ML110970607
| ML110970607 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 04/06/2011 |
| From: | NRC/RGN-II |
| To: | Progress Energy Carolinas |
| References | |
| 50-324/10-302, 50-325/10-302 | |
| Download: ML110970607 (170) | |
Text
PROGRESS ENERGY CAROLINAS BRUNSWICK TRAINING SECTION SIMULATOR SCENARIO 2010-2 NRC EXAM SCENARIO #1 J
Appendix D Scenario Outline Form ES-D-1 Facility: BRUNSWICK Scenario No.: 2010-2 # I Op-Test No.: DRAFT Examiners: Operators:
(SRO)
(RO)
(BOP)
Initial Conditions: The plant is operating at 50% power during startup following a refueling outage.
Core Spray Pump 2A out of service.
Turnover: Following shift turnover, raise reactor power to 60% and place the second Reactor Feedwater Pump in service.
Event Maif. No. Event Event Description No. Type*
0 N/A N/A Determine LCO for 2A Core Spray lnoperabHity (TS) 1 N/A R-RO Raise power to 60%
R-SRO 2 N/A N-BOP Place the second Reactor Feedwater Pump in service.
N-SRO 3 ESO22F C-RO Inadvertent RCIC initiation .(TS)(AOP)
C-SRO K4510C C-BOP 2A Steam Packing Exhauster trip.
ZUA2I5 C-SRO 5 P27391 I C-RO 2A Reactor Recirculation pump flow controller slowly fails downscale.
C-SRO (TS)(AOP) 6 EEO3OM C-BOP Loss of MCC 2XC.(TS)
C-SRO 7 ESO25M M-All RCIC steam line break ESO24F E51-F008 Thermal overload Manual reactor Scram prior to MSOT/L 7a K5623A C-BOP North RHR room cooler failure K5623B C-SRO South RHR room cooler trip after start 8 Emergency Depressurization required (2 areas above Max Safe Operating Temperature or EQ envelope exceeded) 8a RPV depressurized with level in the normal band.
(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Paoe2of34
SCENARIO DESCRIPTION The plant is operating at 50% power during startup following a refueling outage.
Event 0 While the ROs are walking the control boards, prior to assuming the watch, the SRO will determine TS 3.5.1, Condition A, Required Action is to restore 2A Core Spray to Operable Status within 7 days of inoperability.
Event I Raise reactor power to > 60% using reactor recirculation flow.
Event 2 Place the second reactor feed pump in service lAW 20P-32.
Event 3 RCIC will inadvertently initiate. The crew should respond per OAOP-03.0 and trip RCIC. RCIC should be declared inoperable per TS 3.5.3.
Event 4 SPE 2A will trip causing a loss of gland sealing header pressure. SPE 2B will be placed in service.
Event 5 2A Reactor Recirculation pump flow controller slowly fails downscale requiring entry into 2AOP-4.0, Low Core Flow and locking the scoop tube. Based upon time to lock the 2A scoop tube TS 3.4.1 entry may be required.
Event 6 MCC 2XC will trip due to breaker failure (loss of power to E51-F007).
Event 7 A line rupture will develop in the RCIC steam supply which cannot be isolated due to loss of power to E51-F007 and the E51-F008 will thermally trip. OAOP-05 and SCCP will be entered and the Reactor Building temperatures and radiation levels will rise.
The crew should insert a manual scram when they recognize there is an unisolable steam leak in Secondary Containment before SRHR reaches Maximum Safe Operating Temperature. After the scram is inserted the crew should enter EOP RSP and EOP-01-RVCP. Reactor building pressure will go positive requiring entry into RRCP.
Event 7a 2B RHR room cooler will auto start and will later trip when SRHR Room temperature reaches 190°F. The 2A RHR room cooler will not operate. As temperatures in multiple areas of the RB rise the crew may Anticipate Emergency Depressurization.
If Emergency Depressurization is anticipated, the RPV will be rapidly depressurized to the main condenser.
Event 8 If emergency depressurization is not anticipated, secondary containment temperatures will exceed maximum safe operating values in two areas, or EQ Envelopes will be reported as being exceeded, which will require emergency depressurization.
