ND-18-0034, Enclosures 2 and 4: Redacted COL Operational Programs and Other License Conditions Implementation Schedule and Redacted Preoperational Test Procedure Completion Schedule
| ML18026A906 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 01/25/2018 |
| From: | Southern Nuclear Operating Co |
| To: | Office of New Reactors |
| Shared Package | |
| ML18026A902 | List: |
| References | |
| ND-18-0034 | |
| Download: ML18026A906 (17) | |
Text
Southern Nuclear Operating Company ND-18-0034 Enclosure 2 Redacted COL Operational Programs and Other License Conditions Implementation Schedule (This Enclosure consists of 6 pages, including this cover page)
Enclosure 2 to ND-18-0034 Vogtle Electric Generating Plant - Units 3 and 4 Combined License tCOLl Operational Programs and Other License Conditions Implementation Schedule Redacted Version COL Reference Program Name Implementation Date FSAR Reference 02.D.(111 Unit 3 Initial Fuel Load [ ]
N/A 02.D.(1U [ ]
Unit 4 Initial Fuel Load N/A 02.D.MU [ ]
Unit 3 Inservice Inspection Table 13.4-201 Item 1 02.0.(111 [ ]
Unit 4 Inservice Inspection Table 13.4-201 Item 1 02.0.(111 [ ]
Inservice Testing Table 13.4-201 Item 2 02.0.(1 OKal and 02.0.(111 [ ]
Environmental Qualification Table 13.4-201 Item 3 02.0.(111 [ ]
Unit 3 Preservice Inspection Table 13.4-201 Item 4 02.0.(111 [ ]
Unit 4 Preservice Inspection Table 13.4-201 Item 4 02.0.(1 OKbl and 02.0.(111 [ ]
Reactor Vessel Material Surveillance Table 13.4-201 Item 5 02.0.(1 OKcl and 02.0.(111 [ ]
Preservice Testing Table 13.4-201 Item 6 02.0.(1 OKdl and 02.0.(111 [ ]
Containment Leakage Rate Testing Table 13.4-201 Item 7 02.0.(101(e11. and 02.0.(111 Fire Protection - Oesignated Storage Areas [ ]
Table 13.4-201 Item 8 (per RG 1.1891 02.0.(101(e12. and 02.0.(111 Fire Protection - New Fuel Areas (per RG [ ]
Table 13.4-201 Item 8 1.189) 02.0.(101(e13. and 02.0.(111 [ ]
Fire Protection - All other features Table 13.4-201 Item 8 Radiological Effluent Technical [ ]
02.0.(1 OKfl and 02.0.(111 Specifications/Standard Radiological Effluent Table 13.4-201 Item 9 Controls 02.0.(1 OKal and 02.0.(111 [ ]
Offslte Dose Calculation Manual Table 13.4-201 Item 9 Page 2 of 6
Enclosure 2 to ND-18-0034 Vogtle Electric Generating Plant - Units 3 and 4 Combined License tCOLl Operational Programs and Other License Conditions implementation Schedule Redacted Version COL Reference Implementation Date Program Name FSAR Reference 02.D.(10)(m and02.D.(1U Radiological Environmental Monitoring [ ]
Table 13.4-201 Item 9 02.0.(101(11 and 02.0.(111 Process Control
[ ]
Table 13.4-201 Item 9 Radiation Protection Program: Prior to Initial [ ]
02.0.(101(111. and 02.0.(111 Receipt of Byproduct, Source, or Special Table 13.4-201 Item 10 Nuclear Materials 02.0.(101(112. and 02.0.(111 Radiation Protection Program: Prior to Receipt Table 13.4-201 Item 10 of Fuel Onsite 02.0.(101(113. and 02.0.(111 Radiation Protection Program: Prior to Initial [ ]
Table 13.4-201 Item 10 Fuel Load 02.0.(101(114. and 02.0.(111 Radiation Protection Program: Prior to [ ]
Table 13.4-201 Item 10 Shipment of Radioactive Waste 02.0.(111 Non-Licensed Plant Staff Training (non- [ ]
Table 13.4-201 Item 11 radioactive) 02.0.(111 Non-Licensed Plant Staff Training (portions [ ]
