ML18085A627
| ML18085A627 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 04/20/2018 |
| From: | Paul Kallan NRC/NRO/DNRL/LB4 |
| To: | Whitley B H Southern Nuclear Operating Co |
| kallan p/415-2809 | |
| Shared Package | |
| ML18085A620 | List: |
| References | |
| EPID L-2017-LLA-0093, LAR 17-023 | |
| Download: ML18085A627 (12) | |
Text
ATTACHMENT TO LICENSE AMENDMENT NO. 122 TO FACILITY COMBINED LICENSE NO. NPF-92 DOCKET NO.52-026 Replace the following pages of the Facility Combined License No. NPF-92 with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change. Facility Combined License No. NPF-92 REMOVE INSERT 7 7 Appendix A to Facility Combined License Nos. NPF-91 and NPF-92 REMOVE INSERT ii ii 3.3.13-1 3.3.13-1 3.3.13-2 3.3.13-2 --- 3.3.13-3 3.7.4-1 3.7.4-1 Appendix C to Facility Combined License No. NPF-92 REMOVE INSERT C-167 C-167 C-168 C-168 C-173 C-173 C-178 C-178 C-367 C-367 (7) Reporting Requirements (a) Within 30 days of a change to the initial test program described in FSAR Section 14, Initial Test Program, made in accordance with 10 CFR 50.59 or in accordance with 10 CFR Part 52, Appendix D, Section VIII, for Changes and SNC shall report the change to the Director of NRO, or the designee, in accordance with 10 CFR 50.59(d). (b) SNC shall report any violation of a requirement in Section 2.D.(3), Section 2.D.(4), Section 2.D.(5), and Section 2.D.(6) of this license within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Initial notification shall be made to the NRC Operations Center in accordance with 10 CFR 50.72, with written follow up in accordance with 10 CFR 50.73. (8) Incorporation The Technical Specifications, Environmental Protection Plan, and ITAAC in Appendices A, B, and C, respectively of this license, as revised through Amendment No. 122, are hereby incorporated into this license. (9) Technical Specifications The technical specifications in Appendix A to this license become effective upon a Commission finding that the acceptance criteria in this license (ITAAC) are met in accordance with 10 CFR 52.103(g). (10) Operational Program Implementation SNC shall implement the programs or portions of programs identified below, on or before the date SNC achieves the following milestones: (a) Environmental Qualification Program implemented before initial fuel load; (b) Reactor Vessel Material Surveillance Program implemented before initial criticality; (c) Preservice Testing Program implemented before initial fuel load; (d) Containment Leakage Rate Testing Program implemented before initial fuel load; (e) Fire Protection Program 1. The fire protection measures in accordance with Regulatory Guide (RG) 1.189 for designated storage building areas (including adjacent fire areas that could affect the storage area) implemented before initial receipt 7 Amendment No. 122 Technical Specifications VEGP Units 3 and 4 ii Amendment No. 123 (Unit 3) Amendment No. 122 (Unit 4) TABLE OF CONTENTS Page 3.3 INSTRUMENTATION (continued) 3.3.8 Engineered Safety Feature Actuation System (ESFAS) Instrumentation ...................................................................................... 3.3.8 - 1 3.3.9 Engineered Safety Feature Actuation System (ESFAS) Manual Initiation ..................................................................................... 3.3.9 - 1 3.3.10 Engineered Safety Feature Actuation System (ESFAS) Reactor Coolant System (RCS) Hot Leg Level Instrumentation ......... 3.3.10 - 1 3.3.11 Engineered Safety Feature Actuation System (ESFAS) Startup Feedwater Flow Instrumentation ............................................. 3.3.11 - 1 3.3.12 Engineered Safety Feature Actuation System (ESFAS) Reactor Trip Initiation ........................................................................... 3.3.12 - 1 3.3.13 Engineered Safety Feature Actuation System (ESFAS) Main Control Room Isolation, Air Supply Initiation, and Electrical Load De-energization ........................................................... 3.3.13 - 1 3.3.14 Engineered Safety Feature Actuation System (ESFAS) Spent Fuel Pool Level Instrumentation ................................................ 3.3.14 - 1 3.3.15 Engineered Safety Feature Actuation System (ESFAS) Actuation Logic Operating ................................................................ 3.3.15 - 1 3.3.16 Engineered Safety Feature Actuation System (ESFAS) Actuation Logic Shutdown ................................................................ 3.3.16 - 1 3.3.17 Post Accident Monitoring (PAM) Instrumentation ...................................... 3.3.17 - 1 3.3.18 Remote Shutdown Workstation (RSW) ..................................................... 3.3.18 - 1 3.3.19 Diverse Actuation System (DAS) Manual Controls ................................... 3.3.19 - 1 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits ............................................................... 3.4.1 - 1 3.4.2 RCS Minimum Temperature for Criticality ................................................... 3.4.2 - 1 3.4.3 RCS Pressure and Temperature (P/T) Limits .............................................. 3.4.3 - 1 3.4.4 RCS Loops ................................................................................................... 3.4.4 - 1 3.4.5 Pressurizer ................................................................................................... 3.4.5 - 1 3.4.6 Pressurizer Safety Valves ............................................................................ 3.4.6 - 1 3.4.7 RCS Operational LEAKAGE ........................................................................ 3.4.7 - 1 3.4.8 Minimum RCS Flow ..................................................................................... 3.4.8 - 1 3.4.9 RCS Leakage Detection Instrumentation .................................................... 3.4.9 - 1 3.4.10 RCS Specific Activity .................................................................................. 3.4.10 - 1 3.4.11 Automatic Depressurization System (ADS) Operating .......................... 3.4.11 - 1 3.4.12 Automatic Depressurization System (ADS) Shutdown, RCS Intact ...... 3.4.12 - 1 3.4.13 Automatic Depressurization System (ADS) Shutdown, RCS Open ...... 3.4.13 - 1 3.4.14 Low Temperature Overpressure Protection (LTOP) .................................. 3.4.14 - 1 3.4.15 RCS Pressure Isolation Valve (PIV) Integrity ............................................ 3.4.15 - 1 3.4.16 Reactor Vessel Head Vent (RVHV) ........................................................... 3.4.16 - 1 3.4.17 Steam Generator (SG) Tube Integrity ........................................................ 3.4.17 - 1