Event 8a Once the reactor is depressurized and RPV level is being maintained +170-200, the scenario may be terminated.
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OBJECTIVES SRO
- 1. 341 224B1 02 Determine Actions Required For Limiting Conditions For Operation
- 2. 344205B402, Direct Shift Response To A Moderator Temperature Decrease Per AOP-03.0
- 3. 344206B402 Direct Shift Response To A Recirculation Flow Control Failure Causing A Decreasing Flow Per AOP-04.0
- 4. 344207B502, Direct Actions To Control Secondary Containment Area Temperatures Per EOP-03-SCCP
- 5. 3442088502, Direct Actions To Control Secondary Containment Area Radiation Levels Per EOP-03-SCCP
- 6. 344209B502, Direct Actions To Control Secondary Containment Water Level Per EOP-03-SCCP
- 7. 344233B502, Direct Actions To Anticipate Emergency Depressurization Per EOP 01-RVCP
- 8. 344217B502, Direct Actions To Control RPV Level Per EOP-01-RVCP
- 9. 3442278502, Direct Actions To Control An Unmonitored Radioactive Release With The Release Rate Less Than That Requiring An Alert Declaration Per EOP-04-RRCP RO
- 1. 202014B401 Respond To A Recirc Flow Control Failure Decreasing Per AOP 04.0
- 3. 2722018401 Respond To An Area Radiation Annunciator Per APP UA-03
- 4. 2000658501 Monitor Reactor Water Level Instrumentation Per EOP Caution I
- 5. 200601B401 Respond to radioactive spills, high radiation and airborne activity per AOP-5.0
- 6. 2006038501 Perform immediate actions for a reactor scram
- 7. 200219B501 Rapidly Depressurize the Reactor Using the Bypass Valves per EOP 01-RVCP REFERENCES A. OP-26.1 B. OP-32 C. GP-04 D. AOP-03.0 E. AOP-04.0 F. AOP-05.0 G. 01-50 H. EOP-01-RSP I. EOP-01-RVCP J. EOP-02-PCCP K. EOP-03-SCCP L. EOP-04-RRCP M. Conduct Of Operations Manual N. Technical Specifications
- 0. Plant Emergency Procedures P. Annunciator Panel Procedures Paae4of34
SIMULATOR SETUP A. Initial Conditions
- 1. IC 9
- 2. Rx Pwr 50%
- 3. core Age BOC B. Event Triggers Event Trigger Event / Trigger Description 1 N/A Normal Operation (Raise reactor power and place REP 2 in-service) 2 1 Manually Initiated (ESO22E RCIC Inadvertent Start) 3 2 Manually Initiated (2A SPE trip) 4 3 Manually Initiated (RR 2A Elow control fails low) 5 4 Manually Initiated (Loss of MCC 2XC E51-E007) 6 5 Manually Initiated (RCIC Steam Leak in SRHR) 7 6 Auto Initiated (RHR Room Temp> 190°E trips B RHR room cooler) 8 N/A Emergency Depressurization 7 Maximize Hotwell Makeup C. Malfunctions Malfunctions Summary Maif ID Mult Description current Target Rmptime Actime Dactime Trig ID Value Value ESO22F cic INADVERTANT START FALSE TRUE 1 EEO3OM 2XC INDIVIDUAL BUS FAILURE FALSE TRUE 4 E5025F RCIC STM BRK SOUTH RHR
- 0 100% 3 mm 5 ESO24F RCIC STM ISOL VLV MOTOR OVLD TRUE TRUE Remotes Summary Remf ID Mult Description current Target Rmptime Actime Trig ID Value Value ED_IABKCFO5 BKR CTL DC FUSES CORE SPRAY OUT OUT PUMP 2A CFIAHWMUC HOTWELL M/U VLV CONTROLLER AUTO MAN 7 CF_IAHWMUM HW MAN CNTR SR FOR M/U 0 1.0 7 CF_IAHWRJC HOTWELL REJECT VLV CONTROLLER MAN MAN 7 CF_IAHWRJM HW MAN CNTR S.P. FOR REJECT .1400 0 7 Paoe5of34
