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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
UNITED STATES NUCLEAR REGULATORY COMMISSION une 19, 2018
SUBJECT:
SEQUOYAH NUCLEAR PLANT - NRC EVALUATION OF CHANGES, TESTS, AND EXPERIMENTS REPORT NUMBER 05000327/2018010 AND 05000328/2018010
Dear Mr. Shea:
On June 8, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Sequoyah Nuclear Plant, Units 1 and 2, and the NRC inspectors discussed the results of this inspection with Chris Reneau and other members of your staff. The results of this inspection are documented in the enclosed report.
The NRC inspectors did not identify any finding or violation of more than minor significance.
This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely,
/RA/
Marvin D. Sykes, Chief Engineering Branch 1 Division of Reactor Safety Docket Nos. 50-327, 50-328 License Nos. DPR-77 and DPR-79
Enclosure:
Inspection Report 05000327/2018010 and 05000328/2018010
Inspection Report
Docket Numbers: 050000327, 05000328 License Numbers: DPR-77 and DPR-79 Report Numbers: 05000327/2018010, 05000328/2018010 Enterprise Identifier: I-2018-010-0009 Licensee: Tennessee Valley Authority Facility: Sequoyah Nuclear Plant Units 1 and 2 Location: Soddy Daisy, TN Inspection Dates: June 4-8, 2018 Inspectors: Bradley Davis, Reactor Inspector (Team Lead)
Marcus Riley, Reactor Inspector Nadiyah Morgan, Reactor Inspector Approved By: M. Sykes, Chief Engineering Branch 1 Division of Reactor Safety
Enclosure
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring Tennessee Valley
Authoritys performance by conducting a 10 CFR 50.59 inspection at Sequoyah 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.
No findings or more than minor violations were identified.
INSPECTION SCOPE
Inspections were conducted using the appropriate portions of the inspection procedure (IP) 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, conducted walkdowns and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
REACTOR SAFETY
71111.17T - Evaluations of Changes, Tests and Experiments
Main article: IP 71111.17
The inspectors evaluated the following samples for compliance with Title 10, Code of Federal Regulations (CFR) 50.59, Changes, tests, and experiments, from June 4, 2018, to June 8, 2018:
10 CFR 50.59 Evaluations - 71111.17T 1. Design Change Notice (DCN) 23343, Identify Design Basis Flood Barriers for the Shield Buildings 2. DCN 23779, West Main Steam Valve Vault Room Blowoff Panel Modification 3. DCN 23396, Issue Design Output Portion of the Emergency Operating Procedure Setpoint Calculation SQS20110 4. DCN 23538-02, Controls Upgrade for Main and Bypass Feedwater Regulating Valve 5. DCN 23364, Replace Obsolete parts of Exo Sensor Incore Thermocouple Monitoring System 6. DCN 23527, Replacement of 125V DC Vital Battery Charges II, III, and IV 10 CFR 50.59 Screening/Applicability Determinations - 71111.17T 7. DCN 23234, Replace Relief Valves for Essential Raw Cooling Water, Component Cooling, and Containment Spray Systems 8. DCN 23623, Degraded Non-Conforming Motor Operated Valve (MOV) Modifications -
Gears/Actuator/Motor/Cables Reroute
9. DCN 21192, Generic ASCO Solenoid Valve Replacement
10. DCN 22778-01, Install Motor Driven Auxiliary Feedwater Pump 1A-A Relief Valve (SQN-1-VLV-003-0908-A) and Motor Driven Auxiliary Feedwater Pump 18-B Relief Valve ( SQ N-1 -VL V-003-0909-B)11. DCN 22778-02, Install Turbine Driven Auxiliary Feedwater Pump 1A-S Relief Valve (SQN-1-VLV-003-0910)12. DCN 23353, Replacement of Penetration 1-PENE-302-0009-B and Removal from Equipment Qualification (EQ) Program of Penetrations 1-PENE-302-0226-S and 1-PENE-302-0040-S 13. DCN 23056, Mark Emergency Diesel Generator (EDG) Lube Oil Dipstick to Indicate 6-Day & 7-Day Volumes 14. DCN 21892-03, Install a Current Control Unit on 2-FSV-43-61 15. DCN 23270, Replace MOV Motors for 1-FCV-3-47, 1-FCV-3-87, 1-FCV-3-100 & 2-FCV-3-33 16. DCN 23372, Replace Unit 2 Pressurizer Heater Transformers 17. DCN 23609, Replacement of EQ Containment Sump Level Transmitters 18. DCN23733, Remove Crankcase Pressure Switch Trip Function from EDGs 1A-A, 1B-B, 2A-A, 2B-B
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On June 8, 2018, the inspectors presented the inspection results to Mr. Chris Reneau, and other members of the licensee staff.
