ML23199A160
| ML23199A160 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 02/03/2023 |
| From: | NRC/RGN-III/DORS/OB |
| To: | Point Beach |
| Jim Nance | |
| Shared Package | |
| ML22007A027 | List: |
| References | |
| Download: ML23199A160 (1) | |
Text
Form 3.3-1 Scenario Outline Facility:
Point Beach Scenario #: 1 Scenario Source:
Op. Test #: Feb 2023 Examiners:
Applicants/
Operators:
Initial Conditions:
100% Power, MOC, Boron @ 1000 ppm Turnover:
Unload and secure G01 EDG from loaded surveillance.
Critical Tasks:
- 1. Close PORV before adequate SCM is lost
- 2. Actuate Manual Rx Trip prior to Step 4 of CSP.S-1 Event No.
Malf.
No.
Event Type*
Event Description 1
N/A (N) BOP Unload G01 EDG following surveillance 2
(C) BOP (C/TS) SRO High Vibrations on W-1B1, Containment Accident Recirc Fan 3
(C) ATC (C/TS) SRO 1RC-431C (PZR PORV) Sticks open (CT) 4 (C) BOP (C) SRO CW Degradation (Fish intrusion) 5 (R) ATC Perform Rapid Power Reduction 6
(C/MC) ATC (C/TS) SRO Reactor Coolant Leak / Charging to maximum to control PZR Level 7
(M) CREW LOCA / SI / Auto Rx Trip Fails 8
(C/MC) ATC (C) SRO Manual Rx Trip successful in inserting Control Rods (CT)
Termination Criteria:
Critical Tasks have been evaluated Crew transition to EOP-1 At the discretion of the Lead Evaluator
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS)Tech Spec, (MC)Manual Control
CT1: Close PZR PORV before adequate SCM is lost Initiating Cue: Both of the following:
o Annunciators for PZR level deviation o Indication that (RED light) that the PORV is open o Indications of high temperature in discharge line o Lowering PZR pressure and level Performance Feedback: All of the following:
o Valve indication (GREEN light) that the block valve is closed o Lowering temperature indications in discharge line o Raising PZR pressure and level Success Path: 1RC-431C PZR PORV is isolated by closing 1RC-515 (PORV Block Valve)
Measurable Performance Standard: Manually close PZR block valve prior to Reactor Coolant Subcooling Margin of 30°F.
Safety Significance: If no operator action is taken, a loss of Subcooling Margin would occur. A loss of Subcooling Margin would result in loss of adequate core cooling as the primary system reaches saturation conditions.
CT2: Manually Trip the Reactor prior to Step 4 of CSP-S.1 Initiating Cue: Both of the following:
o Rod bottom lights NOT LIT o Reactor Power greater than 5%
Performance Feedback: All of the following:
o All rod bottom lights LIT o Reactor Power lowering into NIS Source Range Success Path: By actuating Alternate Rod Insertion, this will insert all withdrawn control rods into the core shutting down the nuclear chain reaction as part of EOP-1 Step 1 RNO AND CSP-S.1 Step 1 (Immediate Operator Actions).
Measurable Performance Standard: Insert negative reactivity into the core prior to entering step 4 of CSP-S.1.
Safety Significance: If no operator action is taken, the reactor will continue to generate power and continue to challenge the Core Cooling Safety Function. Step 4 of CSP-S.1 will shift mitigation strategies to boration to restore the subcriticality safety function.
Scenario Executive Summary Initial Conditions / Turnover:
Point Beach Unit 1 will be at 100% during the middle of the operating cycle with RCS Boron concentration at 1000 ppm. No Xenon transient is in progress. No equipment is out of service.
Technical Specification LCO 3.8.1 Condition E was entered approximately two (2) hours ago to conduct monthly surveillance of G-01, Emergency Diesel Generator. All required actions for this LCO Condition have been completed. TS-81, Emergency Diesel Generator G-01 Monthly Surveillance has been completed up to Step 5.50. All required data was recorded, and the analysis will be completed by the off-going shift.
Direction(s) for the Shift:
Shutdown the G-01, Emergency Diesel Generator in accordance with TS-81, Emergency Diesel Generator G-01 Monthly Surveillance beginning at Step 5.50. Auxiliary Operators have been briefed and standing by to complete the evolution.
Event #1 - G-01, EDG Surveillance Crew will continue with TS 81 at Step 5.50 and complete the unloading, shutdown, and return to standby condition G-01, Emergency Diesel Generator. Attachment E is not required to be performed. This event is completed once the EDG is aligned in the standby condition and Step 5.66 is complete and with the concurrence of the lead evaluator.
Event #2 - High Vibration on W-1B1, Containment Accident Recirculation Fan A high vibration condition will develop on the W-1B1, Containment Recirculation Fan. Crew will respond to ARB C01 B 4-3 and secure the fan and start the W-1A1 fan. SRO will determine Tech Spec LCO 3.6.6 (Containment Cooling Systems) Condition C. This event is complete when the A Containment Accident Fan is started, and Tech Specs have been determined and with the concurrence of the Lead Evaluator.
Event #3 - 1RC-431C (PZR PORV) Sticks Open A malfunction will cause 1RC-431C to stick open (Rate of Leakage provides ~2 min before trip criteria). Crew will respond to ARB 1C04 1C 1-4 (PZR Safety / Relief line High Temp) which will direct the crew to close 1RC-515 (PORV Block valve). This action is also contained in AOP-1A (Rx Coolant Leak). SRO will determine Tech Spec LCO 3.4.1 (PZR Pressure < COLR)
Condition A and LCO 3.4.11 (PZR PORV) Condition B. This event is complete when the plant is stabilized, and Tech Specs have been determined and with the concurrence of the lead evaluator.
Event #4 - Circulating Water Degradation (Fish Intrusion)
A fish intrusion will be in progress which causes a high differential level on the traveling screen.
ARB C01 A 4-5 directs Aux Operator to report conditions at the CWPH. Operator will report pump bay level lowering slowly and excessive debris breaking shear pins, which will require the
crew to reduce Circ Water flow to one pump using AOP-13A (CW System Malfunction). This event is complete when AOP-17A is entered.
Event #5 - Rapid Power Reduction Based on the reduction to one (1) Circ Water pump running, the crew will enter AOP-17A (Rapid Power Reduction) to reduce power to within Figure 1 of AOP-13A. This event is completed when target reactor power is being approached and with the concurrence of the lead evaluator.
Event #6 - Reactor Coolant Leak A small reactor coolant leak (approximately 30 gpm) will develop that will result in PZR level lowering (less than max charging capability) and lowering PZR pressure. Crew will enter AOP-1A (Reactor Coolant Leak) and manually take control of charging flow and adjust to stabilize and recover PZR level. This event is completed when PZR level and pressure are in control of the crew and with the concurrence of the lead evaluator. SRO will analyze Technical Specifications and determine TS LCO 3.4.13 (RCS Leakage) Condition A.
Event #7 (Major) - Small Break LOCA / SI / Automatic Reactor Trip Fails The small coolant leak will propagate quickly into a small break LOCA (exceeding charging pump capacity) such that an automatic reactor trip and safety injection signals are generated, and the crew will enter EOP-0 (Reactor Trip or Safety Injection). The automatic Reactor trip will not be successful. Crew will address the failed reactor trip (outlined below) and progress through EOP-0 and transition to EOP-1 (Reactor or Secondary Coolant Leak).
Event #8 - Manual Reactor Trip Successful in Inserting Control Rods Crew will manually trip the reactor. Train A Switch will not be successful; however, the Train B switch will be successful in inserting all withdrawn control rods into the reactor.
Scenario Termination The scenario is terminated when the Critical Tasks have been evaluated, the crew has transitioned to EOP-1 (through RHR Termination) and at the discretion of the Lead Evaluator.
Page 1 of 19 Form 3.3-2 Required Operator Actions Op. Test No.: _____
Scenario No.: __1__
Event No.: __1__
Event
Description:
Unload, Secure, and place in standby the G-01 Emergency Diesel Generator Symptoms/Cues: None Time Position Applicants Actions or Behavior NOTE: Prior to taking the shift, it is expected that the crew will have conducted the required pre-shift briefs, pre-marking of procedures, and reactivity briefs and conduct any required calculations. All communications with transmission have been completed.
Crew will be given direction to unload, shutdown, and place in a standby configuration the G-01 Emergency Diesel Generator.
TS 81 (Emergency Diesel Generator G-01 Monthly), Section 5.50 BOP 5.50.1 ENSURE G-01 Emergency Diesel Generator Logsheet LOADED PRIOR TO SHUTDOWN Section is COMPLETE Step 5.50.2 is N/A BOP Observes NOTE prior to step 5.50.3 Unload G-01 Emergency Diesel Generator as follow:
REDUCE load to about 300 kW with G-01 Diesel Generator Governor control switch.
DRIVE KVARs to zero with G-01 Diesel Generator Voltage Regulator control switch.
BOP 5.50.4 PLACE 1A52-60-CS, G-01 Diesel Generator to Bus 1A-05 Breaker Control Switch to TRIP and RECORD time.
SRO / BOP 5.51 RECORD G-01 total time at full load (step 5.50.4 minus step 5.41).
BOP/AO Step 5.52 will be coordinated between the AO (Simulator Booth Instructor and the BOP)
BOP 5.53 VARY G-01 output voltage approximately +100 and - 100 volts from nominal voltage to wipe voltage regulator potentiometer.
Page 2 of 19 Op. Test No.: _____
Scenario No.: __1__
Event No.: __1__
Event
Description:
Unload, Secure, and place in standby the G-01 Emergency Diesel Generator Symptoms/Cues: None Time Position Applicants Actions or Behavior BOP Observes NOTE prior to step 5.54 ADJUST G-01 voltage to 4160 VAC BOP Observes NOTE prior to step 5.55 ADJUST G-01 frequency to 60 Hz Step 5.56 Is an Independent Verification (Coordinated with the Training Instructor)
BOP / AO 5.57 ENSURE Sump Tank level is greater than 400 gallons.
(14.8 inches as indicated on LG-7909).
Step 5.58 is N/A BOP Observes CAUTION and NOTES prior to step 5.59 PLACE G-01 Diesel Generator Control Switch to STOP BOP 5.60 IF required to reset misalignment light, THEN PLACE 1A52-60-CS to TRIP, AND BACK TO AUTO.
BOP 5.60 IF required to reset misalignment light, THEN PLACE 2A52-73-CS to TRIP, AND BACK TO AUTO.
BOP Observes NOTE prior to step 5.62 PLACE G-01 Diesel Generator Mode Selector switch to AUTO to return G-01 to standby status.
Event Termination When G-01 EDG is in standby status and at the discretion of the lead evaluator.
Page 3 of 19 Op. Test No.: _____
Scenario No.: __1__
Event No.: __2__
Event
Description:
High Vibrations on W-1B1Containment Accident Recirculation Fan Symptoms/Cues: Annunciator C01 B 4-3 alarms, WHITE Fan B light illuminates Time Position Applicants Actions or Behavior ARP C01 1F 4-3, UNIT 1 CONTAINMENT RECIRC FAN VIBRATION HIGH BOP 6.1. Check for white high vibration lamp (indicating light on C01).
BOP 6.2. Secure fan, if possible BOP 6.3. Notify DOS/DSS SRO / BOP Directs / starts the W-1A1 Containment recirc fan.
SRO TS 3.6.6 (Containment Spray and Cooling Systems):
Condition C (One accident fan cooler inoperable): Restore accident cooler fan to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> AND within 144 hours0.00167 days <br />0.04 hours <br />2.380952e-4 weeks <br />5.4792e-5 months <br /> of failure to meet the LCO.
Event Termination When the affected fan is secured with the A fan running, after evaluation of Tech Specs, and at the discretion of the lead evaluator.
Page 4 of 19 Op. Test No.: _____
Scenario No.: __1__
Event No.: __3__
Event
Description:
1RC-431C (PZR PORV) Fails Open Symptoms/Cues: Various annunciators, Rx Pressure lowering, PORV Open light (Red) is ON Time Position Applicants Actions or Behavior ARB 1C04 1C 1-4, PRESSURIZER SAFETY OR RELIEF LINE TEMPERATURE HIGH, Section 5.0 OPERATOR RESPONSES BOP 5.1. Check for associated alarms BOP 5.2. Check condition of pressurizer relief tank (will note that PRT pressure is rising).
BOP, SRO 5.3. Notify SM/OS CREW 5.4. Refer to AOP-1A, if necessary SRO, BOP
- CT*
5.5. IF leakage is determined to be minor, AND directed by the Shift Manager for troubleshooting of leakage, THEN close the desired PORV block valve(s):
SRO 5.6. Initiate troubleshooting to determine leaking PORV in accordance with the Work Management Process, as necessary NOTE: The crew may elect to enter AOP-1A, Reactor Coolant Leak to address the stuck open PORV, those actions are listed below:
AOP-1A, REACTOR COOLANT LEAK SRO, BOP
- 1. Check Safety Injection Not Required:
PZR level - WITHIN 10% OF PROGRAM LEVEL RCS Subcooling - GREATER THAN 30°F SRO, BOP
- 2. Check Reactor Trip Not Required:
- a. Check reactor - CRITICAL
- 3. Check PZR Level - STABLE AT OR TRENDING TO PROGRAM LEVEL
Page 5 of 19 Op. Test No.: _____
Scenario No.: __1__
Event No.: __3__
Event
Description:
1RC-431C (PZR PORV) Fails Open Symptoms/Cues: Various annunciators, Rx Pressure lowering, PORV Open light (Red) is ON Time Position Applicants Actions or Behavior SRO, ATC
- 4. Check PZR Pressure - STABLE AT OR TRENDING TO DESIRED PRESSURE RNO - IF PZR pressure trending lower, THEN perform the following:
- a. Ensure spray valves shut
- a. Normal Spray Valves - 1RC-431A and 431B
- b. Auxiliary Spray Valve - 1CV-296
- b. Operate PZR heaters as necessary to establish PZR pressure at program.
- 5. Check Reactor Makeup Control:
Makeup set at proper boric acid concentration Makeup armed and in auto SRO
- 6. Notify DSM And Implement Emergency Plan NOTE: Prior to Step 7, a procedural note is listed stating that Steps 7 through 18 may be performed in any order pending the location of the leak, the crew should diagnose the leak is from the PZR PORV; therefore, ONLY that step will be listed here.
- CT*
- 11. Check PZR PORVs And Safety Valves - FULLY SEATED
- a. Check PORVs - FULLY SEATED:
Check PORVs - SHUT - 1RC-430 and 1RC-431C RNO - Perform the following:
- 21. Determine RCS Leakage
- a. Perform OI-55, PRIMARY LEAK RATE CALCULATION SRO
- 22. Determine if Plant Shutdown is required RNO - Return to Procedure and step in effect
Page 6 of 19 Op. Test No.: _____
Scenario No.: __1__
Event No.: __3__
Event
Description:
1RC-431C (PZR PORV) Fails Open Symptoms/Cues: Various annunciators, Rx Pressure lowering, PORV Open light (Red) is ON Time Position Applicants Actions or Behavior SRO TS 3.4.1 (RCS Pressure / Temperature Limits):
Condition A (Rx pressure not within limits of COLR (<2205 psig)): Restore Rx Pressure within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> SRO TS 3.4.11 (PZR PORVs):
Condition B (PORV INOPERABLE and NOT capable of being cycled):
o Close associated block valve (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />); AND o Remove power from associated block valve (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />); AND o Restore PORV to OPERABLE status (72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />)
Event Termination When the PORV block valve is closed, primary is stable, and Tech Specs have been addressed OR at the discretion of the lead evaluator.
Page 7 of 19 Op. Test No.: _____
Scenario No.: __1__
Event No.: __4__
Event
Description:
CW degradation (Fish Intrusion)
Symptoms/Cues: Various annunciators, degrading CW flow, degrading MC Vacuum Time Position Applicants Actions or Behavior ARB C01 A 4-5, TRAVELING SCREEN DIFFERENTIAL LEVEL HIGH Section 6.0 OPERATOR RESPONSES BOP 6.1 Dispatch Auxiliary Operator to CWPH to perform local actions AO will report:
Debris (fish kill) in the traveling screens and forebay Debris is excessive Screen wash is NOT effective at removing the debris Pump bay level lowering slowly NOTE: The desired outcome is for the crew to enter AOP-13A, CW System Malfunctions AOP-13A, CIRCULATING WATER SYSTEM MALFUNCTIONS SRO, BOP
- 1. Circulating Water System - INTACT No report of significant rupture No condenser pit high level alarm No condenser water box low level alarm No Turbine Hall sump high level alarm
- 2. Check CW pumps - ONLY ONE RUNNING PER UNIT:
RNO - Perform the following:
- a. IF necessary to to restore forebay OR pumpbay levels, THEN stop circulating water pumps as necessary:
IF both Unit 1 circulating pumps running, THEN stop one pump
- b. Reduce load as necessary to maintain turbine load per FIGURE 1, UNIT 1 & 2 CONDENSER BACKPRESSURE, and generator gas temperature using AOP-17A, RAPID POWER REDUCTION
Page 9 of 19 Op. Test No.: _____
Scenario No.: __1__
Event No.: __5__
Event
Description:
Rapid Power Reduction Symptoms/Cues: One of the Circulating Water Pumps have been turned off (AOP-13A)
Time Position Applicants Actions or Behavior AOP-17A, RAPID POWER REDUCTION SRO, ATC
- 1. Check power - GREATER THAN 100%
RNO - Go to Step 3 SRO
- 3. Determine Desired Power Level Or Condition To Be Met Control Room Supervisor announce desired power level or condition using less than or equal to 3%/min ramp rate.
- 4. Commence Boration As Necessary To Target Load.
- a. Set boric acid flow totalizer to desired quantity - 1YIC-110
- b. Set boric acid flow controller to desired flowrate - 1HC-110
- c. If desired, Start second boric acid transfer pump
- d. Place Reactor Makeup Mode Selector Switch to Borate
- e. Place Reactor Makeup Control Switch to Start.
- 5. Select Turbine Rate And Reduce Load:
Operator Automatic Load Rate Control
- a. Ensure EH controls are set for Operator Auto
- b. Ensure "First Stage In" is selected.
- c. IF first stage pressure is unavailable, THEN select "First Stage Out".
- d. Ensure the appropriate load rate is selected on load rate thumb-wheel o 1%/min (position 1) o 2%/min (position 2) o 3%/min (position 3)
- e. Select target end-point on reference control
- f. WHEN temperature reduction of at least 0.5ºF is observed on Tavg-Tref indicator, THEN depress "GO" push-button.
- g. Continue with next step.
- 9. Check PZR Pressure - CONTROLLING IN AUTO
Page 10 of 19 Op. Test No.: _____
Scenario No.: __1__
Event No.: __5__
Event
Description:
Rapid Power Reduction Symptoms/Cues: One of the Circulating Water Pumps have been turned off (AOP-13A)
Time Position Applicants Actions or Behavior SRO, ATC
- 16. Determine Desired End Point - LESS THAN 60% TURBINE LOAD RNO - Go to Step 38 SRO
- 38. Check If Boration Should Be Stopped IF turbine on-line, THEN continue boration until Bank D rods are positioned to control axial flux near its target value.
Refer to ROD 1.2 of Reactor Operating Data Book SRO, BOP
- 39. Contact Chemistry To Sample RCS For Iodine Within 2 To 6 Hours Following Power Change SRO, BOP
- 42. Determine If Reactor Shutdown Is Desired RNO - Return to Procedure and step in effect Event Termination When the power reduction is in progress (this evolution does NOT need to be completed prior to proceeding to the next event).
Page 11 of 19 Op. Test No.: _____
Scenario No.: __1__
Event No.: __6__
Event
Description:
Reactor Coolant Leak (within Charging capability)
Symptoms/Cues: Various annunciators, PZR level and pressure slowly lowering with no corresponding lowering in temperature Time Position Applicants Actions or Behavior AOP-1A, REACTOR COOLANT LEAK SRO, ATC
- 1. Check Safety Injection Not Required:
PZR level - WITHIN 10% OF PROGRAM LEVEL RCS Subcooling - GREATER THAN 30°F SRO, ATC
- 2. Check Reactor Trip Not Required:
- a. Check reactor - CRITICAL
- 3. Check PZR Level - STABLE AT OR TRENDING TO PROGRAM LEVEL RNO - IF PRZ level trending lower, THEN perform the following:
- a. Control charging flow from running charging pumps
- b. IF PZR level continues to lower, THEN isolate letdown
- c. Start non-running charging pump and inform Shift Manager.
- 4. Check PZR Pressure - STABLE AT OR TRENDING TO DESIRED PRESSURE RNO - IF PZR pressure trending lower, THEN perform the following:
- b. Operate PZR heaters as necessary to establish PZR pressure at program.
Condition A (RCS Leakage NOT within limit NOT due to pressure boundary or primary to secondary leakage):
o Reduce LEAKAGE to within limits (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />)
Page 12 of 19 Op. Test No.: _____
Scenario No.: __1__
Event No.: __7 & 8__
Event
Description:
SBLOCA with ATWS Symptoms/Cues: Various annunciators, Containment Humidity and pressure rising, PZR level and pressure lowering with no corresponding lowering in temperature Time Position Applicants Actions or Behavior AOP-1A, REACTOR COOLANT LEAK CREW
- 2. Check Safety Injection Not Required:
PZR level - WITHIN 10% OF PROGRAM LEVEL RCS Subcooling - GREATER THAN 30°F RNO - Preform the following:
- a. Manually trip the reactor
- b. After the reactor has tripped, THEN manually initiate safety injection.
- c. Manually initiate Containment Isolation
- d. Go to EOP-0 Unit 1, REACTOR TRIP OR SAFETY INJECTION NOTE: Based on the rate and severity of the SBLOCA, the crew may not have adequate time to perform AOP-1A Step 1 as the automatic Rx Trip setpoints may have been exceeded, this is acceptable.
EOP-0, REACTOR TRIP OR SAFETY INJECTION NOTE: EOP-0 Steps 1-4 are IMMEDIATE OPERATOR ACTIONS SRO, ATC
- CT*
- 1. Verify Reactor Trip RNO - Manually trip reactor (Train A and Train B switch)
Once the ATC manually trips the reactor:
Reactor trip and bypass breakers - OPEN All rod position indicators - LESS THAN 20 STEPS All rod bottom lights - LIT Neutron flux - LOWERING SRO, BOP
- 2. Verify Turbine Trip
- a. Turbine stop valves - BOTH SHUT
Page 13 of 19 Op. Test No.: _____
Scenario No.: __1__
Event No.: __7 & 8__
Event
Description:
SBLOCA with ATWS Symptoms/Cues: Various annunciators, Containment Humidity and pressure rising, PZR level and pressure lowering with no corresponding lowering in temperature Time Position Applicants Actions or Behavior SRO, BOP
- 3. Verify Power to AC safeguards busses:
- a. Check safeguards busses - At least one TRAIN ENERGIZED (Train A and Train B)
- 4. Check if SI Is Actuated:
- a. Any SI annunciators - LIT
- 5. Perform Attachment A, Automatic Action Verification, while continuing with this procedure.
- 6. Verify AFW Pumps - RUNNING
- a. Motor-Driven Pump - RUNNING
- b. Turbine-driven Pump - RUNNING
- 7. Check RCP Seal Cooling:
Component cooling flow to RCP thermal barriers -
NORMAL
Page 14 of 19 Op. Test No.: _____
Scenario No.: __1__
Event No.: __7 & 8__
Event
Description:
SBLOCA with ATWS Symptoms/Cues: Various annunciators, Containment Humidity and pressure rising, PZR level and pressure lowering with no corresponding lowering in temperature Time Position Applicants Actions or Behavior SRO, ATC
- 8. Check RCS temperatures:
- a. Condenser Steam Dumps - AVAILABLE Place Steam Dump Mode Selector Switch in MANUAL
o RCS average temperature - STABLE AT OR TRENDING TO 547°F RNO - Perform the following:
- 1. IF temperature is less than 547°F AND lowering, THEN perform the following:
- a. Stop dumping steam
- b. IF cooldown continues, THEN control total feed flow:
Maintain total feed flow greater than or equal to 275 gpm until level is greater than [52%] 33% in at least one S/G.
- c. IF cooldown continues, THEN isolate main steam lines:
- a. Shut both main steam isolation valves:
1MS-2018 1MS-2017
- b.