SIMULATOR SETUP D. Overrides Switches Tag ID Description Position! Actual Override Rmptime Actime Dactime Trig Target Value Value P2739A1 1 RECIRC A FLOW CONTROL .1 .53 .53 45 SEC 3 K4510C STM PACKING EXHAUSTER NORMAL ON OFF 2 CLOSE Dl K4510C STM PACKING EXHAUSTER START OFF OFF 2 CLOSE Dl K4510C STM PACKING EXHAUSTER STOP OFF ON 2 CLOSE Dl K5623A RHR PMP RM VENT FAN B AUTO ON OFF 6 K5623A RHR PMP RM VENT FAN B OFF OFF OFF 6 K5623A RHR PMP RM VENT FAN B ON OFF OFF 6 K5623A RHR PMP RM VENT FAN A AUTO ON OFF K5623A RHR PMP RM VENT FAN A OFF OFF OFF K5623A RHR PMP RM VENT FAN A ON OFF OFF Lamps Tag ID Description Position! Actual Override Rmptime Actime Dactime Trig Taroet Value Value Annunciator Summary Activate Deactivate Trig Event Panel Tag Title Value (ramp Time (sec) Time (sec) rate) 3 XU-3 ZUA215 STM PACKING EXHAUSTER ON 0 SEC NA 2 A OVLD TRIP Pacie6of34
E. Materials
- 1. ENP-24 for IC-9 (Sequence 2A)
- 2. OGP-04 marked up to Step 5.2.22.
- 3. Mark-up OGP-04, Attachment 1, for 30, 40 and 50% power.
F. Special Instructions
- 1. Ensure Exam In Progress Stop Signs posted at all simulator entrances.
- 2. Advance all chart recorders to indicate steady state conditions.
- 3. Place all SPDS displays to the Critical Plant Variable display (#100).
- 4. Ensure appropriate keys have blanks in switches.
- 7. Ensure reference material is in appropriate location.
- 8. Verify all log books have blank sheets only.
- 9. Ensure ENP-24 for lC-9 @ P603.
- 10. Verify APRM GAF5 are < 1.00 (allow time for stabilization)
- 11. Have the computer on the Heat Balance page 1.
- 12. Reduce reactor power to 50% with Recirc Flow.
- 13. Load scenario file, NRC 1.scn, if required.
- 14. Place 2B Stator Cooling pump in service.
- 15. Place red cap on Core Spray Pump 2A.
- 16. Ensure Master Level Controller setpoint at 190 inches.
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SHIFT BRIEFING Plant Status The plant is operating at -5O% power during startup following a refuel outage.
OGP-04 is completed up to step 5.2.22.
Alternate Power verifications lAW OGP-04, are being performed by the Reactor Engineer.
Equipment Out of Service Core Spray Pump 2A is under clearance for breaker repair and is expected to be returned to service in two hours.
Plan of the Day Determine LCO for Core Spray Pump 2A inoperability effective upon assuming the watch.
Raise power to 60% and prepare to place the second feed pump in service.
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SCENARIO TRAINING INFORMATION A. Instructor Notes
- 1. This guide is designed to meet the requirements of an examination scenario for Initial License as outlined in NUREG-1021, Revision 9, ES-301 and Appendix D.
- 2. During the execution of this scenario, the students should be rated on the performance of the objectives, compliance with general simulator performance standards, and for overall team skills in accordance with TAP-409 and NUREG-1 021, ES-303.
B. Common Student Problems/Errors None C. Simulator Deficiencies There are no known simulator deficiencies applicable to this scenario.
D. CREW CRITICAL TASKS (Critical Tasks are identified to ensure scenario validity and do not constitute pass/fall criteria for Initial License.)
- 1. Manually Scram the Reactor before an area reaches Maximum Safe Operating value.
- 2. Depressurize the RPV by performing or anticipating Emergency Depressurization.
