Scenario 1 — Load Reduction / LBLOCA
Simulator | 8 Events | 2 Critical Tasks
Initial Conditions: Salem Unit 2 is at 100% power BOL
Turnover: The crew is directed to reduce power to 89% power at 10% per hour IAW S2.OP-IO.ZZ-0004 using boration, control rods and turbine load control in preparation for Main Turbine Valve testing.
Turnover: The crew is directed to reduce power to 89% power at 10% per hour IAW S2.OP-IO.ZZ-0004 using boration, control rods and turbine load control in preparation for Main Turbine Valve testing.
Major Events:
- Planned Load Reduction to 89% at 10%/hour
- 24 Vacuum Pump trips
- 2N41 Power Range Channel Fails High (TS)
- RCS Leak — 20 gpm (TS)
- Large Break LOCA (leak worsens to 350 gpm)
- Auto SI fails to actuate on both trains
- #2 ECAC Fails to Start on SEC Signal
- Two Phase A valves (2CV116 and 284) fail to close
▶ Show Event Sequence & Expected Responses
| # | Event | Expected Crew Response |
|---|---|---|
| 1 | Planned Load Reduction to 89% | CRS briefs crew on power reduction. RO initiates boration IAW S2.OP-SO.CVC-0006. PO initiates turbine load reduction IAW S2.OP-SO.TRB-0002 — adjust ramp rate to 10%/hr, set to 89%, select GO. |
| 2 | 24 Vacuum Pump trips | PO reports trip. CRS enters S2.OP-AB.COND-0001, Loss of Condenser Vacuum. PO initiates Att 1 CAS, dispatches operator for Att 2 local checks. PO starts 22 and 25 vacuum pumps — 22 trips after start, 25AR25 fails to open. Backpressure stabilizes below trip setpoint. |
| 3 | 2N41 Power Range Channel fails high | RO reports rods stepping in, no runback. RO places rod control in Manual. CRS enters S2.OP-AB.NIS-0001, NIS Malfunction. CRS directs removal of 2N41 from service IAW S2.OP-SO.RPS-0001 (place in Tripped Condition). CRS evaluates TS 3.3.1.1 — one PR channel inoperable. |
| 4 | RCS Leak — 20 gpm inside containment | RO reports 2R11A containment radiation rising, PZR level lowering, RCS pressure lowering. CRS enters S2.OP-AB.RC-0001, RCS Leak. RO determines leak rate. RO swaps to centrifugal charging pump. CRS evaluates TS 3.4.7.2 for identified/unidentified leakage. |
| 5 | Large Break LOCA — leak worsens to 350 gpm | RO reports leak exceeds makeup capability. CRS implements Att 1 CAS — Trip the reactor. RO manually trips reactor, verifies trip. CRS enters EOP-TRIP-1. |
| 6 | Auto SI fails to actuate on both trains | RO manually actuates SI on one train, verifies other train actuated. Continues EOP-TRIP-1 immediate actions: backs up turbine trip, verifies 4KV vital buses energized, verifies SI initiated. |
| 7 | #2 ECAC fails to start on SEC signal | PO reports #2 ECAC failed. PO blocks and resets 2C SEC. RO starts #2 ECAC. PO throttles AFW flow. RO reports containment pressure >15 psig — Phase B and Spray auto-initiated. MSLI auto-initiated. |
| 8 | Two Phase A valves (2CV116, 284) fail to close | PO reports 2CV116 and 284 NOT in required position. CRS directs manual closure. At least one valve on each penetration must be closed before transitioning out of TRIP-1. (Critical Task #1) |
Critical Tasks:
CT#1 (CT-11): Close containment isolation valves such that at least one valve is closed on each Phase A penetration before transition out of TRIP-1. Safety significance: preserves containment boundary to minimize fission product release following LOCA.
CT#2 (CT-36): Transfer to cold leg recirculation before RWST Lo-Lo level (1.2 feet) is reached or ECCS pump cavitation. Includes time-critical operator actions: (1) Close 2SJ69 within 3.7 min of RWST Lo Level, (2) Stop 22 CS pump within 5.5 min, (3) ECCS pumps verified in recirculation within 11.2 min. Safety significance: failure to transfer before RWST empties results in loss of all pumped safety injection and containment spray.
CT#1 (CT-11): Close containment isolation valves such that at least one valve is closed on each Phase A penetration before transition out of TRIP-1. Safety significance: preserves containment boundary to minimize fission product release following LOCA.
CT#2 (CT-36): Transfer to cold leg recirculation before RWST Lo-Lo level (1.2 feet) is reached or ECCS pump cavitation. Includes time-critical operator actions: (1) Close 2SJ69 within 3.7 min of RWST Lo Level, (2) Stop 22 CS pump within 5.5 min, (3) ECCS pumps verified in recirculation within 11.2 min. Safety significance: failure to transfer before RWST empties results in loss of all pumped safety injection and containment spray.
EOP Pathway:
S2.OP-AB.COND-0001 (vacuum pump trip) → S2.OP-AB.NIS-0001 (PR channel fail) → S2.OP-AB.RC-0001 (RCS leak) → EOP-TRIP-1 (reactor trip/SI) → EOP-LOCA-1 (RCS leak identified, SI termination criteria, RWST Lo Level) → EOP-FRTS-1 (possible Purple path on Thermal Shock — enter/exit, no actions) → EOP-LOCA-3 (transfer to cold leg recirculation) → Scenario terminated after ECCS aligned to recirculation
S2.OP-AB.COND-0001 (vacuum pump trip) → S2.OP-AB.NIS-0001 (PR channel fail) → S2.OP-AB.RC-0001 (RCS leak) → EOP-TRIP-1 (reactor trip/SI) → EOP-LOCA-1 (RCS leak identified, SI termination criteria, RWST Lo Level) → EOP-FRTS-1 (possible Purple path on Thermal Shock — enter/exit, no actions) → EOP-LOCA-3 (transfer to cold leg recirculation) → Scenario terminated after ECCS aligned to recirculation
Source: 20-01 ESG-1 | View Scenario PDF
Connections
- Related systems: RCS, ECCS, Containment, Containment Spray, RPS/SSPS, Feed & Condensate, AFW
- Related EOPs: EOP-TRIP-1 — Reactor Trip or Safety Injection, EOP-LOCA-1 — Loss of Reactor or Secondary Coolant, EOP-LOCA-3 — Transfer to Cold Leg Recirculation
- Related procedures: AB.RC-0001 — Reactor Coolant System Leak, AB.CHEM-0001 — Secondary Chemistry Abnormality
- Related exam: 2023 NRC Operating Exam