Ensure both main steam isolation bypass valves are shut:
1MS-234 1MS-236
- 2. IF RCS Temperature is GREATER THAN 547°F AND Rising THEN:
o DUMP steam to condenser o DUMP steam using ADVs
Page 15 of 19 Op. Test No.: _____
Scenario No.: __1__
Event No.: __7 & 8__
Event
Description:
SBLOCA with ATWS Symptoms/Cues: Various annunciators, Containment Humidity and pressure rising, PZR level and pressure lowering with no corresponding lowering in temperature Time Position Applicants Actions or Behavior SRO, ATC
- 9. Check PZR PORVs and Spray Valves:
- 10. Check if RCPs Should Be Stopped:
- a. RCPs - ANY RUNNING
- b. SI pumps - AT LEAST ONE RUNNING AND CAPABLE OF DELIVERING FLOW
- c. RCS subcooling based on core exit thermocouples -
LESS THAN [40°F] 31°F RNO - Go to Step 11 SRO, ATC
- 11. Check if S/G Are NOT Faulted:
- a. Check pressures in both S/Gs:
No S/G pressure lowering in an uncontrolled manner No S/G completely depressurized SRO, ATC
- 12. Check if S/G Tubes are NOT Ruptured:
S/G levels - NOT RISING IN AN UNCONTROLLED MANNER Secondary system radiation monitor levels - NORMAL Condenser air ejector:
o 1RE-215 o RE-225 S/G Blowdown o 1RE-219 o 1RE-222 Main Steam Line o 1RE-231 for S/G A o 1RE-232 for S/G B
Page 16 of 19 Op. Test No.: _____
Scenario No.: __1__
Event No.: __7 & 8__
Event
Description:
SBLOCA with ATWS Symptoms/Cues: Various annunciators, Containment Humidity and pressure rising, PZR level and pressure lowering with no corresponding lowering in temperature Time Position Applicants Actions or Behavior SRO, ATC
- 13. Check if RCS Is Intact:
- a. Containment radiation levels - NORMAL Containment o 1RE-102 o 1RE-107 Containment High Range o 1RE-126 o 1RE-127 o 1RE-128 Containment sump A level on 1C20 - NORMAL o 1LI-958 o 1LI-959 Containment pressure - NORMAL RNO:
Notify STA to MONITOR CSP Status per CSP-ST.0 Unit 1, CSF STATUS TREES Go to EOP-1 Unit 1, LOSS OF REACTOR OR SECONDARY COOLANT EOP-1, LOSS OF REACTOR OR SECONDARY COOLANT SRO, ATC
- 1. Check if RCPs Should be Stopped:
- a. RCPs - ANY RUNNING
- b. SI pumps - AT LEAST ONE RUNNING AND CAPABLE OF DELIVERING FLOW
- c. RCS subcooling based on core exit thermocouples -
LESS THAN 31°F RNO - Go to Step 2 SRO, ATC
- 2. Check if S/G are NOT Faulted
- a. Check pressures in both S/Gs:
NO S/G pressure lowering in an uncontrolled manner AND NO S/G completely depressurized SRO, ATC
- 3. Check Intact S/G Level:
- a. S/G level - GREATER THAN 33%
- b. Control feed flow to maintain S/G level between 33% and 63%
Page 17 of 19 Op. Test No.: _____
Scenario No.: __1__
Event No.: __7 & 8__
Event
Description:
SBLOCA with ATWS Symptoms/Cues: Various annunciators, Containment Humidity and pressure rising, PZR level and pressure lowering with no corresponding lowering in temperature Time Position Applicants Actions or Behavior SRO, ATC
- 4. Check Secondary Radiation
- a. Request Chemistry to sample both S/Gs for activity
- b. Request local surveys of main steam lines
- c. Secondary system radiation monitor levels - NORMAL Condenser air ejector:
o 1RE-215 (3-5) o RE-225 (7-1)
S/G blowdown:
o 1RE-219 (5-3) o 1RE-222 (1-7)
Main steam line:
o 1RE-231 (3-9) for S/G A o 1RE-232 (5-2) for S/G B
- d. Secondary activity samples and surveys - NORMAL (WHEN available)
- 5. Check PZR PORVs and Block Valves
- a. Power to PORV block valves - AVAILABLE
- b. PORVS - BOTH SHUT 1RC-430 1RC-431C
- 7. Reset Isolation and Lockout Signals:
Containment Isolation 1B-03 and 1B-04 NON safeguards equipment lockouts SRO, ATC
- 8. Establish Instrument Air to Containment
- a. Check instrument air header pressure - GREATER THAN 80 psig
- b. Open instrument air containment isolation valves one at a time:
1IA-3047 1IA-3048
Page 18 of 19 Op. Test No.: _____
Scenario No.: __1__
Event No.: __7 & 8__
Event
Description:
SBLOCA with ATWS Symptoms/Cues: Various annunciators, Containment Humidity and pressure rising, PZR level and pressure lowering with no corresponding lowering in temperature Time Position Applicants Actions or Behavior SRO, ATC
- 9. CHECK POWER SUPPLY TO CHARGING PUMPS
- 10. Check if Charging Flow Has Been Established
- a. RWST Level - GREATER THAN 10%
- c. Charging pumps - AT LEAST ONE RUNNING
- d. Start additional charging pumps and adjust speed on running charging pumps as necessary to establish desired charging flow
- e. Adjust charging line flow controller as necessary to maintain labyrinth seal P greater than 20 inches.
- 11. Check if ECCS Flow Should be Terminated
- a. RCS subcooling based on core exit thermocouples -
GREATER THAN 37°F
- b. Secondary heat sink:
o Level in at least one intact S/G - GREATER THAN
[52%] 33%
OR o Total feed flow to intact S/Gs - GREATER THAN OR EQUAL TO 275 gpm
- c. RCS pressure:
Pressure - GREATER THAN 1725 psig AND Pressure - STABLE OR RISING RNO - Go to Step 12 SRO, ATC
- 12. Check if Containment Spray Should Be Stopped
- a. Containment Spray Pumps - ANY RUNNING RNO - IF NO spray pumps have been stopped by operator action, THEN OBSERVE CAUTION PRIOR TO STEP 13 and go to Step 13.
Page 19 of 19 Op. Test No.: _____
Scenario No.: __1__
Event No.: __7 & 8__
Event
Description:
SBLOCA with ATWS Symptoms/Cues: Various annunciators, Containment Humidity and pressure rising, PZR level and pressure lowering with no corresponding lowering in temperature Time Position Applicants Actions or Behavior SRO, ATC
- 13. Check If RHR Pumps Should Be Stopped:
- a. Check RCS pressure:
- 1) Pressure - GREATER THAN 325 psig
- 2) Pressure - STABLE OR RISING
- c. Stop both RHR pumps and place in auto:
1P-10A 1P-10B Scenario Termination Critical Tasks have been evaluated RHR pumps have been stopped and returned to AUTO using EOP-1 At the discretion of the Lead Evaluator
Page 1 of 4 Form 3.3-1 Scenario Outline Facility:
Point Beach Scenario #:
2 Scenario Source:
Op. Test #:
Feb 2023 Applicants/
Examiners:
Operators:
Initial Conditions:
2% Power in MODE 2. RCS boron concentration is 1000 ppm. No equipment out of service.
Turnover:
Continue the Reactor Startup to Power Operation Critical Tasks**:
- 2. Isolate the steam leak Event No.
Malf. No.
Event Type*
Event Description**
1 (R) ATC Raise power to 4%.
2 (N) BOP Perform TS 39 Train A 3
(C) BOP (C/TS) SRO Low Gas pressure on ECCS accumulator 4
(C/MC) ATC (C) SRO 1CV-135 Letdown Line Backpressure controller oscillations in AUTO; works in manual 5
(C/MC) BOP (C/TS) SRO Component Cooling Pump trip with failure to start standby pump. AOP-9B 6
(C) ATC (C) SRO Seismic Event causing multiple CRs to drop / Rx Trip 7
(M) CREW After the Reactor Trip, a Steam Line Break occurs downstream of MSIV, 1MS-2017 (CT) 8 (C) CREW MSIVs fail to auto close on SLI signal (manual operation not successful, direction of local action required) (CT)
Termination Criteria:
Critical Tasks have been evaluated Transition from EOP-2 to EOP-1 At the discretion of the Lead Evaluator
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS)Tech Spec, (MC)Manual Control
- Details on subsequent pages
Page 2 of 4 Critical Task Details:
CT1: Control AFW flow to minimize RCS cooldown Initiating Cue: All of the following:
o Uncontrolled depressurization of both SGs o Cooldown rate in RCS cold legs exceeds 100°F per hour Performance Feedback:
o Control board indications show that AFW flow was lowered o Indication (and establishment) of minimum flow to both S/Gs Success Path: Valve position and flow rate indication that AFW continues to be delivered to both SGs at a rate of approximately 50 gpm per S/G.
Performance Standard: Manipulation of controls as required throttling AFW flow sufficiently to prevent a severe ORANGE challenge to the integrity CSF but not less than the 50 gpm per SG.
Safety Significance: Failure to control AFW flow rate to the SGs leads to an unnecessary and avoidable severe challenge to the integrity CSF. Also, failure to perform the critical task increases challenges to the subcriticality CSF beyond those irreparably introduced by the postulated plant conditions.
CT2: Isolate the steam leak Initiating Cue: All of the following:
o Uncontrolled depressurization of both SGs o Cooldown rate in RCS cold legs exceeds 100°F per hour Performance Feedback:
o S/G pressures stabilize (consistent with RCS cooldown) o MSIVs indicate closed o Lowering rate of RCS cooldown.
Success Path: Crew directs LOCAL closing of the MSIVs IAW EOP 2, Attachment A, Local Shutting of MSIV or IAW ECA-2.1, Attachment B, Local Shutting of MSIV.
Measurable Performance Standard: The crew must DIRECT LOCAL closing of both MSIVs prior to completing step 1 of ECA-2.1.
Safety Significance: Failure to isolate a faulted SG that can be isolated causes challenges to CSFs beyond those irreparably introduced by the postulated conditions. Also, depending upon plant conditions, it could constitute a failure by the crew to "demonstrate the ability to recognize a failure or an incorrect automatic actuation of an ESF system or component."
Failure to isolate a steam leak can result in challenges to the following CSFs:
o Integrity o Subcriticality
Page 3 of 4 Scenario Executive Summary Initial Conditions / Turnover:
Point Beach Unit 1 will be at 2% conducting a reactor startup following completion of a maintenance outage with RCS Boron concentration at 1000 ppm. CL 2F (MODE 2 to MODE 1 Checklist) is complete. IT 08A (Cold Start of Turbine-Driven Auxiliary Feed Pump and Valve Test) is not required.
Currently at OP-1C Step 5.3.2.
Direction(s) for the Shift:
Continue the reactor plant startup using OP-1C at step 5.3.1 to establish 4% power. CL 2F (MODE 2 to MODE 1 Checklist) is complete. IT 08A (Cold Start of Turbine-Driven Auxiliary Feed Pump and Valve Test) is not required.
Crew is to conduct TS 39 Train A, 1MS-2018 Main Steam Isolation Valve Operability Trip Test Unit 1.
Operators are stationed at 1MS-2018 to record the stroke times and positions. IST coordinator is available for reference data and manual stroke of 1MS-234 is NOT required.
Event #1 - Reactor Startup Crew will continue with OP-1C at Step 5.3.1. This event is completed once the reactor is approximately 4% and ready to complete step 5.3.2 or at the direction of the lead evaluator.
Event #2 - Tech Spec Surveillance on 1MS-2018 Crew will conduct the surveillance (no issues) This event is completed once the BOP portions of the surveillance are complete.
Event #3 - Low N2 Pressure on 1T-34B Accumulator A low nitrogen gas pressure condition will develop on accumulator 1T-34B. Crew should pause the startup and respond to ARP C01 B 4-8 and determine gas pressure is approximately 700 psig. Crew will take action using OI-100 (Adjusting SI accumulator level, pressure, and PORV backup nitrogen pressure Unit 1), to pressurize the accumulator. SRO will evaluate and enter Tech Spec LCO 3.5.1 Condition B (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to restore to OPERABLE). This event is completed when the accumulator is re-pressurized, and the TS determination has occurred and / or at the direction of the lead evaluator.
Event #4 - 1CV-135 Letdown Line Backpressure controller oscillations, works in manual Receives the 1C04 1C 106 annunciator and determines letdown pressure and flow are oscillating. The ATC identifies the 1CV-135 controller is cycling and recommends placing letdown pressure control to manual, references ARB 1C04 1C 1-6 Letdown Pressure High, and stabilizes letdown pressure and flow. The SRO directs entry into AOP-1D, Unit 1 CVCS malfunctions, references Step 36 for a failure of 1CV-135, and directs the ATC to places the controller in manual.
Event #5 - Component Cooling Pump trip with Auto-Start failure of Standby Pump 1P-11A, (running CCW pump) will trip and its standby CCW pump will not auto start. Crew will respond to various ARPs and enter AOP-9B, Component Cooling System Malfunctions. Crew will start 1P-11B CCW pump manually and verify CCW cooled component temperatures return to normal ranges. SRO will evaluate and enter Tech Spec LCO 3.7.7 Condition A. This event is complete when the plant is stable, Tech Specs have been evaluated and at the direction of the Lead Evaluator.
Page 4 of 4 Event #6 - Seismic Event / Multiple CRs drop / Reactor Trip A seismic event occurs and causes three control rods to drop into the core. Crew will reference AOP-6A and note that more than one rod bottom light is illuminated and trip the reactor. EOP-0 will be entered. This event goes into the next without delay.
Event #7 (Major) - Steam Line Break on the B Steam Line Downstream of the MSIV Approximately 15 seconds after the reactor trip (PRIOR TO completion of EOP-0 Step 4), a steam line break will occur on the turbine side of 1MS-2017, Main Steam Isolation Valve. The steam line break will actuate an automatic safety injection signal and an automatic MSIV isolation actuation.
Uncontrolled depressurization of both steam generators will occur causing the crew to transition from EOP-0, Step 11 to EOP-2. With both steam generators depressurizing in an uncontrolled manner, the crew will transition from EOP-2, Step 2 to contingency procedure ECA-2.1. Once in the ECA-2.1 the crew will attempt to locally isolate the steam leak and will establish 50 gpm of AFW flow to each steam generator to minimize RCS cooldown. Once the steam leak is locally isolated and prior to ECA-2.1, Step 9 the crew will transition back to EOP-2 and then at Step 7 go to EOP-1.
Event #8 - MSIVs Fail to Close on Auto Steam Line Isolation and Manual Control Switch Manipulation The steam line break will actuate an automatic MSIV isolation actuation. The MSIVs will not close on the AUTO signal or when the crew attempts to manually close them from the main control room control switches. The crew must direct LOCAL closing of the MSIVs IAW EOP-2, Attachment A, Local Shutting of MSIV or IAW ECA-2.1, Attachment B, Local Shutting of MSIV.
Scenario Termination This scenario can be terminated when the critical tasks have been evaluated, the crew transitions from EOP-2 to EOP-1, and at the discretion of the lead evaluator.
TR-AA-230-1007-F14, Revision 0 SIMULATOR EXERCISE GUIDE SEG SITE:
PBNP Revision #: 0 LMS ID:
PBN LOI NRC 028E LMS Rev. Date:
SEG TITLE:
2023 NRC Exam Scenario 2 SEG TYPE:
Training Evaluation PROGRAM:
LOCT LOIT Other:
DURATION:
90 minutes Developed by:
John Rogers Instructor/Developer Date Reviewed by:
Andy Zommers Instructor (Instructional Review)
Date Validated by:
John Rogers SME (Technical Review)
Date Approved by:
Adam Moore Training Supervision Date Approved by:
Joe Krear Training Program Owner (Line)
Date
PBN LOI NRC 028E, 2023 NRC Exam Scenario 2, Rev 0 SEG Page 2 of 33 TR-AA-230-1007-F14, Revision 0 Facility:
Point Beach Scenario #:
2 Scenario Source:
Op. Test #:
Feb 2023 Applicants/
Examiners:
Operators:
Initial Conditions:
2% Power in MODE 2. RCS boron concentration is 1000 ppm. No equipment out of service.
Turnover:
Continue the Reactor Startup to Power Operation Critical Tasks**:
- 2. Isolate the steam leak Event No.
Malf. No.
Event Type*
Event Description**
1 (R) ATC Raise power to 4%.
2 (N) BOP Perform TS 39 Train A 3
(C) BOP (C/TS) SRO Low Gas pressure on ECCS accumulator 4
(C/MC) ATC (C) SRO 1CV-135 Letdown Line Backpressure controller oscillations in AUTO; works in manual 5
(C/MC) BOP (C/TS) SRO Component Cooling Pump trip with failure to start standby pump. AOP-9B 6
(C) ATC (C) SRO Seismic Event causing multiple CRs to drop / Rx Trip 7
(M) CREW After the Reactor Trip, a Steam Line Break occurs downstream of MSIV, 1MS-2017 (CT) 8 (C) CREW MSIVs fail to auto close on SLI signal (manual operation not successful, direction of local action required) (CT)
Termination Criteria:
Critical Tasks have been evaluated Transition from EOP-2 to EOP-1 At the discretion of the Lead Evaluator
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS)Tech Spec, (MC)Manual Control
- Details on subsequent pages
PBN LOI NRC 028E, 2023 NRC Exam Scenario 2, Rev 0 SEG Page 3 of 33 TR-AA-230-1007-F14, Revision 0 SIMULATOR EXERCISE GUIDE REQUIREMENTS Terminal Objective:
Given the site simulator and specific plant conditions, the students will be able to respond to various plant abnormal and emergency events, in accordance with site procedures and technical Specifications.
Enabling Objectives:
- 1. None Prerequisites:
- 1. Simulator available
- 2. Students enrolled in Initial License Program Training Resources:
- 1. Floor Instructor as Shift Manager / Shift Technical Advisor
- 2. Simulator Booth Operator
- 3. Communicator
- 4. NRC Evaluators
References:
- 1. AOP-1D, Chemical and Volume Control System Malfunction
- 2. AOP-6A, Dropped Rod
- 3. AOP-9B, Component Cooling System Malfunction
- 4. AOP-24, Response to Instrument Malfunction
- 5. EOP-0, Reactor Trip or Safety Injection
- 6. EOP-2, Faulted Steam Generator
- 7. ECA-2.1, Uncontrolled Depressurization of Both Steam Generators
- 8. OP 1C, Startup to Power Operation Unit 1
- 9. TS 39 TRAIN A, 1MS-2018, Main Steam Isolation Valve Operability Trip Test Unit 1
- 10. OM 3.7, AOP and EOP Procedure Usage For Response To Plant Transients
- 11. Technical Specifications Manual
- 12. Technical Requirements Manual Protected Content:
None Evaluation Method:
Simulator performance will be evaluated in accordance with NUREG 1021.
Operating Experience:
None Risk Significant Operator Actions:
Initiating Event with Core Damage Frequency:
PBN LOI NRC 028E, 2023 NRC Exam Scenario 2, Rev 0 SEG Page 4 of 33 TR-AA-230-1007-F14, Revision 0 UPDATE LOG: Indicate in the following table any minor changes or major revisions made to the material after initial approval.
DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR#
PREPARER DATE REVIEWER DATE 0
Developed for the 2023 ILT NRC Exam
PBN LOI NRC 028E, 2023 NRC Exam Scenario 2, Rev 0 SEG Page 5 of 33 TR-AA-230-1007-F14, Revision 0 OVERVIEW / SEQUENCE OF EVENTS OVERVIEW Initial conditions for the scenario are: Unit 1 is in MODE 2 with power stable at 2%. Plant startup in progress. No equipment OOS.
Examinees will raise power to 4% then perform a surveillance test on 1MS-2018, MSIV. Examinees will respond to low SI Accumulator pressure, a letdown pressure controller failure, and a Component Cooling Water pump trip. A seismic event will cause multiple dropped rods, requiring a reactor trip. A steam line break will occur coincident with the reactor trip.
The scenario will be terminated when the crew completes EOP-2, or per Lead Evaluator.
SEQUENCE OF EVENTS Event #
Description
- 1.
Power Ascension The crew will raise reactor power per OP 1C, Startup to Power Operation, to approximately 4%.
- 2.
Surveillance Test, 1MS-2018 The crew will perform TS 39 TRAIN A, 1MS-2018, Main Steam Isolation Valve Operability Trip Test Unit 1
- 3.
Low Accumulator Pressure Examinees will respond to a low pressure alarm for 1T-34B, SI Accumulator, by repressurizing the accumulator.
SRO will address Technical Specifications
- 4.
1CV-135, Letdown Pressure Controller Failure Letdown Pressure controller, 1CV-135, will oscillate while in automatic.
The examinees will respond by manually controlling letdown pressure, and implement AOP-1D, CVCS Malfunction.
- 5.
Component Cooling Pump Trip The running CCW Pump, 1P-11A will trip, the standby pump will fail to automatically start.
The examinees will respond by starting the standby pump, implementing AOP-9A, Component Cooling Water System Malfunction.
The SRO will assess Technical Specifications
PBN LOI NRC 028E, 2023 NRC Exam Scenario 2, Rev 0 SEG Page 6 of 33 TR-AA-230-1007-F14, Revision 0
- 6.
Seismic Event / Dropped Rods A seismic event will cause three control rods to drop.
The examinees, per AOP-6C, Dropped Rod, will manually trip the reactor due to multiple rods dropped.
The crew will implement EOPs.
- 7.
Steam Line Break / MSIVs Fail to Close Following the reactor trip, a steam line break downstream of 1MS-2017 will occur, resulting in an automatic Safety Injection.
Both MSIVs will fail to close either automatically, or when attempted from the control room.
The MSIV failure will result in the depressurization of both S/Gs and require the crew to implement ECA-2.1, Uncontrolled Depressurization of Both Steam Generators.
Terminate the scenario when the crew completes EOP-2, Faulted Steam Generator Isolation, or per Lead Evaluator.
PBN LOI NRC 028E, 2023 NRC Exam Scenario 2, Rev 0 SEG Page 7 of 33 TR-AA-230-1007-F14, Revision 0 SIMULATOR SET-UP INSTRUCTIONS Perform simulator set up per the site specific Simulator Setup Checklist.
Check Action
- 1.
Reset to IC created for this scenario.
- 2.
Perform Simulator Setup Checklist
- 3.
Open schedule file. Z:/2023 ILT NRC Simulator Files/NRC Scenario 2.sch
- 4.
To record SBT data:
- 1. Launch SBT Report from Thunderbar
- 2. Open Scenario Validation Checklist.sbt (TRex_PB\\Lightning)
- 5.
Take schedule(s) to run
- 6.
Verify required event file(s) open if required
- 7.
Take sim to run
- 8.
Place turnover sheets on CO1 desk
- 9.
Place reactivity sheets on CO1 desk
- 10.
Guard the following:
None Place the following in Pull-Out with an OOS MNT magnet:
None Place red dot on the following alarm:
None Marked up copy of TS 39 Marked up copy of OI 100B (held by SM)
- 11.
- Conduct simulator crew pre-scenario brief using TR-AA-230-1007-F06, Simulator Instructor Pre-Exercise Checklist.
- Brief the scenario evaluators
- Brief surrogates using TR-AA-230-1007-F11, Surrogate Brief Checklist, if necessary
- 12.
Run Scenario
- 13.
To save SBT Data:
- 1. In the SBT Report program click the Generate Report icon (green arrow)
- 2. In Test Title enter a unique test title, to be same as file name
- 3. In report name enter the location the test files are to be saved, use same file name as Test Title
- 4. Click Generate (generates and saves two files in the selected folder)
- 5. Verify files saved in the selected folder
- 6. The generated report and SBT Report program may now be closed
- 7. Collect procedure markups for SBT
- 8. Save any InSight, Alarm, Event, Schedule Files to the secure drive that were in use
- 14.
Reset simulator to appropriate IC.
PBN LOI NRC 028E, 2023 NRC Exam Scenario 2, Rev 0 SEG Page 8 of 33 BOOTH OPERATOR BRIEFING:
Z:/2023 ILT NRC Simulator Files/NRC Scenario 2.sch At Time On Event Action Description 00:00:00 Event Z:/ILT Exams/2023 NRC Exam Simulator Files/NRC #2.evt Event 2: TS 39 (1MS-2018 test) 1 Insert remote LOA1SGN022 to 1.00000 in 30 1MS-234 SG A MAIN STEAM BYPASS 3
Insert remote LOA1SGN022 to 0 in 30 1MS-234 SG A MAIN STEAM BYPASS 2
Insert remote LOA1CAS050 to 0 in 15 IA-638 AIR SUPPLY TO 1MS-2018 4
Insert remote LOA1CAS050 to 1.00000 in 15 IA-638 AIR SUPPLY TO 1MS-2018 5
Insert remote LOA1SGN017 to RESET 1MS-2018R MSIV 1A LOCAL RESET-MOMENTARY Event 3: Accumulator Pressure Drops pressure to just below alarm setpoint of 710psig 6
Insert malfunction VLV1SIS006B to 10.00000 on event 6 delete in 40 1-SI-830B T-34B SI ACCUMULATOR RELIEF VLV SEAT LEAKAGE Local actions for raising accumulator pressure 8
Insert remote LOA1SGS001 to 0.0500 in 10 1SI-838A T-34A+B SI ACC NG SUPPLY VLV 9
Insert remote LOA1SGS001 to 0 in 10 1SI-838A T-34A+B SI ACC NG SUPPLY VLV Event 4: 1CV-135 Oscillations 12 Insert malfunction CNH1CVC014F to 75.00000 in 30 1-HC135 LOW PRESS LETDOWN LINE OSC AUTO ONLY Event 5: CCW Pump Trip 00:00:00 Insert malfunction BKR1CCW002 to Fail_Auto_Cl 1B52-23B P-11B CC WATER PUMP CKTBKR 14 Insert malfunction BKR1CCW001 to Trip 1B52-10A P-11A CC WATER PUMP CKTBKR Event 6: Seismic Event / Dropped Rods 16 Insert remote LOA1ANN004 to SEIS_EVT SEI-6210 Switchgear Seismic Detector 16 Insert remote LOA1ANN005 to SEIS_EVT SEI-6211 Facade Seismic Detector 16 Insert remote LOA1ANN006 to SEIS_EVT SEI-6212 Drum Area Seismic Detector 16 Insert remote LOA1ANN007 to SEIS_EVT delete in 30 SEI-6213 Aux FW Tunnel Seismic Detector 16 Insert malfunction MAL1CRF002-J4 after 10 ROD DROP J4 16 Insert malfunction MAL1CRF002-I9 after 11 ROD DROP I9 16 Insert malfunction MAL1CRF002-L6 after 12 ROD DROP L6 Event 7: Steam Break - inserts when reactor is tripped 17 Insert malfunction MAL1SGN006B after 15 to 3000000.00000 B HDR STEAM LINE BREAK BETWEEN MSIV AND NONRETURN
PBN LOI NRC 26E, 2021 NRC Exam Scenario 5, Rev 0 SEG Page 9 of 33 TR-AA-230-1007-F14, Revision 0 17 Insert malfunction VLV1SGN012 to Stuck_Open 1-MS-2017A SG B MAIN STM NON-RETURN 17 Insert malfunction VLV1SGN014 to Stuck_Open 1-MS-2018A SG A MAIN STM NON-RETURN Event 8: MSIV Failuire - inserts when reactor is tripped 17 Insert malfunction VLV1SGN011 to Open 1-MS-2017 STM GEN NO 1B ISOL 17 Insert malfunction VLV1SGN013 to Open 1-MS-2018 STM GEN NO 1A ISOL Local action to shut MSIVs 19 Insert malfunction VLV1SGN011 to Close 1-MS-2017 STM GEN NO 1B ISOL 20 Insert malfunction VLV1SGN013 to Close 1-MS-2018 STM GEN NO 1A ISOL 21 Insert remote LOA1SGN023 to 0 in 5 1MS-235 P-29 AFP & RADWASTE STM ISOL 22 Insert remote LOA1SGN025 to 0 in 5 1MS-237 P-29 AFP & RADWASTE STM ISOL Event file: Trigger 17: Reactor tripped (jcrftr)
PBN LOI NRC 028E, 2023 NRC Exam Scenario 2, Rev 0 SEG Page 10 of 33 TR-AA-230-1007-F14, Revision 0 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS Bolded steps are Verifiable Actions taken by the Operators.