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EVENT 0 CORE SPRAY PUMP 2A INOPERABILITY While the ROs are walking the control boards, prior to assuming the watch, the SRO will determine TS 3.5.1, Condition A, Required Action is to restore 2A Core Spray to Operable Status within 7 days of inoperability.
Objectives:
SCO Determines TS 3.5.1, Condition A, Required Action is to restore 2A Core Spray to Operable Status within 7 days.
RO I BOP Perform control board walk downs Success Path:
LCO 3.5.1, Condition A addressed.
Simulator Operator Actions:
L If requested to verify back panel relay positions, report complete lAW 20P-26.
Required Operator Actions Inform crew Core Spray pump 2A is required to be restored to operable within 7 days.
SRO Time Action Notes References TS 3.5.1 Determines 2A CS is required to be restore to Operable Status within 7 days.
3.5 EMERGENCY CORE GOOLIN3 SSTEMS (EGOS) AND REACTOR CORE ISCLATION COOLING (RCIG) 3i3T1 3.5.1 ECCSCperalng LCO 3.5.1 ch EGGS injetoftispray sulystern and the Automattc Depressurization. System (ADS function of sx satetyfrelief vIves shall be CPERELE, APPLICADILITY: MODE 1, MOflFR 2 d ccpt hOh prt m rn[nl injection (1-IPCI) ni AflS valves are not required to be OPERABLE Ath reader steam dome prceourc 150 pig.
ACTIONS LCO 3.14.bis nctapçliccbo to HPCI.
CONDTICN REQUIRED ACTION COMPLETION TIME A One lcw pressure EGOS Al Restore low pressure 7 days irjectionspay b3y3tem CC.CC injedianl5pray inoperable, subsystem to OPERABLE status.
CR One lcw pressure coolant irlection (LPC1) pump in ch subsytrn inoprahl.
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EVENT I SHIFT TURNOVER, RAISE REACTOR POWER TO 60%
The crew will complete shift turnover and raise reactor power to 60%.
Malfunctions required: None.
Objectives:
SCO Directs reactor power to be raised using Recirc pump speed control.
RO Performs power increase using Recirc flow control.
Success Path:
Power is raised to 60% power.
Simulator Operator Actions:
E If contacted as the RE for power increase guidance, inform crew to raise power using Reactor Recirc flow.
D If contacted as the RE to monitor power increase, inform crew that you will monitor core performance and when plant is at 60% power inform crew Alt Power at is SAT.
E When directed by the lead examiner, proceed to the next event.
Required Operator Actions Reactivity Manipulation Raise power 10% using Recirc pump speed controls.
SRO Time Action Notes Directs Power to be raised to 60%
power.
RO Time Action Notes Raises power using recirculation flow to 60% power.
Raise flow on one RR Pump (2%)
at a time to stay within mismatch criteria (7.5x1 6 Mlbs jet pump flow if < than 58 MIbs or 3.5x10 6 Mibs if> than 58 Mibs).
Continues alternating Recirc pump increases until power is 60%.
Verifies operation on the Power to Flow map.
Reports alarm clear as RR flow is raised.
A-5 4-8 OPRM TRIP ENABLED BOP Time Action Notes Plant Monitoring EVENT 2 PLACE THE SECOND REACTOR FEED PUMP IN SERVICE Paae 11 of34
BOP Places the second reactor feed pump in service.
Objectives:
SCO Directs placing the second RFP in service lAW 20P-32 Section 5.7.
BOP Places the second reactor feed pump in service lAW 20P-32 Section 5.7.
Success Path:
Place the second RFP in service.
Simulator Operator Actions:
D If contacted as the RE to monitor core performance, inform crew that you will monitor core performance on the computer.
- Acknowledge requests for the Radwaste Operator.
D After RFP B RECIRC VLV, FW-FV-V47, has been closed and when directed by the lead examiner, proceed to the next event.
Required Operator Actions Normal Operations Places Second REP in service.
SRO Time Action Notes Directs Second REP be placed in service lAW 20P-32.
RO Time Action Notes Plant Monitoring Paae 12 of 34
EVENT 2 (CONT) PLACE THE SECOND REACTOR FEED PUMP IN SERVICE BOP Time Action Notes Performs 20P-32, Section 57 Determines initial conditions met.