C-167 Amendment No. 122 2.2.5 Main Control Room Emergency Habitability System Design Description The main control room emergency habitability system (VES) provides a supply of breathable air for the main control room (MCR) occupants and maintains the MCR at a positive pressure with respect to the surrounding areas whenever ac power is not available to operate the nuclear island nonradioactive ventilation system (VBS), MCR differential pressure is not maintained, or high radioactivity is detected in the MCR air supply. (See Section 3.5 for Radiation Monitoring). The VES also limits the heatup of the MCR, the 1E instrumentation and control (I&C) equipment rooms, and the Class 1E dc equipment rooms by using the heat capacity of surrounding structures. The VES is as shown in Figure 2.2.5-1 and the component locations of the VES are as shown in Table 2.2.5-6. 1. a)
C-168 Amendment No. 122 b) c) d) e) The system provides shielding below the VES filter that is sufficient to ensure main control room doses are below an acceptable level during VES operation. c) The MCR Load Shed Panels identified in Table 2.2.5-1 perform their active safety function after receiving a signal from the PMS.
C-173 Amendment No. 122 C-178 Amendment No. 122 Table 2.2.5-5 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 270 2.2.05.07c 271 2.2.05.07d 880 2.2.05.07e 7e) Shielding below the VES filter is capable of providing attenuation that is sufficient to ensure main control room doses are below an acceptable level during VES operation. Inspection will be performed for the existence of a report verifying that the as-built shielding meets the requirements for functional capability. A report exists and concludes that the as-built shielding identified in Table 2.2.5-1 meets the functional requirements and exists below the filtration unit, and within its vertical projection. 272 2.2.05.08 273 2.2.05.09a 274 2.2.05.09b 877 2.2.05.09c 9.c) The MCR Load Shed Panels identified in Table 2.2.5-1 perform their active safety function after receiving a signal from the PMS. Testing will be performed on the MCR Load Shed Panels listed in Table 2.2.5-1 using real or simulated signals into the PMS. The MCR Load Shed Panels identified in Table 2.2.5-1 perform their active safety function identified in the table after receiving a signal from the PMS.
C-367 Amendment No. 122 2.7 HVAC Systems 2.7.1 Nuclear Island Nonradioactive Ventilation System Design Description The nuclear island nonradioactive ventilation system (VBS) serves the main control room (MCR), control support area (CSA), Class 1E dc equipment rooms, Class 1E instrumentation and control (I&C) rooms, Class 1E electrical penetration rooms, Class 1E battery rooms, remote shutdown room (RSR), reactor coolant pump trip switchgear rooms, adjacent corridors, and passive containment cooling system (PCS) valve room during normal plant operation. The VBS consists of the following independent subsystems: the main control room/control support area HVAC subsystem, the class 1E electrical room HVAC subsystem, and the passive containment cooling system valve room heating and ventilation subsystem. The VBS provides heating, ventilation, and cooling to the areas served when ac power is available. The system provides breathable air to the control room and maintains the main control room and control support area areas at a slightly positive pressure with respect to the adjacent rooms and outside environment during normal operations. The VBS monitors the main control room supply air for radioactive particulate and iodine concentrations and provides filtration of main control room/control support area air during conditions of abnormal - airborne radioactivity. In addition, the VBS isolates the HVAC penetrations in the main control room boundary on - particulate or iodine radioactivity in the main control room supply air duct or on a loss of ac power for more than 10 minutes or if main control room differential than 10 minutes. The Sanitary Drainage System (SDS) also isolates a penetration in the main control room boundary on - particulate or iodine radioactivity in the main control room supply air duct or on a loss of ac power for more than 10 minutes or if main control room . Additional penetrations from the SDS and Potable Water System (PWS) into the main control room boundary are maintained leak tight using a loop seal in the piping, and the Waste Water System (WWS) is isolated using a normally closed safety related manual isolation valve. These features support operation of the main control room emergency habitability system (VES), and have been included in Tables 2.7.1-1 and 2.7.1-2. The VBS is as shown in Figure 2.7.1-1 and the component locations of the VBS are as shown in Table 2.7.1-5. 1. 2. a) The components identified in Table 2.7.1-1 as ASME Code Section III are designed and constructed in accordance with ASME Code Section III requirements. b) The piping identified in Table 2.7.1-2 as ASME Code Section III is designed and constructed in accordance with ASME Code Section III requirements. 3. a) Pressure boundary welds in components identified in Table 2.7.1-1 as ASME Code Section III meet ASME Code Section III requirements. b) Pressure boundary welds in piping identified in Table 2.7.1-2 as ASME Code Section III meet ASME Code Section III requirements.