IR 05000327/2019010
| ML19115A223 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 04/25/2019 |
| From: | Jonathan Montgomery NRC/RGN-II/DRS/EB1 |
| To: | James Shea Tennessee Valley Authority |
| References | |
| IR 2019010 | |
| Download: ML19115A223 (22) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION ril 25, 2019
SUBJECT:
SEQUOYAH NUCLEAR PLANT - NRC DESIGN BASES ASSURANCE INSPECTION (TEAM) REPORT 05000327/2019010 AND 05000328/2019010
Dear Mr. Shea:
On March 14, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Sequoyah Nuclear Plant Units 1 and 2, and discussed the results of this inspection with Mr. Matt Rasmussen and other members of your staff. On April 10, 2019, the NRC inspectors discussed the final results of this inspection with Mr. Jonathan Johnson and other members of your staff. The results of this inspection are documented in the enclosed report.
NRC inspectors documented one finding of very low safety significance (Green) in this report.
This finding involved a violation of NRC requirements.
If you contest the violation or significance or severity of the violation documented in this inspection report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN:
Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region II; the Director, Office of Enforcement; and the NRC resident inspector at Sequoyah.
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/
Jonathan M. Montgomery, Acting Chief Engineering Branch 1 Division of Reactor Safety Docket Nos.: 05000327 and 05000328 License Nos.: DPR-77 and DPR-79
Enclosure:
Inspection Report 05000327/2019010 and 05000328/2019010
Inspection Report
Docket Number(s): 05000327 and 05000328 License Number(s): DPR-77 and DPR-79 Report Number(s): 05000327/2019010 and 05000328/2019010 Enterprise Identifier: I-2019-010-0025 Licensee: Tennessee Valley Authority Facility: Sequoyah Nuclear Plant, Units 1 and 2 Location: Chattanooga, TN 37402 Inspection Dates: February 25, 2019, to March 14, 2019 Inspectors: C. Franklin, Reactor Inspector M. Greenleaf, Reactor Inspector R. Patterson, Reactor Inspector E. Stamm, Senior Reactor Inspector M. Yeminy, NRC Contractor H. Leake, NRC Contractor Approved By: Jonathan M. Montgomery, Acting 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 Bases Assurance 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. Findings and violations being considered in the NRCs assessment are summarized in the table below.
List of Findings and Violations Failure to Demonstrate AC Power System Calculations Conform to Design Bases Cornerstone Significance Cross-cutting Report Aspect Section Mitigating Green None 71111.21M Systems NCV 05000327,05000328/2019010-01 Closed The inspectors identified a Green finding and associated Non-cited Violation (NCV) of Title 10 of the Code of Federal Regulations, Part 50, Appendix B, Criterion III, Design Control, for the licensee's failure to verify or check the adequacy of design of the AC power system.
INSPECTION SCOPE
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.
REACTOR SAFETY
===71111.21M - Design Bases Assurance Inspection (Teams)
The inspectors evaluated the following components with listed applicable attributes, permanent modifications, and operating experience:
Design Review - Large Early Release Frequency (LERFs) (IP Section 02.02) ===
Unit 2 Pressurizer Power Operated Relief Valves [2-PCV-068-0340A-A, 0334-B]
- Compliance with the Updated Final Safety Analysis Report (UFSAR),
Technical Specifications (TS), and Technical Requirements Manual (TRM)
- Adequacy of design and licensing documents
- Adequacy of operating procedures
- Adequacy of recent modifications
- System health reports accurately reflect system health
- Translation of vendor specifications
- Design verification of control logic for automatic functions Design Review - Risk-Significant/Low Design Margin Components (IP Section 02.02) (5 Samples)
- (1) Unit 0 Emergency Raw Cooling Water Travelling Water Screens [0-SCN-067-0471, 475, 480, 485]
- Accuracy of design and licensing basis documents
- Material condition and configuration
- Adequacy of the operating procedures
- Adequacy of corrective actions
- Surveillance testing satisfies all essential parameters
- Backwash pump and traveling screen preventive and corrective maintenance is adequate to maintain required availability
- Compliance with vendor instructions for installation, maintenance, and operation of the pumps
- Adequacy of recent modifications
- System Health Reports accurately reflect system health
- Adequacy of internal flood evaluations
- (2) Unit 1 6900V Shutdown Board 1A-A [1-BDA-202-CM-A]
- Compliance with UFSAR, TS, and TS Bases
- Adequacy of maintenance and corrective action activities
- Material condition and configuration
- Design requirements (Voltage, Current, etc.)
