Letter Sequence Meeting |
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EPID:L-2025-LLA-0035, License Amendment Request: Addition of RCS Tcold Engineered Safety Feature Actuation System (ESFAS) Instrumentation Function (Open) |
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MONTHYEARPMNS20250218, Expedited License Amendment Request (LAR) to Add a New Tcold High Function to Technical Specification (TS) Table 3.3.8-1 for Passive Residual Heat Removal Actuation Logic Changes2025-02-12012 February 2025 Expedited License Amendment Request (LAR) to Add a New Tcold High Function to Technical Specification (TS) Table 3.3.8-1 for Passive Residual Heat Removal Actuation Logic Changes Project stage: Approval NL-25-0030, License Amendment Request: Addition of RCS Tcold Engineered Safety Feature Actuation System (ESFAS) Instrumentation Function2025-02-14014 February 2025 License Amendment Request: Addition of RCS Tcold Engineered Safety Feature Actuation System (ESFAS) Instrumentation Function Project stage: Request ML25055A2532025-03-0303 March 2025 SNC Slides - SNC Presentation - Public Meeting on March 3, 2025 - Proposed Vogtle 3 and 4 PRHR LAR Project stage: Meeting PMNS20250291, Follow-Up Meeting - Expedited License Amendment Request (LAR) to Add a New Tcold High Function to Technical Specification (TS) Table 3.3.8-1 for Passive Residual Heat Removal Actuation Logic Changes2025-03-0606 March 2025 Follow-Up Meeting - Expedited License Amendment Request (LAR) to Add a New Tcold High Function to Technical Specification (TS) Table 3.3.8-1 for Passive Residual Heat Removal Actuation Logic Changes Project stage: Meeting ML25079A3312025-03-0606 March 2025, 18 March 2025, 1 April 2025 Summary of March 18, 2025, Follow-Up Observation Meeting Held with Southern Nuclear Operating Company, Inc., Regarding a License Amendment Request to Change Table 3.3.8-1 for Vogtle Electric Generating Plant, Units 3 and 4 Project stage: Request ML25073A1032025-03-18018 March 2025 SNC Slides - Revised - Public Meeting on March 18, 2025 - Proposed Vogtle 3 and 4 PRHR LAR Project stage: Meeting ML25071A1032025-03-18018 March 2025 SNC Presentation Material - Public Meeting - Vogtle 3 and 4 - PRHR LAR - UFSAR 6.3.3.4.1 Markup - 2025-03-18 Project stage: Meeting ML25071A1022025-03-18018 March 2025 SNC Presentation Material - Public Meeting - Vogtle 3 and 4 - PRHR LAR - ISG-06 Applicability Table - 2025-03-18 Project stage: Meeting ML25071A1042025-03-18018 March 2025 SNC Slides -Public Meeting - Vogtle 3 and 4 - PRHR Actuation LAR - 2025-03-18 Project stage: Meeting ML25063A1902025-03-19019 March 2025 Summary of Observation Meeting Held with Southern Nuclear Operating Company, Inc., Regarding a License Amendment Request to Change Table 3.3.8 1 for Vogtle Electric Generating Plant, Units 3 and 4 Project stage: Meeting PMNS20250364, Closed Meeting - Expedited License Amendment Request (LAR) to Add a New Tcold High Function to Technical Specification (TS) Table 3.3.8-1 for Passive Residual Heat Removal Actuation Logic Changes2025-03-20020 March 2025 Closed Meeting - Expedited License Amendment Request (LAR) to Add a New Tcold High Function to Technical Specification (TS) Table 3.3.8-1 for Passive Residual Heat Removal Actuation Logic Changes Project stage: Meeting NL-25-0072, – Units 3 and 4, License Amendment Request: Addition of RCS Tcold Engineered Safety Feature Actuation System (ESFAS) Instrumentation Function - Supplement2025-03-31031 March 2025 – Units 3 and 4, License Amendment Request: Addition of RCS Tcold Engineered Safety Feature Actuation System (ESFAS) Instrumentation Function - Supplement Project stage: Supplement ML25079A3322025-04-0101 April 2025 March 18, 2025, Summary of Follow-Up Observation Meeting Held with Southern Nuclear Operating Company, Inc., Regarding a License Amendment Request to Change Table 3.3.8-1 for Vogtle Electric Generating Plant, Units 3 and 4 Project stage: Meeting ML25084A2622025-04-0202 April 2025 MTS - Meeting Summary - Vogtle 3 and 4 - Closed Meeting on 03-24-2025 - Proposed PRHR License Amendment Request Project stage: Meeting ML25092A1252025-04-0909 April 2025 Request for Withholding Information from Public Disclosure License Amendment Request Supplement to Add New Reactor Coolant System Tcold - High Function for the Technical Specification for the Engineered Safety Feature Actuation System Instr Project stage: Withholding Request Acceptance ML25100A0532025-04-24024 April 2025 Regulatory Audit Plan in Support of the Review of the License Amendment Request to Add a New Tcold - High Function to Engineered Safety Feature Actuation System Instrumentation Project stage: Other