ML23158A209
| ML23158A209 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 07/19/2023 |
| From: | Gleaves W, Lauren Nist NRC/NRR/VPOB |
| To: | Brown R Southern Nuclear Operating Co |
| Gleaves W | |
| Shared Package | |
| ML23158A205 | List: |
| References | |
| EPID L-2023-LLA-0056, LAR-23-005 | |
| Download: ML23158A209 (8) | |
Text
ATTACHMENT TO LICENSE AMENDMENT NO. 189
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
- 7a
- 7b
- 7c
- 7d
- 7e
Appendix A to Facility Combined License No. NPF-92
REMOVE INSERT
3.0-2 3.0- 2
(7) Reporting Requirements
(a) Within 30 days of a change to the initial test program described in UFSAR 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, Processes for Changes and Departures, SNC shall report the change to the Director of NRO, or the Directors 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 Oper ations Center in ac cordance 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 t h r o ug h Am e ndm ent No. 189, ar e h er e b y i n c o r p ora t e d i n t o t h i s l ic en se.
(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) with the following exceptions:
(a) Prior to initial criticality of the reactor core while operating in plant operational Mode 5 (Cold Shutdown) or Mode 6 (Refueling) the following TS are temporarily excluded from becoming effective:
TS 3.3.8, Engineered Safety Feature Actuation System (ESFAS)
Instrumentation, Table 3.3.8-1 o Function 14, RCS Wide Range Pressure - Low o Function 15, Core Makeup Tank (CMT) Level - Low 3 o Function 16, CMT Level - Low 6 o Function 18, IRWST Lower Narrow Range Level - Low 3 TS 3.3.9, Engineered Safety Feature Actuation System (ESFAS)
Manual Initiation, Table 3.3.9-1 o Function 1, Safeguards Actuation - Manual Initiation o Function 6, ADS Stages 1, 2 & 3 Actuation - Manual Initiation o Function 7, ADS Stage 4 Actuation - Manual Initiation o Function 8, Passive Containment Cooling Actuation - Manual Initiation o Function 9, Passive Residual Heat Removal Heat Exchanger Actuation - Manual Initiation
7 Amendment No. 189 o Function 12, In-Containment Refueling Water Storage Tank (IRWST) Injection Line Valve Actuation - Manual Initiation o Function 13, IRWST Containment Recirculation Valve Actuation
- Manual Initiation TS 3.3.10, Engineered Safety Feature Actuation System (ESFAS)
Reactor Coolant System (RCS) Hot Leg Level Instrumentation TS 3.3.14, Engineered Safety Feature Actuation System (ESFAS)
In-containment Refueling Water Storage Tank (IRWST) and Spent Fuel Pool Level Instrumentation, Table 3.3.14-1 o Function 1, Spent Fuel Pool Level - Low 2 TS 3.3.19, Diverse Actuation System (DAS) Manual Controls, Table 3.3.19-1 o Function 2, Passive Residual Heat Removal Heat Exchanger (PRHR HX) control and In-Containment Refueling Water Storage Tank (IRWST) gutter control valves o Function 4, Automatic Depressurization System (ADS) stage 1 valves o Function 5, ADS stage 2 valves o Function 6, ADS stage 3 valves o Function 7, ADS stage 4 valves o Function 8, IRWST injection squib valves o Function 9, Containment recirculation valves o Function 10, Passive containment cooling drain valves o Function 11, Selected containment isolation valves TS 3.3.20, Automatic Depressurization System (ADS) and In-containment Refueling Water Storage Tank (IRWST) Injection Blocking Device, Table 3.3.20-1 o Function 2, ADS and IRWST Injection Block Switches for Manual Unblocking TS 3.4.12, Automatic Depressurization System (ADS) - Shutdown, RCS Intact TS 3.4.13, Automatic Depressurization System (ADS) - Shutdown, RCS Open TS 3.5.5, Passive Residual Heat Removal Heat Exchanger (PRHR HX) - Shutdown, Reactor Coolant System (RCS) Intact TS 3.5.7, In-containment Refueling Water Storage Tank (IRWST) -
Shutdown, MODE 5 TS 3.5.8, In-containment Refueling Water Storage Tank (IRWST) -