(IA) actions are those allowed to be taken from memory, before referencing the procedure, as allowed by OM 3.7, Attachment F, AOP Actions Allowed From Memory.
Event # 1 Power Ascension ACTION Booth: None STUDENT
RESPONSE
Symptoms / Indications Unit 1 is in MODE 2 with power stable at 2%
BOP/RO Perform OP 1C Actions to raise power as directed.
SRO Directs / Supervises OP 1C actions to raise power Crew OP 1C, Startup to Power Operation Unit 1 5.3 Increasing reactor power to between 2% to less than 5%
5.3.1 PULL rods or DILUTE to raise reactor power (NIS) to between 2 to less than 5% rated power. (RO) Crew briefed to use rods to raise power 5.3.2 IF identified as required by Step 4.2, THEN PERFORM the following as appropriate:
TS 39 TRAIN A, 1MS-2018 Main Steam Isolation Valve Operability Trip Test Unit 1 ROLE PLAY Booth Communications:
Respond to reports or direction to field operators as necessary.
SM Communications:
Provide crew direction to raise power.
Respond to reports from crew members as required.
NOTES Continuation Criteria:
After an approximately 2% to 3% power increase, or at the discretion of the Lead Examiner, continue with the next event.
PBN LOI NRC 028E, 2023 NRC Exam Scenario 2, Rev 0 SEG Page 11 of 33 TR-AA-230-1007-F14, Revision 0 Event # 2 Surveillance Test, 1MS-2018 ACTION Booth: Insert Triggers 1 thru 5 to perform local actions as directed by the crew.
STUDENT
RESPONSE
Symptoms / Indications List alarms and key indicators BOP Perform actions per TS 39.
SRO Direct / supervise performance of TS 39 Crew TS 39 TRAIN A, 1MS-2018, Main Steam Isolation Valve Operability Trip Test Unit 1 (BOP) 5.0 PROCEDURE 5.1 ENSURE 1MS-2016, A Steam Generator Atmospheric Steam Dump available by performing the following:
5.1.1 CYCLE 1MS-2016, HX-1A SG Header Atmospheric Steam Dump Control off it's shut seat and back to SHUT.
5.1.2 ENSURE 1MS-2016, HX-1A SG Header Atmospheric Steam Dump controller SET at 1005 psig and in AUTO.
NOTE: Timing of 1MS-2018 will require coordination between Control Room and operator at 1MS-2018.
NOTE: If 1MS-2018 will not shut, record final position and time to reach that position.
5.2 Test 1MS-2018, 1HX-1A SG Header Main Steam Stop Control and Main Steam Stop Solenoid Valves Associated with 1MS-2018 as follows:
5.2.1 CHECK for OPEN indication for 1MS-2018 and RECORD on Attachment A.
5.2.2 To accommodate shrinkage, ENSURE A and B Steam Generator levels are approximately equal to 67%.
5.2.3 On 1C-03, PLACE 1MS-2018-CS, HX-1A SG Steam Header Main Steam Stop Control SW to SHUT position and TIME.
- a. RECORD required data on Attachment A:
5.2.4 Locally CHECK 1MS-2018 Main Steam Stop Solenoid valves have actuated and RECORD on Attachment A.
1MS-2018C-S 1MS-2018D-S 1MS-2018A-S 1MS-2018B-S 5.2.5 IF 1MS-2018 is declared INOPERABLE in Attachment A, THEN MARK as N/A Steps 5.2.6 through 5.2.9.
5.2.6 OPEN 1MS-2018 as follows:
- a. SHUT IA-638, 1MS-2018 SG A Steam Header Main Steam Stop Operating Air Inlet.
PBN LOI NRC 028E, 2023 NRC Exam Scenario 2, Rev 0 SEG Page 12 of 33 TR-AA-230-1007-F14, Revision 0 Event # 2 Surveillance Test, 1MS-2018 Steam Stop Bypass and RECORD on Attachment A.
- c. PLACE 1MS-2018-CS, HX-1A SG Steam Header Main Steam Stop Control SW to OPEN position.
- d. ENSURE vent solenoids RESET:
1MS-2018C-S 1MS-2018D-S
- e. ENSURE supply solenoids RESET:
1MS-2018A-S 1MS-2018B-S
- f. Slowly OPEN IA-638, and CHECK 1MS-2018 opens.
- g. IF 1MS-2018 is NOT OPEN, THEN CYCLE 1MS-2016, HX-1A SG Header Atmospheric Steam Dump Control, to FULL OPEN to equalize pressure across the 1MA-2018 disk.
- h. CHECK for OPEN indication for 1MS-2018 on 1C03.
5.2.7 IF required per step 4.5, THEN PERFORM the following:
- c. Lightly GREASE valve stem with grease specified in LM 2.1, Lube Manual.
5.2.8 SHUT and LOCK 1MS-234, 1HX-1A SG Header 1MS-2018 Main Steam Stop Bypass.
5.2.9 IF required, THEN ADJUST setpoint of 1MS-2016 to reestablish condenser steam dump.
PBN LOI NRC 028E, 2023 NRC Exam Scenario 2, Rev 0 SEG Page 13 of 33 TR-AA-230-1007-F14, Revision 0 Event # 2 Surveillance Test, 1MS-2018 ROLE PLAY Booth Communications:
As AO supporting TS 39:
o When asked, report 1MS-2018 solenoids have actuated (Step 5.2.4) o When directed to shut IA-638, insert Trigger 2, and report the valve is shut. (Step 5.2.6) o When directed to open 1MS-234, insert Trigger 1 and report the valve open.
o When asked, insert Trigger 5 to reset solenoids, report that 1MS-2018 vent and supply solenoids have reset. (Step 5.2.6.d and e) o When directed to slowly open IA-638, insert Trigger 4, and report when the valve is open. (Step 5.2.6.f) o When directed to shut and lock 1MS-234, insert Trigger 3, and report the valve shut and locked. (Stem 5.2.8)
Respond to reports or direction to field operators as necessary.
SM Communications:
Provide crew direction to perform TS 39.
Respond to reports from crew members as required.
NOTES Continuation Criteria:
After TS 39 has been completed, or at the discretion of the Lead Examiner, continue with the next event.
PBN LOI NRC 028E, 2023 NRC Exam Scenario 2, Rev 0 SEG Page 14 of 33 TR-AA-230-1007-F14, Revision 0 Event # 3 Low Accumulator Pressure ACTION Booth: Insert Trigger 6 per Lead Instructor Insert Triggers 8 and 9 when directed by the crew for raising accumulator pressure.
STUDENT
RESPONSE
Symptoms / Indications Alarm CO1 B 4-8, 1T-34B Accumulator Pressure High or Low 1T-34B, SI Accumulator pressure less than 700 psig BOP/RO Acknowledge alarm and review ARB.
SRO Direct the crew to restore accumulator pressure Assess Technical Specifications Crew OI 100, Adjusting SI Accumulator Level, Pressure and PORV Backup Nitrogen Pressure Unit 1 (BOP) 5.2 Pressurizing 1T-34B To Between 710 and 750 Psig 5.2.1 In Control Room, PERFORM the following:
- b. ENSURE the following valves are SHUT:
- 1SI-834A, T-34A SI Accumulator Nitrogen Inlet
- 1SI-834B, T-34B SI Accumulator Nitrogen Inlet
- a. ENSURE the following valves are SHUT:
- 1SI-838C, T-34A/B SI Accumulator Truck Fill Inlet
- 1SI-838A, T-34A/B SI Accumulator Nitrogen Inlet
- 1SI-838B, T-34A/B SI Accumulator Nitrogen Inlet NOTE: Valves inside containment may be marked N/A in accordance with Shift Management direction, based upon plant conditions. It is normally recommended only to be performed during outages.
5.2.3 Inside Containment, PERFORM the following: N/A 5.2.4 ATTACH truck hose connection to Nitrogen fill line at 1SI-838C, T-34A/B SI Accumulator Truck Fill Inlet.
5.2.5 In Control Room, RECORD 1T-34B initial parameters:
- 1LI-934, T-34B SI Accumulator Level Indicator _______ %
- 1LI-935A, T-34B SI Accumulator Level Indicator _______ %
- 1PI-936, T-34B Accumulator Pressure Indicator _______ psig
- 1PI-937A, T-34B Accumulator Pressure Indicator _______ psig 5.2.6 In Control Room, OPEN the following:
- a. 1SI-834B, T-34B SI Accumulator Nitrogen Inlet.
5.2.7 OPEN 1SI-838C, T-34A/B SI Accumulator Truck Fill Inlet.
PBN LOI NRC 028E, 2023 NRC Exam Scenario 2, Rev 0 SEG Page 15 of 33 TR-AA-230-1007-F14, Revision 0 Event # 3 Low Accumulator Pressure 5.2.8 IF problems develop while pressurizing 1T-34B, THEN PERFORM the following:
- a. SHUT the following valves:
- 1SI-834B, T-34B SI Accumulator Nitrogen Inlet
- 1SI-838C, T-34A/B SI Accumulator Truck Fill Inlet.
- Truck fill isolation valve
- b. IF it becomes necessary to change out Nitrogen Tube Trailers while pressurizing 1T-34B, THEN GO TO Subsection 5.5, Nitrogen Tube Trailer Changeout During Unit 1 Accumulator Fill.
5.2.9 THROTTLE OPEN truck fill isolation valve, to begin N2 flow.
5.2.10 OBSERVE accumulator pressure is trending higher on 1PI-937A, T-34B Accumulator Pressure Indicator.
5.2.11 WHEN accumulator pressure is between 710 and 750 PSIG as indicated on 1PI-937A, T-34B Accumulator Pressure Indicator, THEN SHUT the following: (B-1) (Ref 6.4.1)
- 1SI-834B, T-34B SI Accumulator Nitrogen Inlet
- 1SI-838C, T-34A/B SI Accumulator Truck Fill Inlet.
- Truck fill isolation valve 5.2.12 In Control Room, RECORD 1T-34B accumulator final parameters:
- 1LI-934, T-34B SI Accumulator Level Indicator _______ %
- 1LI-935A, T-34B SI Accumulator Level Indicator _______ %
- 1II-936, T-34B Accumulator Pressure Indicator _______ psig
- 1PI-937A, T-34B Accumulator Pressure Indicator _______ psig 5.2.13 VENT Nitrogen Fill Line as follows:
- b. LEAVE 1SI-957 OPEN for approximately 5 minutes OR as directed by Shift Management to ensure pressure released.
5.2.14 IF NO other UNIT 1 SI Accumulator or Unit 1 PORV Backup Nitrogen System will be pressurized, THEN GO TO Subsection 5.4, Realigning Unit 1 SI Accumulator Nitrogen Fill System.
Assess Technical Specifications LCO 3.5.1, Accumulators, Condition B (accumulator pressure less than 700 psig)
CONDITION REQUIRED ACTION COMPLETION TIME B. One accumulator inoperable for reasons other than Condition A B.1 Restore accumulator to OPERABLE status 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
PBN LOI NRC 028E, 2023 NRC Exam Scenario 2, Rev 0 SEG Page 16 of 33 TR-AA-230-1007-F14, Revision 0 Event # 3 Low Accumulator Pressure ROLE PLAY Booth Communications:
When directed to ensure the following valves are shut: 1SI-838C, 1SI-838A, and 1SI-838B, wait 1 minute and report all three valves are shut. (Step 5.2.2)
When directed to attach truck hose connection, wait 1 minute and repot the hose connected. (Step 5.2.4)
When directed to open 1SI-838C, report the valve is open. (Step 5.2.7) - not modeled on sim When directed to throttle open the truck fill isolation, insert Trigger 8 and report the fill valve open. (Step 5.2.9)
When directed to shut 1SI-838C and the truck fill valve, Insert Trigger 9 and report both valves are shut.
Respond to reports or direction to field operators as necessary.
SM Communications:
If necessary inform the crew that relief crew AOs are investigating the cause of the accumulator pressure drop.
Respond to reports from crew members as required.
NOTES Continuation Criteria:
After the crew has restored accumulator pressure and assessed Technical Specifications, or at the discretion of the Lead Examiner, continue with the next event.
PBN LOI NRC 028E, 2023 NRC Exam Scenario 2, Rev 0 SEG Page 17 of 33 TR-AA-230-1007-F14, Revision 0 Event # 4 1CV-135, Letdown Pressure Controller Failure ACTION Booth: Insert Trigger 12 per lead instructor STUDENT
RESPONSE
Symptoms / Indications 1HC-135 output oscillating Letdown pressure oscillations Alarm 1CO4 1C 1-6, Letdown Line Pressure High BOP/RO Diagnoses controller malfunctions and takes manual control of letdown pressure.
Acknowledges alarm and reviews ARB SRO Implements AOP-1D, Chemical and Volume Control System Malfunction Crew AOP-1D, Chemical and Volume Control System Malfunction
- 1. Check RCS leak - NOT IN PROGRESS
- 2. Determine CVCS Malfunction:
o IF letdown line pressure control valve failed, THEN go to Step 36.
- 36. Check LP letdown line pressure control valve - FAILED
- 37. Establish manual control: (RO)
- a. Place LP Letdown line pressure controller - IN MANUAL
- 38. Notify duty station manager and I&C duty and call.
- 39. Return to procedure and step in effect.
ROLE PLAY Booth Communications:
If directed to check CVCS components in the PAB, report that all condition appear normal.
Respond to reports or direction to field operators as necessary.
SM Communications:
Respond to reports from crew members as required.
PBN LOI NRC 028E, 2023 NRC Exam Scenario 2, Rev 0 SEG Page 18 of 33 TR-AA-230-1007-F14, Revision 0 Event # 4 1CV-135, Letdown Pressure Controller Failure NOTES Continuation Criteria:
After the crew has taken action to establish manual control of letdown pressure, or at the discretion of the Lead Examiner, continue with the next event.
PBN LOI NRC 028E, 2023 NRC Exam Scenario 2, Rev 0 SEG Page 19 of 33 TR-AA-230-1007-F14, Revision 0 Event # 5 CCW Pump Trip ACTION Booth: Insert Trigger 14 per Lead Instructor STUDENT
RESPONSE
Symptoms / Indications 1P-11A indicates tripped (white light)
Lowering Component Cooling flow Alarm 1CO3 1D 3-7, Motor Breaker Trip Alarm 1CO3 1D 1-4, 1P-1A RCP Cooling Water Flow Low Alarm 1CO4 1D 1-6, 1P-1B RCP Cooling Water Flow Low BOP/RO Diagnoses loss of 1P-11A with failure of 1P-11B to automatically start Manually start 1P-11B SRO Implements AOP-9B, Component Cooling System Malfunction Crew AOP-9B, Component Cooling System Malfunction
- 1. Check component cooling pumps - AT LEAST ONE RUNNING (BOP)
RNO: IF component cooling surge tank greater than 20%, THEN start one component cooling pump.
o 1P-11B
- 2. Maintain surge tank level
- 3. Check surge tank level - GREATER THAN 10%
- 4. Check component cooling system for inleakage
- 5. Check reactor trip not required
- 6. Check RHR status
- 7. Request Chemistry analyze component cooling water
- 8. Notify DSM and implement Emergency Plan
- 9. Return to procedure and step in effect The crew may take 1P-11A control switch to pull-out to clear the Motor Breaker Trip alarm.
Assess Technical Specifications (SRO)
LCO 3.7.7, Component Cooling Water, Condition A CONDITION REQUIRED ACTION COMPLETION TIME A. One CC pump inoperable A.1 Restore CC pump to OPERABLE status 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> AND 144 hours0.00167 days <br />0.04 hours <br />2.380952e-4 weeks <br />5.4792e-5 months <br /> from discovery of failure to meet the LCO
PBN LOI NRC 028E, 2023 NRC Exam Scenario 2, Rev 0 SEG Page 20 of 33 TR-AA-230-1007-F14, Revision 0 Event # 5 CCW Pump Trip ROLE PLAY Booth Communications:
If directed to check 1P-11A, CCW Pump, wait 2 minutes and report the pump is not running and the motor is hot to the touch.
If directed to check the breaker for 1P-11A (1B52-10A at 1B-03), report the breaker is tripped on over-current.
After 1P-11B has been started, report a SAT start for 1P-11B.
Respond to reports or direction to field operators as necessary.
SM Communications:
Respond to reports from crew members as required.
NOTES Continuation Criteria:
After the crew has started the standby CCW pump and assessed Technical Specifications, or at the discretion of the Lead Examiner, continue with the next event.
PBN LOI NRC 028E, 2023 NRC Exam Scenario 2, Rev 0 SEG Page 21 of 33 TR-AA-230-1007-F14, Revision 0 Event # 6 Seismic Event / Dropped Rods ACTION Booth: Insert Trigger 16 per Lead Instructor Trigger 17 (conditional) inserts when the reactor is tripped.
STUDENT
RESPONSE
Symptoms and Indications:
o CO1 A 2-6, Seismic Detector Actuation o 1CO4 1A 1-5, Rod Bottom Rod Drop 1C04 Indications:
o Rod bottomed indication on IRPI for rods J4, I9, and L6 BOP/RO Diagnose multiple dropped rods - manually trips the reactor Performs EOP-0 Immediate Actions SRO Directs Reactor trip per AOP-6A, Dropped Rod Implements EOP-0, Reactor Trip or Safety Injection AOP-6A, Dropped Rod
- 1. Check only one rod dropped RNO: Perform the following:
- a. Trip the reactor (RO)
- b. Go to EOP-0, Reactor Trip or Safety Injection Note: upon receiving the field report of steam in the Turbine Hall, the crew should take action to attempt to close MSIVs. (MSIVs will fail to close manually from the control room)
EOP-0, Reactor Trip or Safety Injection
- 1. Verify Reactor Trip (RO)
- 2. Verify turbine trip (RO)
Foldout Page 3: FAULTED S/G ISOLATION CRITERIA If any S/G pressure lowering in an uncontrolled manner OR and S/G completely depressurized, THEN the following may be performed:
Isolate feed flow to faulted S/G Maintain total feed flow greater than or equal to 275 gpm until narrow range level in at least one S/G is greater than [52%] 33%
If the crew diagnoses both S/Gs are faulted, then they should reduce total AFW flow to approximately 275 gpm shared between both S/Gs.
PBN LOI NRC 028E, 2023 NRC Exam Scenario 2, Rev 0 SEG Page 22 of 33 TR-AA-230-1007-F14, Revision 0 Event # 6 Seismic Event / Dropped Rods
- 5. Perform Attachment A, Automatic Action Verification, while continuing with this procedure. (BOP)
- a. Condenser steam dumps - AVAILABLE
- Place steam dump mode selector switch in MANUAL
- b. RCS Temperature RNO: Perform the following:
- 1) IF temperature is less than 547°F AND lowering, THEN perform the following: control total feed flow.
a) Stop dumping steam b) IF cooldown continues, THEN control total feed flow Control feed flow to the SGs using 1AF-4000, 1AF-4001, 1FIC-4074A, and 1FIC-4014B, AFW to SG flow control valves c) IF cooldown continues, THEN isolate main steam lines Attempts to shut 1MS-2017/2018, Steam Generator A/B Main Steam Stop CV - MSIVs will fail to close.
- 11. Check if S/G are NOT faulted; RNO: (RO)
- 2) Go to EOP-2, Faulted Steam Generator Isolation (SRO)
BOP performs EOP-0, Attachment A, Automatic Action Verification (BOP)
A1 - Verify feedwater isolation A2 - Verify containment isolation A3 - Verify ECCS Pumps RUNNING
- a. SI pumps - BOTH RUNNING
- b. RHR Pumps - BOTH RUNNING A4 - Verify service water pumps running A5 - Verify containment accident cooling units RUNNING A6 - Verify component cooling water pumps - ONLY ONE RUNNING A7 - Check if main steam lines can remain open (If not already attempted, the examinee may attempt to close 1MS-2017 and 1MS-2018 per RNO step)
Ensure main steam isolation on affected main steam line(s) shut:
o 1MS-2017 o 1MS-2018 A8 - Verify containment spray not required:
A9 - Verify ECCS Flow A10 - Verify AFW valve alignment - PROPPER EMERGENCY ALIGNMENT A11 - Verify proper ECCS valve alignment
PBN LOI NRC 028E, 2023 NRC Exam Scenario 2, Rev 0 SEG Page 23 of 33 TR-AA-230-1007-F14, Revision 0 Event # 6 Seismic Event / Dropped Rods A12 - Check containment spray NOT ACTUATED A13 - Stop any boration via the blender in progress A14 - Ensure the Auxiliary building filter/exhaust fans - OPERATING A15 - Notify the STA to IMPLEMENT Status trees, Notify the SM of any equipment malfunctions previously noted.
A16 - Verify Service Water system alignment A17 - Check miscellaneous valves - SHUT A18 - Check Control Room ventilation A19 - Check cable spreading room ventilation system - OPERATING A20 - Check Computer Room ventilation system - OPERATING A21 - Check AFW recirc fans - ONE RUNNING A22 - Check Circ Water Pump House temperature less than 105°F A23 - Check G03/G04 switchgear room temperature less than 95°F A24 - Periodically check status of spent fuel cooling.
ROLE PLAY Booth Communications:
Shortly after the steam break malfunction is inserted, report as TH AO that the steam break is in the turbine hall. (after IAs)
EOP-0, Att A communications:
o PAB AO: When directed to check rad waste service water valves SHUT at C-180, report the TV-LW61 and TV-LW62 are both SHUT o TH AO: When directed to check Circ Water Pump House temperature, wait 1 minute and report 76°F and stable.
o TH AO: When directed to check G03/G04 switchgear room temperature, wait 1 minute and report 80°F and stable.
Respond to other reports or direction to field operators as necessary.
SM Communications:
Respond to reports from crew members as required.
NOTES
PBN LOI NRC 028E, 2023 NRC Exam Scenario 2, Rev 0 SEG Page 24 of 33 TR-AA-230-1007-F14, Revision 0 Event # 7 Steam Line Break / MSIVs Fail to Close ACTION Booth: Insert Trigger 19 and 20 to locally close MSIVs when directed by the crew.
STUDENT
RESPONSE
CT-2 Action BOP/RO Perform EOP actions as directed.
SRO Implements EOP-2, Faulted Steam Generator Isolation, then Transitions to ECA-2.1, Uncontrolled Depressurization of Both Steam Generators.
Crew EOP-2, Faulted Steam Generator Isolation
- 1. Check main steam isolation
- a. Any MSIV valve - OPEN
- b. Check main steamline isolation signal - NOT ACTUATED RNO: Isolate AFFECTED MSIV(S) if any MSIV can NOT be shut, THEN locally shut MSIV per Attachment A, Local Shutting of MSIV (BOP directs PAB AO) o 1MS-2018 for S/G A o 1MS-2017 for S/G B
- 2. Check if any S/G is not faulted; RNO:
- a. IF both S/G pressure are lowering in an uncontrolled manner, THEN go to ECA-2.1, Uncontrolled Depressurization of Both Steam Generators. (SRO)
CT-2 Isolate Steam Leak (Local action to shut MSIVs and isolate the steam leak may be directed in EOP-2, Step 1 OR ECA-2.1 Step 1)
ECA-2.1, Uncontrolled Depressurization of Both Steam Generators
- 1. Check secondary pressure boundary
- a. Verify shut the following valves
- 1)
MSIVs RNO: Locally shut MSIVs per ATTACHMENT B, Local Shutting of MSIV (This action may have already be given in EOP-2, Step 1)
- 2)
MSIV By-pass valves
- 3)
Feedwater isolation valves
- 4)
Atmospheric steam dumps
- 5)
S/G blowdown isolation valves (BOP)
S/G A 1MS-5958 1MS-2042 S/G B 1MS-5959 1MS-2045
- b. Reset loss of feedwater turbine trip (BOP)
PBN LOI NRC 028E, 2023 NRC Exam Scenario 2, Rev 0 SEG Page 25 of 33 TR-AA-230-1007-F14, Revision 0 Event # 7 Steam Line Break / MSIVs Fail to Close CT-1 Action
- b. Locally shut the following valves while continuing with this procedure
- Main Steam trap isolations 1MS-228 1MS-238 CT-1, Control AFW Flow to minimize RCS cooldown
- 2. Control feed flow to minimize RCS Cooldown
- a. Check cooldown rate in RCS cold legs - LESS THAN 100°F/hr; RNO: Perform the following:
- Reduce feed flow to 50 gpm to each S/G. (BOP)
- Go to Step 2.c
- 3. Check if RCPs should be stopped
- 4. Check PZR PORVs and block valves
- 5. Check Secondary Radiation Once MSIVs have been shut locally, both S/G pressures will begin to rise.
FO2 Faulted S/G Transition Criteria: (SRO)
IF any S/G pressure rises at any time AND SI termination in Steps 9 through 17 is NOT in progress, THEN go to EOP-2 UNIT 1, FAULTED STEAM GENERATOR ISOLATION.
