ML21293A330
| ML21293A330 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 08/12/2021 |
| From: | Chuck Zoia NRC/RGN-III/DRS/OLB |
| To: | |
| Zoia C | |
| Shared Package | |
| ML20139A046 | List: |
| References | |
| Download: ML21293A330 (103) | |
Text
Appendix D Scenario Outline Form ES-D-1 Facility: __Point Beach___ Scenario No.: ______1______ Op-Test No.: __2021__
Examiners: ___________________________ Operators: _____________________________
Initial Conditions: _Reactor power is 28% for flux mapping. G03, EDG is out of service due to ____
_to maintenance with G04, EDG aligned. 1LT-426, PZR Level transmitter (Red) removed from____
_service.________________________________________________________________________
Turnover:_Raise power to 50% at 15% per hour per OP 1C, Startup to Power Operations.________
Critical Tasks:_CT-24, Energize At Least One Emergency Bus _____________________________
_CT-25, Manually Start SW Pump For EDG Cooling______________________________________
Event Malf. Event Event No. No. Type* Description R-RO Normal Up Power 1 N-BOP N-SRO R-BOP Single Dropped Rod C-RO 2
C-SRO 2019 Repeat TS-SRO C-BOP 1HC-478, SG B Atmospheric Steam Dump controller fails in auto, C-SRO valve fully opens, in manual will only close to 50%, requiring local 3 TS-SRO manual isolation valve operation New M-ALL Loss of AC Power to All Safeguards Buses 4 A Train EDG success path C-BOP P-32A/B SW Pumps do not Auto Start after Restoration of 'A' Train C-SRO EDG 5
New C-RO Multiple (4) Stuck Rods Post Trip, requires boration 6 C-SRO 2017 Repeat
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
SEG SIMULATOR EXERCISE GUIDE SITE: PBNP Revision #: 0 LMS ID: PBN LOI NRC 22E LMS Rev. Date:
SEG TITLE: 2021 NRC Exam Scenario 1 SEG TYPE: Training Evaluation PROGRAM: LOCT LOIT Other:
DURATION: 90 minutes Developed by: John Rogers Instructor/Developer Date Reviewed by: Jeff Hinze 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 TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 22E, 2021 NRC Exam Scenario 1, Rev 0 SEG Page 2 of 33 Facility: __Point Beach___ Scenario No.: ______1______ Op-Test No.: __2021__
Examiners: ___________________________ Operators: _____________________________
Initial Conditions: _Reactor power is 28% for flux mapping. G03, EDG is out of service due to ____
_to maintenance with G04, EDG aligned. 1LT-426, PZR Level transmitter (Red) removed from____
_service.________________________________________________________________________
Turnover: Raise power to 50% at 15% per hour per OP 1C, Startup to Power Operations.________
Critical Tasks:_CT-24, Energize At Least One Emergency Bus _____________________________
_CT-25, Manually Start SW Pump For EDG Cooling______________________________________
Event Malf. Event Event No. No. Type* Description R-RO Normal Up Power 1 N-BOP N-SRO R-BOP Single Dropped Rod C-RO 2
C-SRO 2019 Repeat TS-SRO C-BOP 1HC-478, SG B Atmospheric Steam Dump controller fails in auto, C-SRO valve fully opens, in manual will only close to 10%, requiring local 3 manual isolation valve operation TS-SRO New M-ALL Loss of AC Power to All Safeguards Buses 4
A Train EDG success path C-BOP P-32A/B SW Pumps do not Auto Start after Restoration of 'A' Train C-SRO EDG 5
New C-RO Multiple (4) Stuck Rods Post Trip, requires boration 6 C-SRO 2017 Repeat
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 22E, 2021 NRC Exam Scenario 1, Rev 0 SEG Page 3 of 33 SIMULATOR EXERCISE GUIDE REQUIREMENTS Terminal Given the site simulator and specific plant conditions, the students will Objective: be able to respond to various plant abnormal and emergency events, in accordance with site procedures and technical Specifications.
Enabling 1. None Objectives:
Prerequisites: 1. Simulator available
- 2. Students enrolled in Initial License Program Training 1. Floor Instructor as Shift Manager / Shift Technical Advisor Resources: 2. Simulator Booth Operator
- 3. Communicator
- 4. NRC Evaluators
References:
- 1. OP 1C, Startup to Power Operation
- 3. AOP-2A, Secondary Coolant Leak
- 4. AOP-6A, Dropped
- 5. AOP-24, response to Instrument Malfunction
- 6. EOP-0, Reactor Trip or Safety Injection
- 7. EOP-0.1, Reactor Trip Response
- 9. ECA-0.0, Loss of All AC Power
- 10. OM 3.7, AOP And EOP Procedure Usage For Response To Plant Transients
- 11. Technical Specifications Manual
- 12. Technical Requirements Manual Protected None Content:
Evaluation Simulator performance will be evaluated in accordance with Method: NUREG 1021 Operating None Experience:
Risk Significant Initiating Event with Core Damage Frequency:
Operator Actions: INIT-TSW - Loss of SW (1.45E-07 CDF) (8.87E-11 LERF)
LOOP - Loss of Offsite Power (2.51E-06 CDF)
HEP-SW-START - OPERATOR STARTS SW PUMP FROM CONTROL TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 22E, 2021 NRC Exam Scenario 1, Rev 0 SEG Page 4 of 33 ROOM (AFTER AC POWER RESTORATION UPDATE LOG: Indicate in the following table any minor changes or major revisions made to the material after initial approval.
PREPARER DATE
- DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR#
REVIEWER DATE Developed for the 2021 ILT NRC 0
Exam TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 22E, 2021 NRC Exam Scenario 1, Rev 0 SEG Page 5 of 33 OVERVIEW / SEQUENCE OF EVENTS OVERVIEW Initial conditions for the scenario are: Reactor power is stable at approximately 28%, Emergency Diesel Generator (EDG) G03 is out of service for maintenance with G04 aligned to 1A-06 and 2A-06, and 1LT-426 Pressurizer Level channel is removed from service.
Examinees will initiate a power ascension per OP-1C. The crew will then be required to respond to a dropped rod and an instrument failure per AOPs. The crew will also respond to a loss of all AC safeguards power, Service Water pump failures, and stuck control rods using emergency procedures.
The scenario will be terminated when the crew completes through Step 6 of EOP-0.1, Reactor Trip Response.
SEQUENCE OF EVENTS Event # Description
- 1. OP 1C Power Ascension The crew will raise reactor power approximately 3% to 5% utilizing the provided reactivity plan.
- 2. Dropped Rod - K9 Rod K9 will drop to the bottom of the core, causing automatic outward rod motion.
The crew will respond per AOP-6A, Dropped Rod, to stop outward rod motion and stabilize the plant.
The SRO will address Technical Specifications
- 3. 1HC-478, Loop B ADV Hand Controller, Fails High The S/G B ADV Controller fails high causing the associated atmospheric steam dump valve (ADV) to open.
The crew will respond per AOP-2A, Secondary Leak, and AOP-24, Response to Instrument Malfunction to isolate the B S/G ADV and stabilize the plant.
The SRO will address Technical Specifications.
- 4. Loss of AC Power to All Safeguards Buses The loss of Station Transformer 1X-04 and the failures of Emergency Diesel Generators to automatically restore safeguards power results in a loss of all AC safeguards power to Unit 1.
The crew will respond per ECA-0.0 to trip Unit 1 reactor and restore power to a safeguards bus.
TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 22E, 2021 NRC Exam Scenario 1, Rev 0 SEG Page 6 of 33
- 5. A Train Service Water Pumps Fail to Start Upon power restoration, A Train Service Water pumps will fail to automatically start.
The crew will start Service Water pumps to ensure adequate Service Water cooling flow per ECA-0.0.
- 6. Stuck Rods (4)
When the reactor is tripped, rods B6, B8, C5, and E11 will be stuck at their initial fully withdrawn positions.
The crew will respond by borating the RCS to ensure adequate shutdown margin per EOP-0.1, Reactor Trip Response.
Terminate the scenario when crew has completed Step 6 of EOP-0.1, Reactor Trip Response, or per Lead Evaluator.
TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 22E, 2021 NRC Exam Scenario 1, Rev 0 SEG Page 7 of 33 SIMULATOR SET-UP INSTRUCTIONS Perform simulator set up per the site specific Simulator Setup Checklist.
Check Action
- 1. Reset to IC-30
- 2. Perform Simulator Setup Checklist
- 3. Open schedule file. Z:\2021 ILT NRC Exam Simulator Files\ILT NRC Scenario 1
- 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 RO desk
- 9. Place reactivity sheets on RO desk
- 10. Guard the following:
G01, G02, G04 EDGs Place the following OOS:
G03 EDG 1LT-426 Pressurizer Level Place red dots on the G03 alarm and PZR Level:
C02 E 2-1 C02 E 2-2 1C04 1C 3-3
- 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.
TR-AA-230-1007-F14, Revision 0
SEG PBN LOI NRC 22E, 2021 NRC Exam Scenario 1, Rev 0 Page 8 of 33 BOOTH OPERATOR BRIEFING:
Review the scenario sequence, event triggers and expected field communications.
Z:/2021 ILT NRC Exam Simulator Files/NRC Scenario 1.sch At Time On Event Action Description Preloads / Initial Conditions 00:00:00 Insert malfunction MAL1DSG001B DIESEL G03 FAILURE TO START 00:00:00 Insert malfunction XMT1RCS007C to -15 1-LT426 PRZR NARROW RANGE LEVEL FIXED BIAS Event 2: Dropped Rod 1 Insert malfunction MAL1CRF002-K9 on event 1 ROD DROP K9 Event 3: SG B ADV Controller (HC-478) fails High 3 Insert malfunction CNH1PCS013E to 100.00000 on event 3 1-HC478 LOOP B ATM SD HAND CONTROLLER FIXED AUTO ONLY 4 Insert malfunction VLV1SGN009D to 0.10000 on event 4 1-MS-2015 SG B ATMOSPHERIC STM DMP CONTROL FAIL POSITION Insert remote LOA1SGN026 to 0 in 10 1MS-244 SG B ATMOS STM DMP INLET Event 4: Loss of AC 5 Insert malfunction MAL1EPS002 on event 5 LOSS OF LOW VOLTAGE STATION AUX TRANSFORMER X04 00:00:00 Insert malfunction BKR1DSG001 to Failasis 1-A5260 DIESEL GEN NO. G01 TO BUS 1-A05 00:00:00 Insert malfunction MAL1DSG007A EDG G01 FAILURE TO AUTOSTART 00:00:00 Insert malfunction BKR1DSG004 to Failasis 1-A5286 G04 TO 1A06 BRK 86 Event 5: SW Pumps DO not Auto Start 00:00:00 Insert malfunction BKR1SWS001 to Fail_Auto_Cl 1-B5210C P-32A SERVICE WATER PUMP CKTBKR 00:00:00 Insert malfunction BKR1SWS002 to Fail_Auto_Cl 1-B5211C P-32B SERVICE WATER PUMP CKTBKR 00:00:00 Insert malfunction BKR1SWS006 to Fail_Auto_Cl 2-B5234B P-32F SERVICE WATER PUMP CKTBKR Event 6: Stuck Rods Post-Trip 00:00:00 Insert malfunction MAL1CRF001-B6 to Non-Trippable STUCK ROD B6 00:00:00 Insert malfunction MAL1CRF001-B8 to Non-Trippable STUCK ROD B8 00:00:00 Insert malfunction MAL1CRF001-C5 to Non-Trippable STUCK ROD C5 00:00:00 Insert malfunction MAL1CRF001-E11 to Non-Trippable STUCK ROD E11 Insert remote LOA1CVC054 to 1.0000 in 5 1CV-350 BA TO CHG PP SUCT MOV 1-350 00:00:00 Event Z:/2021 ILT NRC Exam Simulator Files/NRC 1.evt Event file: Trigger 4 inserts when 1HC-478 is in MANUAL (x13i263m == 1)
PBN LOI NRC 22E, 2021 NRC Exam Scenario 1, Rev 0 SEG Page 9 of 33 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 OP 1C Power Ascension ACTION Booth: None BOP/RO STUDENT Perform actions as directed.
RESPONSE
SRO Implements OP 1C starting at Step 5.37.
Crew 5.37 Commence Load Escalation (Per the crews reactivity plan.)
5.37.1 ESTIMATE the amount of dilution/rod motion needed for desired load change, and REFER to PPCS Xenon program for timing estimates. (SRO directs; RO performs) 5.37.2 IF rate of load escalation is to be greater than or equal to 15% per hour, THEN CONTACT Chemistry for primary sampling requirements. (no actions needed) 5.37.3 PERFORM the following to begin raising load: (SRO directs, BOP performs)
- a. ENSURE EH Control in OPER AUTO, 1st Stage IN.
- b. ENSURE the Valve Position Limiter (VPL) is set to the desired position.
- c. SET Turbine Controls for desired ramp rate per table below:
% per Thumbwheel INITIAL Hour Setting or N/A 3 6 12 8 15 10 30 15 (The setting depends on the decision of the crew)
- d. ADJUST Turbine Setter to desired turbine load AND DEPRESS GO pushbutton. (BOP uses the up/down arrow buttons, in the Reference Control section of Turbine Control, to set the desired end point.)
5.38 Continuous Action During Power Increase 5.38.1 MAINTAIN controls in AUTO as practicable:
Blender controls (RO)
Turbine controls (BOP) 5.38.2 MAINTAIN Control Banks within the insertion, sequence, and overlap limits specified in the COLOR. LCO 3.1.6 (RO) 5.38.3 MAINTAIN Tavg within 1.5°F of Tref. (RO)
SET desired quantity on 1YIC-11A, Dilution Flow Counter SET desired flow rate on 1HC-111, Reactor Makeup Water Flow Controller TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 22E, 2021 NRC Exam Scenario 1, Rev 0 SEG Page 10 of 33 PLACE Reactor Makeup Mode Selector Switch in DILUTE ENSURE SHUT CV-110A, BA to Z-1 Blender Flow Control Valve PLACE Reactor Makeup Control Switch to START ENSURE Dilution Flow Counter functions properly upon start MONITOR system for proper response ROLE PLAY Booth Communications:
Respond to reports or direction to field operators as necessary.
SM Communications:
Brief the crew to maintain rod control in AUTO. Rod control may be taken to MANUAL to make adjustment to Tavg or AFD, but should be returned to AUTO following rod motion.
Direct the crew to proceed with power ascension as briefed.
NOTES Continuation Criteria:
After a power increase of approximately 3% to 5%, or at the discretion of the Lead Examiner, continue with the next event.
TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 22E, 2021 NRC Exam Scenario 1, Rev 0 SEG Page 11 of 33 Event # 2 Dropped Rod - K9 ACTION Booth: Insert TRIGGER 1 per Lead Evaluator Symptoms and Indications:
STUDENT Rod Bottom Light control rod K-9, Control Bank A
RESPONSE
Control rod K-9 IRPI at approximately 0 POWER RANGE CHANNEL DEVIATION (1C04 1A 3-3)
POWER RANGE ROD DROP (1C04 1A 4-5)
ROD BOTTOM ROD DROP (1C04 1A 1-4)
Power Range NIs drop to between 19% and 24%
BOP/RO Diagnoses the dropped rod and takes manual control of rods. (RO)
Suspends the load ramp if in progress. (SRO directs, BOP perform)
SRO Implements AOP-6A, Dropped Rod Crew (SRO directs)
- 1. Check Only One Rod Dropped (RO)
- 2. Check Main Turbine - ON LINE (BOP)
- 3. (IA) Place Control Rod Bank Selector Switch in - MANUAL (RO)
- 4. (IA) Check Tavg - TRENDING TO PROGRAM VALUE; RNO: Restore Tavg to program value by adjusting turbine load. (BOP)
This may be completed by either of b or c (as determined by the SRO):
- a. Determine the amount of load reduction needed.
- b. Select TURBINE MANUAL and use GV down pushbutton
- c. In OPER AUTO, set the reference setter to the desired value by using the Reference Control down and up buttons; then press GO.
