 06/04/2020
Documents Level 2 Downpower
Evaluation Report
Inspection Type Designation Description or Title Revision or
Procedure Date
71153 Corrective Action CR 1115176 GR5 Relays from ABB have incorrect components 02/25/2016
Documents CR 1142038 Part 21 evaluation for ABB GR5 Relays 03/03/2016
CR 1573472 Loss of 1B-B Shutdown Board Offsite Power 12/16/2019
CR 1573726 250 VDC Station Battery system voltage excursion 12/16/2019
CR 1607726 Transient on Unit 1 Reactor Trip and Safety Injection 05/13/2020
13| ]]