Note: Once the crew lowers AFW flow to both S/G less than 275 gpm per ECA-2.1 a Heat Sink CSF RED path will exist. The crew should apply the Note prior to Step 1 in CSP-H.1 and NOT implement CSP-H.1.
PBN LOI NRC 028E, 2023 NRC Exam Scenario 2, Rev 0 SEG Page 26 of 33 TR-AA-230-1007-F14, Revision 0 Event # 7 Steam Line Break / MSIVs Fail to Close EOP-2, Faulted Steam Generator Isolation (Second entry)
- 1. Check main steam isolation
- 2. Check if any S/G is not faulted
- 3. Identify faulted S/G RNO: IF faulted S/G is NOT identified, THEN perform the following:
- 1) Search for initiating break while continuing with this procedure.
- 2) Go to Step 5
- 5. Check CST level - GREATER THAN 4 ft
- 6. Check secondary radiation
- 7. Go to EOP-1, Loss of Primary or Secondary Coolant ROLE PLAY Booth Communications:
When directed to take action locally to locally shut MSIVs per Attachment A (EOP-2) or Attachment B (ECA-2.1), coordinate with the lead instructor and insert Trigger 19 and 20 when directed. (After the crew has controlled AFW flow per ECA-2.1)
When directed to locally shut 1MS-235, 1MS-237, 1MS-228, and 1MS 238 insert Triggers 21 and 22, report when valves are closed.
Respond to reports or direction to field operators as necessary.
SM Communications:
Respond to reports from crew members as required.
NOTES Scenario Termination Terminate the scenario when the crew completes EOP-2, or per Lead Evaluator.
NOTES Freeze the simulator Determine if the NRC has any follow up questions Save SBT Data (see sim setup instructions)
PBN LOI NRC 028E, 2023 NRC Exam Scenario 2, Rev 0 SEG Page 27 of 33 TR-AA-230-1007-F14, Revision 0 QUANTITATIVE ATTRIBUTES Malfunctions:
Before EOP Entry:
- 1CV-135 controller failure
- Multiple dropped rods
- PR NI failure After EOP Entry:
- MSIVs fail to close Abnormal Events:
- CVCS Malfunction
- Component Cooling System Malfunction
- Seismic Event Major Transients:
- Faulted S/G Critical Tasks:
- 1.
CT1 Control AFW Flow to Minimize RCS Cooldown
- 2.
CT2 Isolate Steam Leak Major Procedures:
OP 1C TS 39 OI 100B AOP-1D AP-9B AOP-6C EOP-0 EOP-2 ECA-2.1 EOP-2
PBN LOI NRC 028E, 2023 NRC Exam Scenario 2, Rev 0 SEG Page 28 of 33 TR-AA-230-1007-F14, Revision 0 CT1 Control AFW Flow to Minimize RCS Cooldown Initiating Cue: All of the following:
o Uncontrolled depressurization of both SGs o Cooldown rate in RCS cold legs exceeds 100°F per hour Performance Feedback:
o Control board indications show that AFW flow was lowered o Indication (and establishment) of minimum flow to both S/Gs Success Path: Valve position and flow rate indication that AFW continues to be delivered to both SGs at a rate of approximately 50 gpm per S/G.
Performance Standard: Manipulation of controls as required throttling AFW flow sufficiently to prevent a severe ORANGE challenge to the integrity CSF but not less than the 50 gpm per SG.
Safety Significance: Failure to control AFW flow rate to the SGs leads to an unnecessary and avoidable severe challenge to the integrity CSF. Also, failure to perform the critical task increases challenges to the subcriticality CSF beyond those irreparably introduced by the postulated plant conditions.
PBN LOI NRC 028E, 2023 NRC Exam Scenario 2, Rev 0 SEG Page 29 of 33 TR-AA-230-1007-F14, Revision 0 CT2 Isolate the Steam Leak Initiating Cue: All of the following:
o Uncontrolled depressurization of both SGs o Cooldown rate in RCS cold legs exceeds 100°F per hour Performance Feedback:
o S/G pressures stabilize (consistent with RCS cooldown) o MSIVs indicate closed o Lowering rate of RCS cooldown.
Success Path: Crew directs LOCAL closing of the MSIVs IAW EOP 2, Attachment A, Local Shutting of MSIV or IAW ECA-2.1, Attachment B, Local Shutting of MSIV.
Measurable Performance Standard: The crew must DIRECT LOCAL closing of both MSIVs prior to completing step 1 of ECA-2.1.
Safety Significance: Failure to isolate a faulted SG that can be isolated causes challenges to CSFs beyond those irreparably introduced by the postulated conditions. Also, depending upon plant conditions, it could constitute a failure by the crew to "demonstrate the ability to recognize a failure or an incorrect automatic actuation of an ESF system or component."
Failure to isolate a steam leak can result in challenges to the following CSFs:
o Integrity o Subcriticality
PBN LOI NRC 028E, 2023 NRC Exam Scenario 2, Rev 0 SEG Page 30 of 33 TR-AA-230-1007-F14, Revision 0 Booth Summary Event #1 OP-1C Power Ascension Action Role Play Event #2 TS 39, Surveillance Test on 1MS-2018 Action Role Play Event #3 SI Accumulator Low Pressure Action Role Play Event #4 Letdown Pressure Controller Failure Action Role Play Event #5 CCW Pump Trip Action Role Play Event #6 Seismic Event / Dropped Rods Action Role Play Event #7 Steam Line Break / MSIVs fail to Close Action Role Play
PBN LOI NRC 028E, 2023 NRC Exam Scenario 2, Rev 0 SEG Page 31 of 33 TR-AA-230-1007-F14, Revision 0 SHIFT TURNOVER INFORMATION PLANT CONDITIONS:
UNIT 1 Time in core life (MWD/MTU):
1500 Reactor power (%):
2% MODE 2 Boron concentration (ppm):
1530 ppm Rod height, CBD @:
129 TECHNICAL SPECIFICATION ACTION CONDITIONS IN EFFECT:
TSAC Description Required Action & Completion Time EQUIPMENT OUT OF SERVICE:
- None.
PLANNED EVOLUTIONS:
- Power ascension per OP 1C.
- TS 39 for 1MS-2018 TURNOVER INFORMATION:
- S/G level is being manually controlled on the by-pass valves.
- On line risk is GREEN.
- Today is Tuesday, day shift.
PBN LOI NRC 028E, 2023 NRC Exam Scenario 2, Rev 0 SEG Page 32 of 33 TR-AA-230-1007-F14, Revision 0 Pre-Scenario Procedure Checks Procedure OS1 1st Check 2nd Check AOP-1D AOP-9B AOP-28 EOP-0 EOP-1 EOP-2 ECA-2.1 Specific ARP/ARBs to be second checked - All Others first checked 1st Check 2nd Check CO1 B 4-8 1CO4 1C 1-6
PBN LOI NRC 028E, 2023 NRC Exam Scenario 2, Rev 0 SEG Page 33 of 33 TR-AA-230-1007-F14, Revision 0 Post-Scenario Procedure Checks Procedure OS1 1st Check 2nd Check AOP-1D AOP-9B AOP-28 EOP-0 EOP-1 EOP-2 ECA-2.1 ARBs 1st Check 2nd Check CO1 B 4-8 1CO4 1C 1-6 RESET IC N/A Booth Cleared Exam Material Magnets Replaced P&IDs cleaned and replaced Red dots removed from alarm windows
Form 3.3-1 Scenario Outline Event No.
Malf.
No.
Event Type*
Event Description 1
N/A (N) BOP Service water pump swap (for February lineup) 2 (I) ATC (I/TS) SRO PRNI Channel 1 Fails high 3
(I) ATC (I/TS) SRO PZR Level Channel 2 (controlling) fails low 4
(C/MC) BOP (C) SRO Trip of running EHC Pump/Standby fails to start 5
(R) ATC (TS) SRO B SG Tube Leak (~30 gpm) IAW AOP 3, Rapid Downpower to <50% Power IAW AOP 17A 6
(M) CREW B SGTR - (EOP-0 -> EOP-3) (CT) 7 (C/MC) BOP (C) SRO Condensate Steam Dump Failure (CSD) requiring use of ADV to Cooldown (CT)
Termination Criteria:
Critical Tasks have been evaluated RCS depressurized IAW E-3 (SI Termination-Step 22)
At the discretion of the Lead Evaluator
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS)Tech Spec, (MC)Manual Control Facility:
Point Beach Scenario #: 4 Scenario Source:
Op. Test #: Feb 2023 Examiners:
Applicants/
Operators:
Initial Conditions:
100% Power, MOC, Boron @ 1000 ppm Turnover:
The plant is at 100% power, A Containment Spray pump is tagged OOS for maintenance. Crew is expected to swap service water pumps.
Critical Tasks:
- 1. Isolate B SG (Steam from & Feed Flow to)
- 2. Control Initial RCS Cooldown
CT2: Control Initial RCS Cooldown Initiating Cue: (Paste from DCC Scen 3) SGTR indications requiring EOP-3 action:
o Uncontrollable rise in B SG level o Hi Steam line rad levels Performance Feedback: All of the following:
o Continuing rise in SG Level o Indications of reactor water inleakage to SG until depressurization Success Path: Performing steps 6-14 of EOP-3 Measurable Performance Standard: Perform Steps 6 - 14 of EOP-3 to identify target SG pressure (Step 6) and cooldown the RCS to ensure RCS temperature is not too high to maintain minimum subcooling (transition to ECA 3.1) or too low causing a challenge to subcriticality (red or orange path).
Safety Significance: Failure to perform the steps in E-3 could result in reduced SGWL inventory necessary for core cooling, increased RCS to ruptures SG break flow, which increases radioactive release to the public. Additionally, failure to control the depressurization could reduce RCS temperature and challenge the reactor vessel integrity.
CT1: Isolate B SG (Steam from & Feed Flow to)
Initiating Cues: (Paste from DDC Scen 3) o B SGTR results in uncontrolled rising level post reactor trip o SG Level continues to rise following AFW flow control o Hi SGWL alarms Performance Feedback: All of the following:
o Valve indication (GREEN light) that the valves closed during isolation Success Path: Isolation of a ruptured SG in E-3, Steps 3 and 4.
Measurable Performance Standard: Perform steps to isolate steam and feed flow by performing steps 3 and 4 of EOP-3 before water release from the ruptured SG PORV or safety valve as indicated by SG NR level indicating 100% with SG WR level stable and a SG PORV or Safety Valve not fully closed.
Safety Significance: Isolating a ruptured SG minimizes release of radioactivity from the SG.
CT3: Depressurize RCS to meet SI Termination Criteria Initiating Cues: (Paste from DDC Scen 3) o B SGTR results in uncontrolled rising level post reactor trip o SG Level continues to rise following AFW flow control o Hi SGWL alarms Performance Feedback: All of the following:
o Valve indication (GREEN light) that the valves closed during isolation Success Path: Depressurize RCS using PZR Spray to meet EOP-3 SI Termination Criteria Measurable Performance Standard: Depressurize RCS to meet SI termination criteria before water release from the ruptured SG PORV or safety valve as indicated by SG NR level indicating 100% with SG WR level stable and a SG PORV or Safety Valve not fully closed.
Safety Significance: Isolating a ruptured SG minimizes release of radioactivity from the SG.
Scenario Executive Summary Initial Conditions / Turnover:
Point Beach Unit 1 will be at 100% during the middle of the operating cycle. A Containment Spray pump is tagged OOS for maintenance.
Direction(s) for the Shift:
Configure SW pumps for February, March, April operation IAW 0-SOP-SW-107, Service Water Pump Operation. An auxiliary operator is on station and ready to perform the evolution.
Event #1 - Service Water Pump Configuration Change Crew will swap SW configurations from A and E running (with C as the 3rd pump) to B and D running (with F as the 3rd pump) using 0-SOP-SW-107. This event will be completed when the SW configuration has been completed.
Event #2 - PRNI Channel 1 Fails high Due to a card malfunction, NE-44 (Power Range Channel YELLOW) will fail high. The crew will investigate and recognize the failed channel and remove it from service using 0-SOP-IC-001 YELLOW, Attachment A (pg 32). Manual rod control will be taken while the channel is removed from service. SRO will evaluate and enter Tech Spec LCO 3.3.1 Condition A, D, R, and S (Functions 2a, 2b, 5, 6, 17b(1), 17c, 17d, and 17e). This event will be completed when the plant is stable, Tech Specs have been evaluated and/or at the direction of the Lead Examiner.
Event #3 - PZR Level Channel Blue (controlling) Fails Low A malfunction causes 1LC-427B to fail low. Crew will respond to various alarms; however, ARP 1C04 1C 1-3, Pressurizer Level Low or High gives guidance to take manual control of charging pumps and refer to AOP-24, Instrument Malfunction. Channel will be removed from service using 0-SOP-IC-001 WHITE. Once the channel is removed from service, auto control will be restored. SRO will evaluate and enter Tech Spec LCO 3.3.1 Condition A and K (Function 8).
This event will be completed when the plant is stable, Tech Specs have been evaluated and/or at the direction of the Lead Examiner.
Event #4 - Trip of running EHC Pump/Standby fails to start. (start standby pump using ARP 1C03 1F 1-11)
A trip of 1P-75 EHC pump will occur (standby fails to auto start). Crew will take action using ARP 1C03 1F 1-11, EH Supply System Unit 1. Crew will take manual action to start 1P-76 and restore EHC pressures to normal operating band. This event will be completed when the plant is stable and/or at the direction of the Lead Examiner.
Event #5 - B SG Tube Leak (~30 gpm) IAW AOP 3, Rapid Downpower to <50% Power IAW AOP 17A.
A 30 gpm SGTL in Steam Generator B will be inserted. Crew will respond to various alarms and take action using AOP-3, Steam Generator Tube Leak. Crew will evaluate leak rate and determine that power needs to be reduced to < 50% in one hour using AOP-17A. This event will be completed when the plant is reducing power and/or at the direction of the Lead Examiner.
Event #6 - (Major) - B SGTR - (EOP EOP-3)
The tube leak will propagate into a tube rupture. Automatic reactor trip and safety injection will occur. Crew will enter EOP-0, diagnose a tube rupture, and go to EOP-3. Crew will depressurize to stop the break flow.
Event #7 - Condensate Steam Dump Failure (CSD) requiring use of ADV to Cooldown.
When the crew attempts to cooldown using the steam dumps, a failure will occur such that the steam dump valves cannot be used. The crew will use atmospheric steam dumps to cooldown.
Scenario Termination The scenario is terminated when the Critical Tasks have been evaluated, the crew has performed an RCS depressurization IAW E-3 (SI Termination-Step 22) and at the discretion of the Lead Evaluator.
Page 1 of 58 Form 3.3-2 Required Operator Actions Op. Test No.: Feb 2023 Scenario No.: __4__
Event No.: __1__
Event
Description:
Service Water Pump Swap Symptoms/Cues: None Time Position Applicants Actions or Behavior NOTE: Prior to taking the shift, it is expected that the crew will have conducted the required pre-shift briefs, pre-marking of procedures, and briefings to commence with normal plant evolution. All communications with transmission have been completed.
0-SOP-SW-107, Rev 7, Section 5.2: SHIFT Service Water Pumps as necessary to maintain desired SW system Pressure and component cooling as follows:
SRO, BOP 5.2.1 STATION an Operator locally in the Pump House to verify proper pump oil level and valve lineup; also to monitor coast down of pumps being secured.
Booth: This step was pre-briefed: if the MCR verifies, confirm an operator is on station.
BOP 5.2.2: MONITOR SW Header pressures to verify proper operation of the SW Pumps being started.
BOP 5.2.3: IF starting a Service Water Pump, Then PLACE P-32-(B, D, F)-CS to START and RELEASE to AUTO.
BOP 5.2.4 NOTE: When SW Header pressure is low in the band, securing a SW pump during a pump shift may bring in C-1 A 3-6, North or South Service Water Header Pressure Low.
BOP 5.2.4: IF securing a Service Water Pump, Then PLACE P-32-(A, E, C)-CS to STOP and RELEASE to AUTO.
BOP 5.2.5: CHECK proper seating of check valves for SW Pumps stopped by audible and Service Water Header pressure indication.
Booth: If asked, report good start/stop of SW pumps, audible seating of check valve was heard.
SRO 5.2.6. This step is N/A.
Event Termination Continue to Event 2 when SW pumps have been swapped and at the discretion of the lead evaluator.
Page 2 of 58 Op. Test No.: Feb 2023 Scenario No.: __4__
Event No.: __2__
Event
Description:
PRNI Channel 1 Fails HIGH Symptoms/Cues: Various annunciators, PRNI Detector N41 (Red 1Y01) indicates UPSCALE Time Position Applicants Actions or Behavior CREW/ATC Crew silences alarms; ATC diagnoses failure SRO SRO directs entry into AOP-24, Response to Instrument Malfunctions.
AOP-24, RESPONSE TO INSTRUMENT MALFUNCTIONS SRO, ATC
- 1. Identify Failed Instrument (1Y01 is identified)
- 2. Check If Failed Instrument Is a Controlling Channel Determines not a controlling channel and goes to Step 5 SRO, ATC
- 5. Using ATTACHMENT A, PPCS PARAMETERS USED TO CALCULATE REACTOR THERMAL OUTPUT, Verify That Failed Instrument Is NOT An Input To RTO Determines failure is NOT an input to Thermal Output and goes to Step 6 SRO, BOP
- 6. Remove Failed Instrument Channel From Service Per 0-SOP-IC-001, ROUTINE MAINTENANCE PROCEDURE REMOVAL OF SAFEGUARDS OR PROTECTION SENSOR FROM SERVICE 0-SOP-IC-001 RED, ROUTINE MAINTENANCE PROCEDURE REMOVAL OF SAFEGUARDS OR PROTECTION SENSOR FORM SERVICE - RED CHANNELS, Section 5.1, Removing Sensor From Service 5.1.1 is N/A SRO 5.1.2. DETERMINE sensor number to be removed from service in Attachment A and REVIEW 0-SOP-IC-002, Technical Specifications LCO-Instrument Cross Reference, to determine applicable Technical Specification requirements.
SRO / BOP 5.1.3. REMOVE and DISCARD sheets from Attachment A and Attachment B that do NOT relate to the affected sensor SRO 5.1.4. SRO CONDUCT a pre-job brief for the sensor to be removed from service
Page 3 of 58 Op. Test No.: Feb 2023 Scenario No.: __4__
Event No.: __2__
Event
Description:
PRNI Channel 1 Fails HIGH Symptoms/Cues: Various annunciators, PRNI Detector N41 (Red 1Y01) indicates UPSCALE Time Position Applicants Actions or Behavior SRO 5.1.5. OBTAIN Shift Manager permission to REMOVE sensor from service.
Booth - Provide Shift Manager authorization to remove sensor from service.
SRO 5.1.6. COMPLETE "Remove From Service" portion of Attachment A for affected sensor.
Attachment A, Channel III - RED. NE-41, Power Range Channel (Page 45),
Remove from Service ATC NOTE: See Precaution 3.4 before taking power range Channel 41 out of service.
- 1. RECORD the as found position of the Rod Control Selector Switch Auto ___ Manual _____
- 2. PLACE the Rod Control Selector Switch in MANUAL ATC/BOP
BOP NOTE: The following step will cause C04 Annunciator 1A 1-1 (2A 1-11), NIS TRIP BYAPSS to ALARM
- 5. On 1C 133, CHECK DROPPED ROD ALARM TEST status light is LIT.
- 7. CHECK C04 Annunciator 1A 1-1 NIS TRIP BYPASS - LIT BOP
- 8. On 1C-130 SELECT BYPASS PR N41 on the following switches:
- a. Power Mismatch Bypass
- b. Rod Stop Bypass
Page 4 of 58 Op. Test No.: Feb 2023 Scenario No.: __4__
Event No.: __2__
Event
Description:
PRNI Channel 1 Fails HIGH Symptoms/Cues: Various annunciators, PRNI Detector N41 (Red 1Y01) indicates UPSCALE Time Position Applicants Actions or Behavior BOP
- 9. On 1C-130 SELECT N41 on the Comparator Channel Defeat Switch.
- 10. On 1C-130 CHECK COMPARATOR DEFEAT status light is LIT.
- 11. In cabinet C-111, PLACE the following bistable trip switches in the TRIP position (toggle switch up) and CHECK expected response.
SRO/ATC NOTE: The next step will cause the following C04 Annunciators to Alarm if they are NOT already LIT due to a channel failure:
1A 3-2, NI-41,42,43 or 44 POWER RANGE LOSS OF DET VOLTAGE 1A 4-2, POWER RANGE HIGH SET POINT CHANNEL ALERT 1A 4-3, POWER RANGE LOW SET OINT CHANNEL ALERT BOP
- 13. On C04 CHECK the following Bistable status lights LIT:
Page 5 of 58 Op. Test No.: Feb 2023 Scenario No.: __4__
Event No.: __2__
Event
Description:
PRNI Channel 1 Fails HIGH Symptoms/Cues: Various annunciators, PRNI Detector N41 (Red 1Y01) indicates UPSCALE Time Position Applicants Actions or Behavior ATC
- 14. CHECK the following C04 Annunciators are LIT:
- a. 1A 3-2, N-41, 42, 43 or 44 POWER RANGE LOSS OF DET VOLTAGE
- b. 1A 4-2, POWER RANGE HIGH SETPOINT CHANNEL ALERT
- c. 1A 4-3, POWER RANGE LOW SETOINT CHANNEL ALERT (if not blocked by P-10).
- 15. On 1C-133 CHECK the following status lights for N-41:
- a. LOSS OF DETECTOR VOLTAGE - LIT
- b. OVER POWER TRIP HIHG RANGE - LIT
- c. OVER POWER ROD STOP - LIT
- d. OVER PWOWER TRIP LOW RANGE - LIT
- e. POWER ABOVE PERMISSIVE P LIT
- f. POWER ABOVE PERMISSIVE P LIT
- g. POWER ABOVE PERMISSIVE P LIT
- h. DROPPED ROD ALARM - LIT
- i.
INSTRUMENT POWER ON - NOT LIT ATC
- 16. CHECK the following Interlocks are in the required state for existing unit conditions: (Via 2x2 indication lights or bistable indication lights on C04).
- a. Low Power Reactor Tips Block, P-7
- b. Power Range Neutron Flux, P-8
- c. Power Range Neutron Flux, P-9
- d. Power Range Neutron Flux, P-10 BOP
- 17. REMOVE the following NE-41 ID points from scan PPCS:
- a. N41, PR 1 RED
- b. N41A, OUTPUT FROM PR 1 TOP DET
- c. N41B, OUTPUT FROM PR 1 BOT DET BOP
- 18. IF Reactor Power is greater than 9%, P-10 Reset, THEN PLACE an operator aid on the EH Control Panel on C03.
Operator aid should state 0-SOP-IC-001, Attachment B, Section 2.0 must be performed prior to decreasing reactor power below 9%.
- 19. Steps 19 and up are N/A for this scenario.
Page 6 of 58 Op. Test No.: Feb 2023 Scenario No.: __4__
Event No.: __2__
Event
Description:
PRNI Channel 1 Fails HIGH Symptoms/Cues: Various annunciators, PRNI Detector N41 (Red 1Y01) indicates UPSCALE Time Position Applicants Actions or Behavior Section 5.1, Removing Sensor From Service SRO 5.1.7. INFORM Shift Manager the affected channel has been removed from service and bypassed per 0-SOP-IC-001 SRO 5.1.8. INFORM STA the affected channel has been removed from service AOP-24, RESPONSE TO INSTRUMENT MALFUNCTIONS SRO Step 7 is N/A SRO
- 8. Check Failure For Technical Specification Or TRM Applicability SRO NOTE: May use 0-SOP-IC-002 to cross reference Technical Specifications SRO 3.2.4 (SR 3.2.4.1, 3.2.4.2)Quad. Power Tilt Ratio Reduce Thermal Power >3% from RTP for each 1% of QPTR
>1.00 within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> AND Determine QPTR within 12 Hours AND perform SR 3.2.1.1, 3.2.1.2 and 3.2.2.1 within 24 Hours and re-evaluate Safety Analysis Table 3.3.1-1 item 2a Power Range Neutron Flux-High Condition D - Place channel in trip in 1 Hour OR Be in Mode 3 within 7 Hours.
Table 3.3.1-1 item 2b Power Range Neutron Flux-Low Condition D Table 3.3.1-1 item 5 Over Temp Delta T Condition D Table 3.3.1-1 item 17b-1 PR Neutron Flux P-7 Condition S - Verify interlock in required state for existing unit conditions within 1 Hour OR be in Mode 2 within 7 Hours.
Table 3.3.1-1 item 17c PR Neutron Flux P-8 Condition S Table 3.3.1-1 item 17d PR Neutron Flux P-9 Condition S Table 3.3.1-1 item 17e PR Neutron Flux P-10 Event Termination When the affected channel is removed from service and Tech Specs have been addressed or at the discretion of the lead examiner.
Page 7 of 58 Op. Test No.: Feb 2023 Scenario No.: __4__
Event No.: __3__
Event
Description:
Pressurizer Level Channel 2 (Controlling) fails low Symptoms/Cues: Various annunciators, LT-428 (Blue) indicates downscale, letdown isolates, Pzr Heaters cutoff, raises charging flow Time Position Applicants Actions or Behavior CREW/ATC Crew silences alarms; ATC diagnoses failure SRO SRO directs entry into AOP-24, Response to Instrument Malfunctions.
AOP-24, RESPONSE TO INSTRUMENT MALFUNCTIONS SRO, ATC
- 1. Identify Failed Instrument (LT-428 is identified)
- 2. Check If Failed Instrument Is a Controlling Channel Determines LT-428 is a controlling channel and goes to Step 5 SRO, ATC
- 3. Establish manual control as required:
Place affected controller in manual OR Place any affected equipment controls in manual SRO directs ATC to place the charging pump operating in Automatic in Manual, SRO, ATC
- 4. Return Affected Parameters to desired value(s)
SRO directs ATC to stabilize Pzr Level by lowering charging flow.