- 6. Notify the following personnel: (SRO directs SM to make notifications) o Reactor Engineering o I&C Supervisor o Maintenance Supervisor
- 8. Check Axial Flux Difference - IN OPERATING BAND (RO)
- 9. Perform PBF-2513, Shutdown Margin For an Operating Reactor WITHIN 1 HOUR (Shift Manager discuss with SRO to hand off to U2 to perform)
- 10. Check Quadrant Power Tilt - LESS THAN 2%; RNO: Perform AOP-6H, Quadrant Power Tilt, while continuing with this procedure. (RO. AOP-6H may be handed off to Unit 2 to perform, but no actions due to initial power level)
- 11. Reset Dropped Rod Alarms on NIS Power Range Cabinets (BOP)
- 12. Reduce Reactor Power - TO LESS THAN OR EQUAL TO 75% WITHIN 2 HOURS OF DROPPED ROD (No actions required due to initial power level)
TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 22E, 2021 NRC Exam Scenario 1, Rev 0 SEG Page 12 of 33 Event # 2 Dropped Rod - K9
- 13. Check Changes in Reactor Power - LESS THAN 15% IN ANY 1 HOUR (RO)
- 14. Confirm Dropped Rod (RO)
- 15. Check Dropped Rod Confirmed (RO)
Note: The temperature transient caused by the dropped rod may result in an automatic letdown isolation. Letdown restoration per AOP-1D, CVCS Malfunction, is not required to meet the objectives of this scenario.
Assess Technical Specifications: (SRO performs)
CONDITION REQUIRED COMPLETION TIME ACTION TS 3.1.4 Rod Group Alignment Limits B. One rod not B.1.1 Verify SDM to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> within limits be within limits provided in COLR TS 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits (PZR Press 2205 psig)
A. One or more RCS A.1 Restore RCS 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> DNB parameters DNB not within limits. parameter(s) to within limit.
ROLE PLAY Booth Communications:
Respond to reports or direction to field operators as necessary.
SM Communications:
Respond to reports from crew members as required.
When SDM calculation called for, discuss with OS to pass it off to Unit 2 so Unit 1 can focus on the event.
NOTES Continuation Criteria:
After the crew has restored Tavg to program and address Technical Specifications, or at the discretion of the Lead Examiner, continue with the next event.
TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 22E, 2021 NRC Exam Scenario 1, Rev 0 SEG Page 13 of 33 Event # 3 1HC-478, Loop B ADV Hand Controller, Fails High ACTION Booth: Insert TRIGGER 3 per Lead Evaluator Symptoms and Indications:
STUDENT 1MS-2015, B ADV, indicating lights - red on, green off
RESPONSE
PPCS alarms Rising reactor power Lowering Tavg Lowering Pzr Level and Pressure BOP (IA) Diagnoses controller failure and attempt to shut 1MS-2015, Atmospheric Dump Valve, from the control room.
SRO Implements AOP-2A, Secondary Coolant Leak Crew (SRO directs)
AOP-2A, Secondary Coolant Leak
- 1. Determine Secondary Leakage Not Hazardous to Personnel or Equipment (BOP monitors)
Plant habitability Containment Pressure < 2 psig Safeguards bus fault Equipment Operability
Rx power 100% per NIs (RO)
SG levels stable of trending to 64% (BOP)
Feed pump suction pressure > 180 psig (BOP)
Condensate Pump motor current < 185 amps (BOP)
Note: Steps 4, and 6 through 10 are diagnostic steps to determine the source of the leak. These steps may be performed in any order. No actions
- 5. Check No Secondary Leakage to Atmosphere
- a. Steam Generator Safety Valves Shut (BOP may contact Security or the PAB AO)
- b. Steam Generator atmospheric steam dump valves shut
RNO: Perform the following: (SRO directs)
- 1) Manually shut valve(s) (BOP)
Place 1HC-478 to Manual Take manual potentiometer to full close Note valve position lights do not indicate fully closed
- 2) IF valve(s) will NOT shut, THEN locally shut associated isolation valve:
o 1MS-244 for 1MS-2015 (BOP directs AO)
Note: Steps 11 through 14 do not require any operator action.
TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 22E, 2021 NRC Exam Scenario 1, Rev 0 SEG Page 14 of 33 Event # 3 1HC-478, Loop B ADV Hand Controller, Fails High
- 15. Check Plant Shutdown and Cooldown Required (SRO)
RNO: Return to Procedure and Step in Effect Assess Technical Specifications: (SRO)
CONDITION REQUIRED COMPLETION TIME ACTION TS 3.7.4 Atmospheric Dump Valve (ADV) Flowpath A. One required A. 1 Restore 7 days ADV flowpath required ADV inoperable flowpath to OPERABLE status.
ROLE PLAY Booth Communications:
PAB AO: 5 minutes after inserting trigger 3, or 2 minutes after being directed to investigate, report flow noise at the Unit 1 B Atmospheric Dump Valve.
PAB AO: If asked, after the crew attempts to shut the B ADV from the CR, report that 1MS-2015 is 10% OPEN and not moving.
PAB AO: When directed, use LOA1SGN026 to SHUT 1MS-244, Isolation for 1MS-2015, as directed by the crew. Report that flow noise has stopped when 1MS-244 is shut.
PAB AO: If asked, report that all S/G Safety Valves are shut.
Respond to other reports or direction to field operators as necessary.
SM Communications:
Respond to reports from crew members as required.
If requested, obtain Main Steam P&ID for the crew. (#51)
NOTES Continuation Criteria:
After the crew isolates the B ADV and assesses Technical Specifications, or at the discretion of the Lead Examiner, continue with the next event.
TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 22E, 2021 NRC Exam Scenario 1, Rev 0 SEG Page 15 of 33 Event # 4 Loss of AC Power to All Safeguards Buses ACTION Booth: Insert TRIGGER 5 per Lead Evaluator STUDENT Symptoms and Indications:
RESPONSE Dimming of lights in the Control Room UNIT 1 4.16 KV BUS UNDER VOLTAGE (C02D 1-4)
UNIT 1 480 V BUS UNDER VOLTAGE (C02D 2-1) 13.8 KV MAIN OR TIE BREAKER TRIP (C02E 2-8)
BOP Diagnoses loss of AC power to both trains of safeguards busses and performs immediate actions of ECA-0.0, Loss of All AC Power.
SRO Implements ECA-0.0, Loss of All AC Power Conditions for CT-24 event start Crew (ECA-0.0) (SRO directs) here 1. Verify Reactor Trip (RO)
Reactor Trip and By-Pass Breakers - OPEN RNO: Manually trip reactor (RO)
- 2. Verify Turbine Trip (RO)
Places 1P-1A and 1P-1B handswitches in STOP.
- b. Place steam dump mode control - MANUAL (BOP)
- a. PZR PORVs - BOTH SHUT
- b. Letdown orifice outlet valves - SHUT
- e. RCS Sample valves - SHUT (BOP) 1SC-966A, PZR Steam Space sample containment isolation valve 1SC-966B, PZR liquid space sample containment isolation valve 1SC-966C, RCS hot leg sample containment isolation valve.
- f. Head vent system - ENERGIZED; RNO: Go to Step 5 (RO)
Perform the following: (BOP)
PBN LOI NRC 22E, 2021 NRC Exam Scenario 1, Rev 0 SEG Page 16 of 33 Event # 4 Loss of AC Power to All Safeguards Buses
- 6. TRY TO RESTORE POWER TO ANY SAFEGUARDS BUS (BOP)
BOP or RO may call TH AOs to investigate EDGs (G01 fails to start, can be manually started but will not close onto bus 1A-05; G02 is running; G03 is OOS; G04 is running but fails to close onto bus 1A-06)
- a. Emergency Diesel Generators - ALL RUNNING
- a. RNO: Try to start non-running EDGs
- 1) Ensure diesel mode selector switch in AUTO
- 2) Place control switch to START (G-01)
- 3) Ensure generator field flash occurs
- 4) Ensure green READY TO LOAD light is energized
- 5) IF No diesel is running, THEN Go to Step 10
- b. AC Safeguards buses - AT LEAST ONE TRAIN ENERGIZED
- b. RNO: IF NO 4160v SAFEGUARDS BUS is energized, THEN Go to Step 7
- 7. Restore Power to A Safeguards Bus: (BOP)
- a. Check G RUNNING
- 1) IF G-01 is running AND breaker 1A52-60, G-01 to Bus 1A-05 Breaker, is NOT closed, THEN perform the following:
a) Ensure 1A52-57, 1A-03 to 1A-05 Bus Tie Breaker, is open.
b) Try to auto close breaker by placing control switch to trip position then release.
c) IF breaker will NOT auto close, THEN perform the following:
- 1. Place Mode Selector switch in EXERCISE.
- 2. Turn sync switch ON
- 3. At C-02, manually CLOSE breaker control switch.
- 4. Turn sync switch OFF.
d) IF 1A-05 and 1B-03 are energized, THEN Go to Step 9.
- a. RNO: Check G RUNNING
- 2) IF G-02 is running AND 1A-05 is still NOT energized, THEN perform the following:
a) Ensure 1A52-57, 1A-03 to 1A-05 bus tie breaker is OPEN.
b) Ensure 1A52-60, G-01 to 1A-05 breaker, is OPEN and in PULLOUT.
CT-24 action. c) (CT) Unlock (Key 43) and place 1A52-66, G-02 to Conditions for 1A-05 breaker control switch in auto. (Energizes CT-25 event start 1A-05) here e) IF 1A-05 and 1B-03 are energized, THEN Go to Step 9.
- 9. (or Step 46 per FOP) Verify One Train of Safeguards Bus Energized (subsequent steps listed below in Event #5) (BOP)
TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 22E, 2021 NRC Exam Scenario 1, Rev 0 SEG Page 17 of 33 Event # 4 Loss of AC Power to All Safeguards Buses ROLE PLAY Booth Communications:
TH AO: If directed to investigate G-01 failure to start, wait 2 minutes and report all conditions appear normal for G-01.
TH AO: If directed to investigate output breakers for G-01 and/or G-04 failure to close, wait 2 minutes and report that conditions appear normal locally.
TH AO: If directed to investigate the 1X-04 lockout, wait 3 minutes and report there is no apparent cause locally.
Respond to other reports or direction to field operators as necessary.
SM Communications:
Respond to reports from crew members as required.
NOTES TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 22E, 2021 NRC Exam Scenario 1, Rev 0 SEG Page 18 of 33 Event # 5 A Train Service Water Pumps Fail to Start ACTION Booth: None STUDENT Symptoms and Indications:
RESPONSE SW Header pressure, north and south, approximately 30 psig NORTH OR SOUTH SERVICE WATER HEADER PRESSURE LOW (C01A 3-5) 1P-30A OR B (2P-30A OR B) CIRC PUMPS COOLING WATER FLOW LOW (C01A 3-7 and 4-7)
G-01 (G-02) EMER DIESEL COOLER LOW FLOW (C02D 3-6 and C02F 3-1)
BOP Starts Service Water pumps to restore SW system pressure.
SRO Implements ECA-0.0, Loss of ALL AC Power Crew
- 9. (or Step 46 per FOP) Verify One Train of Safeguards Bus Energized (BOP)
BOP or RO may call TH AOs to investigate SW Pumps and their breakers (1B-03, 1B-04, 2B-04, and 2B-03)
- a. AC Safeguards buses - AT LEAST ONE TRAIN ENERGIZED
- b. Monitor running EDG status
- c. Service Water header pressure - GREATER THAN OR EQUAL TO
- c. CT-25 action 50 psig.
- c. (CT) RNO: Manually start pumps and align valves as necessary to establish service water header pressure greater than or equal to 50 psig.
Place control switch for P-32A, P-32B, and/or P-32F to start to raise pressure greater than 50 psig. Starting one pump should be adequate to restore header pressure. (P-32C has no power.)
- e. Return to procedure and step in effect and implement CSPs as necessary.
ROLE PLAY Booth Communications:
Respond to reports or direction to field operators as necessary.
If asked, all pumps are ready for start. Also, all pumps started are sat.
SM Communications:
Respond to reports from crew members as required.
TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 22E, 2021 NRC Exam Scenario 1, Rev 0 SEG Page 19 of 33 Event # 5 A Train Service Water Pumps Fail to Start NOTES TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 22E, 2021 NRC Exam Scenario 1, Rev 0 SEG Page 20 of 33 Event # 6 Stuck Rods (4)
ACTION Booth: None Symptoms and Indications:
STUDENT Control Rods B6 and B8, in Shutdown Bank A, and C5 and E11, in Control RESPONSE Bank A at 225 steps on IRPIs B6, B8, C5, and E11 rod bottom lights NOT LIT RO Recognize not all rods fully inserted, uses backup indications to verify the reactor is tripped.
SRO Implements EOP-0, Reactor Trip or Safety Injection and EOP-0.1, Reactor Trip
Response
Crew EOP-0, Reactor Trip or Safety Injection (SRO directs)
- 1. Verify Reactor Tripped; RNO: Manually trip reactor. (RO performs since not all rods on the bottom)
- 2. Verify Turbine Trip (RO)
- a. Check safeguards buses - At least one train ENERGIZED
- b. Check safeguards buses - All ENERGIZED; RNO: Try to restore power to de-energized buses while continuing with this procedure.
(Shift Manager will discuss with SRO having Unit 2 restore power to B Train using the AOP-18 and 19 procedures.)
- a. Any SI annunciators - LIT No lights lit
IF SI is not required, THEN perform the following:
- 2) Go to EOP-0.1, Reactor Trip Response.
Note: The crew may manually actuate SI/CI based on plant conditions. The steps for this alternate flow-path are listed below as Event 6a.
EOP-0.1, Reactor Trip Response (SRO directs)
With NO RCPs running, Check RCS WR Cold Leg temp stable at or trending to 547ºF (RO)
- 2. Check feedwater status
- b. Transfer feedwater control to bypass regulating valves: (BOP) o Check main feedwater pumps - AT LEAST ONE RUNNING TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 22E, 2021 NRC Exam Scenario 1, Rev 0 SEG Page 21 of 33 Event # 6 Stuck Rods (4) o Control feedwater flow using regulating bypass valves:
o Maintain both S/G levels - BETWEEN 33% and 63%.
o Reset Loss of Feedwater Turbine Trip o Stop any running AFW pumps.
- 3. Verify all control rods - FULLY INSERTED (RO)
RNO: IF two or more control rods are NOT fully inserted, THEN initiate emergency boration:
- b. Perform the following to adjust charging flow: (RO)
- 1) Control charging pump speed as necessary to maintain flow GREATER THAN OR EQUAL TO 60 gpm.
Places AUTO Charging Pump in MANUAL and dials manual pot to achieve 60 gpm
- 2) Control charging flow as necessary to maintain labyrinth seal P GREATER THAN 20 inches.
Manipulates 1HC-142 dial to maintain > 20 inches on Lab Seal DP.
- c. Start one boric acid transfer pump (RO)
- d. Open emergency borate valve: 1CV-350. (No power to open valve)
Evaluators note: If the crew decides to have the PAB AO locally open 1CV-350, steps e. and f. apply. If the crew does not locally open the valve and continues with the RNO column, steps e. and f.
have no actions.
- e. Borate 2825 gallons for each control rod not fully inserted. (11,300 gallons)
- f. WHEN emergency boration is complete, THEN control charging as necessary to establish desired charging flow.
- g. IF emergency boration can NOT be established, THEN perform boration per OP-5B while continuing with this procedure. (RO)
RO may direct the PAB AO to locally open 1CV-350
- a. Determine desired output concentration.
- b. Set 1HC-111, RMUW Flow Control, to desired flowrate and in AUTO
- c. Set 1HC-110, Boric Acid Flow Control to desired flowrate and in AUTO
- e. Place Makeup Mode Selector to AUTO
- f. Place Makeup Control Switch to START
- g. Monitor VCT level and ensure automatic operation.
- 4. Check PZR level control
- a. PZR Level - GREATER THAN 12%. (RO verifies)
- b. Charging - IN SERVICE; RNO: Place charging in service. (RO) o Ensure RCS cold leg normal charging isolation valve is open:
1CV-1298. (valve is open but with no power for indication) o IF no charging pumps are running AND component cooling water flow to any RCP thermal barrier is lost, THEN locally TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 22E, 2021 NRC Exam Scenario 1, Rev 0 SEG Page 22 of 33 Event # 6 Stuck Rods (4) shut affected RCP seal injection throttle valve before starting charging pumps.
o Start charging pumps to establish at least one running.
Place handswitch to START and hold, or START and release then START again (for the VFD logic) o Start additional charging pumps as necessary to establish desired charging flow.
Dials manual pot to achieve desired flow o Maintain labyrinth seal P greater than 20 inches. 1HC-142 Manipulates 1HC-142 dial to maintain > 20 inches on Lab Seal DP.
- c. Letdown - IN SERVICE; RNO WHEN PZR level is greater than 12%,
THEN place letdown in service: (RO) o Open letdown line containment isolation valves 1CV-371 and 1CV-371A o Open RCS cold leg letdown isolation valve. 1RC-427 o Ensure component cooling flow to non-regenerative heat exchanger is established. 1HC-130 o Ensure charging flow is at least 21 gpm o Adjust backpressure as necessary and open letdown isolation valves to establish desired letdown flow.