- Coordination and relaying
- Design verification of bounding design basis events, including fast bus transfer between offsite power sources
- (3) Unit 2 Charging Pump 2A-A/Room Cooler [2-PMP-062-0108, 2-CLR-030-0183]
- Accuracy of design and licensing basis documents
- Material condition and configuration
- Adequacy of the operating procedures
- Adequacy of corrective actions
- Adequate net positive suction head (NPSH) and available margin
- Sufficient pump head and flow rate to account for all scenarios
- Surveillance testing satisfies all essential parameters
- Pump preventive and corrective maintenance is adequate to maintain required availability
- Room heat load vs cooling capacity to maintain maximum allowable room temperature
- Impact of turbine building environment on room temperature
- Single failure criterion for room cooling
- Compliance with vendor instructions for installation, maintenance, and operation of the pumps
- Adequacy of recent modifications
- Adequate calculations of pump minimum flow and NPSH (for all sources of suction)
- System Health Reports accurately reflect system health
- (4) Unit 1 Refueling Water Storage Tank (RWST) Level Transmitters [1-LT-063-0050-D, -
0051-E, 0052-F, 0053-G]
- Compliance with UFSAR and TS
- Accuracy of design and licensing basis documents
- Adequacy of corrective actions
- Consistency of tank and transmitter design drawings with design bases
- Effectiveness of emergency operating procedures, including time-critical operator actions associated with RWST outlet valve failure to close
- Capability of design, including calculations for instrumentation setpoints and uncertainties, tank capacity, vortexing limits, pump flow rates, and RWST inventory depletion during time-critical actions
- Adequacy of required completion times for automatic and manual switchover from the RWST to the containment sump during safety injection
- (5) Unit 2 Steam Generator Level Control Valves [2-LCV-003-148-B, -156-A]
- Accuracy of design and licensing documents
- Adequacy of operating procedures
- Capability to adequately control flow rate to the steam generators
- Adequacy of corrective actions
- Compliance with vendor instructions
- Adequacy of recent modifications
- System health reports accurately reflect system health Modification Review - Permanent Mods (IP Section 02.03) (4 Samples)
- (1) Replacement of 125V DC Vital Battery Charger I [DCN 23209]
- (2) Degraded Non-Conforming MOV Modifications [DCN 23623]
- (3) Replace 8 EDG Starting Air Compressors, Dryers, and Pressure Switches [DCN
===23634]
- (4) Replacement of Shutdown Board PCB 6.9kV/480V Transformers [DCN 23680] Review of Operating Experience Issues (IP Section 02.06) ===
- (1) NRC Information Notice (IN) 2017-06, Battery and Battery Charger Short-Circuit Current Contributions to a Fault on the Direct Current Distribution System
- (2) NRC IN 1997-60, Incorrect Unreviewed Safety Question Determination Related to Emergency Core Cooling System Swapover from the Injection Mode to the Recirculation Mode
INSPECTION RESULTS
Failure to Demonstrate AC Power System Calculations Conform to Design Bases Cornerstone Significance Cross-cutting Report Aspect Section Mitigating Green None 71111.21M Systems NCV05000327,05000328/2019010-01 Closed The inspectors identified a Green finding and associated Non-cited Violation (NCV) of Title 10 of the Code of Federal Regulations, Part 50, Appendix B, Criterion III, Design Control, for the licensee's failure to verify or check the adequacy of design of the AC power system.