- 5. Using ATTACHMENT A, PPCS PARAMETERS USED TO CALCULATE REACTOR THERMAL OUTPUT, Verify That Failed Instrument Is NOT An Input To RTO Determines failure is NOT an input to Thermal Output and goes to Step 6 SRO, BOP
- 6. Remove Failed Instrument Channel From Service Per 0-SOP-IC-001, ROUTINE MAINTENANCE PROCEDURE REMOVAL OF SAFEGUARDS OR PROTECTION SENSOR FROM SERVICE 0-SOP-IC-001 RED, ROUTINE MAINTENANCE PROCEDURE REMOVAL OF SAFEGUARDS OR PROTECTION SENSOR FORM SERVICE - BLUE CHANNELS, Section 5.1, Removing Sensor From Service 5.1.1 is N/A
Page 8 of 58 Op. Test No.: Feb 2023 Scenario No.: __4__
Event No.: __3__
Event
Description:
Pressurizer Level Channel 2 (Controlling) fails low Symptoms/Cues: Various annunciators, LT-428 (Blue) indicates downscale, letdown isolates, Pzr Heaters cutoff, raises charging flow Time Position Applicants Actions or Behavior SRO 5.1.2. DETERMINE sensor number to be removed from service in Attachment A and REVIEW 0-SOP-IC-002, Technical Specifications LCO-Instrument Cross Reference, to determine applicable Technical Specification requirements.
SRO / BOP 5.1.3. REMOVE and DISCARD sheets from Attachment A and Attachment B that do NOT relate to the affected sensor SRO 5.1.4. SRO CONDUCT a pre-job brief for the sensor to be removed from service SRO 5.1.5. OBTAIN Shift Manager permission to REMOVE sensor from service.
Booth - Provide Shift Manager authorization to remove sensor from service.
SRO 5.1.6. COMPLETE "Remove From Service" portion of Attachment A for affected sensor.
Attachment A, Channel III - RED. LT-428, Pressurizer Level (Page 15), Remove from Service ATC
- 1. PLACE charging pump speed control in MANUAL and ADJUST as necessary to MAINTAIN desired charging flow.
- 3. In cabinet C-110, PLACE Pressurizer Level defeat switch L/428A to Defeat 3 (428 CH III)
- 4. Unless directed otherwise by the Shift Manager, PLACE the charging pump speed control in AUTO, as follows:
a) PLACE one of operating P-2A, B, OR C Charging Pump Speed Controllers, HC-428A, B, OR C, in Manual-Balance.
b) In cabinet C-110, ADJUST LC-428F Charging Pump Speed Controller in MANUAL, to Null-Out selected HC-428A, B, OR C.
Page 9 of 58 Op. Test No.: Feb 2023 Scenario No.: __4__
Event No.: __3__
Event
Description:
Pressurizer Level Channel 2 (Controlling) fails low Symptoms/Cues: Various annunciators, LT-428 (Blue) indicates downscale, letdown isolates, Pzr Heaters cutoff, raises charging flow Time Position Applicants Actions or Behavior ATC c) After HC-428A, B, OR C has been Nulled-Out, Then PERFORM the following:
PLACE selected Charging Pump Speed Controller, HC-428A, B, OR C, in AUTO PLACE LC-428F, Charging Pump Speed Controller, in AUTO.
- 5. RESET and ENERGIZE Pressurizer heaters as necessary to maintain RCS pressure on program.
- 6. In cabinet C-116, PLACE bistable trip switch listed below in the TRIP position (toggle switch up) and CHECK expected response.
- 7. Remove from scan PPCS point ID LT428, PZR LVL 3 BLU
- 8. Remaining steps in Attachment A are for return to service and N/A Section 5.1, Removing Sensor From Service SRO 5.1.7. INFORM Shift Manager the affected channel has been removed from service and bypassed per 0-SOP-IC-001 SRO 5.1.8. INFORM STA the affected channel has been removed from service AOP-24, RESPONSE TO INSTRUMENT MALFUNCTIONS SRO Step 7 is N/A SRO
- 8. Check Failure For Technical Specification Or TRM Applicability SRO NOTE: May use 0-SOP-IC-002 to cross reference Technical Specifications
Page 10 of 58 Op. Test No.: Feb 2023 Scenario No.: __4__
Event No.: __3__
Event
Description:
Pressurizer Level Channel 2 (Controlling) fails low Symptoms/Cues: Various annunciators, LT-428 (Blue) indicates downscale, letdown isolates, Pzr Heaters cutoff, raises charging flow Time Position Applicants Actions or Behavior SRO Table 3.3.1-1 item 8 Pressurizer Water Level-High Action K K.1 Place channel in trip. (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ) OR K.2 Reduce THER M AL POWER to < P-7. (7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />)
Table 3.3.3-1 item 14 Pressurizer Level (2 Per SG)
Action D D.1 Place channel in trip. (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />)
OR D.2 Be in MODE 3. (7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />)
SRO Directs entry into AOP-1D, CVCS Malfunction, to restore Letdown.
AOP-1D, CVCS MALFUNCTION SRO, ATC
- 2. Determine CVCS Malfunction:
2.1. If Inadvertent Letdown Isolation Occurred - THEN go to Step 48 SRO, ATC
- 48. Check Letdown, INADVERTANTLY ISOLATED ATC
- 49. Reduce Charging to - MINIMUM This step should already have been performed during transient mitigation strategy of AOP-24.
- 50. Check that Letdown Restoration Can Be Performed ATC
- 52. Ensure Normal Charging - IN SERVICE ATC
- 53. Check PZR Level - Greater Than 20%
Page 11 of 58 Op. Test No.: Feb 2023 Scenario No.: __4__
Event No.: __3__
Event
Description:
Pressurizer Level Channel 2 (Controlling) fails low Symptoms/Cues: Various annunciators, LT-428 (Blue) indicates downscale, letdown isolates, Pzr Heaters cutoff, raises charging flow Time Position Applicants Actions or Behavior ATC
- 54. Establish Letdown:
- a. Open Letdown Line Containment Isolation valves 1CV-371A 1CV-371
- b. Open RC Loop B Cold Leg Letdown Isolation valve 1RC-427
- c. Ensure component cooling flow to Non regen Heat Exchanger - ESTABLISHED 1HC-130 d.
- d. Ensure charging flow - AT LEAST 20 GPM
- e. Adjust back pressure and open Letdown Orifice Outlet valves - ESTABLISH DESIRED LETDOWN FLOW 1CV-200A 1CV-200B 1CV-200C ATC
- 55. Check PZR Level - At Program Level SRO
- 56. Notify Duty Station Manager SRO
- 57. Return to Procedure and Step in Effect.
Event Termination When the affected channel is removed from service, letdown restored, and Tech Specs have been addressed or at the discretion of the lead examiner.
Page 12 of 58 Op. Test No.: Feb 2023 Scenario No.: __4__
Event No.: __4__
Event
Description:
Trip of Running EHC Pump, Standby Pump Fails to Start Symptoms/Cues: Various annunciators, Loss of running amps on EHC pump. No amps or breaker closure indications on the standby EHC pump.
Time Position Applicants Actions or Behavior ARP 1C03 1F 1-11, EH SUPPLY SYSTEM UNIT 1 SRO, BOP
- 3. Operator Actions:
3.1 For an EH Pump(s) trip perform the following:
3.1.1 Ensure one EH Pump is running.
Crew will diagnose plant conditions to determine the standby pump did NOT start and START the IP-076 EH Pump.
Booth: If dispatched to perform pre or post running checks on the standby EHC pump (1P-076), acknowledge request and after 1 minute report checks sat.
3.1.2 Check EH Pressure being maintained in normal the normal band.
Event Termination When the standby EHC pump has been started or at the discretion of the lead examiner.
Page 13 of 58 Op. Test No.: Feb 2023 Scenario No.: __4__
Event No.: __5__
Event
Description:
B SG Tube Leak (~30 gpm) IAW AOP 3, Rapid Downpower to <50%
Power IAW AOP 17A Symptoms/Cues: Various annunciators, lowering Reactor pressure and Pressurizer level, rising level in B SG.
Time Position Applicants Actions or Behavior AOP-1A, REACTOR COOLANT LEAK CREW Crew observes lowering reactor pressure, lowering pressurizer level.
SRO Directs RO to either perform the actions of AOP-1A, Reactor Coolant Leak, or immediate actions of 1-E-0, Reactor Trip or Safety Injection.
- 1. Check Safety Injection Not Required:
PZR level - WITHIN 10% OF PROGRAM LEVEL RCS Subcooling - GREATER THAN 30°F SRO, ATC
- 2. Check Reactor Trip Not Required:
- a. Check Reactor - CRITICAL
- 3. Check PZR Level - STABLE AT OR TRENDING TO PROGRAM LEVEL.
RNO:
IF PZR Level trending lower, THEN Perform the following:
- a. Control charging flow from running charging pumps.
- b. IF PZR level continues to lower, THEN isolate letdown.
- c. Start Non-running charging pump and inform Shift Manager.
- 5. Check Reactor Makeup Control:
Makeup Set at proper boric acid concentration Makeup armed and in auto SRO
- 6. Notify DSM and Implement Emergency Plan Booth: Acknowledge report if called.
Page 14 of 58 Op. Test No.: Feb 2023 Scenario No.: __4__
Event No.: __5__
Event
Description:
B SG Tube Leak (~30 gpm) IAW AOP 3, Rapid Downpower to <50%
Power IAW AOP 17A Symptoms/Cues: Various annunciators, lowering Reactor pressure and Pressurizer level, rising level in B SG.
Time Position Applicants Actions or Behavior SRO, ATC
- 7. Check Steam Generator Tubes - INTACT
- a. Secondary RMS Indication - STABLE Condenser Air ejector:
1RE-215 1RE-225 Steam generator blowdown:
1RE-219 1RE-222 Main Steam Line:
1RE-231 1RE-232
- b. Steam generator chemistry samples - NORMAL Boric Acid Abnormal Activity
- c. Main steam line radiation survey - NORMAL
- d. S/G levels - NORMAL for EXISING STEAM FLOW AND FEED FLOW RNO:
Go to AOP-3, Unit 1, Steam Generator Tube Leak.
Booth: If asked for chemistry samples or surveys, acknowledge request.
AOP-3, Steam Generator Tube Leak SRO, ATC
- 1. Check PZR Level - STABLE AT OR TRENDING TO PROGRAM LEVEL.
RNO:
IF PZR Level trending lower, THEN Perform the following:
- a. Control charging flow from running charging pumps.
- b. IF PZR level continues to lower, THEN isolate letdown.
- c. Start Non-running charging pump and inform Shift Manager.
- 2. Check if VCT Level can be maintained:
- 3. Notify DSM, Chemistry, and Implement Emergency Plan Booth: Acknowledge reports as necessary.
Page 15 of 58 Op. Test No.: Feb 2023 Scenario No.: __4__
Event No.: __5__
Event
Description:
B SG Tube Leak (~30 gpm) IAW AOP 3, Rapid Downpower to <50%
Power IAW AOP 17A Symptoms/Cues: Various annunciators, lowering Reactor pressure and Pressurizer level, rising level in B SG.
Time Position Applicants Actions or Behavior SRO, ATC
- 4. Identify Affected S/G High radiation from any S/G steam Line 1RE-231 1RE-232 OR High radiation from any S/G Sampel or Local Surveys by RP OR Abnormal S/G sample results Boric Acid Activity pH OR Unexpected rise in any S/G narrow range level OR Unexpected S/G level deviation alarms OR High radiation from any S/G blowdown line 1RE-219 Isolate S/G sample valves one at a time and check blowdown activity for trends 1MS-2083 for A S/G 1MS-2084 for B S/G Crew identifies S/G B SRO, ATC
- 5. Determine Leak Rate:
Direct Chemistry to perform CAMP 014, STEAM GENERAROT TUBE LEAK RATE CALCULATION Estimate Leak rate based on RCS Mass Balance OI 55, Primary Leak Rate Calculation SRO, ATC Note: Primary to secondary leakage in excess of 72 GPD in either steam generator violates TS 3.4.13, RCS Operational leakage.
- 6. Check if Plant Should be Shut Down
- a. Confirmed leakage - Greater than or equal to 36 GPD.
RNO - Go to NP 3.2.4, Primary to secondary leak rate monitoring program.
Page 16 of 58 Op. Test No.: Feb 2023 Scenario No.: __4__
Event No.: __5__
Event
Description:
B SG Tube Leak (~30 gpm) IAW AOP 3, Rapid Downpower to <50%
Power IAW AOP 17A Symptoms/Cues: Various annunciators, lowering Reactor pressure and Pressurizer level, rising level in B SG.
Time Position Applicants Actions or Behavior SRO, ATC Caution - Action response time clock starts when the first RMS monitor indicates a tube leak has developed.
- 7. Determine action response based on S/G Leakage:
Crew identifies requirement to reduce power to less than or equal to 50% in one hour AND be in Mode 3 in next two hours.
- 8. Place Unit in MODE 3 OP-3A Unit 1, POWER OPERATION TO HOT SHUTDOWN OR AOP-17A, RAPID POWER REDUCTION Booth: If Senior Ops Management is called on preference of shutdown method, direct entry into AOP-17A.
Page 17 of 58 Op. Test No.: Feb 2023 Scenario No.: __4__
Event No.: __5__
Event
Description:
B SG Tube Leak (~30 gpm) IAW AOP 3, Rapid Downpower to <50%
Power IAW AOP 17A Symptoms/Cues: Various annunciators, lowering Reactor pressure and Pressurizer level, rising level in B SG.
Time Position Applicants Actions or Behavior AOP-17A, Rapid Power Reduction SRO, ATC
- 1. Check Power -GREATER THAN 100%.
1N-41B, Power Range Channel 1N-42B, Power Range Channel 1N-43B, Power Range Channel 1N-44B, Power Range Channel RNO: Go to Step 3 SRO
- 3. Determine Desired Power Level or Condition to be Met Control Room Supervisor announce desired power level or condition using less than or equal to 3%/min ramp rate.
- 4. Commence Boration as Necessary to Target Load
- a. Set boric acid flow totalizer to desired quantity 1YIC-110
- b. Set boric acid flow controller to desired flow rate 1HC-110
- c. If desired, Start second boric acid transfer pump
- d. Place Reactor Makeup Mode Selector Switch to Borate
- e. Place Reactor Makeup Control Switch to Start SRO, BOP NOTES Effects on temperature from boric acid injection should be seen prior to commencing turbine load reduction.
Turbine load should be monitored closely when shifting from "First Stage Out" to "First Stage In". If turbine load goes up, adjustments using step 5 to return the turbine to its initial load is appropriate.
Fold out page shall be monitored through the remainder of this procedure.
Page 18 of 58 Op. Test No.: Feb 2023 Scenario No.: __4__
Event No.: __5__
Event
Description:
B SG Tube Leak (~30 gpm) IAW AOP 3, Rapid Downpower to <50%
Power IAW AOP 17A Symptoms/Cues: Various annunciators, lowering Reactor pressure and Pressurizer level, rising level in B SG.
Time Position Applicants Actions or Behavior SRO, BOP
- 5. Select Turbine RateAnd Reduce Load:
Operator Automatic Load Rate Control
- a. Ensure EH controls are set for Operator Autob.
- b. Ensure "First Stage In" is selected.
- c. IF first stage pressure is unavailable, THEN select "First Stage Out".
- d. Ensure the appropriate load rate is selected on load rate thumb-wheel1%/min (position 1)2%/min (position 2)3%/min (position 3)
- e. Select target end-point on reference control
- f. WHEN temperature reduction of at least 0.5ºF is observed on Tavg-Tref indicator, THEN depress "GO" push-button.
- g. Continue with next step.
- 6. Notify Power System Supervisor (PSS) of Load Reduction.
Booth: Acknowledge report when called.
- 7. Check Rod Control System - IN AUTO RNO - Perform one of the following:
IF Manual rod control desired due to existing plant conditions, THEN operate control rods in manual to -
MAINTAIN TAVG WITHIN 5°F of TREF OR Place rod control system in - AUTO Rods may still be in Manual from prior event.
- 10. Check PZR Level - Controlling in Auto RNO - Control charging and letdown flows to maintain pressurizer level - WITHIN 10% of PROGRAM LEVEL SRO, BOP
- 11. Check Steam Generator Level - Controlling in Auto SRO, BOP
- 12. Ensure Main Feed Pump Seal Water Pump - Running 1P-99A 1P-99B
Page 19 of 58 Op. Test No.: Feb 2023 Scenario No.: __4__
Event No.: __5__
Event
Description:
B SG Tube Leak (~30 gpm) IAW AOP 3, Rapid Downpower to <50%
Power IAW AOP 17A Symptoms/Cues: Various annunciators, lowering Reactor pressure and Pressurizer level, rising level in B SG.
Time Position Applicants Actions or Behavior SRO, ATC
- 13. Maintain RCS Tavg:
Greater than 540°F Less than 577°F Within 7°F of program Tavg SRO, ATC
- 17. Establish One Train of feed and Condensate:
- a. When feed flow is less than 2.4E+6 lbm/hr per S/G, THEN Secure all but one main feed pump o 1P-28A o 1P-28B Secure all but one condensate pump o 1P-25A o 1P-25B SRO, BOP
- 18. Check Turbine Load - Less than 50%
Check Operability of P-9 interlock SRO SRO Tech Specs:
TS 3.4.13, RCS Operational leakage Condition B: Primary to secondary leakage not within limit:
Be in Mode 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> AND Be in Mode 5 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> Event Termination When a ramp of >10% has been completed or at the discretion of the lead examiner.
Page 20 of 58 Op. Test No.: Feb 2023 Scenario No.: __4__
Event No.: __6 & 7__
Event
Description:
B SGTR - E0 - E3 Symptoms/Cues: Various annunciators, rapidly lowering Reactor pressure and Pressurizer level, rising level in B SG.
Time Position Applicants Actions or Behavior EOP-0, REACTOR TRIP OR SAFETY INJECTION NOTE: EOP-0 Steps 1-4 are IMMEDIATE OPERATOR ACTIONS SRO, ATC
- 1. Verify Reactor Trip Reactor trip and bypass breakers - OPEN All rod position indicators - LESS THAN 20 STEPS All rod bottom lights - LIT Neutron flux - LOWERING SRO, BOP
- 2. Verify Turbine Trip
- 3. Verify Power to AC safeguards busses:
- a. Check safeguards busses - At least one TRAIN ENERGIZED (Train A and Train B)
- 4. Check if SI Is Actuated:
- a. Any SI annunciators - LIT
- 5. Perform Attachment A, Automatic Action Verification, while continuing with this procedure.
EOP Attachment A actions start on Page 45.
- 6. Verify AFW Pumps - RUNNING
- a. Motor-Driven Pump - RUNNING
- b. Turbine-driven Pump - RUNNING
- 7. Check RCP Seal Cooling:
Component cooling flow to RCP thermal barriers - NORMAL
Page 21 of 58 Op. Test No.: Feb 2023 Scenario No.: __4__
Event No.: __6 & 7__
Event
Description:
B SGTR - E0 - E3 Symptoms/Cues: Various annunciators, rapidly lowering Reactor pressure and Pressurizer level, rising level in B SG.
Time Position Applicants Actions or Behavior SRO, ATC
- 8. Check RCS temperatures:
- a. Condenser Steam Dumps - AVAILABLE Place Steam Dump Mode Selector Switch in MANUAL
o RCS average temperature - STABLE AT OR TRENDING TO 547°F RNO - Perform the following:
- 1. IF temperature is less than 547°F AND lowering, THEN perform the following:
- a. Stop dumping steam
- b. IF cooldown continues, THEN control total feed flow:
Maintain total feed flow greater than or equal to 275 gpm until level is greater than [52%] 33% in at least one S/G.
- c. IF cooldown continues, THEN isolate main steam lines:
- a. Shut both main steam isolation valves:
1MS-2018 1MS-2017
- b.
Ensure both main steam isolation bypass valves are shut:
1MS-234 1MS-236
- 2. IF RCS Temperature is GREATER THAN 547°F AND Rising THEN:
o DUMP steam to condenser o DUMP steam using ADVs SRO, ATC
- 9. Check PZR PORVs and Spray Valves:
- c. Auxiliary spray valve - SHUT o 1CV-296
Page 22 of 58 Op. Test No.: Feb 2023 Scenario No.: __4__
Event No.: __6 & 7__
Event
Description:
B SGTR - E0 - E3 Symptoms/Cues: Various annunciators, rapidly lowering Reactor pressure and Pressurizer level, rising level in B SG.
Time Position Applicants Actions or Behavior SRO, ATC
- 10. Check if RCPs Should Be Stopped:
- a. RCPs - ANY RUNNING
- b. SI pumps - AT LEAST ONE RUNNING AND CAPABLE OF DELIVERING FLOW
- c. RCS subcooling based on core exit thermocouples - LESS THAN [40°F] 31°F RNO - Go to Step 11 SRO, ATC
- 11. Check if S/G Are NOT Faulted:
- a. Check pressures in both S/Gs:
No S/G pressure lowering in an uncontrolled manner No S/G completely depressurized SRO, ATC
- 12. Check if S/G Tubes are NOT Ruptured:
S/G levels - NOT RISING IN AN UNCONTROLLED MANNER Secondary system radiation monitor levels - NORMAL Condenser air ejector:
o 1RE-215 o RE-225 S/G Blowdown o 1RE-219 o 1RE-222 Main Steam Line o 1RE-231 for S/G A o 1RE-232 for S/G B SRO directs entry into EOP-3, Unit 1, Steam Generator Tube Rupture for B SG
Page 23 of 58 Op. Test No.: Feb 2023 Scenario No.: __4__
Event No.: __6 & 7__
Event
Description:
B SGTR - E0 - E3 Symptoms/Cues: Various annunciators, rapidly lowering Reactor pressure and Pressurizer level, rising level in B SG.
Time Position Applicants Actions or Behavior SRO, ATC EOP-3, Unit 1 SGTR NOTES
- Chemistry should be available for sampling during this procedure.
- Foldout page shall be monitored throughout this procedure.
- 1. Check if RCPs Should Be Stopped:
- a. RCS subcooling based on core exit thermocouples - LESS THAN
[40°F] 31°F
- a. Go to Step 2.
- b. RCPs - ANY RUNNING
- b. Go to Step 2.
- c. SI pumps - AT LEAST ONE RUNNING AND CAPABLE OF DELIVERING FLOW
- c. Go to Step 2.
- 2. Identify Ruptured S/G(s):
o Unexpected rise in any S/G level o High radiation from any S/G steam line:
- 1RE-231 for S/G A
- 1RE-232 for S/G B o High radiation from any S/G sample or survey:
- Request Chemistry to sample both S/Gs for activity
- Request local surveys of main steamlines Booth: If requested, acknowledge request for Chemistry sampling and RP surveys.
Continue with Steps 7 through 13, WHEN ruptured S/G(s) are identified, THEN OBSERVE CAUTIONS PRIOR TO STEP 3, do Step 3 through Step 6.
Page 24 of 58 Op. Test No.: Feb 2023 Scenario No.: __4__
Event No.: __6 & 7__
Event
Description:
B SGTR - E0 - E3 Symptoms/Cues: Various annunciators, rapidly lowering Reactor pressure and Pressurizer level, rising level in B SG.
Time Position Applicants Actions or Behavior SRO, ATC SRO, ATC CAUTIONS
- If the turbine driven AFW pump is the only available source of feed flow, steam supply to turbine driven AFW pump must be maintained from one S/G.
- One S/G must be maintained available for RCS cooldown.
- 3. Isolate Flow From Ruptured S/G(s):
- a. IF S/G A is ruptured, THEN isolate S/G A:
- 1) 1HC-468 "A" ADV Controller - SET TO 1050 psig
- 2) Ensure 1MS-2016 -
SHUT
- 3) Shut 1MS-2020, TDAFWP Steam Supply.
- 4) Ensure S/G blowdown is isolated:
o 1MS-5958 - SHUT o 1MS-2042 - SHUT
- a. IF S/G B is ruptured, THEN go to step 3.b
- 2) WHEN S/G pressure is less than 1050 psig, THEN verify 1MS-2016 is shut. IF 1MS-2016 will not shut, THEN:
o Place 1HC-468 to manual and shut 1MS-2016 o Locally shut 1MS-227 to isolate 1MS-2016
- 3) Verify 1MS-235 is shut. IF 1MS-235 cannot be shut AND 1P-53 is running, THEN secure 1P-29, TDAFW pump.
- 5) Perform the following:
- Locally isolate steam header using ATTACHMENT D while continuing with this procedure.
- Use intact ADV as steam release path
Page 25 of 58 Op. Test No.: Feb 2023 Scenario No.: __4__
Event No.: __6 & 7__
Event
Description:
B SGTR - E0 - E3 Symptoms/Cues: Various annunciators, rapidly lowering Reactor pressure and Pressurizer level, rising level in B SG.
Time Position Applicants Actions or Behavior SRO, ATC
- CT*
(Step 3.a Continued)
- 6) Locally shut the following:
- 1MS-235, P-29 AFP
/Radwaste Isolation
- 1MS-228 Main Steam Trap Isolation
- 7) Check S/G A - ISOLATED
- 7) IF ruptured S/G can NOT be isolated from intact or faulted S/G, THEN go to ECA-3.1 UNIT 1, SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY
- b. IF S/G B is ruptured, THEN isolate S/G B:
- 1) Set 1HC-478 "B" ADV Controller - TO 1050 psig
- 2) Ensure 1MS-2015 - SHUT
- 3) Shut 1MS-2019, TDAFWP Steam Supply.
- 4) Ensure S/G blowdown is isolated:
o 1MS-5959 - SHUT o 1MS-2045 - SHUT
- b. IF S/G A is ruptured, THEN go to step 3.a
IF 1MS-2015 will not shut, THEN:
o Place 1HC-478 to manual and shut 1MS-2015 o Locally shut 1MS-244 to isolate 1MS-2015
- 3) Verify 1MS-237 is shut.