Manipulates 1CV-135 to achieve desired backpressure Opens one of the Letdown Orifice Valves, 1CV 200A/B/C
- d. PZR Level - TRENDING TO 20% (RO)
ROLE PLAY Booth Communications:
PAB AO: If directed to locally open 1CV-350, wait 2 minutes, use LOA1CVC054 to open 1CV-350, report when complete.
Respond to reports or direction to field operators as necessary.
SM Communications:
Respond to reports from crew members as required.
When EOP-0 directs trying to restore power to deenergized buses, discuss with the SRO having Unit 2 restore power with the AOP-18 and AOP-19 procedures.
NOTES TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 22E, 2021 NRC Exam Scenario 1, Rev 0 SEG Page 23 of 33 Event # 6a Stuck Rods (4) - Alternate Procedure Path ACTION Booth: None Symptoms and Indications:
STUDENT B6, B8, C5, and E11 rod bottom lights NOT LIT
RESPONSE
RO Recognize not all rods fully inserted, uses backup indications to verify the reactor is tripped.
SRO Implements EOP-0, Reactor Trip or Safety Injection and EOP-1.1, SI Termination Crew EOP-0, Reactor Trip or Safety Injection (SRO directs)
- 5. Perform Attachment A, Automatic Action Verification, while continuing with this procedure. (BOP)
- 11. Check if S/G are NOT faulted (RO)
- 12. Check if S/G tubes are NOT ruptured (RO)
- a. RCS Subcooling based on core exit thermocouples - GREATER THAN 37°F
- b. Secondary Heat Sink:
o Level in at least one S/G - GREATER THAN 33%
OR o Total feed flow to S/Gs - GREATER THAN OR EQUAL TO 275 gpm
- c. RCS Pressure:
Pressure - GREATER THAN 1725 psig AND Pressure - STABLE OR RISING
- b. PZR Level - GREATER THAN 11%
A1 - Verify feedwater isolation A2 - Verify containment isolation A3 - Verify ECCS Pumps RUNNING
- a. SI pumps - BOTH RUNNING
- b. RHR Pumps - BOTH RUNNING; TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 22E, 2021 NRC Exam Scenario 1, Rev 0 SEG Page 24 of 33 Event # 6a Stuck Rods (4) - Alternate Procedure Path 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 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 105F A23 - Check G03/G04 switchgear room temperature less than 95F A24 - Periodically check status of spent fuel cooling.
EOP-1.1, SI Termination (SRO Directs)
- 2. Reset isolation and lockout signals (BOP)
Containment isolation 1B03 and 1B04 non-safeguards equipment lockouts
- 3. Establish Instrument Air to containment (BOP)
- b. Open instrument air containment isolation valves one at a time:
IA 3047 IA-3048
- 4. Check if charging flow has been established (RO)
- a. Stop both SI pumps and place in auto
- c. Stop both RHR pumps and place in auto
- 7. Check if containment spray should be stopped (BOP)
- a. Containment spray pumps - ANY RUNNING; RNO: Go to Step 8
- 8. Verify All Control Rods - FULLY INSERTED (RO)
RNO: IF two or more control rods are NOT fully inserted, THEN initiate emergency boration:
- b. Establish maximum charging flow: (RO)
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PBN LOI NRC 22E, 2021 NRC Exam Scenario 1, Rev 0 SEG Page 25 of 33 Event # 6a Stuck Rods (4) - Alternate Procedure Path
- 1) Ensure all available charging pumps are operating.
- 2) Manually control charging pump speed, limit charging flow to <140 gpm.
- 3) Maintain labyrinth seal P GREATER THAN 20 inches.
- 4) Fully open charging flow control valve - 1HC-142.
- c. Start one boric acid transfer pump (RO)
- d. Open emergency borate valve: 1CV-350. (No power to open valve)
Evaluators note: If the crew decides to have the PAB AO locally open 1CV-350, steps e. and f. apply. If the crew does not locally open the valve and continues with the RNO column, steps e. and f.
have no actions.
- e. Borate 2825 gallons for each control rod not fully inserted. (11,300 gallons)
- f. WHEN emergency boration is complete, THEN control charging as necessary to establish desired charging flow.
- g. IF emergency boration can NOT be established, THEN perform boration per OP-5B while continuing with this procedure. (RO)
RO may direct the PAB AO to locally open 1CV-350
- a. Determine desired output concentration.
- b. Set 1HC-111, RMUW Flow Control, to desired flowrate and in AUTO
- c. Set 1HC-110, Boric Acid Flow Control to desired flowrate and in AUTO
- e. Place Makeup Mode Selector to AUTO
- f. Place Makeup Control Switch to START
- g. Monitor VCT level and ensure automatic operation.
TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 22E, 2021 NRC Exam Scenario 1, Rev 0 SEG Page 26 of 33 Event # 6a Stuck Rods (4) - Alternate Procedure Path 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 76F and stable.
o TH AO: When directed to check G03/G04 switchgear room temperature, wait 1 minute and report 80F and stable.
PAB AO: If directed to locally open 1CV-350, wait 2 minutes, use LOA1CVC054 to open 1CV-350, report when complete.
Respond to reports or direction to field operators as necessary.
SM Communications:
Respond to reports from crew members as required.
When EOP-0 directs trying to restore power to deenergized buses, discuss with the SRO having Unit 2 restore power with the AOP-18 and AOP-19 procedures.
NOTES Scenario Termination Terminate the scenario when the crew has completed Step 4 of EOP-0.1, (alternate path: Step 8 of EOP-1.1), or per Lead Evaluator.
Freeze the simulator NOTES Determine if the NRC has any follow up questions Save SBT Data (see sim setup instructions)
TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 22E, 2021 NRC Exam Scenario 1, Rev 0 SEG Page 27 of 33 QUANTITATIVE ATTRIBUTES Malfunctions:
Before EOP Entry:
Dropped rod (K9) 1HC-478 Loop B ADV controller fails high After EOP Entry:
A train Service Water pumps fail to auto start 4 stuck rods Abnormal Events:
Dropped Rod Secondary Coolant leak to atmosphere via ADV Major Transients:
Loss of All AC to Safeguards Buses Critical Tasks:
- 1. CT-24 Energize at least one emergency bus
- 2. CT-25 Manually start service water pumps for EDG cooling Major Procedures:
AOP-6A AOP-1D (potential) AOP-2A AOP-24 (potential)ECA-0.0 EOP-0 EOP-0.1 TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 22E, 2021 NRC Exam Scenario 1, Rev 0 SEG Page 28 of 33 CT-24 Energize at least one AC emergency bus Critical Task:
Energize at least one AC emergency bus prior to placing safeguards equipment switches in pull-out.
Plant Conditions:
Reactor trip Station blackout At least one EDG can be connected to an AC emergency bus Cues:
Indication and/or annunciation that all AC emergency buses are de-energized Bus energized lamps extinguished Circuit breaker position Bus voltage EDG status Performance Indicator:
Manipulation of controls as required to energize at least one ac emergency bus Bus energized lamp(s) illuminated Circuit breaker position lamps indicate closed Bus voltage indication shows nominal voltage present Feedback:
Indication that at least one ac emergency bus is energized Safeguards equipment sequences onto the energized bus EDG status Basis:
SAFETY SIGNIFICANCE -- Failure to energize an ac emergency bus constitutes misoperation or incorrect crew performance in which the crew does not prevent degraded emergency power capacity. Failure to perform the critical task also results in needless degradation of any barrier to fission product release, specifically of the RCS barrier at the point of the RCP seals. In this case, at least one ac emergency bus can be energized from the control room. Failure to perform the critical task means that RCS inventory lost through the RCP seals cannot be replaced. It also means that the RCP seals remain without cooling and gradually deteriorate. As the seals deteriorate the rate of RCS inventory loss increases.
TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 22E, 2021 NRC Exam Scenario 1, Rev 0 SEG Page 29 of 33 CT-25 Manually start Service Water pump for EDG cooling Critical Task:
Manually start service water pump(s) such that the EDG does not fail due to damage from overheating.
Plant Conditions:
Station blackout with subsequent restoration of ac power from one EDG SW pumps aligned to provide cooling for the running EDG fail to start automatically when the associated ac emergency bus is reenergized by the EDG An SW pump aligned to provide cooling for the running EDG can be started, provided that manual action is taken as necessary All other EDGs inoperable Cues:
Indication and/or annunciation that one ac emergency bus is energized by an EDG
- Circuit breaker position lamps indicate breaker closed
- Bus voltage indication shows nominal voltage present
- EDG status AND Indication and/or annunciation that no SW pump is running
- Control switch indication that the circuit breakers or contactors for all SW pumps are open
- SW header pressure indicator reads < 50 psig Performance Indicator:
Manipulation of controls as required to start the SW pump(s) powered from the ac emergency bus energized by the EDG Control switch indication that the circuit breaker or contactor for a SW pump aligned to supply cooling water to the running EDG is closed Feedback:
Indication and/or annunciation that a SW pump is running, aligned to supply cooling water to the running EDG SW low flow condition clear (G-02 Emerg Diesel Cooler Low Flow alarm clear)
SW low pressure condition clear (SW Header Pressure Low alarm clear)
Basis:
SAFETY SIGNIFICANCE -- Failure to manually start the SW pump under the postulated plant conditions means that the EDG is running without SW cooling. Running the EDG without SW cooling leads to a high-temperature condition that can result in EDG failure due to damage caused by engine overheating. Under the postulated plant conditions, the running EDG is the only operable EDG. Thus, failure to perform the critical task constitutes misoperation or incorrect crew performance in which the crew does not prevent degraded emergency power capacity.
TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 22E, 2021 NRC Exam Scenario 1, Rev 0 SEG Page 30 of 33 Booth Summary Event #1 OP-1C Power Ascension Action Booth: None Role Play Respond to reports or direction to field operators as necessary.
Event #2 Dropped Rod Action Booth: Insert TRIGGER 1 per Lead Evaluator Role Play Respond to reports or direction to field operators as necessary.
Event #3 B ADV Stuck Open Action Booth: Insert TRIGGER 3 per Lead Evaluator Trigger 4 inserts when 1HC-478 is placed in MANUAL.
Role Play PAB AO: 5 minutes after inserting trigger 3, or 2 minutes after being directed to investigate, report flow noise at the Unit 1 B Atmospheric Dump Valve.
PAB AO: If asked, after the crew attempts to shut the B ADV from the CR, report that 1MS-2015 is 10% OPEN and not moving.
PAB AO: When directed, use LOA1SGN026 to SHUT 1MS-244, Isolation for 1MS-2015, as directed by the crew. Report that flow noise has stopped when 1MS-244 is shut.
PAB AO: If asked, report that all S/G Safety Valves are shut.
Respond to other reports or direction to field operators as necessary.
Event #4 Loss of All AC Safeguards Power Action Booth: Insert TRIGGER 5 per Lead Evaluator Role Play TH AO: If directed to investigate G-01 failure to start, wait 2 minutes and report all conditions appear normal for G-01.
TH AO: If directed to investigate output breakers for G-01 and/or G-04 failure to close, wait 2 minutes and report that conditions appear normal locally.
TH AO: If directed to investigate the 1X-04 lockout, wait 3 minutes and report there is no apparent cause locally.
Respond to other reports or direction to field operators as necessary.
Event #5 A Train Service Water Pumps Fail to Auto Start Action Booth: None Role Play Respond to reports or direction to field operators as necessary.
Event #6 Stuck Rods (4)
Action Booth: None Role Play PAB AO: If directed to locally open 1CV-350, wait 2 minutes, use LOA1CVC054 to open 1CV-350, report when complete.
Respond to reports or direction to field operators as necessary.
TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 22E, 2021 NRC Exam Scenario 1, Rev 0 SEG Page 31 of 33 SHIFT TURNOVER INFORMATION PLANT CONDITIONS:
UNIT 1 Time in core life (MWD/MTU): 1500 Reactor power (%): 28%
Boron concentration (ppm): 1786 ppm Rod height, CBD @: 141 TECHNICAL SPECIFICATION ACTION CONDITIONS IN EFFECT:
TSAC Description Required Action & Completion Time U1 3.3.1.A/K RPS one channel inoperable 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 /> EQUIPMENT OUT OF SERVICE:
G03 Emergency Diesel Generator for maintenance.
1LT-426 Pressurizer Level Transmitter.
PLANNED EVOLUTIONS:
Power ascension per OP 1C, Startup to Power Operation. Startup is following a short forced outage. The crew has been maintaining the current power for about two hours for flux mapping.
TURNOVER INFORMATION:
G04 Emergency Diesel Generator is aligned to both 1A06 and 2A06 4160 Safeguards Busses.
On line risk is GREEN.
Today is Tuesday, day shift.
TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 22E, 2021 NRC Exam Scenario 1, Rev 0 SEG Page 32 of 33 Pre-Scenario Procedure Checks Procedure SRO st nd 1 Check 2 Check P&ID #51 AOP-1D AOP 2A AOP 6A AOP 6H AOP 24 EOP 0 EOP-0.1 EOP-1.1 ECA-0.0 Specific ARP/ARBs to be second checked - All Others first checked st nd 1 Check 2 Check 1C04 1A 1-5 1C04 1A 1-7 1C04 1A 3-3 1C04 1A 4-5 1C03 1E2 1-2 1C03 1E2 1-5 TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 22E, 2021 NRC Exam Scenario 1, Rev 0 SEG Page 33 of 33 Post-Scenario Procedure Checks Procedure SRO st nd 1 Check 2 Check AOP-1D AOP 2A AOP 6A AOP 6H AOP 24 EOP 0 EOP-0.1 EOP-1.1 ECA-0.0 st nd 1 Check 2 Check 1C04 1A 1-5 1C04 1A 1-7 1C04 1A 3-3 1C04 1A 4-5 1C03 1E2 1-2 1C03 1E2 1-5 RESET IC N/A Booth Cleared Exam Material Magnets Replaced Alarm window dots removed.
P&IDs cleaned and replaced TR-AA-230-1007-F14, Revision 0
Appendix D Scenario Outline Form ES-D-1 Facility: __Point Beach___ Scenario No.: ______2______ Op-Test No.: __2021__
Examiners: ___________________________ Operators: _____________________________
Initial Conditions: _0% power Mode 2. G02, EDG is OOS with G01, EDG is aligned, 1W-3A, ______
_Containment Shroud Fan OOS, 1PT-949, Containment Pressure transmitter removed from service.
Turnover:_A plant up power to the POAH is planned per OP 1B, Reactor Startup ________________
Critical Tasks:_CT-5, Manually Start At Least One Low-Head ECCS Pump _____________________
_CT-36, Transfer to Cold Leg Recirculation ______________________________________________
Event Malf. Event Event No. No. Type* Description Diesel High particulate reported 1 TS-SRO NEW R-RO 2 Raise Power to POAH N-SRO P-32A, Service Water Pump Trips, crew manually starts a standby C-BOP service water pump to restore system pressure.
3 C-SRO TS-SRO 2017 Repeat 1P-1B RCP thrust bearing failure/vibrations requiring manual C-RO reactor trip (degradation of flow or a trip of the pump) 4 C-SRO NEW Reactor Trip breakers fail to auto open and buttons on 1C04 are C-RO unsuccessful (C01 still works) 5 C-SRO 2017 Repeat 6 M-ALL LBLOCA RHR Pump Failures. 1P-10B RHR pump trips, 1P-10A RHR pump C-RO fails to auto start.
7 C-SRO 2017 Repeat
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
SEG SIMULATOR EXERCISE GUIDE SITE: PBNP Revision #: 0 LMS ID: PBN LOI NRC 23E LMS Rev. Date:
SEG TITLE: 2021 NRC Exam Scenario 2 SEG TYPE: Training Evaluation PROGRAM: LOCT LOIT Other:
DURATION: 90 minutes Developed by: John Rogers Instructor/Developer Date Reviewed by: Jeff Hinze 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 TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 23E, 2021 NRC Exam Scenario 2, Rev 0 SEG Page 2 of 34 Facility: __Point Beach___ Scenario No.: ______2______ Op-Test No.: __2021__
Examiners: ___________________________ Operators: _____________________________
Initial Conditions: _0% power Mode 2. G02, EDG is OOS with G01, EDG is aligned, 1W-3A, ______
_Containment Shroud Fan OOS, 1PT-949, Containment Pressure transmitter removed from service.
Turnover: A plant up power to the POAH is planned per OP 1B, Reactor Startup ________________
Critical Tasks:_CT-5, Manually Start At Least One Low-Head ECCS Pump _____________________
_CT-36, Transfer to Cold Leg Recirculation ______________________________________________
Event Malf. Event Event No. No. Type* Description TS-SRO Diesel High particulate reported 1
NEW R-RO Raise Power to POAH 2
N-SRO C-BOP P-32A, Service Water Pump Trips, crew manually starts a standby C-SRO service water pump to restore system pressure.