Description:
On October 31, 2012, the NRC issued license amendment numbers 332 and 325 to the licensee, granting a change to their Technical Specifications 3.8.1 and 4.8.1. The change was necessary as a result of modifications to the plant design and operating configuration that would install generator circuit breakers (GCBs) and new unit station service transformers (USSTs) to allow their use as a qualified offsite power supply.
Technical Specification Bases B 3.8.1 stated, "Offsite power will normally be supplied from the USSTs to the 6.9kV Shutdown Boards via the 6.9 kV Unit Boards, and will automatically transfer at least one power supply to an alternate power supply ([Common Station Service Transformer] CSST A or CSST C) on a trip of the Power Circuit Breakers (PCBs)." Also stated in the licensees Bases, the licensee identified the following electrical configurations that demonstrate compliance with their Technical Specification requirement of maintaining two qualified offsite circuits between the offsite transmission network and the onsite Class 1E AC Electrical Power Distribution System:
1. Two Common station service transformers (CSSTs) windings X and Y providing power to their respective 6.9 kV unit boards.
2. A train and unit specific USST with the ability to fast transfer to a respective CSST upon loss of a unit specific USST and a CSST different than that of the one receiving a postulated fast transfer (X and Y windings) providing power to their respective 6.9 kV unit boards.
In all analyzed cases, whenever a USST was being utilized as a qualified offsite source, the ability to fast transfer to a CSST was explicitly required to be available. The transfer is necessary because the opening of the stations PCBs (needed to isolate the generator in the event of a failure of the non-1E GCBs) would remove power to the USSTs, thereby removing their capability of providing offsite power during normal plant operations, as well as design basis accidents, and postulated environmental events.
In reviewing the licensees design of their fast transfer system and its impact on the safety related 6.9 kV shutdown boards, inspectors were referred to the licensees calculation SQNETAPAC, Auxiliary Power System, Rev. 89. The purpose of the calculation was to analyze and document the acceptability of the plant AC power system as defined in UFSAR Sections 8.2 and 8.3. Inspectors reviewed the calculation and determined that the calculation failed to model limiting voltage transients following design basis fast (automatic) transfers from the USSTs to the CSSTs, to verify that they would not result in actuation of the degraded voltage relays - leading to a loss of offsite power.
The licensee provided SQN-APS-005, Fast Bus Transfer, Rev. 2, as their documented analysis of the effect fast transfer would have on their 1E power system. As stated in the licensees response to a request for additional information (dated August 23, 2012), the calculation was intended to present an analysis demonstrating that the transfer would not exceed 1.33 Volts per Hertz, in accordance with American National Standards Institute (ANSI) standard C50.41. Inspectors reviewed the calculation and determined that, while the calculation analyzed a transfer from the CSST to the USSTa transfer that could be less limiting, the calculation failed to analyze a bus transfer from the USST to the CSST. In addition to this, inspectors determined that the calculation failed to comprehensively model the stations configuration including, but not limited to, the licensees failure to:
1. Evaluate the effects non-motor (static) loads would have on the voltage and phase angle of the bus being transferred during the dead bus time.
2. Consider the tripping of the main generator excitation system prior to tripping the main generator (approximately 10 cycles), during which time the voltage of the shutdown board could experience greater transient conditions due to the loss of some voltage regulation provided by the excitation system.
3. Consider the motoring of the main generator, and its lagging phase angle effects.
Inspectors concluded that calculations SQNETAPAC and SQN-APS-005 failed to demonstrate the adequacy of the design of the fast transfer scheme necessary to qualify the USSTs as offsite sources, and failed to ensure the integrity of the safety-related equipment powered by the offsite circuits. Additionally, inspectors noted that the station could not provide previous runs of the ETAP software which generated the outputs for calculation SQNETAPAC because the previous runs were not retrievable, and that the base model used in the calculation did not represent the as-designed condition of the stations electrical system.
Corrective Action(s): The licensee determined the equipment to be operable. The licensee plans to revise calculations SQNETAPAC and SQN-APS-005.