IF 1MS-237 cannot be shut AND 1P-53 is running, THEN secure 1P-29, TDAFW pump.
Page 26 of 58 Op. Test No.: Feb 2023 Scenario No.: __4__
Event No.: __6 & 7__
Event
Description:
B SGTR - E0 - E3 Symptoms/Cues: Various annunciators, rapidly lowering Reactor pressure and Pressurizer level, rising level in B SG.
Time Position Applicants Actions or Behavior SRO, ATC
- CT*
Step 3b continued:
- 6) Locally shut the following:
- 1MS-237, P-29/Radwaste Isolation
- 1MS-238 Main Steam Trap Isolation
- 7) Check B SG - ISOLATED
- 5) Perform the following:
- Locally isolate steam header using ATTACHMENT D while continuing with this procedure.
- Use intact ADV as steam release path
- 7) IF ruptured S/G can NOT be isolated from intact or faulted S/G, THEN go to ECA-3.1 UNIT 1, SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED.
Step 3b is a Critical Task:
- CT-1: Isolate B SG (Steam from & Feed Flow to)
Page 27 of 58 Op. Test No.: Feb 2023 Scenario No.: __4__
Event No.: __6 & 7__
Event
Description:
B SGTR - E0 - E3 Symptoms/Cues: Various annunciators, rapidly lowering Reactor pressure and Pressurizer level, rising level in B SG.
Time Position Applicants Actions or Behavior SRO, ATC CAUTION If any ruptured S/G is faulted, feed flow to that S/G should remain isolated during subsequent recovery actions unless needed for RCS cooldown.
- 4. Check Ruptured S/G(s) Level:
- a. Level - GREATER THAN
[52%] 33%
- a. Maintain feed flow to ruptured S/Gs until level is greater than
[52%] 33%.
WHEN ruptured S/G level is greater than [52%] 33%, THEN do step 4.b.
Continue with Step 5.
Page 28 of 58 Op. Test No.: Feb 2023 Scenario No.: __4__
Event No.: __6 & 7__
Event
Description:
B SGTR - E0 - E3 Symptoms/Cues: Various annunciators, rapidly lowering Reactor pressure and Pressurizer level, rising level in B SG.
Time Position Applicants Actions or Behavior SRO, ATC
- CT*
(Step 4 Continued)
- b. IF S/G A is ruptured, THEN Stop feed flow to S/G A:
- b. IF S/G B is ruptured, THEN go to Step 4.c.
- 1) Locally isolate 1P-53 flow to S/G A
- 2) Ensure 1AF-4001 TDAFWP flow control valve - SHUT
- 2) Locally isolate 1P-29 flow to S/G A:
- 3) Ensure AF-4023, SSG supply valve - SHUT
- 3) Locally isolate P-38 flow to S/G A:
- c. IF S/G B is ruptured, THEN Stop feed flow to S/G B:
- c. IF S/G A is ruptured, THEN go to Step 4.b.
- 1) Locally isolate 1P-53 flow to S/G B
- 2) Locally isolate 1P-29 flow to S/G B:
- 3) Ensure AF-4021, SSG supply valve - SHUT
- 3) Locally isolate P-38B flow to S/G B:
- 1AF-44 Step 4.c is a Critical Task:
- CT-1: Isolate B SG (Steam from & Feed Flow to)
Page 29 of 58 Op. Test No.: Feb 2023 Scenario No.: __4__
Event No.: __6 & 7__
Event
Description:
B SGTR - E0 - E3 Symptoms/Cues: Various annunciators, rapidly lowering Reactor pressure and Pressurizer level, rising level in B SG.
Time Position Applicants Actions or Behavior SRO, ATC
- 5. Check Ruptured S/G(s)
Pressure - GREATER THAN 590 psig Go to ECA-3.1 UNIT 1, SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED.
- Major steam flow paths from the ruptured S/G(s) should be isolated and S/G Level shall be greater than [52%] 33% before initiating RCS cooldown.
- If RCPs are NOT running, the following steps may cause a false Integrity Status Tree Indication for the ruptured loop. Disregard the ruptured loop T-cold indication until after performing Step 29.
NOTES
- RCS cooldown should proceed as quickly as possible after SI reset and should not be limited by the 100°F/hr Technical Specification SRO, ATC 6 Initiate RCS Cooldown:
- a. Check SI signal status:
- 1) ANY Auto SI signal - IN
- 1) IF Pressurizer Pressure is less than 1900 psig, THEN Block SI.
IF Pressurizer Pressure is greater than 1900 psig OR SI can NOT be blocked, THEN lock in SI signal as follows:
a) Manually actuate SI and Containment Isolation.
b) Trip all SI bistables:
- 2) Reset SI
Page 30 of 58 Op. Test No.: Feb 2023 Scenario No.: __4__
Event No.: __6 & 7__
Event
Description:
B SGTR - E0 - E3 Symptoms/Cues: Various annunciators, rapidly lowering Reactor pressure and Pressurizer level, rising level in B SG.
Time Position Applicants Actions or Behavior SRO, ATC NOTE For step 6.b, ATTACHMENT G may be detached and used
- b. Determine required core exit temperature:
Ruptured S/G Pressure (psig)
Required Core Exit Temperature for Depressurization
(°F)
Stabilization Pressure/
Temperature ADV/CSD Setpoint (temp)
GREATER THAN OR EQUAL TO 1100 515 580 psig (485F) 1000 TO 1099 500 500 psig (470F) 900 TO 999 490 450 psig (460F) 800 TO 899 475 390 psig (445F) 700 TO 799 460 330 psig (430F) 600 TO 699 440 260 psig (410F)
LESS THAN 600 430 230 psig (400F)
- CT*
(Step 6 continued)
- c. Dump steam to condenser from intact S/Gs at maximum rate:
- 1) Place Steam Dump Mode Selector switch in Manual
- 2) Set Condenser Steam Dump Controller to stabilization pressure from step 6.b:
- 3) IF 1HC-484 is not responding in AUTO, THEN:
a) Place 1HC-484 to manual b) Fully open all Condenser steam dumps c) Stabilize RCS Temperature at Stabilization temperature from Step 6.b.
- c. Manually or locally dump steam at maximum rate from intact S/G:
a) Set atmospheric steam dump controller to stabilization pressure from step 6.b:
o 1MS-2016 for S/G A (1HC-468) o 1MS-2015 for S/G B (1HC-478) b) IF Atmospheric Steam Dump is not controlling in Automatic, THEN
- 1) Place Intact SG ADV Controller to Manual.
- 2) Fully Open Intact SG ADV.
- 3) Stabilize RCS temperature at Stabilization temperature from step 6.b.
c) IF Atmospheric Steam Dump is NOT available, THEN dump steam using alternate means:
- 1) Place 1HC-484 to manual
- 2) Place Steam Dump Mode Selector switch in Manual
- 4) Direct plant personnel to stay clear of LP turbine rupture disks.
- 5) Open MSIV bypass valve:
o 1MS-234 for S/G A o 1MS-236 for S/G B
- 6) Fully open all condenser steam dumps.
IF NO intact S/G is available, THEN perform the following:
o Use faulted S/G.
OR o Go to ECA-3.1 UNIT 1, SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED.
Crew will be required to use Atmospheric Steam Dumps.
Step 6.c is a Critical Task:
CT2: Control Initial RCS Cooldown
Page 32 of 58 Op. Test No.: Feb 2023 Scenario No.: __4__
Event No.: __6 & 7__
Event
Description:
B SGTR - E0 - E3 Symptoms/Cues: Various annunciators, rapidly lowering Reactor pressure and Pressurizer level, rising level in B SG.
Time Position Applicants Actions or Behavior SRO, ATC 7 Check Intact S/G Level:
- a. S/G Level - GREATER THAN [52%] 33%
- a. Maintain total feed flow greater than or equal to 275 gpm until level is greater than [52%] 33% in at least one S/G.
- b. Control feed flow to maintain S/G level between
[52%] 36% and 63%
- b. IF level in intact S/G continues to rise in an uncontrolled manner, THEN perform the following:
- 1) Stop RCS cooldown.
- 2) OBSERVE NOTES PRIOR TO STEP 1 and return to Step 1.
SRO, ATC CAUTION If any PZR PORV opens because of high PZR pressure, Step 8.b should be repeated after pressure lowers to less than 2335 psig.
Page 33 of 58 Op. Test No.: Feb 2023 Scenario No.: __4__
Event No.: __6 & 7__
Event
Description:
B SGTR - E0 - E3 Symptoms/Cues: Various annunciators, rapidly lowering Reactor pressure and Pressurizer level, rising level in B SG.
Time Position Applicants Actions or Behavior SRO, ATC 8 Check PZR PORVs And Block Valves:
- a. Power to PORV block valves - AVAILABLE
- a. Restore power to block valves.
- b. PORVs - BOTH SHUT
- b. IF PZR pressure is less than 2335 psig, THEN manually shut PORVs.
IF any PORV can NOT be shut, THEN manually shut its block valve:
o 1RC-515 for 1RC-431C o 1RC-516 for 1RC-430 IF its block valve can NOT be shut, THEN go to ECA-3.1 UNIT 1, SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED.
- c. Open one block valve unless it was shut to isolate an open PORV.
Page 34 of 58 Op. Test No.: Feb 2023 Scenario No.: __4__
Event No.: __6 & 7__
Event
Description:
B SGTR - E0 - E3 Symptoms/Cues: Various annunciators, rapidly lowering Reactor pressure and Pressurizer level, rising level in B SG.
Time Position Applicants Actions or Behavior SRO, ATC 9 Check SI Signal Status:
- a. Check SI Signal Status -
PREVIOUSLY BLOCKED OR RESET
- a. Perform the following:
- 2) IF no auto SI signal is in, THEN perform the following:
a) IF Pressurizer Pressure is less than 1900 psig, THEN Block SI.
b) IF Pressurizer Pressure is greater than 1900 psig OR SI can NOT be blocked, THEN lock in SI signal as follows:
- 1) Manually actuate SI and Containment Isolation.
- 2) Trip all SI bistables:
- Containment Isolation
Page 35 of 58 Op. Test No.: Feb 2023 Scenario No.: __4__
Event No.: __6 & 7__
Event
Description:
B SGTR - E0 - E3 Symptoms/Cues: Various annunciators, rapidly lowering Reactor pressure and Pressurizer level, rising level in B SG.
Time Position Applicants Actions or Behavior SRO, ATC 11 Establish Instrument Air To Containment:
- a. Check instrument air header pressure -
GREATER THAN 80 psig
- a. Perform the following:
- 1) Start air compressors as necessary to establish instrument air header pressure greater than 80 psig.
- b. Open instrument air containment isolation valves one at a time:
- b. IF NO valve can be opened, THEN gag open one valve:
- 1) Manually hold valve switch in open position.
- 2) Locally gag open valve.
SRO, ATC CAUTION RCS pressure should be monitored. If RCS pressure lowers in an uncontrolled manner to less than [450 psig] 325 psig, the RHR pumps must be manually restarted to supply water to the RCS.
12 Check If RHR Pumps Should Be Stopped:
- a. Go to Step 13.
- b. RCS pressure - GREATER THAN [450 psig] 325 psig
- b. Go to Step 13.
- c. Stop both RHR pumps and place in auto:
Page 36 of 58 Op. Test No.: Feb 2023 Scenario No.: __4__
Event No.: __6 & 7__
Event
Description:
B SGTR - E0 - E3 Symptoms/Cues: Various annunciators, rapidly lowering Reactor pressure and Pressurizer level, rising level in B SG.
Time Position Applicants Actions or Behavior SRO, ATC 13 Establish Maximum Charging Flow:
- a. Charging pumps - AT LEAST ONE RUNNING
- a. IF component cooling water flow to any RCP thermal barrier is lost, THEN go to Step 14.
- b. Align charging pump suction to RWST:
- 1) Open RWST to charging pump suction MOV:
- 1) Locally open 1CV-112B.
- 2) Shut VCT outlet to charging pump suction MOV:
- 2) Locally shut 1CV-112C.
- CT*
14 Check If RCS Cooldown Should Be Stopped:
- a. Core exit thermocouple temperatures - LESS THAN REQUIRED TEMPERATURE FOR DEPRESSURIZATION FROM STEP 6.b.
- a. Do NOT continue until core exit thermocouple temperatures are less than required temperature for depressurization.
- b. Check CSD OR ADV -
CONTROLLING IN AUTOMATIC
- b. Perform the following:
- 1) WHEN core exit thermocouple temperatures - LESS THAN STABILIZATION TEMPERATURE THEN STABILIZE AT STABILIZATION TEMPERATURE.
Step 14 is a Critical task:
CT2: Control Initial RCS Cooldown
Page 37 of 58 Op. Test No.: Feb 2023 Scenario No.: __4__
Event No.: __6 & 7__
Event
Description:
B SGTR - E0 - E3 Symptoms/Cues: Various annunciators, rapidly lowering Reactor pressure and Pressurizer level, rising level in B SG.
Time Position Applicants Actions or Behavior SRO, ATC 15 Check Ruptured S/G(s)
Pressure - STABLE OR RISING IF pressure continues to lower to less than 250 psid above the pressure of the S/G used for cooldown, THEN go to ECA-3.1 UNIT 1, SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED SRO, ATC 16 Check RCS Subcooling Based On Core Exit Thermocouples -
GREATER THAN [82°F]
57°F Go to ECA-3.1 UNIT 1, SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED.
SRO, ATC NOTE For step 17, ATTACHMENT F may be used if desired
Page 38 of 58 Op. Test No.: Feb 2023 Scenario No.: __4__
Event No.: __6 & 7__
Event
Description:
B SGTR - E0 - E3 Symptoms/Cues: Various annunciators, rapidly lowering Reactor pressure and Pressurizer level, rising level in B SG.
Time Position Applicants Actions or Behavior SRO, ATC
- CT*
17 Depressurize RCS To Minimize Break Flow And Refill PZR:
- a. Normal PZR spray -
AVAILABLE
- a. OBSERVE CAUTIONS AND NOTE PRIOR TO STEP 18 and go to Step 18.
- b. Spray PZR with maximum available spray until any of the following conditions satisfied:
o Both of the following:
- 1) RCS PRESSURE - LESS THAN RUPTURED S/G PRESSURE
- 2) PZR level - GREATER THAN [26%] 11%
OR o Both of the following:
- 1) RCS pressure - WITHIN 300 psid OF RUPTURED S/G PRESSURE
- 2) Pzr level greater than
[50%]41%
OR o PZR level - GREATER THAN
[71%] 72%
OR o RCS subcooling based on core exit thermocouples -
LESS THAN [62°F] 37°F
- b. IF normal spray is NOT effective, THEN OBSERVE CAUTIONS AND NOTE PRIOR TO STEP 18 and go to Step 18.
Page 39 of 58 Op. Test No.: Feb 2023 Scenario No.: __4__
Event No.: __6 & 7__
Event
Description:
B SGTR - E0 - E3 Symptoms/Cues: Various annunciators, rapidly lowering Reactor pressure and Pressurizer level, rising level in B SG.
Time Position Applicants Actions or Behavior SRO, ATC Step 17, Continued:
- c. Shut spray valves:
- 1) Normal spray valves:
- 1) Stop spray flow: a) Place manual override switch to close for failed spray valve(s).
o 1RC-431A-S for 1RC-431A o 1RC-431B-S for 1RC-431B b) IF any spray valve can NOT be shut using manual override, THEN stop RCP(s) as necessary to stop spray flow:
o For 1RC-431A-S, stop RCP A
o For 1RC-431B-S, stop RCP B
- d. OBSERVE CAUTION PRIOR TO STEP 20 and go to Step 20.
Step 17 is a Critical Task:
CT3: Depressurize RCS to meet SI Termination Criteria SRO, ATC NOTES
- The upper head region may void during RCS depressurization if RCPs are NOT running. This will result in a rapidly rising PZR level.
- For step 18, ATTACHMENT F may be used if desired.
Page 40 of 58 Op. Test No.: Feb 2023 Scenario No.: __4__
Event No.: __6 & 7__
Event
Description:
B SGTR - E0 - E3 Symptoms/Cues: Various annunciators, rapidly lowering Reactor pressure and Pressurizer level, rising level in B SG.
Time Position Applicants Actions or Behavior SRO, ATC 18 Depressurize RCS Using PZR PORV To Minimize Break Flow And Refill PZR:
- a. At least one PZR PORV -
AVAILABLE
- a. Go to Step 19
- b. Open one PZR PORV until any of the following conditions satisfied:
o Both of the following:
- 1) RCS pressure - LESS THAN RUPTURED S/G PRESSURE
- 2) PZR level - GREATER THAN [26%] 11%
OR o PZR level - GREATER THAN [71%] 72%
OR o RCS subcooling based on core exit thermocouples -
LESS THAN [62°F] 37°F
- c. Shut PZR PORV
- c. Shut associated block valve:
o 1RC-515 for 1RC-431C o 1RC-516 for 1RC-430
Page 41 of 58 Op. Test No.: Feb 2023 Scenario No.: __4__
Event No.: __6 & 7__
Event
Description:
B SGTR - E0 - E3 Symptoms/Cues: Various annunciators, rapidly lowering Reactor pressure and Pressurizer level, rising level in B SG.
Time Position Applicants Actions or Behavior SRO, ATC
- d. Check RCS Pressure -
RISING
- d. Shut associated block valve:
o 1RC-515 for 1RC-431C o 1RC-516 for 1RC-430 IF RCS pressure continues to lower, THEN perform the following:
- 1) Monitor PRT conditions for indication of leakage from the PZR PORV:
- Pressure
- Temperature
- Level
- 2) Go to ECA-3.1 UNIT 1, SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED.
Page 42 of 58 Op. Test No.: Feb 2023 Scenario No.: __4__
Event No.: __6 & 7__
Event
Description:
B SGTR - E0 - E3 Symptoms/Cues: Various annunciators, rapidly lowering Reactor pressure and Pressurizer level, rising level in B SG.
Time Position Applicants Actions or Behavior SRO, ATC 19 Depressurize RCS Using Aux Spray To Minimize Break Flow And Refill PZR:
- a. Establish auxiliary spray:
- 1) Ensure at least one charging pump is running.
- 2) Open auxiliary spray valve:
- 3) Shut RCS loop A cold leg normal charging isolation valve to establish 250 psid across 1CV-296 to force it open:
- a. Return to Step 17.b.
IF auxiliary spray can NOT be established, THEN go to ECA-3.3 UNIT 1, SGTR WITHOUT PRESSURIZER PRESSURE CONTROL.
- b. Spray PZR with maximum available spray until any of the following conditions satisfied:
o Both of the following:
- 1) RCS PRESSURE - LESS THAN RUPTURED S/G PRESSURE
- 2) PZR level - GREATER THAN
[26%] 11%
OR o Both of the following:
- 3) RCS pressure - WITHIN 300 psid OF RUPTURED S/G PRESSURE
- 4) Pzr level greater than
[50%]41%
OR o PZR level - GREATER THAN
[71%] 72%
OR o RCS subcooling based on core exit thermocouples - LESS THAN [62°F] 37°F
- b. IF auxiliary spray is NOT effective, THEN OBSERVE CAUTIONS AND NOTE PRIOR TO STEP 18 and return to Step 18.
Page 43 of 58 Op. Test No.: Feb 2023 Scenario No.: __4__
Event No.: __6 & 7__
Event
Description:
B SGTR - E0 - E3 Symptoms/Cues: Various annunciators, rapidly lowering Reactor pressure and Pressurizer level, rising level in B SG.
Time Position Applicants Actions or Behavior SRO, ATC CAUTION SI must be terminated when termination criteria are satisfied to prevent overfilling the ruptured S/G(s).
20 Check If ECCS Flow Should Be Terminated:
- a. PZR level - GREATER THAN
[26%] 11%
- a. Return to Step 5.
- b. Secondary heat sink:
o Intact S/G level - GREATER THAN [52%] 33%
OR o Total feed flow to S/Gs GREATER THAN OR EQUAL TO 275 gpm
- b. IF neither condition is satisfied, THEN go to ECA-3.1 UNIT 1, SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED.
- c. Go to ECA-3.1 UNIT 1, SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED.
- d. RCS subcooling based on core exit thermocouples - GREATER THAN [62°F] 37°F
- d. Go to ECA-3.1 UNIT 1, SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED.
SRO, ATC 21 Stop Both SI Pumps And Place In Auto:
Page 44 of 58 Op. Test No.: Feb 2023 Scenario No.: __4__
Event No.: __6 & 7__
Event
Description:
B SGTR - E0 - E3 Symptoms/Cues: Various annunciators, rapidly lowering Reactor pressure and Pressurizer level, rising level in B SG.
Time Position Applicants Actions or Behavior SRO, ATC 22 Establish Charging Flow:
- a. Ensure RCS loop A cold leg normal charging isolation valve -
OPEN
- OPEN 1CV-1298
- b. Charging pumps - AT LEAST ONE RUNNING
- b. Perform the following:
- 1) IF component cooling water flow to any RCP thermal barrier is lost, THEN locally shut affected RCP(s) seal injection throttle valve before starting charging pumps:
o 1CV 300A, RCP A o 1CV 300B, RCP B
- 2) Start charging pumps as necessary.
- c. Adjust charging pumps as necessary to maintain PZR level -
GREATER THAN OR EQUAL TO [26%] 11%
- d. RCP labyrinth seal P - GREATER THAN 20 inches.
- CT*
23 Ensure Adequate RCS Depressurization:
- a. Check normal spray -
AVAILABLE
- a. Go To Step 24.
- b. Spray PZR with maximum available spray until either of the following conditions are satisfied:
o RCS pressure - LESS THAN RUPTURED S/G PRESSURE OR o Pzr level - GREATER THAN [71%]72%.
- c. Stop RCS depressurization.
Step 23 is a Critical Task:
CT3: Depressurize RCS to meet SI Termination Criteria Event Termination When RCS depressurization to meet SI termination criteria has been completed or at the discretion of the lead examiner.
Page 45 of 58 Op. Test No.: Feb 2023 Scenario No.: __4__
Event No.: __6 & 7__
Event
Description:
B SGTR - E0 - E3 Symptoms/Cues: Various annunciators, rapidly lowering Reactor pressure and Pressurizer level, rising level in B SG.
Time Position Applicants Actions or Behavior BOP EOP-0 Attachment A: Automatic Action Verification:
A1 Verify Feedwater Isolation:
- a. Ensure feedwater isolation valves BOTH SHUT:
- 1CS-3124 for S/G A
- 1CS-3125 for S/G B
- a. IF feedwater isolation valves can NOT be closed, THEN perform the following:
- 2) Shift feedwater regulating bypass valve controllers to manual and shut 1HC-480 1HC-481 IF any feedline can NOT be isolated, THEN perform the following:
- a. Containment isolation panels "A" and B - ALL LIGHTS LIT
- a. Perform the following
- 1) Manually actuate Containment Isolation.
- 2) IF any containment isolation valve is open, THEN manually shut valve(s). Refer to ATTACHMENT B, CONTAINMENT ISOLATION VALVES.
Page 46 of 58 Op. Test No.: Feb 2023 Scenario No.: __4__
Event No.: __6 & 7__
Event
Description:
B SGTR - E0 - E3 Symptoms/Cues: Various annunciators, rapidly lowering Reactor pressure and Pressurizer level, rising level in B SG.
Time Position Applicants Actions or Behavior BOP A3 Verify ECCS Pumps RUNNING:
- a. SI Pumps - BOTH RUNNING
- b. RHR Pumps - BOTH RUNNING
BOP A4 Verify Service Water Pumps Running:
- a. Service water pumps - SIX RUNNING
- a. WHEN SI sequence is complete, THEN manually start pumps.
BOP A5 Verify Containment Accident Cooling Units RUNNING:
- a. Containment accident recirculation fans - ALL RUNNING
- a. WHEN SI sequence is complete, THEN manually start fans.
- b. Manually open AT LEAST ONE valve.
Page 47 of 58 Op. Test No.: Feb 2023 Scenario No.: __4__
Event No.: __6 & 7__
Event
Description:
B SGTR - E0 - E3 Symptoms/Cues: Various annunciators, rapidly lowering Reactor pressure and Pressurizer level, rising level in B SG.
Time Position Applicants Actions or Behavior BOP A6 Verify Component Cooling Water Pumps -
ONLY ONE RUNNING o 1P-11A o 1P-11B IF NO component cooling water pump is running, THEN perform the following:
- a. Manually start one component cooling water pump by placing control switch to stop and then start.
IF both component cooling water pumps are running, THEN place one pump in standby.
BOP A7 Check If Main Steam Lines Can Remain Open:
- a. Any MSIV valve - OPEN
- a. Go to Step A8.
- b. Containment pressure -
LESS THAN OR EQUAL TO 15 psig
- b. Isolate both steam lines:
- 1) Shut both main steam isolation valves:
1MS-2018 for S/G A 1MS-2017 for S/G B
- 2) Go to Step A8.
- c. High-high steam flow bistable lights - NOT LIT
- c. Ensure main steam isolation on affected main steam line(s) shut:
1MS-2018 for S/G A 1MS-2017 for S/G B
- d. High steam flow bistable lights - NOT LIT
- d. IF RCS average temperature is LESS THAN 543°F, THEN ensure main steam isolation valve on affected main steam line(s) shut:
1MS-2018 for S/G A 1MS-2017 for S/G B
Page 48 of 58 Op. Test No.: Feb 2023 Scenario No.: __4__
Event No.: __6 & 7__
Event
Description:
B SGTR - E0 - E3 Symptoms/Cues: Various annunciators, rapidly lowering Reactor pressure and Pressurizer level, rising level in B SG.