3 TS-SRO 2017 Repeat C-RO 1P-1B RCP thrust bearing failure/vibrations requiring manual C-SRO reactor trip (degradation of flow or a trip of the pump) 4 NEW C-RO Reactor Trip breakers fail to auto open and buttons on 1C04 are C-SRO unsuccessful (C01 still works) 5 2017 Repeat 6 M-ALL LBLOCA C-RO RHR Pump Failures. 1P-10B RHR pump trips, 1P-10A RHR pump C-SRO fails to auto start.
7 2017 Repeat
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 23E, 2021 NRC Exam Scenario 2, Rev 0 SEG Page 3 of 34 SIMULATOR EXERCISE GUIDE REQUIREMENTS Terminal Given the site simulator and specific plant conditions, the students will Objective: be able to respond to various plant abnormal and emergency events, in accordance with site procedures and technical Specifications.
Enabling 1. None Objectives:
Prerequisites: 1. Simulator available
- 2. Students enrolled in Initial License Program Training 1. Floor Instructor as Shift Manager / Shift Technical Advisor Resources: 2. Simulator Booth Operator
- 3. Communicator
- 4. NRC Evaluators
References:
- 1. OP 1B, Reactor Startup
- 2. OP 1C, Startup to Power Operation Unit 1
- 3. OP 5E, Establishing and Securing Excess Letdown, Bypass of CV-135, or Head Vent Letdown
- 4. AOP-1B, Reactor Coolant Pump Malfunction
- 5. AOP-9A, Service Water System Malfunction
- 6. EOP-0, Reactor Trip or Safety Injection
- 7. EOP-1, Loss of Reactor or Secondary Coolant
- 9. CSP-P.1, Response to Imminent Pressurized Thermal Shock Condition
- 10. OM 3.7, AOP and EOP Procedure Usage for Response to Plant Transients
- 11. Technical Specifications Manual
- 12. Technical Requirements Manual Protected None Content:
Evaluation Simulator performance will be evaluated in accordance with Method: NUREG 1021.
Operating None Experience:
TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 23E, 2021 NRC Exam Scenario 2, Rev 0 SEG Page 4 of 34 Risk Significant Initiating Event with Core Damage Frequency:
Operator Actions: Large LOCA (3.25E-08 CDF) (6.22E-11 LERF)
HEP-RHR-EOP13-LL - OPS FAIL TO ALIGN SI FOR LOW CONT SUMP RECIRC (LLOCA/MLOCA) (2.70E-02)
UPDATE LOG: Indicate in the following table any minor changes or major revisions made to the material after initial approval.
PREPARER DATE
- DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR#
REVIEWER DATE Developed for the 2021 ILT NRC 0
Exam TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 23E, 2021 NRC Exam Scenario 2, Rev 0 SEG Page 5 of 34 OVERVIEW / SEQUENCE OF EVENTS OVERVIEW Initial conditions for the scenario are: unit 1 is in MODE 2 with reactor power below the POAH, 1W-3A, Containment Shroud Fan is OOS, Emergency Diesel Generator G-02 is OOS with EDG G-01 aligned to 1A-05 and 2A-05, and 1PT-949, Containment Pressure instrument has been removed from service.
Examinees will start the scenario by raising reactor power to the POAH. Then the crew will respond to a loss of one running Service Water pump and Reactor Coolant Pump high vibrations. RCP vibrations will exceed criteria requiring the crew to manually trip the reactor. Coincident with the reactor trip, a LB LOCA will occur. The crew will respond per EOPs to establish containment sump recirculation.
The scenario will be terminated when the crew has established one train of containment sump recirculation.
SEQUENCE OF EVENTS Event # Description
- 1. Diesel High Particulate Reported The SM will receive communications from chemistry concerning the diesel fuel oil sample SRO addresses a report of high particulate in a diesel fuel oil sample.
- 3. P-32A, Service Water Pump Trips P-32A, Service Water pump will trip due to a winding ground.
The crew will implement AOP-9A, Service Water System Malfunction, to start a standby service water pump and restore system pressure.
The SRO will assess Technical Specifications
- 4. High Reactor Coolant Pump Vibration - 1P-1B High vibration levels will occur on 1P-1B, Reactor Coolant Pump due to a bearing failure.
The Crew will respond to the high vibrations per AOP-1B, Reactor Coolant Pump Malfunction.
Conditions with the RCP will degrade, requiring the crew to trip the reactor and trip the RCP.
- 5. Reactor Trip - Trip Pushbuttons Fail When the crew attempts to manually trip the reactor, the first set of trip pushbuttons will not work. The second set of pushbuttons will trip the reactor.
Coincident with the reactor trip, a LBLOCA will occur.
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PBN LOI NRC 23E, 2021 NRC Exam Scenario 2, Rev 0 SEG Page 6 of 34
- 6. LBLOCA - RHR Pump Failures A LBLOCA occurs coincident with the reactor trip.
Safety Injection will automatically actuate due to the LOCA.
1P-10A RHR Pump will fail to auto start, may be manually started.
1P-10B RHR Pump will auto start, but trip and be unavailable for the reminder of the scenario.
- 7. Containment Sump Recirculation The crew will implement EOP-1.3, Transfer to Containment Sump Recirculation - Low Head Injection, and establish one train of sump recirculation.
Terminate the scenario when crew has established one train of containment sump recirculation, or per Lead Evaluator.
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PBN LOI NRC 23E, 2021 NRC Exam Scenario 2, Rev 0 SEG Page 7 of 34 SIMULATOR SET-UP INSTRUCTIONS Perform simulator set up per the site specific Simulator Setup Checklist.
Check Action
- 1. Reset to IC-31
- 2. Perform Simulator Setup Checklist
- 3. Open schedule file. Z:/2021 NRC Exam 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:
G01, G03, G04 EDGs 1W-3B Shroud Fan Place the following OOS:
G02 EDG 1W-3A, Shroud Fan 1PT-949, Containment Pressure Place red dots on the G02 alarms and Containment Pressure Channel Alert:
C02 F 2-1 C02 F 2-2 C01 B 1-5 Set recorder NR 45 to Low Power page at 30 sec/div
- 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 TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 23E, 2021 NRC Exam Scenario 2, Rev 0 SEG Page 8 of 34
- 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.
TR-AA-230-1007-F14, Revision 0
SEG PBN LOI NRC 23E, 2021 NRC Exam Scenario 2, Rev 0 Page 9 of 34 BOOTH OPERATOR BRIEFING:
Review the scenario sequence, event triggers and expected field communications.
Z:/2021 NRC Exam Simulator Files/NRC Scenario 2.sch On At Time Action Description Event Preloads / Initial Conditions 00:00:00 Insert malfunction MAL2DSG001A DIESEL G02 FAILURE TO START 00:00:00 Insert malfunction BKR1CNM017 to Fail_Cntrl_Fuse 1-B523A W-3A CTL ROD SHROUD FAN CKTBKR 00:00:00 Insert malfunction XMT1CNM016A to -6 1-PT949 LOOP B CONT PRESSURE XMTR FIXED OUTPUT 00:00:00 Event Z:/2021 ILT NRC Exam Simulator Files/NRC 2.evt Event 3: P-32A SW pump trip 00:00:00 Insert malfunction PMP1SWS002C to 75.00000 0-P32B SERVICE WATER PUMP B HEAD CAPACITY 00:00:00 Insert malfunction PMP1SWS004C to 75.00000 0-P32D SERVICE WATER PUMP D HEAD CAPACITY 1 Insert malfunction MOT1SWS001 to Winding_Ground on event 1 P32A SERVICE WATER PUMP MOTOR 19 Insert remote LOA1SWS001 to 0 in 5 on event 19 SW-10 P32A SW PUMP DISCH 20 Insert remote LOA1CWS023 to TRUE on event 20 delete in 5 1C-068A/C-068B LOCAL PANEL ALARM RESET 21 Insert remote LOA2CWS023 to TRUE on event 21 delete in 5 2C-069A/C-069B LOCAL PANEL ALARM RESET Event 4: RCP High Vibration 3 Insert malfunction MAL1RCP007B to 89.7 in 600 on event 3 RCP MOTOR THRUST BEARING FAILURE PUMP B 1-YVPNBFH RCP B FRAME HORIZ VIBRATION FIXED 3 Insert malfunction XMT1RCP015A to 2.3 in 600 on event 3 OUTPUT 1-YVPNBFV RCP B FRAME VERT VIBRATION FIXED 3 Insert malfunction XMT1RCP016A to 2.4 in 600 on event 3 OUTPUT 1-YVPNBSH RCP B SHAFT HORIZ VIBRATION FIXED 3 Insert malfunction XMT1RCP017A to 17.2 in 600 on event 3 OUTPUT 1-YVPNBSV RCP B SHAFT VERT VIBRATION FIXED 3 Insert malfunction XMT1RCP018A to 17.3 in 600 on event 3 OUTPUT After pump trip 7 Insert malfunction MAL1RCP007B to 48.79930 in 100 on event 7 RCP MOTOR THRUST BEARING FAILURE PUMP B
SEG PBN LOI NRC 19E, 2019 NRC Exam Scenario 1, Rev 0 Page 10 of 34 1-YVPNBFH RCP B FRAME HORIZ VIBRATION FIXED 7 Insert malfunction XMT1RCP015A to 0.49829 in 10 on event 7 OUTPUT 1-YVPNBFV RCP B FRAME VERT VIBRATION FIXED 7 Insert malfunction XMT1RCP016A to 0.49829 in 10 on event 7 OUTPUT 1-YVPNBSH RCP B SHAFT HORIZ VIBRATION FIXED 7 Insert malfunction XMT1RCP017A to 3.98335 in 10 on event 7 OUTPUT 1-YVPNBSV RCP B SHAFT VERT VIBRATION FIXED 7 Insert malfunction XMT1RCP018A to 3.98335 in 10 on event 7 OUTPUT Event 5: DBA LOCA 5 Insert malfunction MAL1RCS001 to Hot_Leg_A on event 5 DBA LOCA Event 6: Trip pushbutton Failure 00:00:00 Insert malfunction MAL1PPL001A to Fails_To_Open REACTOR TRIP BREAKER 52/RTA FAILURE 00:00:00 Insert malfunction MAL1PPL001B to Fails_To_Open REACTOR TRIP BREAKER 52/RTB FAILURE 15 Insert malfunction MAL1PPL001B to Trip on event 15 REACTOR TRIP BREAKER 52/RTB FAILURE 15 Insert malfunction MAL1PPL001A to Trip on event 15 REACTOR TRIP BREAKER 52/RTA FAILURE Event 7: RHR Pump Fail to Start 00:00:00 Insert malfunction BKR1RHR001 to Fail_Auto_Cl 1-B5212A P-10A RH REMOVAL PUMP CKTBKR Insert malfunction MOT1RHR002 after 30 to Winding_Ground on 5 1-P10B RESIDUAL HEAT REMOVAL PUMP MOTOR event 5 EOP-1.3 LOAs 9 Insert remote LOA1SWS048 after 60 to 0.38000 in 30 SW-322 1HX-12A CC HTEXCH OUTLET 9 Insert remote LOA1SWS051 after 180 to 0.10000 in 30 SW-360 HX-12B CCW SW OUTLET 9 Insert remote LOA1CCW018 after 270 to 0 in 30 1CC-744B CCW BYPASS/TEST LOOP OUTLET STOP VALVE 9 Insert remote LOA1CCW016 after 420 to 0 in 30 1CC-740A NON-REGEN HX-3A&B INLET VALVE 9 Insert remote LOA1CCW021 after 450 to 0 in 30 1CC-750A SEAL STR HX-5 INLET VALVE 11 Insert remote LOA1SIS030 after 60 to 0 in 30 1SI-897A HANDWHEEL GAG 11 Insert remote LOA1SIS031 after 180 to 0 in 30 1SI-897B HANDWHEEL GAG Event file:
Trigger 5 and 7 Unit 1 Reactor Trip (JCRFTR)
Trigger 15: trigger 16 AND trigger 17 (et_array(16) & et_array(17))
Trigger 16: 1C04 Trip Pushbuttons (x14i057a == 1 l x14i055a == 1)
Trigger 17: C01 Trip Pushbuttons (x01i142a == 1 l x01i141a == 1)
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PBN LOI NRC 23E, 2021 NRC Exam Scenario 2, Rev 0 SEG Page 11 of 34 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 Diesel High Particulate Report ACTION Booth: None SRO STUDENT SRO reviews Technical Specifications and determines LCO 3.8.3 Diesel Fuel RESPONSE Oil and Starting Air is not met. TSAC 3.8.3.B must be entered for G01 and G02 (7 days both units).
CONDITION REQUIRED ACTION COMPLETION TIME TS 3.8.3, Diesel Fuel Oil and Starting Air B. One or more standby B.1 Restore fuel oil total 7 days emergency power particulates within sources with stored fuel limits.
oil total particulates not within limits.
TRM 4.12, Diesel Fuel Oil, provides limits.
The EDGs are not declared OOS unless the RA 3.8.3.B cannot be met.
ROLE PLAY Booth Communications:
Calls SM SM communications:
SM receives a call from Work Control Center which stated Chemistry called with Fuel Oil results taken during the performance of IT 14 G-01, Inservice Test of Fuel Oil Transfer System Pumps and Valves G-01. T-175A, G-01/G-02 EDG Fuel Oil Storage Tank particulate was 17mg/L. The sample results were confirmed by Chemistry to be accurate.
NOTES Continuation Criteria:
After completion of TS review, or at the discretion of the Lead Examiner, continue with the next event.
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PBN LOI NRC 23E, 2021 NRC Exam Scenario 2, Rev 0 SEG Page 12 of 34 Event # 2 Raise Reactor Power to POAH ACTION Booth: None BOP/RO STUDENT Perform OP 1B actions as directed.
RESPONSE
SRO Implements OP 1B, Reactor Startup to raise power to POAH starting from Step 5.16.48.d.
Crew (SRO direct and oversight of reactivity change. RO perform. BOP peer check) (RO or BOP may inform AOs of continuation of startup.)
5.16.48.d. RAISE neutron flux to point of adding heat (POAH) [using rods] as indicated by any of the following: (MARK as N/A indications NOT used.)
Lowering startup rate on SUR meter.
Lowering slope of trace on recorder NR-45.
Reactor Engineering Reactivity Computer indicates point of adding heat has been reached. (Not modeled in simulator) 5.16.49 ALLOW flux level to rise further to CONFIRM onset of nuclear heating reactivity effect and remain below 2% power.
5.16.50 LOWER flux level to point of adding heat (POAH) as determined in Step 5.16.48.d.
5.16.51 RECORD flux level and DIRECT Reactor Engineering to set POAH on reactivity computer (Options - Flux-Nuclear Heat Determination-Set-Accept).
N-35 __________ amps N-36 __________ amps (SRO direct SM to notify RE to set POAH on reactivity computer)
ROLE PLAY Booth Communications:
Respond to reports or direction to field operators as necessary.
SM communications:
Brief the crew on current plant conditions and planned reactor startup tasks.
Provide direction to the crew to raise power to POAH, using control rods, (approximately 4.0 E-6 amps).
Acknowledge direction from SRO to have RE set POAH.
NOTES Continuation Criteria:
After power has been raised to POAH, or at the discretion of the Lead Examiner, continue with the next event.
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PBN LOI NRC 23E, 2021 NRC Exam Scenario 2, Rev 0 SEG Page 13 of 34 Event # 3 P-32A, Service Water Pump Trips ACTION Booth:
Insert TRIGGER 1 per Lead Evaluator Insert Trigger 19 when directed by the crew Note: RCP high vibration alarm (Event #4) occurs approximately 8 minutes after the trigger is entered.
Booth: Insert TRIGGER 3 per Lead Evaluator Symptoms and Indications:
STUDENT Annunciators RESPONSE o C02 D 3-2, 1B-03 480 V Bus Ground Fault o C01 B 3-4, Unit 1 Motor Breaker Trip o C01 A 3-5, North or South Service Water Header Pressure Low o C02 D 3-6, G-01 Emer Diesel Cooler Low Flow o C02 F 3-1, G-02 Emer Diesel Cooler Low Flow C01 indications:
o P-32A Service Water, white light o North and South SW header pressure lowers BOP/SRO Diagnoses loss of P-32A Service Water pump. (BOP)
Starts a standby service water pump to restore service water header pressure to greater than 50 psig. (BOP)
SRO Implements AOP-9A, Service Water System Malfunction.