Corrective Action Reference(s): CRs 1494559, 1497075, and 1498362
Performance Assessment:
Performance Deficiency: The team determined that the failure to check or verify the adequacy of the design of the AC power system was a performance deficiency of Title 10 of the Code of Federal Regulations, Part 50, Appendix B, Criterion III, Design Control.
Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Design Control attribute of the Mitigating Systems cornerstone. Specifically, the revised outputs of the calculations would result in a significant loss of margin, reducing the reliability of the AC power system.
Significance: The inspectors assessed the significance of the finding using Appendix A, Significance Determination of Reactor Inspection Findings for At - Power Situations. The finding was determined to be Green since it was a deficiency affecting the design or qualification of a mitigating structure, system, or component and its operability was maintained.
Cross-cutting Aspect: Not Present Performance. No cross cutting aspect was assigned to this finding because the inspectors determined the finding did not reflect present licensee performance.
Enforcement:
Violation: Title 10 CFR Part 50, Appendix B, Criterion III, Design Control, states, in part, that design control measures shall provide for verifying or checking the adequacy of design, such as by the performance of design reviews, by the use of alternate or simplified calculational methods, or by the performance of a suitable testing program.
Contrary to the above, since February 17, 2012, the licensee failed to verify or check the adequacy of design of the AC Power System. Specifically, the licensee failed to demonstrate the adequacy of the design of the fast transfer scheme necessary to qualify the USSTs as offsite sources and ensure the integrity of the safety-related equipment powered by the offsite circuits.
Enforcement Action: This violation is being treated as a Non-Cited Violation, consistent with Section 2.3.2 of the Enforcement Policy.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On March 14, 2019, the inspectors presented the design bases assurance inspection results to Mr. Matt Rasmussen and other members of the licensee staff.
- On April 10, 2019, the inspectors presented the final design bases assurance inspection results to Mr. Jonathan Johnson and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection Type Designation Description or Title Revision or
Procedure Date
71111.21M Calculations 03D53EPMWLL063094 AFW Hydraulic Analysis Rev. 16
1-FCV-63-073 Documentation of Design Basis Review, Required Rev. 6
Thrust Calc and Valve & Actuator Capability
Assessment for 1-FCV-63-073
2-FCV-63-040 Documentation of Design Basis Review, Required Rev. 5
Thrust Calc and Valve & Actuator Capability
Assessment for 2-FCV-63-040
30-D053-EPM-BVC- Determination of Required ERCW and Air Flow rates Rev. 9
2788 to ESF Room Coolers
AFW Hydraulic Analysis AFW Level Control Valve Opening Time Rev. 1
B45 870106427 MELB Safe Shutdown Analysis Rev. 4
B45870106428 MELB Flooding Study Rev. 18
B87951205003 ERCW Screen Wash System Hydraulic Analysis Rev. 3