Time Position Applicants Actions or Behavior BOP A8 Verify Containment Spray Not required:
- a. Containment pressure recorder - HAS REMAINED LESS THAN 25 psig
- a. Perform the following: 1) Check containment spray actuated:
- Annunciator {C01 B 2-6},
CONTAINMENT SPRAY, lit IF containment spray has NOT actuated, THEN manually actuate containment spray.
- a. RCS wide range pressure
- LESS THAN [1850 psig]
1725 psig
- a. Go to Step A10.
- b. Manually start pumps and align valves.
- c. RCS wide range pressure
- LESS THAN [450 psig] 325 psig
- c. Go to Step A10.
- d. RHR pumps - FLOW INDICATED
- d. Manually start pumps and align valves.
BOP A10 Verify AFW valve alignment - PROPER EMERGENCY ALIGNMENT Manually align valve as necessary.
Page 49 of 58 Op. Test No.: Feb 2023 Scenario No.: __4__
Event No.: __6 & 7__
Event
Description:
B SGTR - E0 - E3 Symptoms/Cues: Various annunciators, rapidly lowering Reactor pressure and Pressurizer level, rising level in B SG.
Time Position Applicants Actions or Behavior BOP A11 Verify Proper ECCS Valve Alignment:
- a. Unit 1 SI Active status panel ALL LIGHTS LIT
- b. Unit 1 SI - Spray Ready status panel - NO LIGHTS LIT Manually align valves as necessary.
BOP A12 Check Containment Spray NOT ACTUATED Check containment spray alignment:
- a. Unit 1 Spray Active status panel - NO LIGHTS LIT
- 1. Ensure all containment spray pump discharge MOVs are open.
- 2. Ensure at least one containment spray pump is running:
- 3. IF two containment spray pumps are running, THEN Place one containment spray pump in pull out:
- 4. WHEN containment spray has been actuated for GREATER THAN two minutes, THEN ensure spray additive eductor suction valve is open on the running train:
o 1SI-836A, train A o 1SI-836B, train B
Page 50 of 58 Op. Test No.: Feb 2023 Scenario No.: __4__
Event No.: __6 & 7__
Event
Description:
B SGTR - E0 - E3 Symptoms/Cues: Various annunciators, rapidly lowering Reactor pressure and Pressurizer level, rising level in B SG.
Time Position Applicants Actions or Behavior BOP A13 Stop any boration via the blender in progress:
- Place Reactor Makeup Control Switch to STOP BOP A14 Ensure the Auxiliary Building Filter/Exhaust Fans -
OPERATING:
- W-30A
- W-21A OR
- W-30B
- W-21B Align Auxiliary Building Filter/ Exhaust Fans per OI 39, CONTROLLED SIDE VENTILATION SYSTEM.
BOP A15 Perform the following:
- a. Notify STA to IMPLEMENT Status Trees
- b. Notify Shift Manager of any equipment malfunctions previously noted.
Page 51 of 58 Op. Test No.: Feb 2023 Scenario No.: __4__
Event No.: __6 & 7__
Event
Description:
B SGTR - E0 - E3 Symptoms/Cues: Various annunciators, rapidly lowering Reactor pressure and Pressurizer level, rising level in B SG.
Time Position Applicants Actions or Behavior BOP A16 Verify Service Water System Alignment:
- a. Service water isolation valves - SHUT
- At least one spent fuel pool heat exchanger A isolation MOV - SHUT o SW-2927A, inlet MOV o SW-2930A, discharge MOV
- At least one spent fuel pool heat exchanger B isolation MOV - SHUT o SW-2927B, inlet MOV o SW-2930B, discharge MOV
- At least one auxiliary building A/C condenser isolation MOV - SHUT o SW-2816, train A o SW-4479, train B
- At least one water treatment system inlet MOV - SHUT o SW-4478, train A o SW-2817, train B
- a. Perform the following:
- 1) Manually shut valve(s).
- 2) IF any isolation valve will NOT shut, THEN locally shut valve or associated manual isolation valve.
- b. Locally check at least one radwaste service water valve
- SHUT (blowdown evap panel C-180) o TV-LW61, train A o TV-LW62, train B
- b. Perform the following:
- 1) Locally shut valve(s).
- 2) IF any valve will NOT shut, THEN locally shut associated manual isolation valve.
Page 52 of 58 Op. Test No.: Feb 2023 Scenario No.: __4__
Event No.: __6 & 7__
Event
Description:
B SGTR - E0 - E3 Symptoms/Cues: Various annunciators, rapidly lowering Reactor pressure and Pressurizer level, rising level in B SG.
Time Position Applicants Actions or Behavior BOP Step A16, cont:
- c. Annunciator C01 B 2-3, UNIT 1 CONTAINMENT RECIRC COOLERS WATER FLOW LOW -
CLEAR
- c. IF flow is less than 800 GPM, THEN perform the following:
- 1) Ensure non-affected unit's service water isolation valves are both shut:
- 2) Isolate service water to non-safety loads as necessary to clear annunciator.
BOP A17 Check Miscellaneous Valves -
SHUT
- a. RS-SA-9, Unit 1 steam supply to rad waste system Locally at C-180 BDE panel shut valve(s)
Page 53 of 58 Op. Test No.: Feb 2023 Scenario No.: __4__
Event No.: __6 & 7__
Event
Description:
B SGTR - E0 - E3 Symptoms/Cues: Various annunciators, rapidly lowering Reactor pressure and Pressurizer level, rising level in B SG.
Time Position Applicants Actions or Behavior BOP A18 Check Control Room Ventilation:
- a. Control Room Ventilation - IN MODE 5
- Control Room recirc fans
- AT LEAST ONE RUNNING o W-13B1 o W-13B2
- Control Room charcoal filter fans - AT LEAST ONE RUNNING o W-14A o W-14B
- Control Room damper solenoid valve - PURPLE LIGHT LIT
- a. Align Control Room ventilation per 0-SOP-VNCR-002, CONTROL AND COMPUTER ROOM VENTILATION SYSTEM NORMAL OPERATION.
BOP NOTE To ensure room temperatures are not exceeded, steps A19 through A24 may be performed in parallel.
A19 Check Cable Spreading Room Ventilation System -
OPERATING.
- a. Ensure Cable Spreading Room recirc fans - ONE RUNNING:
o W-13A1 o W-13A2
- b. Ensure CSR Chilled Water recirc pumps -
ONE RUNNING:
o P-111A o P-111B Restore Ventilation per AOP-30, TEMPORARY VENTILATION FOR VITAL AREAS.
Page 54 of 58 Op. Test No.: Feb 2023 Scenario No.: __4__
Event No.: __6 & 7__
Event
Description:
B SGTR - E0 - E3 Symptoms/Cues: Various annunciators, rapidly lowering Reactor pressure and Pressurizer level, rising level in B SG.
Time Position Applicants Actions or Behavior BOP A20 Check Computer Room Ventilation System -
OPERATING
- a. Ensure Control Room recirc fans - ONE RUNNING:
o W-13B1 o W-13B2
- b. Ensure Control Room chilled water recirc pumps -
ONE RUNNING:
o P-112A o P-112B Restore Ventilation per AOP-30, TEMPORARY VENTILATION FOR VITAL AREAS.
BOP CAUTION Maintain Diesel Loading per AOP-22, EDG LOAD MANAGEMENT.
A21 Check AFW recirc fans - ONE RUNNING:
o W-46 o W-46A Restore Ventilation per AOP 30, TEMPORARY VENTILATION FOR VITAL AREAS.
BOP A22 Check Circulating Water Pump House Temperature Less Than 105°F:
- TI-6645 At the circulating water pump house, open the rollup doors.
Page 55 of 58 Op. Test No.: Feb 2023 Scenario No.: __4__
Event No.: __6 & 7__
Event
Description:
B SGTR - E0 - E3 Symptoms/Cues: Various annunciators, rapidly lowering Reactor pressure and Pressurizer level, rising level in B SG.
Time Position Applicants Actions or Behavior BOP A23 Check G03/G04 Switchgear Room Temperature less than 95°F.
o TI-4965 - G03 Switchgear Room o TI-4966 - G04 Switchgear Room IF 1A-06 or 2A-06 is energized, THEN perform AOP-30, TEMPORARY VENTILATION FOR VITAL AREAS.
BOP A24 Periodically check status of spent fuel cooling:
- Spent Fuel Pool Temp High Level High or Low (C01 C 4-
- 10) - CLEAR IF level less than 62' 8" El. OR temperature greater than 120°F, THEN dispatch personnel to initiate actions per AOP-8F, LOSS OF SPENT FUEL POOL COOLING.
END Attachment A
Page 56 of 58 Op. Test No.: Feb 2023 Scenario No.: __4__
Event No.: __6 & 7__
Event
Description:
B SGTR - E0 - E3 Symptoms/Cues: Various annunciators, rapidly lowering Reactor pressure and Pressurizer level, rising level in B SG.
Time Position Applicants Actions or Behavior BOP EOP-1 Attachment B, Containment Isolation Valves
Page 57 of 58 Op. Test No.: Feb 2023 Scenario No.: __4__
Event No.: __6 & 7__
Event
Description:
B SGTR - E0 - E3 Symptoms/Cues: Various annunciators, rapidly lowering Reactor pressure and Pressurizer level, rising level in B SG.
Time Position Applicants Actions or Behavior BOP End Attachment B
Page 58 of 58 Op. Test No.: Feb 2023 Scenario No.: __4__
Event No.: __6 & 7__
Event
Description:
B SGTR - E0 - E3 Symptoms/Cues: Various annunciators, rapidly lowering Reactor pressure and Pressurizer level, rising level in B SG.
Time Position Applicants Actions or Behavior Scenario Termination Critical Tasks have been evaluated RCS Depressurization sufficient to meet SI Termination Criteria At the discretion of the Lead Evaluator
Form 3.3-1 Scenario Outline Event No.
Malf.
No.
Event Type*
Event Description 1
N/A (N) BOP (TS) SRO Shift Control Room Recirc Fans 2
(C) BOP (C) SRO High feed pump vibrations on 1P-28A SG Feed pump 3
(R) ATC Rapid power reduction to less than 60% power 4
(I) BOP (I/TS) SRO Failure Low of LT-462 (Blue) (Steam Generator Level Loop A) 5 (M) CREW LBLOCA, reactor trip/SI - (EOP EOP-1) 6 (C/MC) ATC (C) SRO SI auto actuation failure. Requires manual actuation of SI (CT) 7 (C/MC) BOP (C) SRO Containment accident cooling unit 1W-1D1 fails to auto start (E0 Attachment A, Step A5 failure) 8 (M) CREW Transfer to Containment Sump Recirc IAW EOP-1.3 (CT)
Termination Criteria:
Critical Tasks have been evaluated RHR suction transferred to the ECCS sump At the discretion of the Lead Evaluator
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS)Tech Spec, (MC)Manual Control Facility:
Point Beach Scenario #: 5 Scenario Source:
Op. Test #: Feb 2023 Examiners:
Applicants/
Operators:
Initial Conditions:
65% Power, MOC, Boron @ 1000 ppm.
Turnover:
The crew is directed to shift Main Control Room recirc fans.
Critical Tasks:
- 1. Manually initiate SI
CT1: Manually initiate SI when required by E-0 Initiating Cue: The following indications:
o Indications of a large break LOCA inside containment o Reactor pressure lowering rapidly o Pressurizer Level lowering rapidly o Annunciator alarms o Rising containment pressures o No safety injection pumps running with valid initiation signals Performance Feedback: All of the following:
o Primary conditions will continue to degrade with ongoing plant conditions without safety injection o Manual initiation of SI will result in system actuation Success Path: At least one required train of safety injection actuated Measurable Performance Standard: Manually initiate Safety Injection prior to completion of EOP-0 Step 4.
Safety Significance: If no operator action is taken, the reactor would be under LOCA conditions without cooling water injection, resulting in core damage.
CT2: Transfer the suction of the RHR pumps to the Containment Sump prior to meeting the loss of suction criteria Initiating Cue: The following indications:
o Lowering RWST level to less than 34%
o Containment Sump Level >38 o Indication of high injection flow rates during LOCA Performance Feedback: All of the following:
o Valve indication as transfer is made in EOP-1.3 o Continuing lowering RWST level until transition is made o Continuing rising containment sump levels Success Path: at least 1 train of RHR pumps swapped to the containment sump IAW EOP-1.3 Measurable Performance Standard: Manually align RHR for cold leg recirculation prior to meeting the loss of pump suction criteria provided in EOP-1.3.
Safety Significance: If no operator action is taken, the running RHR pumps would lose their suction source resulting in loss of injection and cooling capabilities to the reactor core during LOCA conditions.
Scenario Executive Summary Initial Conditions / Turnover:
Point Beach Unit 1 will be at 65% during the middle of the operating cycle to set initial conditions for testing. No equipment OOS and no Tech Spec LCOs in effect.
Direction(s) for the Shift:
The crew is directed to shift running Control Room Recirculation Fans using 0-SOP-VNCR-002, Control and Computer Room Ventilation System Normal Operation.
Event #1 - Shift Control Room Recirc Fans Crew will shift from W-13B1 to W-13B2 using 0-SOP-VNCR-002, Control and Computer Room Ventilation System Normal Operation. By procedure, the SRO will declare CREFs INOPERABLE and enter TS LCO 3.7.9 Condition A (and TRM LCO 3.7.9 C?). Once the shift is complete, CREFs will be declared OPERABLE and exit the TRM LCO Condition. This event will be completed when the recirc fans are shifted, TS exited and/or at the direction of the Lead Examiner.
Event #2 - High feed pump vibrations on 1P-28A S/G Feed Pump (requires securing feed pump)
Crew will respond to abnormal noise / field report of 1P-28A S/G Feed Pump vibrating (imminent failure). Crew will enter AOP-2B, Feedwater System Malfunctions for an abnormal S/G Feed Pump. Crew will secure the feed pump and commence a rapid power reduction to less than 60% using AOP-17A. This carries directly to the next event.
Event #3 - Rapid power reduction to less than 60% power The crew will enter AOP-17A to reduce power to less than 60%. Crew will reduce turbine load and borate as needed to reduce power and stabilize the plant with one S/G Feed Pump in operation. This event will be completed when the plant is less than 60%, stabilization efforts are in progress and/or at the direction of the Lead Examiner Event #4 - Failure Low of LT-462 (Blue) (Steam Generator Level Loop A)
A card failure will occur and cause LT-462 (S/G Level Loop A BLUE) to fail low. Crew will respond to various annunciators. ARB 1C03 1E2 4-3 (S/G A Low-Low Level Alert) refers to AOP-24 (instrument / channel failure), where the crew will remove the affected instrument from service using 0-SOP-IC-001 BLUE. SRO will analyze Technical Specifications and determine TS LCO 3.3.1 (RPS) Conditions A and D (function 13), LCO 3.3.2 (ESFAS) Conditions A and D (Functions 5b and 6b). This event is complete when the plant is stabilized, and Tech Specs have been determined and with the concurrence of the lead evaluator.
Event #5 - (Major) - LBLOCA A large break LOCA will be inserted causing an automatic Reactor trip and safety injection signals. Crew will enter EOP-0 and transition to EOP-1.
Event #6 - SI Fails to Auto Initiate Crew will note during EOP-0 immediate operator actions that the automatic SI signal did not work. Crew will manually initiate safety injection and continue in EOP-0.
Event #7 - Containment accident cooling unit 1W-1A1 Fails to Auto Start on ESF Signal Crew will perform EOP-0, Attachment A and note that on Step A5, Containment accident recirculation fan 1W-1A1 failed to start. BOP will take action to manually start the fan.
Event #8 - Transfer to Containment Sump Recirc IAW EOP-1.3 Crew will transition to EOP-1, Loss of Reactor or Secondary Coolant and determine that containment sump recirculation is required (based on FOP criteria in EOP-1) and go to EOP-1.3, Transfer to Containment Sump Recirculation - Low Head Injection. Crew will align ECCS in piggyback mode to maintain the core covered.
Scenario Termination The scenario is terminated when the Critical Tasks have been evaluated, the crew has transferred RHR suction to the ECCS sump, and at the discretion of the Lead Evaluator.
TR-AA-230-1007-F14, Revision 0 SIMULATOR EXERCISE GUIDE SEG SITE:
PBNP Revision #: 0 LMS ID:
PBN LOI NRC 030E LMS Rev. Date:
SEG TITLE:
2023 NRC Exam Scenario 5 SEG TYPE:
Training Evaluation PROGRAM:
LOCT LOIT Other:
DURATION:
90 minutes Developed by:
John Rogers Instructor/Developer Date Reviewed by:
Andy Zommers Instructor (Instructional Review)
Date Validated by:
John Rogers SME (Technical Review)
Date Approved by:
Adam Moore Training Supervision Date Approved by:
Joe Krear Training Program Owner (Line)
Date
PBN LOI NRC 030E, 2023 NRC Exam Scenario 5, Rev 0 SEG Page 2 of 30 TR-AA-230-1007-F14, Revision 0 Form 3.3-1 Scenario Outline Event No.
Malf.
No.
Event Type*
Event Description 1
N/A (N) BOP (TS) SRO Shift Control Room Recirc Fans 2
(C) BOP (C) SRO High feed pump vibrations on 1P-28A SG Feed pump 3
(R) ATC Rapid power reduction to less than 60% power 4
(I) BOP (I/TS) SRO Failure Low of LT-462 (Blue) (Steam Generator Level Loop A) 5 (M) CREW LBLOCA, reactor trip/SI - (EOP EOP-1) 6 (C/MC) ATC (C) SRO SI auto actuation failure. Requires manual actuation of SI (CT) 7 (C/MC) BOP (C) SRO Containment accident cooling unit 1W-1D1 fails to auto start (E0 Attachment A, Step A5 failure) 8 (M) CREW Transfer to Containment Sump Recirc IAW EOP-1.3 (CT)
Termination Criteria:
Critical Tasks have been evaluated RHR suction transferred to the ECCS sump At the discretion of the Lead Evaluator
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS)Tech Spec, (MC)Manual Control Facility:
Point Beach Scenario #: 5 Scenario Source:
Op. Test #: Feb 2023 Examiners:
Applicants/
Operators:
Initial Conditions:
65% Power, MOC, Boron @ 1000 ppm.
Turnover:
The crew is directed to shift Main Control Room recirc fans.
Critical Tasks:
- 1. Manually initiate SI
PBN LOI NRC 030E, 2023 NRC Exam Scenario 5, Rev 0 SEG Page 3 of 30 TR-AA-230-1007-F14, Revision 0 SIMULATOR EXERCISE GUIDE REQUIREMENTS Terminal Objective:
Given the site simulator and specific plant conditions, the students will be able to respond to various plant abnormal and emergency events, in accordance with site procedures and technical Specifications.
Enabling Objectives:
- 1. None Prerequisites:
- 1. Simulator available
- 2. Students enrolled in Initial License Program Training Resources:
- 1. Floor Instructor as Shift Manager / Shift Technical Advisor
- 2. Simulator Booth Operator
- 3. Communicator
- 4. NRC Evaluators
References:
- 2. AOP-17A, Rapid Power Reduction
- 3. AOP-24, Response to Instrument Malfunction
- 4. EOP-0, Reactor Trip or Safety Injection
- 5. EOP-1, Loss of Reactor or Secondary Coolant
- 7. 0-SOP-VNCR-002, Control and Computer Room Ventilation System Normal Operation
- 8. 0-SOP-IC-001 BLUE, Routine maintenance Procedure Removal of Safeguards or Protection Sensor from Service - Blue Channels
- 9. OM 3.7, AOP and EOP Procedure Usage For Response To Plant Transients
- 10. Technical Specifications Manual
- 11. Technical Requirements Manual Protected Content:
None Evaluation Method:
Simulator performance will be evaluated in accordance with NUREG 1021.
Operating Experience:
None
PBN LOI NRC 030E, 2023 NRC Exam Scenario 5, Rev 0 SEG Page 4 of 30 TR-AA-230-1007-F14, Revision 0 Risk Significant Operator Actions:
Initiating Event with Core Damage Frequency:
UPDATE LOG: Indicate in the following table any minor changes or major revisions made to the material after initial approval.
DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR#
PREPARER DATE REVIEWER DATE 0
Developed for the 2023 ILT NRC Exam
PBN LOI NRC 030E, 2023 NRC Exam Scenario 5, Rev 0 SEG Page 5 of 30 TR-AA-230-1007-F14, Revision 0 OVERVIEW / SEQUENCE OF EVENTS OVERVIEW Initial conditions for the scenario are: Unit 1 is at MOL with power at approximately 65%. No equipment is OOS.
Examinees will shift Control Room recirculating fans. They will respond to a Main Feed pump malfunction requiring a rapid power reduction, and a Steam Generator level instrument failure. A large break LOCA will occur, examinees will implement EOPs.
The scenario will be terminated when the crew has established containment sump recirculation. or per Lead Evaluator.
SEQUENCE OF EVENTS Event #
Description
- 1.
Shift Control Room Recirculation Fans The crew will shift running control room recirculation fans per 0-SOP-VNCR-002, Control and Computer Room Ventilation System Normal Operation.
- 2.
1P-28A, Steam Generator Feed Pump Malfunction The crew will respond to a field report of noise and excessive vibration on 1P-28A.
The crew will implement AOP-2B, Feedwater System Malfunction and secure the failing feed pump.
- 3.
Rapid Power Reduction The crew will implement AOP-17A, Rapid Power Reduction in response to the feed pump malfunction to lower power and stabilize the plant with one feed pump operating.
- 4.
1LT-462, Steam Generator Level Fails Low (BLUE)
S/G A level instrument 1LT-462 will fail low, causing a rise in actual S/G level.
The crew will implement AOP-2B, Feedwater System Malfunction, to manually control the A FRV and stabilize S/G level, and AOP-24, Instrument Malfunction.
SRO will address Technical Specifications
- 5.
Large Break LOCA / SI Fails to Auto Actuate A large break LOCA will occur causing an automatic reactor trip, but SI will fail to automatically actuate.
The crew will manually actuate SI/CI.
The crew will implement EOPs.
PBN LOI NRC 030E, 2023 NRC Exam Scenario 5, Rev 0 SEG Page 6 of 30 TR-AA-230-1007-F14, Revision 0
- 6.
Containment Accident Fan Fails to Auto Start When SI is manually actuated, 1W-1D1, Containment Accident Fan will fail to start automatically; may be manually started.
- 7.
Transfer to Containment Sump Recirculation The crew will implement EOP-1.3, Transfer to Containment Sump Recirculation - Low Head Injection, in response to the Large break LOCA.
Terminate the scenario when the crew has established containment sump recirculation, or per Lead Evaluator.
PBN LOI NRC 030E, 2023 NRC Exam Scenario 5, Rev 0 SEG Page 7 of 30 TR-AA-230-1007-F14, Revision 0 SIMULATOR SET-UP INSTRUCTIONS Perform simulator set up per the site specific Simulator Setup Checklist.
Check Action
- 1.
Reset to IC created for this scenario.
- 2.
Perform Simulator Setup Checklist
- 3.
Open schedule file. Z:/2023 ILT NRC Simulator Files/NRC Scenario 5.sch
- 4.
To record SBT data:
- 1. Launch SBT Report from Thunderbar
- 2. Open Scenario Validation Checklist.sbt (TRex_PB\\Lightning)
- 5.
Take schedule(s) to run
- 6.
Verify required event file(s) open if required
- 7.
Take sim to run
- 8.
Place turnover sheets on CO1 desk
- 9.
Place reactivity sheets on CO1 desk
- 10.
Guard the following:
None Place the following in Pull-Out with an OOS MNT magnet:
None Place red dot on the following alarm:
None Prepare a 0-SOP-IC-001 BLUE to remove LT-462 from service.
- 11.
- Conduct simulator crew pre-scenario brief using TR-AA-230-1007-F06, Simulator Instructor Pre-Exercise Checklist.
- Brief the scenario evaluators
- Brief surrogates using TR-AA-230-1007-F11, Surrogate Brief Checklist, if necessary
- 12.
Run Scenario
- 13.
To save SBT Data:
- 1. In the SBT Report program click the Generate Report icon (green arrow)
- 2. In Test Title enter a unique test title, to be same as file name
- 3. In report name enter the location the test files are to be saved, use same file name as Test Title
- 4. Click Generate (generates and saves two files in the selected folder)
- 5. Verify files saved in the selected folder
- 6. The generated report and SBT Report program may now be closed
- 7. Collect procedure markups for SBT
- 8. Save any InSight, Alarm, Event, Schedule Files to the secure drive that were in use
- 14.
Reset simulator to appropriate IC.
PBN LOI NRC 030E, 2023 NRC Exam Scenario 5, Rev 0 SEG Page 8 of 30 BOOTH OPERATOR BRIEFING:
Z:/2023 ILT NRC Simulator Files/NRC Scenario 5.sch At Time On Event Action Description Event 2 and 3: MFP Malf / Power Reduction 1
Insert remote LOA1CFW083 to ON 1P-99A SGFP SEAL WATER INJECT PUMP CS 1
Insert remote LOA1CFW084 after 5 to ON 1P-99B SGFP SEAL WATER INJECT PUMP CS Event 4: 'A' S/G Level Fails Low 3
Insert malfunction XMT1SGN008A to 0 in 60 1-LT462 STM GEN A NR LEVEL FIXED OUTPUT Event 5: LB LOCA 5
Insert malfunction MAL1RCS002D to 29.00000 in 10 on event 5 RCS LEAK LOOP B HOT LEG Event 6: SI Fails to Actuate 00:00:00 Insert malfunction RLY1PPL078 to Fail_As_Is 1-SIA-A TRAIN "A" AUTO SI INITIATION 00:00:00 Insert malfunction RLY1PPL079 to Fail_As_Is 1-SIA-B TRAIN "B" AUTO SI INITIATION Event 7: 'D' Accident Fan Fails to Start 00:00:00 Insert malfunction BKR1CNM001 to Fail_Auto_Cl 1B52-15A W-1A1 CONTAINMENT FAN CKTBKR Event 8: Containment Sump Recirc 1SI-897A and 897B 7
Insert remote LOA1SIS030 to 0 in 5 1SI-897A HANDWHEEL GAG 7
Insert remote LOA1SIS031 to 0 in 5 1SI-897B HANDWHEEL GAG Attachment A of EOP-1.3 9
Insert remote LOA1CCW016 to 0 in 10 on event 9 1CC-740A NON-REGEN HX-3A&B INLET VALVE 9
Insert remote LOA1CCW021 after 60 to 0 in 10 on event 9 1CC-750A SEAL STR HX-5 INLET VALVE 9
Insert remote LOA1SWS048 after 120 to 0.10000 in 10 on event 9 SW-322 1HX-12A CC HTEXCH OUTLET 9
Insert remote LOA1SWS051 after 180 to 0.10000 in 10 on event 9 SW-360 HX-12B CCW SW OUTLET 9
Insert remote LOA1CCW018 after 240 to 0 in 10 on event 9 1CC-744B CCW BYPASS/TEST LOOP OUTLET STOP VALVE
PBN LOI NRC 030E, 2023 NRC Exam Scenario 5, Rev 0 SEG Page 9 of 30 TR-AA-230-1007-F14, Revision 0 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS Bolded steps are Verifiable Actions taken by the Operators.