Notify Radwaste Operator to monitor CDD flows and place additional demineralizers in service as necessary.
Ensure RFP B LP SUPPLY VLV, RHS-V1, is open Slowly raise RFPT B speed by placing RFPT B LOWER/RAISE speed control switch in RAISE until speed is greater than approximately 2550 rpm When RFPT B speed is greater than approximately 2550 rpm, then raise RFPT B SP CTL, C32-SIC-R6OIB, output to match DFCS STPT and SPEED STPTon Panel P603 to within 100 rpm.
Notify Radwaste Operator to monitor CDD effluent conductivity for each demineralizers in service Confirm the following RFPT B speed signals on Panel P603 agree within approximately 100 rpm:
. DFCS STPT (speed demand from DFCS).
. SPEED STPT (speed demand from 5009 control)
Place MAN/DFCS control switch in DFCS.
Slowly raise RFPT B speed by depressing the raise pushbutton on C32-SIC-R601 B until REP discharge pressure is approximately equal to reactor pressure.
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EVENT 2 (CONT) PLACE THE SECOND REACTOR FEED PUMP IN SERVICE BOP Time Action Notes Open REP B DISCH VLV, FW-V4 Slowly raise RFPT B speed, using RFPT B SP CTL, C32-SIC-R6O1B, until B DEM is approximately equal to A DEM of the on line REP.
DEPRESS AIM pushbutton on RFPT B SP CTL,C32-SIC-R6O1B, AND CHECK AIM indicator changes to A (automatic).
When pump suction flow is greater than 3.9 x i6 Ibm/hr, and heater drains are forward pumping, then close RFP B RECIRC VLV, FW-FV V47, by momentarily placing control switch in CLOSE.
When REP B RECIRC VLV closes, then adjust level setpoint on MSTR REPT SPIRX LVL CTL, C32-SIC-R600, to 187 inches.
Notifies Radwaste Operator to monitor CDD effluent conductivity for each demineralizers in service Paae 14 of 34
EVENT 3 INADVERTENT RCIC INITIATION RCIC will inadvertently initiate. The crew should respond per OAOP-03.O and trip RCIC.
RCIC should be declared inoperable per TS 3.5.3..
Objectives:
5CC Direct shift response to a moderator temperature decrease.
RO Shutdown the RCIC system with an automatic initiation signal present.
Success Path:
RCIC shutdown and Tech Specs 3.5.3 RCIC System Condition A Verify HPCI is OPERABLE and restore RCIC to OPERABLE status within 14 days.
Simulator Operator Actions:
LI When the directed by the lead examiner, initiate Trigger I to inadvertently start RCIC.
LI If RCIC has been running for >5 minutes, and crew has not recognized RCIC running, call control room as AO and ask why RCIC is running.
LI If asked as l&C to investigate, acknowledge the request LI If asked as RE to monitor thermal limits, acknowledge the request.
LI If asked as chemistry for Rx Coolant Sample, acknowledge the request.
LI When directed by the lead examiner, proceed to the next event.
Required Operator Actions Instrument/Component Malfunction RCIC shutdown Technical Specification TS 3.5.3 RCIC System SRO Time Action Notes Direct entry into OAOP-03.O.
Direct I concur RCIC operation to be terminated.
May contact RE to monitor thermal limits due to the cold water injection from RCIC.
Contact l&C to investigate RCIC logic.
Tech Spec 3.5.3 RCIC System Determine Condition A applies Required Action A.1, Immediately verify HPCI is OPERABLE AND Required Action A.2, Restore RCIC to OPERABLE within 14 days.
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EVENT 3 (CONT) INADVERTENT RCIC INITIATION RO Time Action Notes Recognize and report RCIC injection Enter and announce 0AOP-03.0 Verify inadvertent initiation by two HPCI & RCIC auto start on RPV Water independent indications and trip RCIC. Level Lo Lo (105 inches) should have automatically Scrammed prior to this level, Depress TURBINE TRIP, E51-S1 7, push button to trip the RCIC turbine Monitors reactor power and thermal limits.