AOP-9A, Service Water System Malfunction
- 1. Check forebay level greater than -11.5 feet (BOP)
- 2. Check pump bay level greater than -11.5 feet (BOP)
- 3. Check annunciator travelling screen differential level high alarm clear (BOP)
- 4. Check north or south service water header pressure low alarm clear; RNO:
Perform the following:
- a. Start service water pumps - Maintain pressure between 50 psig and 90 psig. (starts one pump to restore pressure to >50 psig)
(BOP) o P-32C o P-32E o P-32F
- e. If any service water pump tripped or recently stopped, then ensure affected pump in pullout and locally shut associated pump discharge valve. (BOP) o SW-10 for P-32A
- f. Go to Step 9. (SRO)
- 9. Notify duty station manager and enter applicable TSACs. (SRO)
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PBN LOI NRC 23E, 2021 NRC Exam Scenario 2, Rev 0 SEG Page 14 of 34 Event # 3 P-32A, Service Water Pump Trips
- 10. Check if Emergency Plan should be implemented per EPIP-1.2, Emergency Classification
- 12. Check zurn strainer normal (BOP)
- 13. Ensure service water header valves are open (BOP)
- 14. Check component alarms clear (BOP)
- 15. Observe note prior to Step 1 and return to Step 1. (SRO)
- 1. Check forebay level greater than -11.5 feet (BOP)
- 2. Check pump bay level greater than -11.5 feet (BOP)
- 3. Check annunciator travelling screen differential level high alarm clear (BOP)
- 4. Check north or south service water header pressure low alarm clear (BOP)
- 5. Check zurn strainer - NORMAL (BOP)
- 6. Check component alarms clear (BOP)
- 7. Check service water system intact (BOP)
- 8. Return to procedure and step in effect. (SRO)
Assess Technical Specifications: (SRO)
CONDITION REQUIRED COMPLETION TIME ACTION TS 3.7.8, Service Water System A. One SW pump inoperable A.1 Restore SW 7 days AND pump to AND Both Units in MODE 1, 2, OPERABLE 14 days from 3, or 4 status. discovery of failure to meet the LCO TRM 3.7.7, Service Water System D. One SW pump inoperable D.1 Declare LCO Within the completion AND 3.7.8, Required time of LCO 3.7.8, Requirements of TRM Table action A.1 not Required action A.1 3.7.7-2 not met met.
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PBN LOI NRC 23E, 2021 NRC Exam Scenario 2, Rev 0 SEG Page 15 of 34 Event # 3 P-32A, Service Water Pump Trips ROLE PLAY Booth Communications:
TH AO: If directed to investigate the loss of P-32A, Wait 2 minutes and report that P-32A is not running, and otherwise appears normal.
TH AO: If directed to shut SW-10, P-32A Discharge Isolation valve, wait 1 minute, Insert Trigger 19, and report when complete.
TH AO: If directed to service water system conditions / check zurn strainer normal, wait 1 minute and report that service water strainers are operating normally, power available, and strainer P is normal, and the system is intact.
Reset circulating water pump cooling low flow alarms.
Respond to reports or direction to field operators as necessary.
SM Communications:
Respond to reports from crew members as required.
Continuation Criteria:
NOTES After Service Water header pressure has been restored and Technical Specifications have been addressed, or at the discretion of the Lead Examiner, continue with the next event.
Note: It is recommended that the next event trigger be inserted after Service Water Pump(s) started to restore pressure, due to the lag time before the alarm comes in.
Note: RCP high vibration alarm occurs approximately 8 minutes after the trigger 3 is entered.
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PBN LOI NRC 23E, 2021 NRC Exam Scenario 2, Rev 0 SEG Page 16 of 34 Event # 4 High Reactor Coolant Pump Vibration - 1P-1B ACTION Booth: Insert TRIGGER 3 per Lead Evaluator Note: RCP high vibration alarm occurs approximately 8 minutes after the trigger is entered.
Trigger 7 deletes malfunctions when the reactor is tripped.
Symptoms and Indications:
STUDENT 1P-1A & B RCP VIBRATION ALARM (1C04 1C 1-5)
RESPONSE
1TR-2001 TEMPERATURE MONITOR (1C04 1C 3-10)
PPCS Indications:
o 1P-1B Shaft vibration, Horizontal and Vertical, up to 17 mils o 1P-1B Frame vibrations elevated at just over 2 mils o 1P-1B Seal Injection temperature 212.7°F o PPCS Alarms for Shaft vibrations for RCP B TR-2001 1P-1B Upper and Lower Thrust Bearing temperatures 89.7°C BOP/RO Acknowledge alarms and reference ARBs (RO)
Review PPCS screen (RCPs/ 2155) for vibration readings (RO or BOP)
May direct an AO to 1C-76 to get local readings (in the Rod Drive Room)
SRO Implements AOP-1B, Reactor Coolant Pump Malfunction Crew
- 1. Check annunciator P-1A&B RCP Vibration Alarm - CLEAR; RNO: check if RCP shutdown is required (RO)
- a. Vibration readings on PPCS page RCPS or locally at 1C-76 o Shaft vibration greater than or equal to 20 mils.
o Shaft vibration greater than or equal to 15 mils and rising at 1 mil/hr o Frame vibration greater than or equal to 5 mils o Frame vibration greater than or equal to 3 mils and rising at 0.2 mil/hr
- b. IF RCP shutdown required, THEN go to Step 19.
- 2. Check annunciator 1TR-2001 temperature monitor alarm - CLEAR (RO)
Note: Crew identifies FO1 RCP Trip Criteria is met, then performs step 19.
o RCP Shaft Vibration:
o Greater than or equal to 15 mils and rising at 1 mil/hr.
- a. Trip reactor Evaluator Note: RO should carry out immediate actions of EOP-0 at TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 23E, 2021 NRC Exam Scenario 2, Rev 0 SEG Page 17 of 34 Event # 4 High Reactor Coolant Pump Vibration - 1P-1B this time.
- b. Stabilize plant using EOPs while continuing with this procedure
- c. Trip affected RCP
- d. Check at least one RCP running
- e. Shut associated PZR normal spray valve
- f. Check affected RCP has been tripped for 3 minutes
TH AO: If directed to check RCP vibration reading on 1C-76 in rod drive room, wait 2 minutes and report vibration readings as read from RCPs PPCS page.
Respond to reports or direction to field operators as necessary.
SM Communications:
Respond to reports from crew members as required.
NOTES Continuation Criteria:
Once AOP-1B Step 19 actions have been completed, or at the discretion of the Lead Examiner, continue with the next event.
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PBN LOI NRC 23E, 2021 NRC Exam Scenario 2, Rev 0 SEG Page 18 of 34 Event # 5 Reactor Trip - Trip Pushbuttons Fail ACTION Booth: None Symptoms and Indications:
STUDENT First set of Reactor Trip Pushbuttons depressed with no system response
RESPONSE
BOP/RO Attempts to manually trip the reactor, when first set of pushbuttons fail, uses alternate pushbuttons to trip the reactor. Performs EOP-0 Immediate Actions.
The BOP may be directed by the RO to depress the second set of pushbuttons; or the RO may do it themselves.
SRO Implements EOP-0, Reactor Trip or Safety Injection Crew
- 1. Verify Reactor Trip; RNO: manually trip reactor (RO)
- 2. Verify turbine trip (RO)
- 2) Go to EOP-0.1, Reactor Trip Response. (SRO)
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 Note: Once EOP-0 immediate actions have been completed, the crew will complete the actions of AOP-1B, Step 19.
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PBN LOI NRC 23E, 2021 NRC Exam Scenario 2, Rev 0 SEG Page 19 of 34 Events LBLOCA - RHR Pump Failures - Containment Sump Recirc
- 6 and #7 ACTION Booth: Insert Trigger 5 per Lead Evaluator.
STUDENT Symptoms and Indications:
RESPONSE Rapid loss of Pressurizer level and pressure Containment high pressure Numerous alarms on 1C04 and C01 RMS Server alarms for radiation in Containment 1P-10A RHR Pump not running following the SI sequence Crew EOP-0 continued: (returns to EOP-0 Step 4 from EOP-0.1 when SI actuates)
- a. Any SI annunciators - LIT CT-5 event
- b. Both trains of SI - ACTUATED; RNO: Manually actuate both trains starts here of SI and Containment Isolation Recognizes that 1P-10A failed to start and 1P-10B tripped.
After Step 4 is complete RO or BOP may request, or SRO may direct, 1P-10A be manually started at this point. *Otherwise this will happen in Attachment A step A3.
CT-5 action* (CT-5) manually start 1P-10A (RO or BOP)
May direct the AOs to check out 1P-10B and its breaker.
Foldout Page #1 RCP Trip Criteria: If both conditions listed below occur, THEN trip both RCPs (RO)
RCS subcooling - LESS THAN [40F] 31F SI Pumps - AT LEAST ONE RUNNING AND CAPABLE OF DELIVERING FLOW
- 5. Perform Attachment A, Automatic Action Verification, while continuing with this procedure. (BOP)
Evaluator Note: Already stopped per foldout page
- 11. Check if S/G are NOT faulted (RO)
- 12. Check if S/G tubes are NOT ruptured (RO)
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PBN LOI NRC 23E, 2021 NRC Exam Scenario 2, Rev 0 SEG Page 20 of 34 Events LBLOCA - RHR Pump Failures - Containment Sump Recirc
- 6 and #7 CT-36 event starts here EOP-1, Loss of Reactor or Secondary Coolant Foldout Page #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:
o RWST Level - LESS THAN 60%
o RCS Pressure less than [450 psig] 325 psig AND RHR flow greater than 550 gpm 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; RNO: WHEN SI sequence is complete CT-5 action* (CT-5) THEN manually start RHR Pumps.
see previous If not already performed, this is where the BOP starts 1P-10A.
page for note. 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 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; RNO: Check containment spray alignment
- 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.
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 TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 23E, 2021 NRC Exam Scenario 2, Rev 0 SEG Page 21 of 34 Events LBLOCA - RHR Pump Failures - Containment Sump Recirc
- 6 and #7 A22 - Check Circ Water Pump House temperature less than 105F A23 - Check G03/G04 switchgear room temperature less than 95F A24 - Periodically check status of spent fuel cooling.
ROLE PLAY Booth Communications:
PAB AO: If directed to investigate 1P-10B trip, wait 2 minutes and report the motor is stopped and hot to the touch.
TH AO: If directed to check the breaker for 1P-10B at 1B04, wait 2 minutes and report the breaker has tripped on overcurrent.
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 76F and stable.
o TH AO: When directed to check G03/G04 switchgear room temperature, wait 1 minute and report 80F and stable.
Respond to reports or direction to field operators as necessary.
SM Communications:
Respond to reports from crew members as required.
NOTES TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 23E, 2021 NRC Exam Scenario 2, Rev 0 SEG Page 22 of 34 Events Containment Sump Recirculation
- 6 and # 7 ACTION Booth:
Insert TRIGGER 9 when directed by crew for EOP-1.3, Att A alignment.
Insert TRIGGER 11 when directed by crew to isolate SI test lines.
STUDENT Symptoms and Indications RESPONSE RCS pressure near Containment pressure ECCS Flow (RHR) approximately 1500 gpm RWST level lowering Crew Implements 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
- 7. Check if Train B SI flow should be stopped
- c. Stop Train B RHR pump and place in pull-out Pump tripped on ground fault
- 8. Monitor core cooling (RO)
- 10. (CT-36) Isolate component cooling flow to containment
- 11. (CT-36) 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)
- 12. Check Service Water pumps - SIX RUNNING (BOP)
- 13. Check service water supply ring header - CONTINOUS FLOWPATH ESTABLISHED (BOP)
- 14. Establish component cooling flow to RHR heat exchangers:
- a. Ensure component cooling pumps - AT LEAST ONE RUNNING TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 23E, 2021 NRC Exam Scenario 2, Rev 0 SEG Page 23 of 34 Events Containment Sump Recirculation
- 6 and # 7 (BOP)
- 16. Align SI test lines for recirculation
- a. Check containment spray discharge valves - AT LEAST ONE OPEN IN EACH TRAIN (BOP)
- b. (CT-36) Locally shut both SI test line return isolation valves:
(BOP or RO directs PAB AO) 1SI-897A 1SI-897B
- 18. Check Train A Ready for Recirculation (BOP)
- 19. Check Train B Ready for Recirculation; (SRO)
RNO: Try to prepare train B for recirculation while continuing with this procedure.
This train is unavailable due to pump tripped
- a. WHEN RWST level is less than or equal to 34%, THEN immediately return to this procedure and continue with Step 23.
- b. Implement Critical Safety Procedures and continue with procedure and step in effect.
Note: The crew should address CSP-P.1, Response to Imminent Pressurized Thermal Shock Condition, and implement EOP-1, Loss of Reactor or Secondary Coolant until RWST level reaches 34%.
Note: Time compression may be used here to SNAP forward to 34% RWST level at the discretion of the lead examiner. No significant actions will take place in EOP-1 or CSP-P.1. IC 39 is snapped to 36% RWST, before the low level alarm actuates.
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PBN LOI NRC 23E, 2021 NRC Exam Scenario 2, Rev 0 SEG Page 24 of 34 Events Containment Sump Recirculation
- 6 and # 7 IC 41 is snapped at 34%, after the low level alarm was acknowledged.
CSP-P.1 is exited during the first step due to low RCS pressure and high RHR flow.
EOP-1, the following steps are expected to be performed while waiting for RWST level:
- 1. Check if RCPs Should be stopped; (No actions needed)
RNO Go to step 2
- 2. Check if S/Gs are NOT faulted (No actions needed)
- 3. Check intact S/G level (BOP)
Will control level and total flow with AFW flow control valves
- 4. Check Secondary Radiation (No actions needed)
- 5. Check Pzr PORVs and Block Valves (No actions needed)
- 8. Establish Air to Containment (BOP)
Check Air pressure >80 psig Open 1IA-3047 and 1IA-3048 on at a time When RWST level lowers to 34%, the crew will return to EOP-1.3, step 23:
EOP-1.3, Transfer to Containment Sump Recirculation - Low Head Injection
- a. Check RHR train B - READY FOR RECIRCULATION; RNO:
OBSERVE CAUTION PRIOR TO STEP 27 and go to Step 27.
- a. Check RHR train A - READY FOR RECIRCULATION
- b. Check SI test line return isolation AOVs - AT LEAST ONE SHUT CT-36 actions c. (CT-36) Open train A RHR pump suction from containment complete sump B MOV: 1SI-851A
Containment sump level RHR pump operation - NORMAL Low head injection flow - STABLE TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 23E, 2021 NRC Exam Scenario 2, Rev 0 SEG Page 25 of 34 Events Containment Sump Recirculation
- 6 and # 7 ROLE PLAY Booth Communications:
PAB AO: When directed to perform EOP-1.3, Attachment A alignment, insert trigger 9, and report when all actions are complete.
PAB AO: When directed to shut 1SI-897A and 1SI-897B, insert trigger 11 and report when complete.
Respond to reports or direction to field operators as necessary.
STA Communication:
When CSF Status Trees are in effect and plant conditions are met, report to the SRO that CSF INTEGRITY RED path conditions exist.
SM Communications:
Respond to reports from crew members as required.
NOTES Scenario Termination Terminate the scenario when the crew has established one train of sump recirculation, or per Lead Evaluator.
Freeze the simulator NOTES Determine if the NRC has any follow up questions Save SBT Data (see sim setup instructions)
TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 23E, 2021 NRC Exam Scenario 2, Rev 0 SEG Page 26 of 34 QUANTITATIVE ATTRIBUTES Malfunctions:
Before EOP Entry:
P-32A, SW Pump winding ground, pump trip RCP 1P-1B high vibration After EOP Entry:
One set of reactor trip pushbuttons fail 1P-10B RHR Pump trip 1P-10A RHR Pump fails to auto start Abnormal Events:
Service Water System Malfunction RCP Malfunction Major Transients:
- 1. CT-5 Manually start at least one low head ECCS pump
- 2. CT-36 Establish at least one train of sump recirculation Major Procedures:
AOP-9A AOP-1B EOP-0 EOP-1 EOP-1.3 CSP-P.1 EOP-1 EOP-1.3 TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 23E, 2021 NRC Exam Scenario 2, Rev 0 SEG Page 27 of 34 CT-5 Manually start at least one low head ECCS pump Critical Task:
Manually start at least one low-head ECCS pump to establish successful sump recirculation.