Table 13.4-201 Item 11 applicable to radioactive material) 02.0.(101(k1 and 02.0.(111 Reactor Operator Training [ ]
Table 13.4-201 Item 12 02.0.(111 Reactor Operator Requalification [ ]
Table 13.4-201 Item 13 02.0.(111 Unit 3 Emergency Planning: Full Participation [ ]
Table 13.4-201 Item 14 Exercise 02.0.(111 Unit 3 Emergency Planning: Onsite Exercise [ ]
Table 13.4-201 Item 14 02.0.(111 Unit 4 Emergency Planning: Full Participation [ ]
Table 13.4-201 Item 14 Exercise 02.0.(111 [ ]
Unit 4 Emergency Planning: Onsite Exercise Table 13.4-201 Item 14 02.0.(111 Emergency Planning: Detailed Implementing [ ]
Table 13.4-201 Item 14 Procedures for Emergency Plan Physical Protection Program (for special 02.0.(101(o1 and 02.0.(111 nuclear material before Protected Area Is [ ]
Table 13.4-201 Item 15 operational)
Page 3 of 6
Enclosure 2 to ND-18-0034 Vogtle Electric Generating Plant - Units 3 and 4 Combined License tCOLl Operational Programs and Other License Conditions Implementation Schedule Redacted Version COL Reference implementation Date Program Name FSAR Reference 02.D.(11)
Physical Security Program [ ]
Table 13.4-201 Item 15 02.D.ri11 Safeguards Contingency Program [ ]
Table 13.4-201 Item 15 02.D.ni)
Security Training and Qualification Program [ ]
Table 13.4-201 Item 15 02.D.f11)
Quality Assurance [ ]
Table 13.4-201 Item 16 02.D.(11)
Maintenance Rule [ ]
Table 13.4-201 Item 17 02.D.f10im and 02.0.(111 MQV Testing [ ]
Table 13.4-201 Item 18 02.D.(101(m11.and 02.0.(111 Initial Test Program - Component [ ]
Table 13.4-201 Item 19 02.0.(101(m12. and 02.0.(111 Initial Test Program - Pre-Qperational [ ]
Table 13.4-201 Item 19 02.0.(101(m13. and 02.0.(111 Initial Test Program - Startup [ ]
Table 13.4-201 Item 19 02.0.(111 FFO for Construction Workers and First-Line [ ]
Table 13.4-201 Item 20 Supervisors 02.0.(111 FFO for Construction Management and [ ]
Table 13.4-201 Item 20 Qversight Personnel 02.0.(111 FFO for Security Personnel (WECTEC1 [ ]
Table 13.4-201 Item 20 02.0.(111 FFO for Security Personnel (SNC) [ ]
Table 13.4-201 Item 20 02.0.(111 FFO for FFO personnel [ ]
Table 13.4-201 Item 20 02.0.(111 FFO for TSC and EQF personnel [ ]
Table 13.4-201 Item 20 02.0.(111 FFO for Qperations [ ]
Table 13.4-201 Item 20 02.0.(111 Cyber Security [ ]
Table 13.4-201 Item 21 Page 4 of 6
Enclosure 2 to ND-18-0034 Vogtle Electric Generating Plant - Units 3 and 4 Combined License ICOLl Operational Programs and Other License Conditions Implementation Schedule Redacted Version COL Reference Implementation Date Program Name FSAR Reference 02.D.(10)(n) and 02.D.(11) Special Nuclear Material Control and [ ]
Table 13.4-201 Item 22 Accounting Construction inspection procedures for steel [ ]
concrete composite construction activities for 02.D.(121(f)1.
seismic Category 1nuclear island structural Section 3.8.4.8 modules for minimum required reinforcement, steel plate thickness, and concrete thickness.
Construction inspection procedures for steel [ ]
concrete composite construction activities for 02.D.(12imi.
seismic Category 1shield building modules for Section 3.8.4.8 minimum required reinforcement, steel plate thickness, and concrete thickness.