DOCUMENTS REVIEWED
Procedures
IP-ENG-001, Nuclear Standard Design Process, Rev. 0
0-SI-SXV-000-264.0, Testing Setpoint of ASME Code Class 2 & 3 Safety and Relief Valves and
Vacuum Breakers, Rev. 15
0-AR-DG-1A-LCL, Diesel Generator 1A-A Local Panel, Rev. 22
0-SI-SLT-000-257.0, Type B Local Leak Rate Test, Rev. 15
ES-1.3, Transfer to RHR Containment Sump, Rev. 23
NPG-SPP-03.15, FSAR Management, Rev. 2
NPG-SPP-09.4, 10 CFR 50.59 Evaluations of Changes Tests and Experiments, Rev. 12
NPG-SPP-09.3, Plant Modifications and Engineering Change Control, Rev. 28
NPG-SPP-09.5, Temporary Modifications and Temporary Configuration Changes, Rev. 13
NPG-SPP-12.7, Computer Software Control, Rev. 8
Drawings
1,2-47W450-3, Mechanical - Essential Raw Cooling Water, Rev. 23
1,2-45N703-2, 125 VDC Vital Battery Board II Single Line - Sheet 2, Rev. 42
1,2-45N767-10, Schematic Alarm for Engine 1A1, Rev. 6
1,2-45N767-2, 6900V Diesel Generators Schematic Diagram - Sh 2, Rev. 35
1,2-45N767-9, Schematic Alarm for Engine 1A2, Rev. 8
1,2-47W803-1, Feedwater Flow Diagram, Rev. 116
1,2-47W881-5-1, Mechanical Flow Diagram Water Quality and Sampling System, Rev. 15
2-45N724-3, 6900V Shutdown Board 2A-A Single Line Wiring Diagrams, Rev. 28
Calculations
03D53EPMRJP030491, Documentation of Design Bases Review, Required Thrust Calc and
Valve and Actuator Capability Assessment for 1-FCV-03-047, Rev. 8
03D53EPMRJP030591, Documentation of Design Bases Review, Required Thrust Calc and
Valve and Actuator Capability Assessment for 1-FCV-03-087, Rev. 8
03D53EPMRJP030691, Documentation of Design Bases Review, Required Thrust Calc and
Valve and Actuator Capability Assessment for 1-FCV-03-100, Rev. 8
B87150730001, Purge Air Ductwork Qualification for Hydrostatic Pressure, Rev. 2
B8790051027, Compute the Blowout Capacity of Blowout Plugs in the West Steam Valve
Room, Rev. 1
B87900822005, Blow-out Plugs - West Main Steam Valve Room - Reliability Study of as Built
Condition and Mod. Recommendations
B87910809021, Dynamic Analysis of Blow-Away Roofs and Hatches of East and West Main
Steam Valve Vault Panels
B87930202006, Main Steam Valve Vault Subcompartment Pressure Analysis, Rev. 2
E31880203208, Shutdown Board 1A-A 480V Transformers (500KVA), Rev. 2
EDQ0000942016000322, Incore Thermal Monitoring System Software Quality Assurance
Documentation, Rev. 1
EDQ0002502013000067, 125V DC Vital Battery Charger I, II, III, IV - Power Relays, Rev. 1
MDQ0000032015000278, Auxiliary Feedwater Pump Alternative Min-flow Relief Valve Sizing,
Rev. 0
MDQ0000822014000219, Diesel Generator Lube Oil Volume for 6 and 7 Days of Operation,
Rev. 0
NDQ0063980038, RWST and Containment RHR Sump Safety and Operational Limits, RWST
Setpoint Required Accurary and LBLOCA Sump Minimum Levels, Rev. 17