Plant Conditions:
Large-break LOCA Reactor trip SI RCS pressure below the shutoff head of the low-head ECCS pumps Both low-head ECCS pumps fail to automatically start upon SI At least one low-head ECCS pump can be started, provided that manual action is taken as necessary Cues:
Indication and/or annunciation that low-head ECCS pumped injection is required SI actuation RCS pressure below the shutoff head of the low-head ECCS pumps AND Indication and/or annunciation that no low-head ECCS pump is injecting into the core Control switch indication that the circuit breakers or contactors for both low-head ECCS pumps are open All low-head ECCS pump discharge pressure indicators read zero All flow rate indicators for low-head pumped injection read zero Performance Indicator:
Manipulation of controls as required to start at least one low-head ECCS pump Control switch indication that the circuit breaker or contactor for at least one low-head ECCS pump is closed Feedback:
Indication and/or annunciation that at least one low-head ECCS pump is injecting Flow rate indication of injection from at least one low-head ECCS pump Basis:
SAFETY SIGNIFICANCE -- Failure to manually start at least one low-head ECCS pump under the postulated conditions constitutes misoperation or incorrect crew performance in which the crew does not prevent degraded emergency core cooling system (ECCS) capacity. In this case, at least one low-head ECCS pump can be manually started from the control room. Therefore, failure to manually start a low-head ECCS pump also represents a failure by the crew to demonstrate the following abilities:
Effectively direct or manipulate engineered safety feature (ESF) controls that would prevent a significant reduction of safety margin (beyond that irreparably introduced by the scenario)
Recognize a failure or an incorrect automatic actuation of an ESF system or component Additionally, under the postulated plant conditions, failure to manually start a low-head ECCS pump (when it is possible to do so) is a violation of the facility license condition. The acceptable results obtained in the FSAR analysis of a large-break LOCA are predicated on the assumption of minimum ECCS pumped injection. The analysis assumes that a minimum pumped ECCS flow rate, which varies with RCS pressure, is injected into the core. The flow rate values assumed for minimum pumped injection are based on operation of one each of the TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 23E, 2021 NRC Exam Scenario 2, Rev 0 SEG Page 28 of 34 following ECCS pumps: high-head pump, intermediate-head pump, and low-head pump. Operation of this minimum required complement of ECCS injection pumps is consistent with the FSAR assumption that only minimum safeguards are actuated. For both the minimum and maximum cases specified in Comment 1 of this critical task worksheet and for all cases in between, failure to perform the critical task means that the plant is needlessly left in an unanalyzed condition. Performance of the critical task would return the plant to a condition for which analysis shows acceptable results.
TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 23E, 2021 NRC Exam Scenario 2, Rev 0 SEG Page 29 of 34 CT-36 Transfer to cold leg recirculation Critical Task:
Transfer to cold leg recirculation and establish ECCS recirculation flow from at least one train of RHR prior to loss of suction of running ECCS pumps.
Plant Conditions:
LOCA inside containment RWST level decreases to 34%
Containment recirculation sump level is at or above 38 inches Transfer to cold leg recirculation can be performed manually from switches in the control room Cues:
Indication and/or annunciation that safety injection is actuated AND Indication and/or annunciation that RWST level is at or below 34%
AND Indication that containment sump level is at or above 38 inches Performance Indicator:
Manipulation of controls as required to transfer to cold leg recirculation and establish ECCS recirculation flow that at least meets the assumptions of the plant-specific LOCA analyses:
Valve position indication that the cold leg recirculation flow path is established Control switch indication that the circuit breakers or contactors for the low-head injection pumps are closed Feedback:
Flow indication of the recirculation of containment sump water through the RHR heat exchangers and into the RCS Basis:
The justification for selecting this task as critical can be thoroughly argued only on the basis of plant-specific requirements. A detailed justification cannot be presented on a generic basis because of the following plant-specific variables:
ECCS recirculation-mode alignments Methods for transfer to cold leg recirculation RWST inventory criteria for initiating switchover RWST inventory transfer allowances for completing transfer of injection pumps and spray pumps The plant-specific justification for selecting this task as critical should be argued along one or more of the following lines:
Improper performance or omission by an operator will result in direct adverse consequence(s) or a significant degradation in the mitigative capability of the plant Operation or correct performance prevents a significant reduction of safety margin beyond that irreparably introduced by the scenario Operation or correct performance prevents unnecessary challenges to the following CSFs:
- Core cooling
- Containment The crew demonstrates the ability to take one or more actions that would prevent a challenge to plant safety TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 23E, 2021 NRC Exam Scenario 2, Rev 0 SEG Page 30 of 34 Booth Summary Event #2 Raise Reactor Power to POAH Action Booth: None Role Play Respond to reports or direction to field operators as necessary.
Event #3 P-32A Service Water Pump Trip Action Booth: Insert TRIGGER 1 per Lead Evaluator Role Play TH AO: If directed to investigate the loss of P-32A, Wait 2 minutes and report that P-32A is not running, and otherwise appears normal.
TH AO: If directed to shut SW-10, P-32A Discharge Isolation valve, wait 1 minute, Insert Trigger 19, and report when complete.
TH AO: If directed to service water system conditions / check zurn strainer normal, wait 1 minute and report that service water strainers are operating normally, power available, and strainer P is normal, and the system is intact.
Reset circulating water pump cooling low flow alarms.
Respond to reports or direction to field operators as necessary.
Event #4 1P-1B RCP High Vibration Action Booth: Insert TRIGGER 3 per Lead Evaluator Note: RCP high vibration alarm occurs approximately 8 minutes after the trigger is entered.
Trigger 7 deletes malfunctions when the RCP is tripped.
Role Play TH AO: If directed to check RCP vibration reading on 1C-76 in rod drive room, wait 2 minutes and report vibration readings as read from RCPs PPCS page.
Respond to reports or direction to field operators as necessary.
Event #5 Reactor Trip - Pushbuttons Fail Action Booth: None Trigger 15 opens reactor trip breakers once the second set of pushbuttons is depressed.
Role Play Respond to reports or direction to field operators as necessary.
Event #6 RHR Pump Failures Action Booth: None Trigger 5 inserts motor winding ground when the reactor is tripped.
Role Play PAB AO: If directed to investigate 1P-10B trip, wait 2 minutes and report the motor is stopped and hot to the touch.
TH AO: If directed to check the breaker for 1P-10B at 1B04, wait 2 minutes and report the breaker has tripped on overcurrent.
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 76F and stable.
o TH AO: When directed to check G03/G04 switchgear room temperature, wait 1 TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 23E, 2021 NRC Exam Scenario 2, Rev 0 SEG Page 31 of 34 minute and report 80F and stable.
Respond to reports or direction to field operators as necessary.
Event #7 LB LOCA - Containment Sump Recirculation Action Booth:
Trigger 5 inserts when the reactor is tripped.
Insert TRIGGER 9 when directed by crew for EOP-1.3, Att A alignment.
Insert TRIGGER 11 when directed by crew to isolate SI test lines.
Role Play PAB AO: When directed to perform EOP-1.3, Attachment A alignment, insert trigger 9, and report when all actions are complete.
PAB AO: When directed to shut 1SI-897A and 1SI-897B, insert trigger 11 and report when complete.
Respond to reports or direction to field operators as necessary.
TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 23E, 2021 NRC Exam Scenario 2, Rev 0 SEG Page 32 of 34 SHIFT TURNOVER INFORMATION PLANT CONDITIONS:
UNIT 1 Time in core life (MWD/MTU): BOL Reactor power (%): 0% (1.3x10E-6 amps in IR)
Boron concentration (ppm): 2250 ppm Rod height, CBD @: 196 TECHNICAL SPECIFICATION ACTION CONDITIONS IN EFFECT:
TSAC Description Required Action & Completion Time U1 3.3.2.A/D One channel inoperable 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 /> EQUIPMENT OUT OF SERVICE:
G02 Emergency Diesel Generator for maintenance.
1PT-949, Containment Pressure instrument.
1W-3A, Control Rod Drive Shroud Fan.
PLANNED EVOLUTIONS:
Raise reactor power to POAH.
TURNOVER INFORMATION:
G01 Emergency Diesel Generator is aligned to both 1A05 and 2A05 4160 Safeguards Busses.
On line risk is GREEN.
Today is Tuesday, day shift.
TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 23E, 2021 NRC Exam Scenario 2, Rev 0 SEG Page 33 of 34 Pre-Scenario Procedure Checks Procedure OS1 1st Check 2nd Check AOP-1B AOP-9A EOP 0 EOP 1 EOP 1.3 CSP-P.1 Specific ARP/ARBs to be second checked - All Others first checked 1st Check 2nd Check C02 D 3-2 C02 D 3-6 C02 F 3-1 1C04 1C 1-5 1C04 1C 3-10 C01 A 3-5 C01 B 3-4 TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 23E, 2021 NRC Exam Scenario 2, Rev 0 SEG Page 34 of 34 Post-Scenario Procedure Checks Procedure OS1 1st Check 2nd Check AOP-1B AOP-9A EOP 0 EOP 1 EOP 1.3 CSP-P.1 1st Check 2nd Check C02 D 3-2 C02 D 3-6 C02 F 3-1 1C04 1C 1-5 1C04 1C 3-10 C01 A 3-5 C01 B 3-4 RESET IC N/A Booth Cleared Exam Material Magnets Replaced P&IDs cleaned and replaced Dots removed from alarm windows TR-AA-230-1007-F14, Revision 0
Appendix D Scenario Outline Form ES-D-1 Facility: __Point Beach___ Scenario No.: ______4______ Op-Test No.: __2021__
Examiners: ___________________________ Operators: _____________________________
Initial Conditions: _Reactor power is 47%. G03, EDG is out of service due to maintenance with ____
_G04, EDG aligned. 1LT-426, PZR Level transmitter (Red) removed from service _______________
Turnover:_Conduct an up power to 100% power at 15% per hour per OP 1C, Startup to Power_____
_Operations_______________________________________________________________________
Critical Tasks:_CT-3, Manually Actuate Containment Cooling ________________________________
_CT-17, Isolate Faulted SG___________________________________________________________
Event Malf. Event Event No. No. Type* Description Letdown inadvertently isolates, needs to be re-established C-RO 1
C-SRO NEW 0LT-4040, T-24A CST Level Transmitter fails low 2 TS-SRO 2017 Repeat R-RO Inadvertent Turbine trip with no reactor trip 3 C-BOP R-SRO NEW Seismic event C-RO 1P-11A, CCW pumps failure due to a mechanical failure requiring 4 C-SRO pump shift TS-SRO 2019 Repeat C-RO Seismic event causes multiple dropped rods, without an automatic 5
C-SRO RX Trip 6 M-ALL Steam Generator fault in containment upstream of the orifice C-BOP 7 Safety Injection fails to actuate C-SRO
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
SEG SIMULATOR EXERCISE GUIDE SITE: PBNP Revision #: 0 LMS ID: PBN LOI NRC 25E LMS Rev. Date:
SEG TITLE: 2021 NRC Exam Scenario 4 SEG TYPE: Training Evaluation PROGRAM: LOCT LOIT Other:
DURATION: 90 minutes Developed by: John Rogers Instructor/Developer Date Reviewed by: Jeff Hinze 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 TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 25E, 2021 NRC Exam Scenario 4, Rev 0 SEG Page 2 of 33 Facility: __Point Beach___ Scenario No.: ______4______ Op-Test No.: __2021__
Examiners: ___________________________ Operators: _____________________________
Initial Conditions: _Reactor power is 47%. G03, EDG is out of service due to maintenance with ____
_G04, EDG aligned. 1LT-426, PZR Level transmitter (Red) removed from service _______________
Turnover: Conduct an up power to 100% power at 15% per hour per OP 1C, Startup to Power_____
_Operations_______________________________________________________________________
Critical Tasks: CT-A Restore Normal or Excess Letdown ______________________
_CT-17, Isolate Faulted SG___________________________________________________________
Event Malf. Event Event No. No. Type* Description C-RO Letdown inadvertently isolates, needs to be re-established 1 C-SRO NEW TS-SRO 0LT-4040, T-24A CST Level Transmitter fails low 2
2017 Repeat R-RO Inadvertent Turbine trip with no reactor trip 3 C-BOP R-SRO NEW C-RO Seismic event C-SRO 1P-11A, CCW pumps failure due to a mechanical failure requiring 4 TS-SRO pump shift 2019 Repeat C-RO Seismic event causes multiple dropped rods, without an automatic 5 RX Trip C-SRO 6 M-ALL Steam Generator fault in containment upstream of the orifice C-BOP Safety Injection fails to actuate 7
C-SRO
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 25E, 2021 NRC Exam Scenario 4, Rev 0 SEG Page 3 of 33 SIMULATOR EXERCISE GUIDE REQUIREMENTS Terminal Given the site simulator and specific plant conditions, the students will Objective: be able to respond to various plant abnormal and emergency events, in accordance with site procedures and technical Specifications.
Enabling 1. None Objectives:
Prerequisites: 1. Simulator available
- 2. Students enrolled in Initial License Program Training 1. Floor Instructor as Shift Manager / Shift Technical Advisor Resources: 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-25, Turbine Trip Without Reactor Trip
- 5. AOP-28, Seismic Event
- 6. EOP-0, Reactor Trip or Safety Injection
- 7. EOP-1, Loss of Reactor or Secondary Coolant
- 9. EOP-2, Faulted Steam Generator Isolation
- 10. OM 3.7, AOP and EOP Procedure Usage For Response To Plant Transients
- 11. Technical Specifications Manual
- 12. Technical Requirements Manual Protected None Content:
Evaluation Simulator performance will be evaluated in accordance with Method: NUREG 1021.
Operating None Experience:
Risk Significant Initiating Event with Core Damage Frequency:
Operator Actions: Steam Break Inside Containment (4.12E-09 CDF) (2.00E-11 LERF)
Failure to isolate AFW to the Faulted Steam Generator from T (1.41E-03)
TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 25E, 2021 NRC Exam Scenario 4, Rev 0 SEG Page 4 of 33 UPDATE LOG: Indicate in the following table any minor changes or major revisions made to the material after initial approval.
PREPARER DATE
- DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR#
REVIEWER DATE Developed for the 2021 ILT NRC 0
Exam TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 25E, 2021 NRC Exam Scenario 4, Rev 0 SEG Page 5 of 33 OVERVIEW / SEQUENCE OF EVENTS OVERVIEW Initial conditions for the scenario are: Unit 1 reactor power is stable at approximately 47% during a plant startup following a short forced outage. Power ascension to 100% is planned for this shift.
Examinees will respond to an inadvertent CVCS letdown isolation and a CST level instrument failure.
A seismic event causes the running CCW pump to degrade. A second seismic event causes two dropped rods, requiring a reactor trip. Coincident with the reactor trip, A S/G faults inside containment; containment spray will fail to automatically actuate.
The scenario will be terminated when the crew has completed actions through Step 7 of EOP-1.1, SI Termination.
SEQUENCE OF EVENTS Event # Description Inadvertent Letdown Isolation Letdown Orifice Isolation valve, 1CV-200A inadvertently closes causing a loss of
- 1. letdown flow.
The crew will respond per AOP-1D, CVCS Malfunction, to minimize charging flow and restore letdown to service.
0LT-4040 Condensate Storage Tank T-24A Level Transmitter fails low
- 2. The crew should reference ARP C01 A 2-9 and ARB C01 A 3-9 for the failed level transmitter and determine the applicable Technical Specifications Required Actions.
Inadvertent Turbine Trip Without Reactor Trip
- 3. The Unit 1 Main Turbine will inadvertently trip with reactor power at approximately 47%. The reactor will not trip.
The crew will stabilize the plant per AOP-25, Turbine Trip Without Reactor Trip Seismic Event / 1P-11A, CCW Pump Failure A seismic event occurs that results in the mechanical failure of 1P-11A, CCW Pump.
- 4. The crew will implement AOP-28, Seismic Event, in response to the Seismic Event.
The crew will respond to the loss of 1P-11A, CCW Pump, per AOP-9B, Component Cooling System Malfunction, to restore CCW system flow.
SRO will address Technical Specifications Multiple Dropped Rods
- 5. A second seismic event causes two rods to drop, requiring a reactor trip.
The crew will respond to AOP-6A, Dropped Rod, to trip the reactor.
TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 25E, 2021 NRC Exam Scenario 4, Rev 0 SEG Page 6 of 33 Faulted Steam Generator Coincident with the reactor trip, the A S/G will fault inside containment.
- 6. Safety Injection and Containment Pressure Condensate Isolation (CPCI) will fail to actuate, SI may be manually actuated.
The crew will isolate the faulted S/G per EOP-2, Faulted Steam Generator Isolation.
Terminate the scenario when crew has completed through Step7 of EOP-1.1, SI Termination, or per Lead Evaluator.
TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 25E, 2021 NRC Exam Scenario 4, Rev 0 SEG Page 7 of 33 SIMULATOR SET-UP INSTRUCTIONS Perform simulator set up per the site specific Simulator Setup Checklist.