Shutdown, MODE 6 TS 3.6.7, Containment Penetrations TS 3.7.13, Spent Fuel Pool Cooling System (SFS) Containment Isolation Valves
7a Amendment No. 189 (b) Prior to initial criticality of the reactor core while operating in plant operational Mode 4 (Safe Shutdown) when any cold leg temperature is 275°F the following TS are temporarily excluded from becoming effective:
TS 3.3.8, Engineered Safety Feature Actuation System (ESFAS)
Instrumentation, Table 3.3.8-1 o Function 14, RCS Wide Range Pressure - Low o Function 15, Core Makeup Tank (CMT) Level - Low 3 o Function 16, CMT Level - Low 6 o Function 18, IRWST Lower Narrow Range Level - Low 3 o Function 19, Reactor Coolant Pump Bearing Water Temperature
- High 2 TS 3.3.9, Engineered Safety Feature Actuation System (ESFAS)
Manual Initiation, Table 3.3.9-1 o Function 3, Containment Isolation - Manual Initiation o Function 6, ADS Stages 1, 2 & 3 Actuation - Manual Initiation o Function 7, ADS Stage 4 Actuation - Manual Initiation o Function 8, Passive Containment Cooling Actuation - Manual Initiation o Function 12, In-Containment Refueling Water Storage Tank (IRWST) Injection Line Valve Actuation - Manual Initiation o Function 13, IRWST Containment Recirculation Valve Actuation
- Manual Initiation TS 3.3.13, Engineered Safety Feature Actuation System (ESFAS)
Main Control Room Isolation, Air Supply Initiation, and Electrical Load De-energization, Table 3.3.13-1 o Function 1, Main Control Room Air Supply Iodine or Particulate Radiation - High 2 TS 3.3.19, Diverse Actuation System (DAS) Manual Controls, Table 3.3.19-1 o Function 4, Automatic Depressurization System (ADS) stage 1 valves o Function 5, ADS stage 2 valves o Function 6, ADS stage 3 valves o Function 7, ADS stage 4 valves o Function 8, IRWST injection squib valves o Function 9, Containment recirculation valves o Function 10, Passive containment cooling drain valves o Function 11, Selected containment isolation valves
7b Amendment No. 189 TS 3.3.20, Automatic Depressurization System (ADS) and In-containment Refueling Water Storage Tank (IRWST) Injection Blocking Device, Table 3.3.20-1 o Function 2, ADS and IRWST Injection Block Switches for Manual Unblocking TS 3.4.11, Automatic Depressurization System (ADS) - Operating TS 3.5.1, Accumulators TS 3.5.6, In-containment Refueling Water Storage Tank (IRWST) -
Operating TS 3.6.1, Containment TS 3.6.2, Containment Air Locks TS 3.6.3, Containment Isolation Valves TS 3.6.6, Passive Containment Cooling System (PCS)
TS 3.6.8, pH Adjustment TS 3.7.4, Secondary Specific Activity TS 3.7.10, Steam Generator (SG) Isolation Valves only for PORV and PORV block valves (SG blowdown isolation valve not excluded)
(c) Prior to initial criticality of the reactor core while operating in plant operational Mode 4 (Safe Shutdown) with all four cold leg temperatures
> 275°F the following TS are temporarily excluded from becoming effective:
TS 3.3.8, Engineered Safety Feature Actuation System (ESFAS)
Instrumentation, Table 3.3.8-1 o Function 3, Containment Radioactivity - High o Function 18, IRWST Lower Narrow Range Level - Low 3 o Function 19, Reactor Coolant Pump Bearing Water Temperature
- High 2 TS 3.3.9, Engineered Safety Feature Actuation System (ESFAS)
Manual Initiation, Table 3.3.9-1 o Function 3, Containment Isolation - Manual Initiation o Function 6, ADS Stages 1, 2 & 3 Actuation - Manual Initiation o Function 7, ADS Stage 4 Actuation - Manual Initiation o Function 8, Passive Containment Cooling Actuation - Manual Initiation o Function 13, IRWST Containment Recirculation Valve Actuation
- Manual Initiation o Function 14, SG Power Operated Relief Valve and Block Valve Isolation - Manual Initiation
7c Amendment No. 189 TS 3.3.13, Engineered Safety Feature Actuation System (ESFAS)