Acknowledge alarms due to RCIC trip A-3 3-4 RCIC PUMP DISCH FLOWLO 4-5 RCIC BAROM CNDSR VAC TANK LVL HI 5-3 RCIC TURBINE TRIPPED A-03 3-5, RCIC TURBINE STM LINE DRN POT LEVEL HI will annunciate requiring the operator to perform the following if it has been in for 5 minutes:
Close TURBINE TRIP & THROTTLE VLV, E51-V8, motor operator.
BOP Time Action Notes Plant Monitor Paae 16 of 34
EVENT 4 STEAM PACKING EXHAUSTER TRIP SPE 2A will trip causing a loss of gland sealing header pressure. SPE 2B will be placed in service.
Objectives:
SCO Direct shift response to SPE trip.
Success Path:
SPE 2B placed in service.
Simulator Operator Actions:
o When the directed by the lead examiner, initiate Trigger 2 to trip SPE 2A.
O If asked as l&C to investigate, acknowledge the request 0 If asked as TBAO to investigate, acknowledge the request.
0 If directed to open FLOAT TRAP OUTLET VALVE, MVD-V52 or prestart check 2B SPE, acknowledge request, wait 1 minute and report prestart SAT and MVD-V52 is open.
0 If directed to close FLOAT TRAP OUTLET VALVE, MVD-V51, wait 1 minute and report MVD-V51 is closed.
0 When directed by the lead examiner, proceed to the next event.
Required Operator Actions Component Malfunction SPE 2A trip with discharge valve failure to auto close.
SRO Time Action Notes Acknowledge report of 2A SPE trip alarms UA-02 1-5 STM PACKING EXHAUSTER A OVLD TRIP 4-5 GLAND SEAL VACUUM LOSS Contacts maintenance to investigate.
Directs placing 2B SPE in service lAW 2OP-26. 1.
Concurs with 2OP-26.1 NOT APPLICABLE (N/A) steps for section to be performed.
Acknowledges alarm reset UA-02 4-5 GLAND SEAL VACUUM LOSS Pacie 17 of34
EVENT 4 (CONT) STEAM PACKING EXHAUSTER TRIP RO Time Action Notes Plant Monitor BOP Time Action Notes Acknowledges & reports 2A SPE trip alarms UA-02 1-5 STM PACKING EXHA USTER A OVLD TRIP 4-5 GLAND SEAL VACUUM LOSS Identifies & reports Exhauster discharge valve failed to auto close and closes STEAM SEAL SPE 2A MO DISCH VLV, OG-MOV-D1, Identifies 20P-26.1 section required to Either Section 5.1 or 8.1 may be utilized start 2B SPE. with steps N/Ad to support place SPE in service.
Directs TBAO to perform prestart checks and to open FLOAT TRAP OUTLET VALVE, MVD-V52.
Announces and starts SPE 2B.
Throttles open STEAM SEAL SPE 2B MO DISCH VLV, OG-MOV-D2, to restore GLAND EXHAUST HEADER, OG-Pl-EPT-9, located on Panel XU-2, to between 10 and 20 inches water vacuum.
Ensures STEAM SEAL SPE 2A MO DISCH VLV, OG-MOV-D1 and STEAM SEAL SPE 2A MO INLET VALVE,OG-MOV-E1 are closed Directs TBAO to close FLOAT TRAP OUTLET VALVE, MVD-V51.
Reports alarm reset UA-02 4-5 GLAND SEAL VACUUM LOSS Paae 18 of 34
EVENT 5 RECIRC FLOW CONTROLLER FAILURE 2A Reactor Recirculation pump flow controller slowly fails downscale requiring entry into 2AOP-4.0, Low Core Flow and locking the scoop tube. Based upon time to lock the 2A scoop tube TS 3.4.1 entry may be required.
Objectives:
SCO Evaluate TS 3.4.1 applicability RO - Lock 2A RR Scoop tube Success Path: Depending on how long the failure occurs before being recognized and stopped may require TS 3.4.1 actions. This event does not require TS evaluation, but may be evaluated if necessary.