Check Action
- 1. Reset to IC-32
- 2. Perform Simulator Setup Checklist
- 3. Open schedule file. Z:/2021 ILT NRC Simulator Files/NRC Scenario 4.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 RO desk
- 9. Place reactivity sheets on RO desk
- 10. Guard the following:
G01, G02, G04 EDGs Place the following OOS:
G03 EDG 1LT-426 Pressurizer Level Place red dots on the G03 alarm and PZR Level:
C02 E 2-1 C02 E 2-2 1C04 1C 3-3
- 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.
TR-AA-230-1007-F14, Revision 0
SEG PBN LOI NRC 25E, 2021 NRC Exam Scenario 4, Rev 0 Page 8 of 33 BOOTH OPERATOR BRIEFING:
Review the scenario sequence, event triggers and expected field communications.
Z:/2021 ILT NRC Simulator Files/NRC Scenario 4.sch On At Time Action Description Event Preloads / Initial Conditions 00:00:00 Insert malfunction MAL1DSG001B DIESEL G03 FAILURE TO START 00:00:00 Insert malfunction XMT1RCS007C to -15 1-LT426 PRZR NARROW RANGE LEVEL FIXED BIAS Event Z:/2021 ILT NRC Exam Simulator Files/NRC 4.evt Event 1: Inadvertent Loss of Letdown 1 Insert malfunction VLV1CVRO5 to Close on event 1 delete in 30 1-CV-200A LTDN ORIFICE STOP VLV NO 1-200A Event 2: CST Level Instrument Failure 2 Insert malfunction XMT1AFW005A to 0 in 5 on event 2 0-LT4040 COND STOR TK T24A LEVEL FIXED OUTPUT Event 3: Inadvertent Turbine Trip 3 Insert malfunction MAL1EHC008 on event 3 INADVERTANT TURBINE TRIP Event 4: Seismic Event / 'A' CCW Pump Failing Schedule Z:\2021 ILT NRC Exam Simulator Files\NRC 4 Seismic 5
1.sch 1-P11A COMPONENT COOLING PUMP NO 1-P11A HEAD 5 Insert malfunction PMP1CCW001C to 50.00000 in 15 on event 5 CAPACITY Event 5: Dropped Rods / 2nd Seismic Event 7 Insert malfunction MAL1CRF002-J4 after 5 on event 7 ROD DROP J4 7 Insert malfunction MAL1CRF002-I3 after 10 on event 7 ROD DROP I3 Schedule Z:\2021 ILT NRC Exam Simulator Files\NRC 4 Seismic 7
2.sch after 5 7 Insert remote LOA1ANN008 to ON on event 7 delete in 5 SEI-RESET Seismic detector reset C-206 Event 6: Faulted Steam Generator Insert malfunction MAL1SGN002A to 10000000.00000 in 10 on event 9 SG A MAIN STEAM LINE BREAK UPSTREAM OF FT 9
11 Insert remote LOA1SGN023 to 0 in 10 on event 11 1MS-235 P-29 AFP & RADWASTE STM ISOL 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
SEG PBN LOI NRC 25E, 2021 NRC Exam Scenario 4, Rev 0 Page 9 of 33 00:00:00 Insert malfunction RLY1PPL018 to Fail_As_Is 1-CPA CPCI ACTUATION RELAY TRAIN A 00:00:00 Insert malfunction RLY1PPL019 to Fail_As_Is 1-CPB CPCI ACTUATION RELAY TRAIN B Seismic Event Schedule Files At Time On Event Action Description 00:00:00 Insert remote LOA1ANN004 to SEIS_EVT SEI-6210 Switchgear Seismic Detector 00:00:00 Insert remote LOA1ANN005 to SEIS_EVT SEI-6211 Facade Seismic Detector 00:00:00 Insert remote LOA1ANN006 to SEIS_EVT SEI-6212 Drum Area Seismic Detector 00:00:00 Insert remote LOA1ANN007 to SEIS_EVT SEI-6213 Aux FW Tunnel Seismic Detector 00:00:00 Insert malfunction ANN-ROA-B06 to On SEISMIC DETECTOR ACTIVATION 00:00:00 Insert malfunction ANN-1BOPF-A01 after 5 to On delete in 15 LO PRESS FEEDWATER HEATER 1A,2A OR 3A LEVE 00:00:00 Insert malfunction ANN-1BOPF-B01 after 5 to On delete in 15 LO PRESS FEEDWATER HEATER 1B,2B OR 3B LEVE 00:00:00 Insert malfunction ANN-1BOPF-D02 after 10 to On delete in 20 STILLING MANIFOLD LEVEL HI 00:00:00 Insert malfunction ANN-1BOPF-B02 after 20 to On delete in 30 HEATER DRAIN TANK LEVEL HI-LO 00:00:00 Insert malfunction ANN-ROD-A01 after 10 to On delete in 20 SERVICE AIR HEADER PRESSURE LOW Event file: Trigger 9 Unit 1 Reactor Trip (JCRFTR)
TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 25E, 2021 NRC Exam Scenario 4, Rev 0 SEG Page 10 of 33 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 Inadvertent Letdown Isolation ACTION Booth: Insert TRIGGER 1 per Lead Evaluator Symptoms and Indications:
STUDENT PPCS Alarms:
RESPONSE o PRIORITY 1 & 2 COMPOSITE ALARM o F-134 LETDOWN LINE FLOW o P-135 LOW PRESS LETDOWN PRESS 1C04 Indications:
o 1PI-135, Letdown Pressure lowers to < 50 psig o 1FI-134, Letdown Line Flow lowers to approximately 0 gpm o Pressurizer level rising o Auto Charging Pump speed lowering o VCT Level lowering Annunciators o PRESSURIZER HIGH LEVEL CHANNEL ALERT (1C04 1C 3-3) o PPCS PRIORITY ALARM (1C20D 2-1)
BOP/RO Diagnoses the loss of letdown and reduces charging flow to minimum.
SRO Implements AOP-1D, CVCS Malfunction Crew
- 48. Check letdown - INADVERTENTLY ISOLATED (RO)
Go to manual on both charging pumps, secure one, and reduce the other Conditions for charging pump to minimum speed CT-A start here
- 50. Check that letdown restoration can be performed (RO)
- 51. Ensure letdown orifice outlet valves -SHUT (RO)
- 52. Ensure normal charging - IN SERVICE (RO)
- 53. Check PZR Level - GREATER THAN 20% (RO)
- 54. Establish letdown (RO)
- a. Open letdown line containment isolation valves
- b. Open RC loop B cold leg letdown isolation valve
- c. Ensure component cooling flow to non-regen heat exchanger -
ESTABLISHED, 1HC-130 TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 25E, 2021 NRC Exam Scenario 4, Rev 0 SEG Page 11 of 33 Event # 1 Inadvertent Letdown Isolation Takes 1HC-130 controller to manual, and establishes flow using pot
- d. Ensure charging flow - AT LEAST 20 GPM Adjusts changing pump controller until min of 20 gpm established
- e. Adjust backpressure and open letdown orifice outlet valves -
ESTABLISH DESIRED LETDOWN FLOW.
CT-A (CT-A) Opens one of 1CV-200A/B/C while maintaining pressure using hand controller 1HC-135, LP Letdown Line Pressure Controller in manual. Once letdown is established and stable, takes hand controllers 1HC-130 and 1HC-135 to Auto
- 55. Check PZR Level - AT PROGRAM LEVEL (RO)
- 57. Return to procedure and step in effect (SRO)
Assess Technical Specifications:
IF PZR level rises >52%, THEN LCO 3.4.9 is NOT MET CONDITION REQUIRED COMPLETION TIME ACTION A. PZR water level A.1 Restore PZR 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> not within limit in water level to MODE 1 within limit.
ROLE PLAY Booth Communications:
Respond to reports or direction to field operators as necessary.
SM Communications:
If asked, direct the crew to restore letdown using 1CV-200B orifice Isolation valve.
Respond to reports from crew members as required.
NOTES Continuation Criteria:
After the crew has restored letdown flow and is controlling charging flow, or at the discretion of the Lead Examiner, continue with the next event.
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PBN LOI NRC 25E, 2021 NRC Exam Scenario 4, Rev 0 SEG Page 12 of 33 Event # 2 0LT-4040 Condensate Storage Tank T-24A Level Transmitter fails low ACTION Booth: Insert TRIGGER 2 per Lead Evaluator Symptoms and Indications:
STUDENT PPCS Alarms:
RESPONSE o L-4040 CST Lvl A Low C01 Indications:
o CST T-24A Level instrument reads 0%
Annunciators o C01 A 2-9, T-24A or B Condensate Storage Tanks - Level High or Low o C01 A 3-9, T-24A or B Condensate Storage Tanks Level Low-Low BOP Diagnoses the CST Level instrument failure. References ARBs, and dispatches AO to investigate locally.
SRO Asses Technical Specifications TS 3.3.3, Post Accident Monitoring (PAM)
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A.1 Restore required 30 days with one required channel to channel inoperable. OPERABLE status.
ROLE PLAY Booth Communications:
TH AO: If directed to locally investigate 0LT-4040 T-24A Condensate Storage Tank Level Transmitter, wait two minutes and THEN report that there doesnt seem to be anything out-of-normal locally.
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 addressed Technical Specifications, or at the discretion of the Lead Examiner, continue with the next event.
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PBN LOI NRC 25E, 2021 NRC Exam Scenario 4, Rev 0 SEG Page 13 of 33 Event # 3 Inadvertent Turbine Trip Without Reactor Trip ACTION Booth: Insert TRIGGER 3 per Lead Evaluator Symptoms and Indications:
STUDENT Annunciators RESPONSE o AUTOMATIC ROD MOTION (1C04 1A 1-7) o REACTOR COOLANT HIGH TAVG TREF DEVIATION (1C04 1A 4-10) o BLEEDER TRIP VALVES AIR PRESSURE (1C03 1D 4-9 LOW) o 20 / AST SOLENOID TRIP (1C03 1E1 4-2) o TURBINE STOP VALVES TWO CLOSED (1C03 1E1 4-3) o TAVG STEAM DUMP CHANNEL ALERT (1C03 1E2 4-2) 1C03 Indications o Condenser Steam Dumps indicate open o S/G Steam Flow drops dramatically and then rises due to CSDs o Turbine Stop Valves indicate closed o Turbine Gov. Valves indicate closed o Turbine First Stage Pressure indicates 0 psig 1C04 Indications o Tavg rising o Tref lowering o NI Power lowering o Control Rods driving IN in AUTOMATIC at maximum rate BOP/RO Diagnoses the turbine trip without reactor trip, places rod control in manual.
SRO Implements AOP-25, Turbine Trip Without Reactor Trip Crew
- 1. Verify turbine trip (BOP)
- 3. Check reactor power - BETWEEN 5% and 50% (RO)
- 4. Stabilize reactor power and temperature.
- a. Set condenser steam dumps to stabilize reactor power referencing ATTACHMENT A, Reactor Power, Tavg and CSD Controller Settings, as needed: (BOP) o Condenser steam dumps to pressure control mode a) Null 1HFC-484 output by adjusting Auto Setpoint to match 1PI-484, Steam Header Pressure.
b) Place condenser steam dump mode selector switch to MANUAL c) Adjust 1HFC-484 Auto Setpoint to match reactor power to controller output.
o Condenser steam dumps to manual control mode:
a) Null 1HFC-484 output by adjusting Auto Setpoint to match 1PI-484, Steam Header Pressure.
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PBN LOI NRC 25E, 2021 NRC Exam Scenario 4, Rev 0 SEG Page 14 of 33 Event # 3 Inadvertent Turbine Trip Without Reactor Trip b) Place 1HFC-484 to auto balance and balance output.
c) Place condenser steam dump mode selector to manual.
d) Place 1HFC-484 to manual.
- b. Stabilize temperature as follows: (RO)
- 1) If temperature is lowering:
a) Step rods out in 3 to 5 step increments to stabilize reactor temperature at approximate reactor power per Attachment A, Reactor Power, Tavg and CSD Controller Settings
- c. Control reactor power between 5% and 40% as directed by shift management. (RO/BOP) 1HFC-484 and rods will be adjusted as necessary to maintain reactor power
- 5. Verify generator trip (BOP)
- 6. Check steam generator levels - STABLE AT OR TRENDING TO NORMAL (BOP)
ROLE PLAY Booth Communications:
TH AO: If AOs are dispatched to investigate the cause of the turbine trip, wait 3 minutes and report that that there is no apparent cause.
Respond to other 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 reactor power and temperature, or at the discretion of the Lead Examiner, continue with the next event.
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PBN LOI NRC 25E, 2021 NRC Exam Scenario 4, Rev 0 SEG Page 15 of 33 Event # 4 Seismic Event / 1P11A, CCW Pump Failure ACTION Booth: Insert TRIGGER 5 per Lead Evaluator Trigger 5 will open and run schedule file NRC Seismic 1.sch. After all events have run, CLOSE schedule file NRC 4 Seismic 1.sch. (This is necessary for the next seismic event to run properly)
TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 25E, 2021 NRC Exam Scenario 4, Rev 0 SEG Page 16 of 33 Event # 4 Seismic Event / 1P11A, CCW Pump Failure Symptoms and Indications:
STUDENT Rumbling sound accompanied by various momentary alarms
RESPONSE
o SEISMIC DETECTOR ACTIVATION (C01A 2-6) o 1C03 1D 1-4 and 1-5 1P-1A(B) RCP COOLING WATER FLOW LOW o 1C03 1F 1-1, 2-1, 3-1, 4-1 LP Feedwater Heater High and Low Level alarms PPCS Alarms:
o SEI-6210 through 6213 SEISMIC DETECTOR alarms 1C03 Indications:
o 1P-11A indicates running but at reduced flow (1FI-619)
BOP/RO Diagnoses reduced CCW system flow.
SRO Implements AOP-28, Seismic Event and AOP-9B, Component Cooling System Malfunction.
Crew AOP-9B, Component Cooling System Malfunction
RNO: IF component cooling surge tank level greater than 20%, THEN start one component cooling pump.
1P-11B AOP-28, Seismic Event (Implemented as a secondary priority)
- 1. Check plant conditions - NORMAL (RO/BOP and crew will contact AOs for field walkdowns)
- 2. Check seismic instruments - NOT TRIGGERED (BOP)
- 3. Notify DSM and implement Emergency Plan (SRO will direct SM to make notifications)
- 4. Perform a walkdown inspection per Attachment A, Seismic Event Checklist (Crew to coordinate with AOs)
Assess Technical Specifications:
CCW LCO 3.7.7 is NOT MET CONDITION REQUIRED COMPLETION TIME ACTION A. One CC pump A.1 Restore CC 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> inoperable pump to AND OPERABLE 144 hours0.00167 days <br />0.04 hours <br />2.380952e-4 weeks <br />5.4792e-5 months <br /> from discovery of status. failure to meet the LCO TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 25E, 2021 NRC Exam Scenario 4, Rev 0 SEG Page 17 of 33 Event # 4 Seismic Event / 1P11A, CCW Pump Failure ROLE PLAY Booth Communications:
PAB AO: One minute after the seismic event, report that 1P-11A, CCW Pump is making an excessive noise and you recommend securing the pump.
PAB AO: If asked, report pre-start check on 1P-11B, CCW pump, SAT PAB AO: After 1P-11B is started, report a SAT start on 1P-11B.
Lead AO: If directed to perform plant walkdowns per AOP-28, Att A, wait 10 minutes and report that the only damage was the CCW Pump.
Respond to other reports or direction to field operators as necessary.
SM Communications:
If asked, plant management has approved continued operation while walkdowns are being performed.
Respond to reports from crew members as required.
NOTES Continuation Criteria:
After the crew has switched operating CCW pumps, or at the discretion of the Lead Examiner, continue with the next event.
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PBN LOI NRC 25E, 2021 NRC Exam Scenario 4, Rev 0 SEG Page 18 of 33 Event # 5 Multiple Dropped Rods (J4 and I3)
ACTION Booth: Check that schedule file NRC 4 Seismic 1.sch is CLOSED, Then Insert TRIGGER 7 per Lead Evaluator STUDENT Symptoms and Indications:
RESPONSE Rumbling sound accompanied by various alarms Annunciators:
o SEISMIC DETECTOR ACTIVATION (C01A 2-6) o ROD BOTTOM ROD DROP (1C04 1A 1-5) o POWER RANGE ROD DROP (1C04 1A 4-5)
PPCS Alarms:
o SEI-6210 through 6213 SEISMIC DETECTOR alarms 1C04 Indications:
o Control Rod I3 (CBA) and J4 (CBC) rod bottom lights lit o Control Rod I3 and J4 IRPI indications at 0 steps BOP/RO Diagnoses multiple dropped rods and trips the reactor. (RO)
Performs EOP-0 Immediate Actions. (RO)
SRO Directs a reactor trip per AOP-6A, Dropped Rod Implements EOP-0, Reactor Trip or Safety Injection Crew AOP-6A, Dropped Rod
- 1. Check only one rod dropped RNO: Perform the following:
o Trip the reactor (RO) o Go to EOP-0, Reactor Trip or Safety Injection (SRO)
EOP-0, Reactor Trip or Safety Injection Conditions for CT-17 start here 1. Verify Reactor Trip (RO)
- 2. Verify Turbine Trip (RO)
RNO: Check if SI is required o Steam line A pressure less than 545 psig IF SI is required, THEN manually actuate both trains of SI and Containment Isolation Foldout Page #3: Faulted S/G Isolation Criteria (BOP)
IF any S/G pressure trending lower in an uncontrolled manner OR any S/G CT-17 action completely depressurized, THEN the following may be performed:
(CT-17) Isolate feed flow to faulted S/G.