OE2-DS196RP, Containment, Electrical Penetration Protection Analysis, Rev. 29
SQEQ-PENE-004, Westinghouse Canister Electrical Penetrations (LVP/C&I), Rev. 60
SQEQ-PENE-005, Conax Electrical Penetrations (LVP/C&I), Rev. 40
SQN-APS-003, 480VAC APS Class 1E Load Coordination Study, Rev. 100
SQN-CPS-051, Circuit Protection Device Evaluation, Rev. 65
SQN-EEB-MS-TI28-0010, Instrument Accuracy Calc 1-LT-63-176, 177, 178, 179 Containment
Sump Level Indication, Rev. 11
SQN-EEB-MS-TI28-0013, Instrument Accuracy Calc 1-LT-63-176, 177, 178, 179 Containment
Sump Switchover, Rev. 15
SQNETAPAC, Auxiliary Power System, Rev. 84
SQS20110, Emergency and Abnormal Operating Procedure Setpoints, Rev. 27
CRs (Condition Reports)
117027 934663
655763 1217684
Design Basis Documents
SQN-DC-V-13.9.8, Sequoyah Nuclear Plant - Auxiliary Feedwater System, Rev. 28
SQN-DC-V-13.9.9, Component Cooling Water System, Rev. 28
SQN-DC-V-21.0, Environmental Design, Rev. 27
SQN-DC-V-27.5, Containment Spray System, Rev. 18
SQN-DC-V-3.0, The Classification of Piping, Pumps, Valves, and Vessels, Rev. 21
Work Orders
05-780558-004 116690396 117918755
05-780558-003 117063742 117918862
113312349 117063744 117918863
113312355 117094249 117918865
113312383 117214605 118175904
114611700 117214614 118514454
115790860 117214618
116101146 117214627
Miscellaneous Documents
Critical Digital Review Fisher DVC6000 Series Digital Valve Controller for TVA 025-
N230353335, Rev. A
DG-E18.1.25, Digital System Develop System Development, Procurement, and Implementation,
Rev. 4
DS-E18.1.25.4, Design for Simple Digital Device Determination, Rev. 3
DS-E18.1.25.8, Cyber Hardening for Digital Devices, Rev. 1
Engineering Change Turnover Package for ECP 23234-07, Replace 1-VLV-067-01590A,
2/29/2015
Engineering Change Turnover Package for ECP 23623-04, RHR HTX B to SIS Pumps,
4/26/2018
EQ14-0774, Evaluation of Conduit Plug Kits and Materials, 2/2/2015
LTR-SCS-17-2, Sequoyah Units 1&2 Main Feedwater Valve Stroke Time Increase - NSSS
Design Transients and Plant Operability Evaluation, 1/6/2017
NPG-SPP-09.2, Equipment Environmental Qualification Program, Rev. 10
PIC 23687, Sleeve #106 Seal Detail Change, Rev. 0
SQN Auxiliary Feedwater System Feasibility Study for Min-Flow Design Pressure Increase,
11/11/2015
SQNEQ-XMTR-009, Rosemount Model 3155N Transmitters Tab D, Rev. 0
SS-E18.15.01, Requirement for Digital Systems (Real-Time Data Acquisition and Control
Computer Systems), Rev. 8
Triconex Approved Topical Report 7286-545-1-A, Rev. 4
Corrective Action Documents Written as a Result of the Inspection
CR 1421144, Vital Charger Maintenance Strategy Gap
CR 1421232, Drawing Note Discrepancy for Battery Charger Limiting Amperage
Enclosure