CDQ0000632016000333 Evaluation of Refueling Water Storage Tank for Rev. 0
Beyond Design Basis Tornado and Flood Loads
EDQ0000632014000103 Instrumentation Evaluation for RWST Volume during Rev. 0
Time Critical Action (TCA) Associated with RWST
Versus Sump Switchover - Level Monitoring, System
GEN-EEB-MS-TI28-0002 Generic Accuracy Calculation - Eagle 21 I/O Rev. 2
Demonstrated Accuracy Calculation
MDQ0009992106000323 Damage Assessment & Repair Strategy for Appendix Rev. 0
R Cold Shutdown Motor Operated Valves
MDQ0072980034 CCP, SIP, and RHR Pump NPSH Evaluation Rev. 11
MDQ0999-980039 MOV Thrust Requirements Considering Pressure Lock Rev. 5
Using ComEd Methodology
OSG7-0020 Safety Injection System (063) 10CFR50.49 Category Rev. 20
and Operating Times
SCG4M01104 Steam Generator AFW Level Control Valves Seismic Rev. 0
Qualification Evaluations
71111.21M Calculations SQN-00-D059 EPM- Generic Letter 89-10 MOV Population At Sequoyah Rev. 19
RJP-061091 Units 1 & 2
SQN-30-D53-EPM- HVAC Cooling Load Calculation Auxiliary Building Rev. 3
ASD01-031287 CCP Rooms Elevation 669
SQN-63-D053 EPM- Documentation of Design Basis Review, Required Rev. 7
RJP-030191 Thrust Calc and Valve & Actuator Capability
Assessment for 1-FCV-63-025
SQN-APPR-1 Analysis of AC/DC Instrument and Control (I&C) Rev. 20
Power Systems to Identify Associated Circuits - 10 CFR 50 Appendix R
SQN-APS-003 480VAC APS Class 1E Load Coordination Study Rev. 88
SQN-APS-005 Fast Bus Transfer Analysis Rev. 2
SQN-CPS-051 Circuit Protection Device Evaluation Rev. 67
SQN-EEB-MS-TI28-0015 Instrument Accuracy Calc: 1-LT-63-50, -51, -52, -53 Rev. 13
SQN-EEB-PL&S Precautions, Limitations and Setpoint for NSSS Rev. 55
SQN-NTB- RWST and Containment RHR Safety and Operational Rev. 17
NDQ0063980038 Limits, RWST Setpoint Required Accuracy, and
LBLOCA and SBLOCA Sump Minimum Levels
SQN-NTB-SQS20110 Emergency and Abnormal Procedure Setpoints Rev. 34
SQN-QN-EEB-MS-TI28- Instrument Accuracy Calc: 1-LT-63-50, -51, -52, -53 Rev. 14
SQN-SQS2-0010 Chemical and Volume Control System Operating Rev. 12
Modes
SQN-SQS2-169 Maximum Temperature of the Piping on the Discharge Rev. 0
of the Pressurizer SRVs and PORVs Following Valve
Actuation.
SQNETAPAC Auxiliary Power System Rev. 89
TPS-SQN-PLN-EDX000- Planning Transmission Study (TSS) - Grid Off-Site Rev. 3
000-2002-001 Power, Transient Stability, and Fault Current
Calculation for 2012 and 2016
71111.21M Corrective Action CR 1133416
Documents CR 1158718
CR 1161344
CR 1170545
CR 1175834
CR 1177144
CR 1180402
CR 1181710
CR 1183483
CR 1184239
CR 1205951
CR 1210311
CR 1215848
CR 1296320
CR 1316043
CR 1328776
CR 1345254
CR 1389095
CR 1406471
CR 1416535
CR 1435427
CR 1472289
CR 1475587
CR 1476134
CR 1476273
CR 1493816
CR 168601
CR 759027
CR 760336
CR 787960
CR 818759
CR 934663
PER 753504
PER 771351
71111.21M Corrective Action PER 934663
Documents
Corrective Action CR 1493643 Drawing Needs to be Updated
Documents CR 1493816 SQN-DC-V-12.2 Issues Found
Resulting from CR 1493833 FSAR Section 3.1.2 not Updated to Reflect USST
Inspection Modification
CR 1493963 Identified Plant Light Out in ERCW Room
CR 1493966 Identified Standing Water in 1A-A Bay
CR 1493970 Identified FME in ERCW Room Sump