02.D.(12)m2. Spent Fuel Rack Metamic Coupon Monitoring [ ]
N/A Program 02.D.(12im3. Fiow Accelerated Corrosion Program [ ]
N/A (including construction phase) 02.D.(12)m4.
Turbine Maintenance and Inspection Program [ ]
Section 10.2.3.6 Availability of documented instrumentation [ ]
02.D.(12)m5.
uncertainties to calculate a power calorlmetric N/A uncertainty Availabilityof administrative controls to [ ]
02.D.M2im6. implement maintenance and contingency N/A activities related to the power calorlmetric uncertainty instrumentation 02.D.M21(f)7. Site-specific severe accident management [ ]
N/A guidelines The operational and programmatic elements [ ]
of the mitigative strategies for responding to 02.D.M21(f18.
circumstances associated with the loss of N/A large areas of the plant due to explosions or fire 02.D.(12Kf19. [ ]
iTP administrative manual procedures Section 14.2.3 Page 5 of 6
Enclosure 2 to ND-18-0034 Vogtle Electric Generating Plant - Units 3 and 4 Combined License fCOLl Operational Programs and Other License Conditions Implementation Schedule Redacted Version COL Reference Program Name implementation Date FSAR Reference 02.D.(12)(f)9. See Enclosure 4 Preoperational testing procedures Section 14.2.3 02.D.(12)(f19. [ ]
Startup testing procedures Section 14.2.3 Page 6 of 6
Southern Nuclear Operating Company ND-18-0034 Enclosure 4 Redacted Preoperatlonal Test Procedure Completion Schedule (This Enclosure consists of 9 pages, Including this cover page)
Enclosure 4 to ND-18-0034 Vogtle Electric Generating Plant - Units 3 and 4 Preoperational Test Procedure Completion Schedule Redacted Version Procedure Number/Name Completion Date 3-FWS-ITPP-501
[ ]
Main and Startup Feedwater System 3-GEN-ITPP-520
[ ]
Control Loop Tuning 3-PWS-ITPP-502
[ ]
Building 315 Potable Water System 3-DAS-ITPP-501
[ ]
Diverse Actuation System 3-RXS-ITPP-501
[ ]
Pre- and Post- Precore Hot Functional Inspection of Reactor Vessel Internals 3-CFS-ITPP-501
[ ]
Turbine Island Chemical Feed System 3-CAS-ITPP-501
[ ]
Compressed and Instrument Air System 3-OCS-ITPP-502
[ ]
OCS Remote Shutdown Workstation 3-LOS-ITPP-501
[ ]
Main Turbine and Generator Lube Oil System 3-RWS-ITPP-501
[ ]
Raw Water System 3-SFS-ITPP-502
[ ]
Spent Fuel Pool Cooling System Flow Path 3-WGS-ITPP-501
[ ]
Gaseous Radwaste System 3-CVS-ITPP-501
[ ]
Chemical and Volume Control System 3-HSS-ITPP-501
[ ]
Hydrogen Seal Oil System 3-HDS-ITPP-501
[ ]
Heater Drain System 3-SWS-ITPP-501
[ ]
Service Water System 3-PMS-ITPP-502
[ ]
PMS Time Response 3-ASS-ITPP-501
[ ]
Auxiliary Steam Supply System 3-ECS-ITPP-501
[ ]
6.9 kV Switchgear Page 2 of 9
Enclosure 4 to ND-18-0034 Vogtle Electric Generating Plant - Units 3 and 4 Preoperational Test Procedure Completion Schedule Redacted Version Procedure Number/Name Compietion Date 3-VFS-ITPP-501
[ ]
Containment Air Filtration System 3-EDS-ITPP-501
[ ]
Non-Class IE DC and UPS System 3-RNS-ITPP-501
[ ]
Normal Residual Heat Removal System 3-SDS-ITPP-501
[ ]
Sanitary Drainage System 3-SMS-ITPP-501
[ ]
Special Monitoring System 3-CNS-ITPP-501
[ ]