Main Control Room Isolation, Air Supply Initiation, and Electrical Load De-energization, Table 3.3.13-1 o Function 1, Main Control Room Air Supply Iodine or Particulate Radiation - High 2 TS 3.3.19, Diverse Actuation System (DAS) Manual Controls, Table 3.3.19-1 o Function 4, Automatic Depressurization System (ADS) stage 1 valves o Function 5, ADS stage 2 valves o Function 6, ADS stage 3 valves o Function 7, ADS stage 4 valves o Function 9, Containment recirculation valves o Function 10, Passive containment cooling drain valves o Function 11, Selected containment isolation valves TS 3.4.11, Automatic Depressurization System (ADS) - Operating TS 3.5.1, Accumulators TS 3.5.6, In-containment Refueling Water Storage Tank (IRWST) -
Operating only for containment recirculation flow paths (injection flow paths not excluded)
TS 3.6.1, Containment TS 3.6.2, Containment Air Locks TS 3.6.3, Containment Isolation Valves TS 3.6.6, Passive Containment Cooling System (PCS)
TS 3.6.8, pH Adjustment TS 3.7.4, Secondary Specific Activity TS 3.7.10, Steam Generator (SG) Isolation Valves only for PORV and PORV block valves (SG blowdown isolation valve not excluded)
7d Amendment No. 189 (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) Environme nt al Qualif icat ion Program impleme nted bef ore init ial 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;
- 1. T he f ire 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
7e Amendment No. 189 Technical Specifications LCO Applicability 3.0
3.0 LCO Applicability
LCO 3.0.5 Equipment removed from service or declared inoperable to comply with ACTIONS may be returned to service under administrative control solely to perform testing required to demonstrate its OPERABILITY or the OPERABILITY of other equipment. This is an exception to LCO 3.0.2 for the system returned to service under administrative control to perform the test required to demonstrate OPERABILITY.
LCO 3.0.6 When a supported system LCO is not met solely due to a support system LCO not being met, the Conditions and Required Actions associated with this supported system are not required to be entered. Only the support system LCO ACTIONS are required to be entered. This is an exception to LCO 3.0.2 for the supported system. In this event, additional evaluations and limitations may be required in accordance with Specification 5.5.7, Safety Function Determination Program (SFDP). If a loss of safety function is determined to exist by this program, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered.
When a support systems Required Action directs a supported system to be declared inoperable or directs entry into Conditions and Required Actions for a supported system, the applicable Conditions and Required Actions shall be entered in accordance with LCO 3.0.2.
LCO 3.0.7 Test Exception LCOs 3.1.8 and 3.1.10 allow specified Technical Specification (TS) requirements to be changed to permit performance of special tests and operations. Unless otherwise specified, all other TS requirements remain unchanged. Compliance with Test Exception LCOs is optional. When a Test Exception LCO is desired to be met but is not met, the ACTIONS of the Test Exception LCO shall be met. When a Test Exception LCO is not desired to be met, entry into a MODE or other specified condition in the Applicability shall be made in accordance with the other applicable Specifications.
Additionally, for Unit 4 only, Combined License Condition 2.D(9) provides temporary exclusions for specified TS requirements prior to becoming permanently effective at initial criticality of the reactor core. Compliance with TS requirements that are excluded from becoming effective while operating in MODES 4, 5, and 6 in accordance with the COL Condition is optional.
VEGP Units 3 and 4 3.0 - 2 Amendment No. 117 (Unit 3)
Amendment No. 189 (Unit 4)