CR 1493973 Identified Clogged Drains in ERCW Building
CR 1494101 Inadequate Testing of Discharge Check Valves
CR 1494419 Unconservative Heat Load from Surface of Pipes
CR 1494452 Comprehensive Pump Test Lists Quarterly Pump Test
as Alternate
CR 1494461 Quarterly Pump Test is not Credited for Check Valve
Closure
CR 1494559 SQNETAPAC Rebaseline Needed
CR 1494707 Apparent Inadequate 50.59 Evaluation for PIC 23696
CR 1496014 Calculation SQNETAPAC, Revision 90, Documents
Several Instances of Using MVARs for 30 Seconds
After a LOCA to Support Grid Voltage
CR 1496213 NRC-Identified RWST Tornado Vulnerability
CR 1496325 Plant Grid Interface Meeting Minutes Reference Typo
CR 1496841 Incorrect TRM References in Calculation SQN-EEB-
MS-TI28-0025, Rev. 14
CR 1497075 SQNETAPAC Revisions using Base Revision Rather
than As-designed Condition
CR 1497921 Calculation Error in NDQ0063980038
CR 1497928 Calculation Error in EDQ0000632014000103
Enhancement
CR 1498200 FSAR Not Revised to Capture New SBLOCA Limiting
Scenario
71111.21M Corrective Action CR 1498253 Lack of Critical Thinking When Evaluating the Last 2B-
Documents B CCP Pump Comprehensive Test
Resulting from CR 1498291 2012 NRC Submittal Validation Information
Inspection CR 1498327 FSAR TSS Clarification Needed
CR 1498336 Higher Pump Motor Horse Power Was Not Used in a
Heat Load Calculation
CR 1498356 CCP Comprehensive Pump Test Uses Computer
Points Rather Than M&TE Equipment
CR 1498362 Calculations SQNETAPAC and SQN-APS-005 Not
Bounding with Regard to Fast Bus Transfer Scenario
CR 1498642 NRC Identified (NDQ0063980038 Needs an
Enhancement Revision to Clarify)
CR 1498643 The PM Issued for Replacement of Unit 2 Room
Coolers Was In an Inactive Status and Should Be
Reactivated
CR 1498719 Reynolds Number Outside the Range for Equation
Applicability
CR 1498781 Based on Frequency of Cleaning the CCP Room Unit
Coolers, Reevaluate Whether a Fouling Factor of
0.001 is Adequate
CR 1499162 1E to Non-1E Coordination Issue
Drawings 0-15E500-1 Key Diagram, Station Aux Power System Rev. 56
0-15E500-3 Transformer Taps & Voltage Limits - Aux Power Rev. 44
System
1, 2 - 47W610-63-2 Mechanical Control Diagram Safety Injection System Rev. 34
1, 2 - 47W610-68-6 Mechanical Control Diagram Reactor Coolant System Rev. 17
1,2-45N657-5 Wiring Diagrams, Separation & Mis Aux RLYS Rev. 27
Schematic Diagrams
1,2-45N703-1 Wiring Diagrams 125V Vital Battery Board I Single Rev. 83
Line - Sheet 1
1,2-45N703-2 Wiring Diagrams 125V Vital Battery Board II Single Rev. 44
Line - Sheet 2
1,2-45N703-3 Wiring Diagrams 125V Vital Battery Board III Single Rev. 49
Line - Sheet 3
71111.21M Drawings 1,2-45N765-1 Wiring Diagram 6900V Shutdown Aux Power Rev. 35
Schematic Diagram SH-1
1,2-47W309-3 Mechanical Large Reservoirs Rev. 0
1-47W600-143 Mechanical Instruments & Controls Rev. 9
1-47W600-241 Mechanical Instruments & Controls Rev. 8
1-5655D26-16 Functional Diagrams, Turbine Trips, Runbacks & Rev. 1
Other Signals
2-47W803-2 Flow Diagram Auxiliary Feedwater Rev. 78
2-47W809-1 Flow Diagram Chemical and Volume Control System Rev. 75
Engineering D23169 Addition of Leak off Piping and Collection System to Rev. 0
Changes ERCW Pumps