ILRT Containment System Leak Rate Test Type A 3-PCS-ITPP-502
[ ]
Passive Containment Cooling System PCCWST 3-WSS-ITPP-501
[ ]
Solid Radwaste System 3-SFS-ITPP-503
[ ]
Spent Fuel Pool Loss of Large Area 3-CCS-ITPP-501
[ ]
Component Cooling Water Systm 3-CVS-ITPP-502
[ ]
Chemical and Volume Control System Precore Hot Functional 3-MTS-ITPP-501
[ ]
Main Turbine System 3-PSS-ITPP-501
[ ]
Primary Sampling System 3-RWS-ITPP-502
[ ]
Raw Water System Well Water Subsystem 3-RXS-ITPP-502
[ ]
Reactor Vessel Internals Vibration 3-SWS-ITPP-502
[ ]
Service Water System Precore Hot Functional 3-VCS-ITPP-502
[ ]
Containment Recirculation Cooling System Precore Hot Functional 3-PMS-ITPP-503
[ 1 PMS Qualified Data Processing System 3-CDS-ITPP-501
[ ]
Condensate System Page 3 of 9
Enclosure 4 to ND-18-0034 Vogtle Electric Generating Plant - Units 3 and 4 Preoperational Test Procedure Completion Schedule Redacted Version Procedure Number/Name Completion Date 3-OCS-ITPP-504
[ ]
OCS Local Control Stations 3-SMS-ITPP-502
[ ]
Special Monitoring System Precore Hot Functional 3-PMS-ITPP-504
[ ]
PMS RT Actuation 3-ECS-ITPP-502
[ ]
480V Load Center 3-EDS-ITPP-502
[ ]
Non-Class IE DCand UPS System Performance 3-MTS-ITPP-502
[ ]
Main Turbine System Precore Hot Functional 3-GEN-ITPP-521
[ ]
HVAC Final Air Balancing 3-RNS-ITPP-5G2
[ ]
Normal Residual Heat Removal System Precore Hot Functional 3-CNS-ITPP-502
[ ]
ILRT Containment System Leak Test Type B 3-CPS-ITPP-501
[ ]
Condensate Polishing System 3-PMS-ITPP-505
[ ]
PMS Nuclear Instrumentation System 3-CCS-ITPP-502
[ ]
Component Cooling Water System Precore Hot Functional 3-PSS-ITPP-502
[ ]
Primary SamplingSystem Precore Hot Functional 3-RXS-ITPP-503
[ 1 Integrated Head Package (IHP) 3-SWS-ITPP-503
[ ]
Service Water Cooling Tower Basin Reserve Volume 3-TCS-ITPP-501
[ ]
Turbine Building Closed Cooling Water System 3-IIS-ITPP-501
[ ]
Incore Instrumentation System 3-VTS-ITPP-501
[ ]
Turbine Building Ventilation System 3-PMS-ITPP-521
[ ]
PMS Logic Page 4 of 9
Enclosure 4 to ND-18-0034 Vogtle Electric Generating Plant - Units 3 and 4 Preoperational Test Procedure Completion Schedule Redacted Version Procedure Number/Name Completion Date 3-GEN-ITPP-518
[ ]
Precore Hot Functional Testing Chemistry 3-WWS-ITPP-501
[ ]
Waste Water System 3-VCS-iTPP-501
[ ]
Containment Recirculation Cooling System 3-PMS-ITPP-522
[ ]
PMSSquib Valve Controller Performance 3-ECS-ITPP-503
[ ]
480V Motor Control Center 3-HCS-ITPP-501
[ ]
Generator Hydrogen and C02 Systems 3-VWS-ITPP-501
[ ]
Central Chilled Water System 3-WLS-ITPP-501
[ ]
Liquid Radwaste System 3-CNS-ITPP-503
[ ]
ILRT Containment System Leak Rate Test Type C 3-MSS-ITPP-501
[ ]
Main Steam System 3-PMS-ITPP-523
[ 1 PMS Containment Pressure High-2 3-PXS-ITPP-502
[ ]
Passive Core Cooling System Flow Test 3-RCS-ITPP-503
[ ]
RCS Primary Hydrostatic 3-PMS-ITPP-524
[ ]
PMS Cold Actuations 3-CMS-ITPP-501
[ ]
Condenser Air Removal System 3-PCS-ITPP-501
[ ]
Passive Containment Cooling System PCCAWST 3-SGS-ITPP-502
[ ]
Steam Generator System 3-TCS-ITPP-503
[ ]
Stator Cooling Water 3-GEN-ITPP-507
[ ]