Ensure 1FIC-4074A, 1P-53 AFP to 1HX-1A FCV in manual and shut AND 1AF-4001 AFP Disch SG A Inlet MOV shut TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 25E, 2021 NRC Exam Scenario 4, Rev 0 SEG Page 19 of 33 Event # 5 Multiple Dropped Rods (J4 and I3)
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%.
Control feed flow to B S/G using 1FIC-4074B, 1P-53 AFP to 1HX-1B FCV and 1AF-4000, 1P29 AFP Disch SG B Inlet MOV
- 5. Perform Attachment A, Automatic Action Verification, while continuing with this procedure. (BOP)
- 8. Check RCS Temperatures (RO) o Condenser steam dumps - AVAILABLE RNO: Adjust S/G(s) atmospheric steam dump controllers to 1005 psig o RCS Temperature With and RCP running: RCS average temperature - STABLE AT OR TRENDING TO 547°F RNO: Perform the following:
- 9. IF temperature is less than 547°F and lowering, THEN perform the following:
o Stop dumping steam o IF cooldown continues, THEN control total feed flow.
Control feed flow to B S/G using 1FIC-4074B, 1P-53 AFP to 1HX-1B FCV and 1AF-4000, 1P29 AFP Disch SG B Inlet MOV o IF cooldown continues, THEN isolate main steam lines Shut 1MS-2017/2018, Steam Generator A/B Main Steam Stop CV
- 12. Check if S/G are NOT faulted (RO)
RNO: Perform the following: (SRO)
Notify STA to MONITOR CSP Status per CSP-ST.0, CSF Status Trees Go to EOP-2, Faulted Steam Generator Isolation 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 TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 25E, 2021 NRC Exam Scenario 4, Rev 0 SEG Page 20 of 33 Event # 6 Faulted A Steam Generator ACTION Booth: TRIGGER 9 will auto insert on reactor trip.
Insert Trigger 11 per crew direction for local S/G isolations STUDENT Symptoms and indications:
RESPONSE Steam Flow indicated on A S/G Containment Pressure rising rapidly to >25 psig (Containment Spray setpoint)
S/G A level and pressure lowering rapidly, inconsistent with plant trip BOP/RO Performs actions as directed.
SRO Implements EOP-2, Faulted Steam Generator Isolation Crew EOP-2, Faulted Steam Generator Isolation
- 1. Check main steam isolation (RO)
- 2. Check if any S/G is not faulted (RO)
- 3. Identify faulted S/G (RO)
CT-17 action 4. (CT-17)Isolate faulted S/G (RO)
- d. Ensure SSG supply valve - SHUT, AF-4023
- e. Isolate flow from faulted S/G:
- 1) Ensure atmospheric steam dump - SHUT, 1MS-2016
- 2) Shut steam supply to turbine-driven AFW pump:
- 3) Ensure S/G blowdown isolation valves - SHUT:
- 4) Locally shut 1P-29 AFP/Radwaste steam isolation:
- 5) Locally shut main steam trap isolation: 1MS-228
- 6. Check secondary radiation (RO)
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PBN LOI NRC 25E, 2021 NRC Exam Scenario 4, Rev 0 SEG Page 21 of 33 Event # 6 Faulted A Steam Generator ROLE PLAY Booth Communications:
PAB AO: When directed to locally shut 1MS-235, AFP/Radwaste steam isolation, and 1MS-228, main steam trap isolation, then insert Trigger 11, wait two minutes and report the valves are shut.
Respond to reports or direction to field operators as necessary.
SM Communications:
Respond to reports from crew members as required.
NOTES TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 25E, 2021 NRC Exam Scenario 4, Rev 0 SEG Page 22 of 33 Event # 6 Faulted A Steam Generator ACTION Booth: None STUDENT RESPONSE 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 A8 - Verify containment spray not required
- a. Containment pressure recorder - HAS REMAINED LESS THAN 25 psig RNO: Perform the following:
- 1) Check containment spray actuated: annunciator C01 B 2-6, CONTAINMENT SPRAY, lit A9 - Verify ECCS Flow A10 - Verify AFW valve alignment - PROPER EMERGENCY ALIGNMENT A11 - Verify proper ECCS valve alignment A12 - Check containment spray NOT ACTUATED RNO: Check containment spray alignment:
- 1. Ensure all containment spray pump discharge valves 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 Takes one of 1P-14A/B, Containment Spray pump to pullout
- 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 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 105F A23 - Check G03/G04 switchgear room temperature less than 95F A24 - Periodically check status of spent fuel cooling.
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PBN LOI NRC 25E, 2021 NRC Exam Scenario 4, Rev 0 SEG Page 23 of 33 Event # 6 Faulted A Steam Generator EOP-1, Loss of Primary or Secondary Coolant:
STUDENT 1. Check if RCPs should be stopped (RO)
RESPONSE a. RCPs - ANY RUNNING; RNO: Go to Step 2 (SRO)
- 2. Check if S/Gs are NOT faulted (BOP)
- 3. Check intact S/G level (BOP)
- a. S/G Level - Greater than [52%] 33%: RNO: Maintain total feed flow greater than 275 gpm until level is greater than [52%] 33% in at least one S/G.
Control feed to B S/G based on level using 1FIC-4074B, 1P-53 AFP to 1HX-1B FCV and 1AF-4000, 1P29 AFP Disch SG B Inlet MOV
- 4. Check secondary radiation (BOP)
- 7. Reset isolation and lockout signals (BOP)
Containment isolation 1B03 and 1B04 non-safeguards equipment lockouts
- 8. Establish Instrument Air to containment (BOP)
- b. Open instrument air containment isolation valves one at a time:
IA 3047 IA-3048
- 9. Check power supply to charging pumps (BOP)
- 10. Check if charging flow has been established (RO)
- 11. Check if ECCS flow should be terminated Evaluator Note: Step 11 is the same as Foldout Page #2
- b. Secondary heat sink: (BOP) o Level in at least one S/G - GREATER THAN [52%] 33%
OR o Total feed flow to intact S/G - GREATER THAN OR EQUAL TO 275 GPM
Pressure - GREATER THAN [1850 psig] 1725 psig AND Pressure - STABLE OR RISING
- d. PZR Level - GREATER THAN [26%] 11% (RO)
EOP-1.1, SI Termination Evaluator Note: Foldout Page #5 may apply upon entry to EOP-1.1.
Foldout Page #5: IF RCS hot leg temperatures are not stable, THEN control steam dump and total feed flow as necessary to stabilize RCS hot leg TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 25E, 2021 NRC Exam Scenario 4, Rev 0 SEG Page 24 of 33 Event # 6 Faulted A Steam Generator temperatures. (BOP)
RCS temperature stabilized using B S/G feed flow and 1HC-478, SG B Atmos Steam Dump Controller
- 2. Reset isolation and lockout signals (BOP)
Containment isolation 1B03 and 1B04 non-safeguards equipment lockouts
- 3. Establish Instrument Air to containment (BOP)
- d. Open instrument air containment isolation valves one at a time:
IA 3047 IA-3048
- 4. Check if charging flow has been established (RO)
- a. Stop both SI pumps and place in auto
- c. Stop both RHR pumps and place in auto
- 7. Check if containment spray should be stopped (BOP)
- a. Containment spray pumps - ANY RUNNING
- b. Containment pressure - LESS THAN 20 psig
- c. Reset containment spray signal
- d. Ensure containment spray pump RWST suction MOVs - OPEN
- e. Stop both containment spray pumps and place in auto
- f. Shut containment spray pump discharge valve and place in auto-after-shut position Shuts 1SI-860A/B/C/D, Containment Spray Pump flow MOVs, and places control switch in Auto
- g. Ensure both spray additive eductor suction valves - SHUT Places 1YIC-926A/B, Spray Add Eductor Suct Flow controller in manual and shuts valve TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 25E, 2021 NRC Exam Scenario 4, Rev 0 SEG Page 25 of 33 Event # 6 Faulted A Steam Generator 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 76F and stable.
o TH AO: When directed to check G03/G04 switchgear room temperature, wait 1 minute and report 80F and stable.
Respond to other 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 crew has completed through Step 7 of EOP-1.1, SI Termination, or per Lead Evaluator.
Freeze the simulator NOTES Determine if the NRC has any follow up questions Save SBT Data (see sim setup instructions)
TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 25E, 2021 NRC Exam Scenario 4, Rev 0 SEG Page 26 of 33 QUANTITATIVE ATTRIBUTES Malfunctions:
Before EOP Entry:
1CV-200A inadvertently shuts CST Level Instrument fails Inadvertent turbine trip 1P-11A CCW Pump failure Two dropped rods After EOP Entry:
Safety Injection fails to auto actuate Abnormal Events:
CVCS Malfunction Instrument Malfunction Turbine Trip Without Reactor Trip Dropped Rod Seismic Event Major Transients:
Faulted Steam Generator Critical Tasks:
- 1. CT-A Restore Letdown
- 2. CT-17 Isolate faulted S/G Major Procedures:
AOP-1D AOP-24 AOP-25 AOP-9B AOP-28 AOP-6A EOP-0 EOP-2 EOP-1 EOP-1.1 TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 25E, 2021 NRC Exam Scenario 4, Rev 0 SEG Page 27 of 33 CT-A Restore normal or excess letdown Critical Task:
Restore letdown or excess letdown prior to automatic reactor trip.
Plant Conditions:
Any condition greater than P-7 Loss of letdown where letdown can be restored from the control room Cues:
PZR level going up VCT level lowering Letdown flow and pressure annunciators PZR High Level Channel Alert Performance Indicator:
Manipulation of controls as required to restore letdown or excess letdown Feedback:
Indication and/or annunciator that letdown has been restored.
Basis:
Taking action to ensure letdown is restored and maintained such that a reactor trip (either manual or automatic) is prevented.
TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 25E, 2021 NRC Exam Scenario 4, Rev 0 SEG Page 28 of 33 CT-17 Isolate faulted steam generator Critical Task:
Isolate the faulted steam generator before creating a challenge to the Integrity CSF.
Plant Conditions:
Faulted Steam Generator Cues:
Indication and/or annunciation that both the following are occurring:
Steam pressure and flow rate indications that make it possible to identify a single SG as faulted AND Valve position and flow rate indication that AFW continues to be delivered to the faulted SG Performance Indicator:
Manipulation of controls as required isolating the faulted SG MSIVs indicate closed Indication of feedline isolation o Feedwater control valves indicate closed o Feedline isolation valves indicate closed o Main feed pumps indicate tripped Indication that AFW flow to the faulted SG is stopped o AFW flow control valves for faulted SG indicate closed Feedback:
Any depressurization of intact SGs stops Steam flow indication from faulted SG decreases to zero RCS cooldown stops Main feedwater flow rate indication of zero AFW flow rate indication to faulted SG of zero Basis:
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 faulted SG can result in challenges to the following CSFs:
Integrity Subcriticality TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 25E, 2021 NRC Exam Scenario 4, Rev 0 SEG Page 29 of 33 Booth Summary Event #1 Inadvertent Letdown Isolation Action Booth: Insert TRIGGER 1 per Lead Evaluator Role Play Respond to reports or direction to field operators as necessary.
Event #2 0LT-4040 Condensate Storage Tank T-24A Level Transmitter fails low Action Booth: Insert TRIGGER 2 per Lead Evaluator Role Play TH AO: If directed to locally investigate 0LT-4040 T-24A Condensate Storage Tank Level Transmitter, wait two minutes and THEN report that there doesnt seem to be anything out-of-normal locally Respond to reports or direction to field operators as necessary.
Event #3 Inadvertent Turbine Trip Without Reactor Trip Action Booth: Insert TRIGGER 3 per Lead Evaluator Role Play Booth Communications:
TH AO: If AOs are dispatched to investigate the cause of the turbine trip, wait 3 minutes and report that that there is no apparent cause.
Respond to other reports or direction to field operators as necessary.
Event #4 Seismic Event / 1P11A, CCW Pump Failure Action Booth: Insert TRIGGER 5 per Lead Evaluator Trigger 5 will open and run schedule file NRC Seismic 1.sch. After all events have run, CLOSE schedule file NRC 4 Seismic 1.sch. (This is necessary for the next seismic event to run properly)
Role Play Booth Communications:
PAB AO: One minute after the seismic event, report that 1P-11A, CCW Pump is making an excessive noise and you recommend securing the pump.
PAB AO: If asked, report pre-start check on 1P-11B, CCW pump, SAT PAB AO: After 1P-11B is started, report a SAT start on 1P-11B.
Lead AO: If directed to perform plant walkdowns per AOP-28, Att A, wait 10 minutes and report that the only damage was the CCW Pump.
Respond to other reports or direction to field operators as necessary.
Event #5 Multiple Dropped Rods (J4 and I3)
Action Booth: Check that schedule file NRC 4 Seismic 1.sch is CLOSED, Then Insert TRIGGER 7 per Lead Evaluator Role Play Respond to other reports or direction to field operators as necessary.
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PBN LOI NRC 25E, 2021 NRC Exam Scenario 4, Rev 0 SEG Page 30 of 33 Event #6 Faulted A Steam Generator Action Booth: Insert TRIGGER 9 per Lead Evaluator Insert Trigger 11 per crew direction for local S/G isolations Role Play Booth Communications:
PAB AO: When directed to locally shut 1MS-235, AFP/Radwaste steam isolation, and 1MS-228, main steam trap isolation, then insert Trigger 11, wait two minutes and report the valves are shut.
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 76F and stable.
o TH AO: When directed to check G03/G04 switchgear room temperature, wait 1 minute and report 80F and stable.
Respond to other reports or direction to field operators as necessary.
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PBN LOI NRC 25E, 2021 NRC Exam Scenario 4, Rev 0 SEG Page 31 of 33 SHIFT TURNOVER INFORMATION PLANT CONDITIONS:
UNIT 1 Time in core life (MWD/MTU): 9500 Reactor power (%): 47%
Boron concentration (ppm): 1111 ppm Rod height, CBD @: 220 TECHNICAL SPECIFICATION ACTION CONDITIONS IN EFFECT:
TSAC Description Required Action & Completion Time U1 3.3.1.A/K RPS one channel inoperable 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 /> EQUIPMENT OUT OF SERVICE:
G03 Emergency Diesel Generator for maintenance.
1LT-426 Pressurizer Level Transmitter.
PLANNED EVOLUTIONS:
Power ascension to 100%.
TURNOVER INFORMATION:
G04 Emergency Diesel Generator is aligned to both 1A06 and 2A06 4160 Safeguards Busses.
On line risk is GREEN.
Today is Tuesday, day shift.
TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 25E, 2021 NRC Exam Scenario 4, Rev 0 SEG Page 32 of 33 Pre-Scenario Procedure Checks Procedure SRO 1st Check 2nd Check AOP-1D AOP-6A AOP-9B AOP-25 AOP-28 EOP-0 EOP-1 EOP-1.1 EOP-2 Specific ARP/ARBs to be second checked - All Others first checked 1st Check 2nd Check 1C20D 2-1 1C03 1E1 4-2 1C03 E1 4-3 1C03 D 1-4 1C03 D 1-5 C01 A 2-9 C01 A 3-9 TR-AA-230-1007-F14, Revision 0
PBN LOI NRC 25E, 2021 NRC Exam Scenario 4, Rev 0 SEG Page 33 of 33 Post-Scenario Procedure Checks Procedure SRO 1st Check 2nd Check AOP-1D AOP-6A AOP-9B AOP-25 AOP-28 EOP-0 EOP-1 EOP-1.1 EOP-2 ARBs 1st Check 2nd Check 1C20D 2-1 1C03 1E1 4-2 1C03 1E1 4-3 1C03 D 1-4 1C03 D 1-5 C01 A 2-9 C01 A 3-9 RESET IC N/A Booth Cleared Exam Material Magnets Replaced P&IDs cleaned and replaced Dots removed from alarm windows TR-AA-230-1007-F14, Revision 0