D23623 Degraded Non-Conforming MOV Modifications - Rev. A
Gears/Actuators/Motor/Cable Reroute
DCN 23209 Replacement of 125V DC Vital Battery Charger I Rev. A
DCN 23396A RWST Swap-over Revised Procedural Actions Rev. A
Considering Interruption of ECCS Flow
Miscellaneous B25900219001 Letter Westinghouse to TVA Sequoyah CH/SI Pump Dated
Motor Horsepower 2/8/90
CNL-16-011 Letter TVA to NRC Technical Specification Change to Dated
Extend the Allowed Completion Time to Restore 3/11/16
Essential Raw Cooling Water System Train to
Operable from 72 Hours to 7 Days
DCN 23680 Replacement of Shutdown Board PCB 6.9kV/480V Rev. A
Transformers
IST Evaluation for 2-LCV-3-156 Completed
6/23/16
IST Evaluation for 1-LCV-3-148 Completed
10/19/16
IST Evaluation for 1-LCV-3-156 Completed
7/14/16
Letter from NRC to TVA Apparent Violation Closure Inspection Report Dated
05000327/2013014 NS 05000328/2013014 12/11/13
71111.21M Miscellaneous Memorandum Memorandum from James
- R. Regg, Chief Dated
Transmissions Systems operations Manager, to 10/21/02
Ronald
- K. Gladney, Communications Requirements
for Sequoyah Nuclear Plant (SQN) Alternate
Alignment
Memorandum Memorandum from John M. Campbell to James R. Dated
Regg and
- B. David Till, Sequoyah Nuclear Plant 3/31/06
(SQN) - Off-Site Power Requirements &
Communications Protocols
NEDP-4 Q-List and UNID Control Rev. 26
NUREG-001 Sequoyah Nuclear Plant Units 1 and 2 Dated
March 1979
OPT200.AC6.9KV 6.9 KV Electrical Distribution System
SCN 17-52 SAR Change Request Dated
5/17/01
SEG#OPL273S1902 AFW Inside Out Rev. 0
SO-18-040 2-FCV-67-146 Degraded Stroke Values Dated
11/30/18
SQN-DC-V-11.2 Design Criteria Document, 125V Vital Battery System Rev. 12
SQN-DC-V-11.4.1 Design Criteria Document, Normal and Emergency AC Rev. 24
Auxiliary Power Systems
SQN-DC-V-12.2 Design Criteria Document, Separation of Electric Rev. 16
Equipment and Wiring
SQN-DC-V-13.9.3 Design Criteria Document, Auxiliary Building Rev. 6
Ventilation and Cooling
SQN-DC-V-13.9.8 Design Criteria Document, Auxiliary Feedwater Rev. 29
System
SQN-DC-V-27.2 Design Criteria Document, Chemical and Volume Rev. 35
Control System
SQN-DC-V-27.3 Design Criteria Document, Safety Injection System Rev. 24
SQN-DC-V-27.4 Design Criteria Document, Reactor Coolant System Rev. 24
SQN-DC-V-27.9 Design Criteria Document, Reactor Protection System Rev. 17
SQN-DC-V-3.0 Design Criteria Document, The Classification of Rev. 21
Piping, Pumps, Valves, and Vessels
71111.21M Miscellaneous SQN-DC-V-46.0 Design Criteria Document, Seismic/Structural Rev. 3
Qualification of Seismic Category I and I(L) In-Line
Valves and Other In-Line Fluid System Components
SQN-VD-A391-0963 Anchor/Darling Valve CO. Carbon Steel Nuclear Dated
Valves 3/4/12
SQN-VD-A391-2863 Anchor/Darling Valve CO. Maximum Thrust Dated
Calculations 3/4/12
SQN-VTD-A998-0010 200 AMP Battery Charger Instriction [Sic] Manual Rev. 1
SQN-VTD-G182-0050 Installation/Maintenance Instructions for ITE Medium Rev. 3
Voltage Power Circuit Breakers 7.5HK
SQN-VTD-G182-0710 Brown Boveri Instructions for I-T-E Single Phase Rev. 1
Voltage Relays
SQN-VTD-G182-0720 Brown Boveri Instructions for Single Phase Voltage Rev. 2
Relays ITE-27N Undervoltage Relay ITE-59N