Thermal Expansion Page 5 of 9
Enclosure 4 to ND-18-0034 Vogtle Electric GJenerating Plant - Units 3 and 4 Preoperational Test Procedure Completion Schedule Redacted Version Procedure Number/Name Completion Date 3-PMS-ITPP-525
[ ]
PMS Hot Actuations 3-VWS-ITPP-502
[ ]
Central Chilled Water System Precore Hot Functional 3-RCS-ITPP-506
[ ]
Reactor Coolant Pump and Reactor Coolant Flow Precore Hot Functional 3-GEN-ITPP-517
[ ]
Precore Hot Functional Test Sequence 3-IDS-ITPP-501
[ ]
Class IE DC and UPS System 3-SSS-ITPP-501
[ ]
Secondary Sampling System 3-FPS-ITPP-502
[ ]
Fire Brigade Support Equipment 3-EFS-ITPP-501
[ ]
Plant Communications System 3-ZOS-ITPP-501
[ ]
Onsite Standby Power System 3-PLS-ITPP-506
[ ]
Control Rod Drive Mechanism Motor-Generator 3-FPS-ITPP-501
[ ]
Fire Protection System 3-DDS-ITPP-501
[ ]
Data Display and Processing System 3-ECS-ITPP-504
[ ]
Ancillary Diesel Generator 3-PGS-ITPP-501
[ ]
Plant Gas System 3-WRS-ITPP-501
[ ]
Radioactive Waste Drain System 3-GSS-ITPP-501
[ ]
Gland Steam System 3-PXS-ITPP-503
[ ]
Passive Core CoolingSystem FlowTesting with the RV Head Installed 3-GEN-ITPP-508
[ ]
Thermal Stratification, Cycling and Striping 3-RMS-ITPP-501
[ ]
Radiation Monitoring System Page 6 of 9
Enclosure 4 to ND-18-0034 Vogtle Electric Generating Plant - Units 3 and 4 Preoperational Test Procedure Completion Schedule Redacted Version Procedure Number/Name Completion Date 3-VYS-ITPP-501
[ ]
Hot Water Heating System 3-RCS-ITPP-502
[ ]
Reactor Coolant System 3-PMS-ITPP-526
[ ]
PMS MCR Isolation and Passive Containment Cooling System Actuation 3-FHS-ITPP-521
[ ]
Fuel Handling System 3-ZAS-ITPP-501
[ ]
Main Generation System 3-CFS-ITPP-502
[ ]
Turbine Island Chemical Feed System Precore Hot Functional 3-VLS-ITPP-501 Containment Hydrogen Monitoring [ ]
3-DRS-ITPP-501
[ ]
Storm Drain System 3-PLS-ITPP-507
[ ]
Control Rod Drive Mechanism Precore Hot Functional 3-TOS-ITPP-501
[ ]
Main Turbine Control and Diagnostics System 3-BDS-ITPP-501
[ ]
Steam Generator Slowdown System 3-VXS-ITPP-501
[ ]
Annex/Auxiliary Building Nonradioactive Ventilation System 3-SSS-ITPP-502
[ ]
Secondary Sampling System Precore Hot Functional 3-GEN-ITPP-509
[ ]
Reactor Coolant System Vibration and Dynamic Effects 3-DDS-ITPP-502
[ ]
Integrated DCIS Performance 3-FWS-ITPP-502
[ ]
Main and Startup Feedwater System Hot Functional 3-PXS-ITPP-504
[ ]
Passive Core Cooling System Precore Hot FunctionalTest 3-DWS-ITPP-501
[ ]
Demineralized Water Transfer and Storage System 3-FHS-ITPP-522
[ ]
Fuel Handling Equipment Indexing Page 7 of 9
Enclosure 4 to ND-18-0034 Vogtle Electric Generating Plant - Units 3 and 4 Preoperational Test Procedure Completion Schedule Redacted Version Procedure Number/Name Completion Date 3-RMS-ITPP-502
[ ]
Portable Personnel Monitors and Radiation Survey Instruments 3-RCS-ITPP-504
[ ]
Pressurizer Pressure Level and Spray Precore Hot Functional 3-VAS-ITPP-502
[ ]
Radiologically Controlled Area Ventilation System Precore Hot Functional 3-SGS-ITPP-504
[ ]
Steam Generator Hydrostatic 3-MSS-ITPP-502
[ ]
Main Steam System Precore Hot Functional 3-PLS-ITPP-520