(IA) actions are those allowed to be taken from memory, before referencing the procedure, as allowed by OM 3.7, Attachment F, AOP Actions Allowed From Memory.
Event # 1 Shift Control Room Recirculation Fans ACTION Booth: None STUDENT
RESPONSE
BOP/RO Performs actions to shift Control Room recirc fans from W-13B1 to W-13B2.
SRO Directs / provides oversight for procedure implementation.
Crew 0-SOP-VNCR-002, Control and Computer Room Ventilation System Normal Operation 5.2.3 IF shifting from W-13B2 to W-13B1, Control Room Recirc Fan, THEN PERFORM the following:
- a. DECLARE CREFS out of service and ENTER TSAC / TRM 3.7.9 for CREFS INOPERABLE. (SRO)
NOTE: CONTROL ROOM AC UNITS AIR FLOW LOW Alarm (4-10 on C01B) will annunciate.
- b. PLACE W-13B2, Control Room Recirc Fan Control Switch to OFF.
(BOP)
- c. PLACE W-13B1, Control Room Recirc Fan Control Switch to ON AND return to AUTO. (BOP)
- d. PLACE W-13B2, Control Room Recirc Fan Control Switch, to AUTO.
(BOP)
- e. IF no operability issues exist, THEN DECLARE CREFS OPERABLE AND EXIT appropriate TSAC /TRM 3.7.9 (SRO)
PBN LOI NRC 030E, 2023 NRC Exam Scenario 5, Rev 0 SEG Page 10 of 30 TR-AA-230-1007-F14, Revision 0 Event # 1 Shift Control Room Recirculation Fans ROLE PLAY Booth Communications:
Respond to reports or direction to field operators as necessary.
SM Communications:
Provide crew direction to shift control room recirc fans per brief.
Respond to reports from crew members as required.
NOTES Continuation Criteria:
After the crew has completed the fan switch, or at the discretion of the Lead Examiner, continue with the next event.
Event # 2 1P-28A, Steam Generator Feed Pump Malfunction
PBN LOI NRC 030E, 2023 NRC Exam Scenario 5, Rev 0 SEG Page 11 of 30 TR-AA-230-1007-F14, Revision 0 Event # 2 1P-28A, Steam Generator Feed Pump Malfunction ACTION Booth: None STUDENT
RESPONSE
Symptoms / Indications Field report of excessive noise and vibration on 1P-28A BOP/RO Secure 1P-28A, Steam Generator Feed Pump on report of pump failure.
SRO Implements AOP-2B, Feedwater System Malfunction.
Crew AOP-2B, Feedwater System Malfunction
- 1. Maintain reactor power less than or equal to 100%
- 2. Determine the secondary malfunction and go to the appropriate step:
o If a Main Feedwater Pump trips or abnormal pump indication, THEN go to Step 8.
- 8. Perform the following for a Feedwater Pump trip or abnormal pump indication:
- b. IF one main feed pump is running and turbine load less than 75%,
THEN reduce turbine load less than 60% per AOP-17A, RAPID POWER REDUCTION (SRO)
- d. Check Main Feed Pumps - NORMAL; RNO: Perform the following:
- 3)
IF affected parameter indicates imminent main feed pump failure and two main feed pumps running, THEN perform the following:
a) IF turbine load greater than 60%, THEN reduce turbine load less than 60% per AOP-17A, Rapid Power Reduction (SRO) b) Stop the affected main feed pump (BOP)
- e. Return to Step 2
- 2. Determine the secondary malfunction and go to the appropriate step
- 3. Check Plant conditions - STABLE
- 4. Check secondary system alignment - NORMAL
- 5. Check change in reactor power - LESS THAN 15% IN ANY ONE HOUR
- 6. Notify the DSM
- 7. Return to procedure and step in effect
PBN LOI NRC 030E, 2023 NRC Exam Scenario 5, Rev 0 SEG Page 12 of 30 TR-AA-230-1007-F14, Revision 0 Event # 2 1P-28A, Steam Generator Feed Pump Malfunction ROLE PLAY Booth Communications:
Per Lead Instructor make the following report as TH AO, The A main feed pump, 1P-28A is failing. There is excessive noise and vibration. Recommend immediately securing the pump.
If asked following 1P-28A being secured, coastdown was UNSAT, the pump came to an abrupt stop.
Respond to reports or direction to field operators as necessary.
SM Communications:
Respond to reports from crew members as required.
NOTES Continuation Criteria:
The next event is initiated per procedure flowpath.
PBN LOI NRC 030E, 2023 NRC Exam Scenario 5, Rev 0 SEG Page 13 of 30 TR-AA-230-1007-F14, Revision 0 Event # 3 Rapid Power Reduction ACTION Booth: Insert Trigger 1 when directed by the crew to start SGFP Seal Water Pumps STUDENT
RESPONSE
Symptoms / Indications Power reduction is directed by AOP-2B BOP/RO Performs AOP actions as directed to lower power to less than 60%
SRO Implements AOP-17A, Rapid Power Reduction Crew AOP-17A, Rapid Power Reduction
- 1. Check power - GREATER THAN 100%
- 3. Determine desired power level or condition to be met (SRO)
- 4. Commence boration as necessary to target load (RO) boric acid quantity and flowrate set from daily reactivity brief based on ramp rate and final power
- a. Set boric acid flow totalizer to desired quantity
- b. Set boric acid flow controller to desired flowrate
- c. If desired, start second boric acid pump
- d. Place reactor makeup mode selector switch to borate
- e. Place reactor makeup control switch to start
- 5. Select turbine rate and reduce load (BOP)
- a. Ensure EH controls are set for operator auto
- b. Ensure First Stage In is selected
- c. If first stage pressure is unavailable, then select First Stage Out
- d. Ensure the proper load rate is selected on the load rate thumbwheel
- e. Select target end-point on reference control
- f. WHEN temperature reduction of at least 0.5°F is observed on Tavg-Tref indicator, THEN depress GO push-button
- g. Continue with next step
- 6. Notify PSS of load reduction (SRO)
- 7. Check rod control system - IN AUTO
- 8. Energize pressurizer backup heaters (RO)
- 9. Check PZR pressure - CONTROLLING IN AUTO
- 10. Check PZR level - CONTROLLING IN AUTO
- 11. Check S/G level - CONTROLLING IN AUTO
- 12. Ensure main feed pump seal water pump - RUNNING (BOP)
- 13. Maintain RCS Tavg
- 14. Check AFD - WITHIN LIMITS
PBN LOI NRC 030E, 2023 NRC Exam Scenario 5, Rev 0 SEG Page 14 of 30 TR-AA-230-1007-F14, Revision 0 Event # 3 Rapid Power Reduction ROLE PLAY Booth Communications:
When directed to start 1P-99A and 1P-99B, SGFP Seal Water Pumps, insert Trigger 1 and report when pumps are running.
Respond to reports or direction to field operators as necessary.
SM Communications:
Respond to reports from crew members as required.
NOTES Continuation Criteria:
After power has been lowered in response to the feed pump malfunction and the plant has been stabilized, or at the discretion of the Lead Examiner, continue with the next event.
PBN LOI NRC 030E, 2023 NRC Exam Scenario 5, Rev 0 SEG Page 15 of 30 TR-AA-230-1007-F14, Revision 0 Event # 4 1LT-462, Steam Generator Level Fails Low (BLUE)
ACTION Booth: Insert Trigger 3 per Lead Instructor STUDENT
RESPONSE
Symptoms / Indications 1LT-462, S/G Level (BLUE) indicates low BOP/RO Initial response / key actions.
SRO Implements AOP-24, Instrument Malfunction Assesses Technical Specifications Crew AOP-24, Instrument Malfunction AOP-24, Response to Instrument Malfunctions
- 1. Identify failed instrument
- 2. Check if failed instrument is a controlling channel
- 3. Establish manual control as required (BOP) - places A S/G feed regulating valve controller in manual
- 4. Return affected parameters to desired value (BOP) - adjust feed flow to return and maintain S/G level at program
- 5. Using Attachment A, PPCS Parameters Used to Calculate RTO, Verify that failed instrument is not an input to RTO.
- 6. Remove failed instrument from service per 0-SOP-IC-001, Routine Maintenance Procedure Removal Of Safeguards Or Protection Sensor From Service
- 7. Return controls to automatic if desired (S/G level must remain in manual control)
- 8. Check failure for Technical Specification or TRM Applicability Assess Technical Specifications (SRO)
LCO 3.3.1 RPS Instrumentation, Conditions A and D (Function 13)
CONDITION REQUIRED ACTION COMPLETION TIME D. One channel inoperable D.1 Place channel in trip OR D.2 Be in MODE 3 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 7 hours LCO 3.3.2, ESFAS, Conditions A and D (Functions 5b and 6b)
CONDITION REQUIRED ACTION COMPLETION TIME D. One channel inoperable D.1 Place channel in trip OR D.2.1 Be in MODE 3 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 7 hours
PBN LOI NRC 030E, 2023 NRC Exam Scenario 5, Rev 0 SEG Page 16 of 30 TR-AA-230-1007-F14, Revision 0 Event # 4 1LT-462, Steam Generator Level Fails Low (BLUE)
AND D.2.2 Be in MODE 4 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> 0-SOP-IC-001 BLUE, Routine maintenance Procedure Removal of Safeguards or Protection Sensor from Service - Blue Channels
- 1. In cabinet C-115, PLACE the following bistable trip switches in the TRIP position (toggle switch up) and CHECK expected response. (BOP)
BISTABLE SWITCHES TO TRIP CABINET C-115 PROVING LAMP BISTABLE LAMP LIT ANNUNCIATOR LIT LO-LO LEVEL (L/462)
Lit Unless Failed Low S/G A LO-LO LEVEL LC462A 1C03 1E2 4-3 (2C03 2E2 4-5)
HIGH LEVEL (L/462)
Lit Unless Failed High S/G A HI LEVEL LC462B 1C03 1E2 1-3 (2C03 2E2 1-5)
LOW LEVEL (L/462)
Lit Unless Failed Low S/G A LO LEVEL LC462C 1C03 1E2 3-3 (2C03 2E2 3-5)
ROLE PLAY Booth Communications:
Respond to reports or direction to field operators as necessary.
SM Communications:
Respond to reports from crew members as required.
NOTES Continuation Criteria:
After the crew has stabilized plant conditions and assessed Technical Specifications, or at the discretion of the Lead Examiner, continue with the next event.
PBN LOI NRC 030E, 2023 NRC Exam Scenario 5, Rev 0 SEG Page 17 of 30 TR-AA-230-1007-F14, Revision 0 Event # 5 Large Break LOCA / SI Fails to Auto Actuate ACTION Booth: Insert Trigger 5 per Lead Instructor STUDENT
RESPONSE
CT1 Action Symptoms and Indications:
o 1CO4 1B 3-4, Pressurizer Pressure Low o 1CO4 1B 4-4, Pressurizer Low Pressure SI 1C04 Indications:
o RCS Pressure off scale low o PZR Level off scale low BOP/RO Performs EOP-0 Immediate actions Manually actuates SI and CI during immediate actions Performs EOP actions as directed SRO Implements EOP-0, Reactor Trip or Safety Injection Crew
- 1. Verify Reactor Trip (RO)
- 2. Verify turbine trip (RO)
Any SI annunciators - LIT Both trains of SI - ACTUATED; RNO: Manually actuate both trains of SI and Containment Isolation (depresses both SI actuation pushbuttons and both CI actuation pushbuttons at CO1)
CT1: Manually actuate SI Foldout Page #1: RCP Trip Criteria: If both conditions listed below occur, THEN trip both RCPs (RO)
RCS subcooling - LESS THAN [40°F] 31°F SI Pumps - AT LEAST ONE RUNNING AND CAPABLE OF DELIVERING FLOW Takes both 1P-1A/B, Reactor Coolant Pumps to STOP
- 5. Perform Attachment A, Automatic Action Verification, while continuing with this procedure. (BOP)
- a. Condenser steam dumps - AVAILABLE
- Place steam dump mode selector switch in MANUAL
- b. RCS Temperature RNO: Perform the following:
- 1) IF temperature is less than 547°F AND lowering, THEN perform
PBN LOI NRC 030E, 2023 NRC Exam Scenario 5, Rev 0 SEG Page 18 of 30 TR-AA-230-1007-F14, Revision 0 Event # 5 Large Break LOCA / SI Fails to Auto Actuate the following: control total feed flow.
a) Stop dumping steam b) IF cooldown continues, THEN control total feed flow Control feed flow to the SGs using 1AF-4000, 1AF-4001, 1FIC-4074A, and 1FIC-4014B, AFW to SG flow control valves c) IF cooldown continues, THEN isolate main steam lines Shut 1MS-2017/2018, Steam Generator A/B Main Steam Stop CV
- 11. Check if S/G are NOT faulted (RO)
- 12. Check if S/G tubes are NOT ruptured (RO)
RNO:Notify STA to MONITOR CSP Status per CSP-ST.0, CSF Status Trees Go to EOP-1, Loss of Reactor or Secondary Coolant ROLE PLAY Booth Communications:
Respond to reports or direction to field operators as necessary.
SM Communications:
Respond to reports from crew members as required.
NOTES Event # 6 Containment Accident Fan Fails to Auto Start ACTION Booth: None
PBN LOI NRC 030E, 2023 NRC Exam Scenario 5, Rev 0 SEG Page 19 of 30 TR-AA-230-1007-F14, Revision 0 Event # 6 Containment Accident Fan Fails to Auto Start STUDENT
RESPONSE
Symptoms / Indications Containment Accident Fan 1W-1D1 red indicating light - not lit BOP Performs EOP-0, Attachment A, Automatic Action Verification A1 - Verify feedwater isolation A2 - Verify containment isolation A3 - Verify ECCS Pumps RUNNING
- a. SI pumps - BOTH RUNNING
- b. RHR Pumps - BOTH RUNNING A4 - Verify service water pumps running A5 - Verify containment accident cooling units RUNNING; RNO: WHEN SI sequence is complete, THEN manually start fans. (Manually starts 1W-1D1)
A6 - Verify component cooling water pumps - ONLY ONE RUNNING A7 - Check if main steam lines can remain open A8 - Verify containment spray not required:
A9 - Verify ECCS Flow A10 - Verify AFW valve alignment - PROPPER EMERGENCY ALIGNMENT A11 - Verify proper ECCS valve alignment A12 - Check containment spray NOT ACTUATED A13 - Stop any boration via the blender in progress A14 - Ensure the Auxiliary building filter/exhaust fans - OPERATING A15 - Notify the STA to IMPLEMENT Status trees, Notify the SM of any equipment malfunctions previously noted.
A16 - Verify Service Water system alignment A17 - Check miscellaneous valves - SHUT A18 - Check Control Room ventilation A19 - Check cable spreading room ventilation system - OPERATING A20 - Check Computer Room ventilation system - OPERATING A21 - Check AFW recirc fans - ONE RUNNING A22 - Check Circ Water Pump House temperature less than 105°F A23 - Check G03/G04 switchgear room temperature less than 95°F A24 - Periodically check status of spent fuel cooling.
PBN LOI NRC 030E, 2023 NRC Exam Scenario 5, Rev 0 SEG Page 20 of 30 TR-AA-230-1007-F14, Revision 0 Event # 6 Containment Accident Fan Fails to Auto Start ROLE PLAY Booth Communications:
EOP-0, Att A communications:
o PAB AO: When directed to check rad waste service water valves SHUT at C-180, report the TV-LW61 and TV-LW62 are both SHUT o TH AO: When directed to check Circ Water Pump House temperature, wait 1 minute and report 76°F and stable.
o TH AO: When directed to check G03/G04 switchgear room temperature, wait 1 minute and report 80°F and stable.
Respond to reports or direction to field operators as necessary.
SM Communications:
Respond to reports from crew members as required.
NOTES Event # 7 Transfer to Containment Sump Recirculation ACTION Booth: Insert Trigger 7 and 9 when directed by the crew for EOP-1.3 field actions STUDENT
RESPONSE
BOP/RO Perform EOP actions as directed.
SRO Implements EOP-1, Loss of Reactor or Secondary Coolant Implements EOP-1.3, Transfer to Containment Sump Recirculation - Low Head Injection Crew EOP-1, Loss of Reactor or Secondary Coolant FOP 6: Containment Sump Recirculation Switchover Criteria IF either condition below is satisfied, THEN go to EOP-1.3, Transfer to Containment Sump Recirculation - Low Head Injection (SRO)
RWST Level - LESS THAN 60%
OR RCS pressure less than [450) 325 psig AND RHR flow greater than 550 gpm
PBN LOI NRC 030E, 2023 NRC Exam Scenario 5, Rev 0 SEG Page 21 of 30 TR-AA-230-1007-F14, Revision 0 Event # 7 Transfer to Containment Sump Recirculation CT2 actions start EOP-1.3, Transfer to Containment Sump Recirculation - Low Head Injection
Using RHR Flow and RCS Pressure indications, SRO determine to continue in EOP-1.3
- 3. Align CCW per Attachment A, local Alignment of Component Colling Water, while continuing with this procedure. (BOP or RO)
Will direct PAB AO to perform Attachment A of EOP-1.3.
Use the plant evacuation alarm and Gaitronics for the announcement
RNO Go to Step 6
- d. Observe CAUTION prior to Step 8 and go to Step 8
- 7. Monitor core cooling (RO)
- 9. Isolate component cooling flow to containment
- 10. Isolate component cooling flow to non-regenerative heat exchanger
- a. Check normal letdown - ISOLATED (RO)
- b. Place non-regen heat exchanger outlet temperature controller in manual and shut valve: 1HC-130 (RO)
- 11. Check Service Water pumps - SIX RUNNING (BOP)
- 12. Check service water supply ring header - CONTINOUS FLOWPATH ESTABLISHED (BOP)
- 13. Establish component cooling flow to RHR heat exchangers:
- a. Ensure component cooling pumps - AT LEAST ONE RUNNING (BOP)
- c. Start second component cooling pump (BOP)
- 15. Align SI test lines for recirculation
- a. Check containment spray discharge valves - AT LEAST ONE OPEN IN EACH TRAIN (BOP)
- b. Locally shut both SI test line return isolation valves:
(BOP or RO directs PAB AO) i 1SI-897A
PBN LOI NRC 030E, 2023 NRC Exam Scenario 5, Rev 0 SEG Page 22 of 30 TR-AA-230-1007-F14, Revision 0 Event # 7 Transfer to Containment Sump Recirculation ROLE PLAY Booth Communications:
When directed to perform Attachment A of EOP-1.3, insert Trigger 9. Report complete once all LOAs have inserted.
When directed to shut 1SI-897A and 1SI-897B, insert Trigger 7, report when valves are shut.
Respond to reports or direction to field operators as necessary.
SM Communications:
When CSF Status Trees are in effect and plant conditions are met, report to the SRO that CSF INTEGRITY RED path conditions exist.
Respond to reports from crew members as required.
NOTES Scenario Termination Terminate the scenario when the crew has established containment sump recirculation, or per Lead Evaluator.
NOTES Freeze the simulator Determine if the NRC has any follow up questions Save SBT Data (see sim setup instructions)
PBN LOI NRC 030E, 2023 NRC Exam Scenario 5, Rev 0 SEG Page 23 of 30 TR-AA-230-1007-F14, Revision 0 QUANTITATIVE ATTRIBUTES Malfunctions:
Before EOP Entry:
- Feed Pump failure
- Instrument failure After EOP Entry:
- Auto SI actuation failure
- Containment accident fan fail to auto start Abnormal Events:
- Feedwater System Malfunction
- Rapid Power Reduction
- Instrument Malfunction Major Transients:
- Large Break LOCA Critical Tasks:
- 1.
CT1 Manually initiate SI when required by EOP-0
- 2.
CT2 Transfer the suction of the RHR pumps to the Containment Sump prior to meeting loss of suction criteria Major Procedures:
AOP-2B AOP-17A AOP-24 EOP-0 EOP-1 EOP-1.3
PBN LOI NRC 030E, 2023 NRC Exam Scenario 5, Rev 0 SEG Page 24 of 30 TR-AA-230-1007-F14, Revision 0 CT1 Manually initiate SI when required by E-0
- Initiating Cue: The following indications:
o Indications of a large break LOCA inside containment o Reactor pressure lowering rapidly o Pressurizer Level lowering rapidly o Annunciator alarms o Rising containment pressures o No safety injection pumps running with valid initiation signals
- Performance Feedback: All of the following:
o Primary conditions will continue to degrade with ongoing plant conditions without safety injection o Manual initiation of SI will result in system actuation
- Success Path: At least one required train of safety injection actuated
- Measurable Performance Standard: Manually initiate Safety Injection prior to completion of EOP-0 Step 4.
- Safety Significance: If no operator action is taken, the reactor would be under LOCA conditions without cooling water injection, resulting in core damage.
PBN LOI NRC 030E, 2023 NRC Exam Scenario 5, Rev 0 SEG Page 25 of 30 TR-AA-230-1007-F14, Revision 0 CT2 Transfer the suction of the RHR pumps to the Containment Sump prior to meeting the loss of suction criteria
- Initiating Cue: The following indications:
o Lowering RWST level to less than 34%
o Containment Sump Level >38 o Indication of high injection flow rates during LOCA
- Performance Feedback: All of the following:
o Valve indication as transfer is made in EOP-1.3 o Continuing lowering RWST level until transition is made o Continuing rising containment sump levels
- Measurable Performance Standard: Manually align RHR for cold leg recirculation prior to meeting the loss of pump suction criteria provided in EOP-1.3.
- Safety Significance: If no operator action is taken, the running RHR pumps would lose their suction source resulting in loss of injection and cooling capabilities to the reactor core during LOCA conditions.
PBN LOI NRC 030E, 2023 NRC Exam Scenario 5, Rev 0 SEG Page 26 of 30 TR-AA-230-1007-F14, Revision 0 Booth Summary Event #1 Shift Control Room Recirculation Fans Action Booth: None Role Play Respond to reports or direction to field operators as necessary.
Event #2 1P-28A, Steam Generator Feed Pump Malfunction Action Role Play Event #3 Rapid Power Reduction Action Role Play Event #4 1LT-462, Steam Generator Level Fails Low (BLUE)
Action Role Play Event #5 Large Break LOCA / SI Fails to Auto Actuate Action Role Play Event #6 Containment Accident Fan Fails to Auto Start Action Role Play Booth Communications:
EOP-0, Att A communications:
o PAB AO: When directed to check rad waste service water valves SHUT at C-180, report the TV-LW61 and TV-LW62 are both SHUT o
TH AO: When directed to check Circ Water Pump House temperature, wait 1 minute and report 76°F and stable.
o TH AO: When directed to check G03/G04 switchgear room temperature, wait 1 minute and report 80°F and stable.
Respond to other reports or direction to field operators as necessary.
PBN LOI NRC 030E, 2023 NRC Exam Scenario 5, Rev 0 SEG Page 27 of 30 TR-AA-230-1007-F14, Revision 0 Event #7 Transfer to Containment Sump Recirculation Action Booth: None Role Play
PBN LOI NRC 030E, 2023 NRC Exam Scenario 5, Rev 0 SEG Page 28 of 30 TR-AA-230-1007-F14, Revision 0 SHIFT TURNOVER INFORMATION PLANT CONDITIONS:
UNIT 1 Time in core life (MWD/MTU):
9500 Reactor power (%):
65%
Boron concentration (ppm):
986 ppm Rod height, CBD @:
178 TECHNICAL SPECIFICATION ACTION CONDITIONS IN EFFECT:
TSAC Description Required Action & Completion Time EQUIPMENT OUT OF SERVICE:
- None.
PLANNED EVOLUTIONS:
- Switch Control Room Recirculation Fans.
TURNOVER INFORMATION:
- On line risk is GREEN.
- Today is Tuesday, day shift.
PBN LOI NRC 030E, 2023 NRC Exam Scenario 5, Rev 0 SEG Page 29 of 30 TR-AA-230-1007-F14, Revision 0 Pre-Scenario Procedure Checks Procedure OS1 1st Check 2nd Check AOP-2B AOP-17A AOP-24 EOP-0 EOP-1 EOP-1.3 Specific ARP/ARBs to be second checked - All Others first checked 1st Check 2nd Check
PBN LOI NRC 030E, 2023 NRC Exam Scenario 5, Rev 0 SEG Page 30 of 30 TR-AA-230-1007-F14, Revision 0 Post-Scenario Procedure Checks Procedure OS1 1st Check 2nd Check ARBs 1st Check 2nd Check RESET IC N/A Booth Cleared Exam Material Magnets Replaced P&IDs cleaned and replaced Red dots removed from alarm windows