Overvoltage Relay
SQN-VTD-T020-0030 Project Technical Manual Power Operated Relief Rev. 3
Valves
SQN-VTD-W120-3810 Instruction Manual for Unit 1 and 2 Centrifugal Rev. 22
Charging Pumps
SQN-VTM-G182-0030 Gould Inc. (Formally I-T-E Imperial Corporation) Indoor Rev. 54
and Outdoor Metal Clad Switchgear and Components
SQN-VTM-T020-0010 Target Rock Corp. Solenoid Operated Valves Rev. 17
SS-E18.10.01 Standard Specification for Environmental Qualification Rev. 4
Requirements for Safety Related Electrical Equipment
TVA-7493 Westinghouse Letter Dated
8/15/79
TVA-DT-01 Standard Specification, Dry Type, Power & Distribution Rev. 0
Transformer
Operability PDO 1496213
Evaluations PDO 753504
Procedures 0-AR-M26-A Annunciator 0-XA-55-26A Rev. 43
71111.21M Procedures 0-PI-EBM-000-001.2 Battery Bank High Level Equalize Charge (Systems Rev. 39
2, 244, 250)
0-SO-250-1 125 Volt DC Vital Power System Rev. 76
0-TI-OPS-000-004.0 Time Critical Operator Actions Rev. 9
1-AR-M1-C AC/DC Control Power 1-XA-55-1C Rev. 59
2-SI-ICC-068-455.0 2-SI-ICC-068-455.0 COPS PCV-68-340A CC Rev. 18
2-SI-IFT-068-456.0 2-SI-IFT-068-456.0 COPS PCV-68-334 FT Rev. 18
2-SI-SXP-062-201.B Centrifugal Charging Pump 2B-B Performance Test Completed
1/31/19
2-SI-SXP-062-203.0 Centrifugal Charging Pumps 2A-A and 2B-B Completed
Comprehensive pump Test and Check Valve Test 11/28/18
2-SI-SXV-003-232.1 Turbine Driven Auxiliary Feedwater Pump Check Rev. 4
Valve Test Unit 2
AOP-M.08 Internal Flooding Rev. 4
AOP-N.03 External Flooding Rev. 59
AOP-P.07 Degraded Grid or Abnormal Voltage Conditions Rev. 15
DS-M18.2.21 Motor Operated Valve Thrust and Torque Calculations Rev. 24
DS-M18.2.22 MOV Design Basis and JOG Review Methodologies Rev. 8
E-0 Reactor Trip or Safety Injection Rev. 40
ES 1.3 Transfer to RHR Containment Sump Rev. 22
ES 1.3 Transfer to RHR Containment Sump Rev. 21
ES-1.3 Transfer to RHR Containment Sump Rev. 23
GOI-6 General Operating Instructions, Apparatus Operations Rev. 184
NEDP-2 Design Calculation Process Control Rev. 23
NEDP-8.0 Evaluations for Procurement of Materials, Items, and Rev. 5
Services
NPG-SPP-01.16 Condition Report Initiation Rev. 2
NPG-SPP-06.9.3 Post-Modification Testing Rev. 10
NPG-SPP-09.14 Generic Letter 89-13 Implementation Rev. 4
NPG-SPP-09.26.14 Motor Operated Valve Program Rev. 4
NPG-SPP-09.3 Plant Modifications and Engineering Change Control Rev. 30
NPG-SPP-09.4 10 CFR 50.59 Evaluations of Changes, Tests, and Rev. 12
Experiments
NPG-SPP-22.300 Corrective Action Program Rev. 12
71111.21M Procedures NPG-SPP-22.500 Operating Experience Program Rev. 7
NPG-SSP-09.1.20 Inservice Testing Program Requirements Rev. 1
NPG-TREND NPG Trending Manual Rev. 9
OPDP-8 Operability Determination Process and Limiting Rev. 24
Conditions for Operation Tracking
TI-28 Technical Instruction, Curve Book Rev. 334
Work Orders 111842240
114412576
114605899
115320081
115420993
115420998
116532954
116859442
117064518
117107091
117352923
117353016
117673650
117732985
117908899
117908901
118021552
118266140
118318157
118594134
118799855
118817993
119127713
119145564
119198833
119199046
119201492
119266171
71111.21M Work Orders 119421920
119793040
119819464
119819466