ML25176A1772025-06-25025 June 2025 NRR E-mail Capture - for Your Action - RAIs - Vogtle 3 and 4 Technical Specifications (TS) 3.3.8, Engineered Safeguards Actuation System Instrumentation License Amendment Request (L-2025-LLA-0035) Project stage: RAI ML25177C9762025-07-0101 July 2025 Extension of the Regulatory Audit Plan in Support of the Review of the LAR to Add a New Reactor Coolant System Tcold - High Function to Engineered Safety Feature Actuation System Instrumentation Project stage: Approval ML25199A0482025-08-0808 August 2025 Issuance of Expedited Amendment to Revise Technical Specification 3.3.8, Engineered Safety Feature Actuation System (ESFAS) Instrumentation Project stage: Approval 2025-03-06
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6.3-40 Revision 12.1 VEGP 3&4 - UFSAR 6.3.3.4 Shutdown Events The passive core cooling system components are available whenever the reactor is critical and when reactor coolant energy is sufficiently high to require passive safety injection. During low-temperature physics testing, the core decay heat levels are low and there is a negligible amount of stored energy in the reactor coolant. Therefore, an event comparable in severity to events occurring at operating conditions is not possible and passive core cooling system equipment is not required. The possibility of a loss of coolant accident during plant startup and shutdown has been considered.
During shutdown conditions, some of the passive core cooling system equipment is isolated. In addition, since the normal residual heat removal system is not a safety-related system, its loss is considered. Containment recirculation may be impacted by shutdown maintenance activities which remove access hatches or curbs located at the 107'-2 plant elevation. Subsection 3.4.1.2.2.1 discusses containment flooding events in further detail.
As a result, gravity injection is automatically actuated when required during shutdown conditions prior to refueling cavity floodup, as discussed in Subsection 6.3.3.3.2. The operator can also manually actuate other passive core cooling system equipment, such as the passive residual heat removal heat exchanger, if required for accident mitigation during shutdown conditions when the equipment does not automatically actuate.
6.3.3.4.1 Loss of Startup Feedwater During Hot Standby, Cooldowns, and Heat-ups During normal cooldowns, the steam generators are supplied by the startup feedwater pumps and steam from the steam generator is directed to either the main condenser or to the atmosphere. There are two nonsafety-related startup feedwater pumps, each of which is capable of providing sufficient feedwater flow to both steam generators to remove decay heat. These pumps are also automatically loaded on the nonsafety-related diesel-generators in the event normal ac power and offsite power are lost. Since these pumps are nonsafety-related, their failure is considered.
In the event of a loss of startup feedwater, the passive residual heat removal heat exchanger is automatically actuated on Low-2 steam generator narrow range water level and provides safety-related heat removal. The passive residual heat removal heat exchanger can maintain the reactor coolant system temperature, as well as provide for reactor coolant system cooldown to conditions where the normal residual heat removal system can be operated.
Since the chemical and volume control system makeup pumps are nonsafety-related, they may not be available. In this case, the core makeup tanks automatically actuate as the cooldown continues and the pressurizer level decreases. The core makeup tanks operate in a water recirculation mode to maintain reactor coolant system inventory while the passive residual heat removal heat exchanger is operating.
The in-containment refueling water storage tank provides the heat sink for the passive residual heat removal heat exchanger. Initially, the heat addition increases the water temperature. Within one to two hours, the water reaches saturation temperature and begins to boil. The steam generated in the in-containment refueling water storage tank discharges to containment. Because the containment integrity is maintained during cooldown Modes 3 and 4, the passive containment cooling system provides the safety-related ultimate heat sink. Therefore, most of the steam generated in the in-containment refueling water storage tank is condensed on the inside of the containment vessel and drains back into the in-containment refueling water storage tank via the condensate return gutter arrangement. This allows it to function as a heat sink for greater than 14 days, as discussed in Subsection 6.3.1.2.1.