[ ]
Digital Rod Position Indication 3-CES-1TPP-501
[ ]
Condenser Tube Cleaning System 3-IDS-ITPP-503
[ ]
Class IE DC and UPS System Low Voltage 3-VLS-ITPP-502
[ ]
Containment Hydrogen Igniters 3-GEN-ITPP-510
[ ]
Normal Residual Heat Removal System Vibration and Dynamic Effects 3-TVS-ITPP-501
[ ]
Closed Circuit Television System 3-BDS-ITPP-502
[ ]
Steam Generator Slowdown System Precore Hot Functional 3-VZS-ITPP-501
[ ]
Diesel Generator Building Heating and Ventilation System 3-ZOS-ITPP-503
[ ]
Onsite Standby Power System Load Sequencing 3-MHS-ITPP-501
[ ]
Nuclear Island Mechanical Handling System 3-PXS-ITPP-505
[ ]
Passive Core CoolingSystem Automatic Depressurization Precore Hot Functional 3-CWS-ITPP-501
[ ]
Circulating Water System 3-FHS-ITPP-523
[ ]
Fuel Assembly Drag 3-RCS-ITPP-505
[ ]
RCS Precore Hot Functional Instrumentation Calibration Page 8 of 9
Enclosure 4 to ND-18-0034 Vogtle Electric Generating Plant - Units 3 and 4 Preoperational Test Procedure Completion Schedule Redacted Version Procedure Number/Name Completion Date 3-PWS-ITPP-501
[ ]
Potable Water System 3-GEN-ITPP-511
[ ]
Passive Core Cooling System Dynamic Effects 3-VBS-ITPP-501
[ ]
Nuclear Island Nonradloactlve Ventilation System 3-VAS-ITPP-501
[ ]
Radlologlcally Controlled Area Ventilation System 3-GEN-ITPP-512
[ ]
Chemical and Volume Control System Dynamic Effects 3-ZFS-1TPP-501
[ ]
Offslte Communication Systems 3-VES-ITPP-501
[ ]
Main Control Room Emergency Habltablllty System 3-VBS-ITPP-502
[ ]
Nuclear Island Nonradloactlve Ventilation System Precore Hot Functional 3-ELS-ITPP-501
[ ]
Plant Lighting System 3-GEN-ITPP-515 Feedwater, Steam Generator and Steam Generator Blowdown Systems Dynamic [ ]
Effects 3-VHS-ITPP-501
[ ]
Health Physics and Hot Machine Shop HVAC System 3-SJS-ITPP-501
[ ]
Seismic Monitoring System 3-VRS-ITPP-501
[ ]
Radwaste Building HVAC System Page 9 of 9
Southern Nuclear Operating Company ND-18-0034 Enclosure 6 Confidential Commercial Information Notice (This Enclosure consists of 2 pages, Including this cover page)
CONFIDENTIAL COMMERCIAL INFORMATION NOTICE Transmitted herewith are confidential commercial information and/or non-confidential commercial information versions of documents furnished to the NRG in connection with SNC's COL Operational Programs and Other License Conditions Implementation Schedule.
In order to conform to the requirements of 10 CFR 2.390 of the Commission's regulations concerning the protection of confidential commercial information so submitted to the NRC, the information which is confidential commercial information in the non-public version is contained within brackets, and where the confidential commercial information has been deleted in the public version, only the brackets remain (the information that was contained within the brackets in the public version having been deleted). The justification for claiming the information so designated as confidential commercial information is indicated in Enclosure 1, Affidavit for Withholding, accompanying this transmittal pursuant to 10 CFR 2.390(b)(1).