Simulator Operator Actions:
LI When the directed by the lead examiner, initiate Trigger 3 to fail 2A RR speed controller (RO should not be looking at P603 in activated).
LI If notified as l&C to investigate, acknowledge request.
LI If notified as RE of Recirc flow control failure, acknowledge request.
LI When directed by the lead examiner, proceed to the next event.
Required Operator Actions Instrument/Component Malfunction 2A RR Flow Controller fails low requiring scoop tube to be locked.
Technical Specification If Jet pump loop flows are not within 10%, Declare loop with lower flow not in service and meet LCO within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SRO Time Action Notes May direct locking 2A RR scoop tube.
Direct entry into AOP-4.0 Contacts l&C to investigate.
Informs RE of RR pump 2A flow control failure.
Acknowledges report of annunciators A-5 4-8 OPRM TRIP ENABLED A-6 2-4 FLUID DRIVE A SCOOP TUBE LOCK Paae 19 of 34
EVENT 5 (CONT) RECIRC FLOW CONTROLLER FAILURE SRO Time Action Notes May Evaluate TS 3.4.1 Jet pump loop flows within 10%
SR 3.4.1.1 Verify recirculation loop jet
- (maximum indicated difference pump flow mismatch with both 7.5 x10 lbs/hr) with total core flow less recirculation loops in operation a. 10%
than 58 x10 6 lbs/hr of rated core flow when operating at
< 75% of rated core flow.
Recirculation Loops Operating 3.4.1 3.4 REAGTOR COOLANT SYSTEM (ROS) 3.4.1 Recirculation Loops Operating LCO 3.4.1 Two recirculation loops with matched flows shall be in operation.
OR One recircutation loop may be in operation provided the following limits are applied when the associated LCO is applicable:
- a. LCO 3.2.1, AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) single loop operation limits specified in the COLR;
- h. LCO 3.2.2, MINIMUM CRITICAL POWER RATIO (MCPR), single loop operation Limits specified in the COLR;
- c. LCO 3.2.3, LINEAR HEAT GENERATION RATE (LHGR), single loop operation limits specified in the COLR and
- d. LCO 3.3.1.1, Reactor Protection System (RPS) Instrumentation, Function lb (Average Power Range Monitors Simulated Thermal PowerHigh). Allowable Value of Table 3.3.1.1-1 is reset for single loop operation, APPLlAB1LlTY: MODES I and 2.
COMPLETION CONDITION REQUIRED AT1ON TIME A. Requirements of the LCO A.1 Satisfy the requirements of 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> not met. the LCO.
(continued)
Brunswf cit Unit 2 3.4-1 Amendment No. 274 Paae2O of 34
EVENT 5 (CONT) RECIRC FLOW CONTROLLER FAILURE BOP Time Action Notes Plant Monitor May adjust Main Generator Manual Voltage regulator to null the DVM.
RO Time Action Notes Identifies & reports RR 2A flow control failure.
Locks 2A RR scoop tube by placing the SCOOP TUBE A LOCK switch to TRIP.
Reports scoop tube locked and alarms A-5 4-8 OPRM TRIP ENABLED A-6 2-4 FLUID DRIVE A SCOOP TUBE LOCK Announces AOP-4.0 entry.
Report jet pump loop flow mismatch (either within 10% or not)
Determines current location on the Power-to-Flow Map.
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EVENT 6 LOSS OF MCC 2XC MCC 2XC will trip due to breaker failure (loss of power to E51-F007).
Objectives:
SCO Direct actions for MCC loss.
BOP I RO Evaluate impact of MCC 2XC loss on plant equipment.
Success Path:
Maintenance directed to investigate 2XC loss.
Simulator Operator Actions:
D When the crew has stabilized the plant after the RR Pump 2A flow controller failure and directed by lead examiner, initiate Trigger 4 to trip MCC 2XC feeder breaker on E7.
D If requested to investigate as AC or Maintenance, acknowledge request.
E When directed by the lead examiner, proceed to the next event.
Required Operator Actions Technical Specification MCC 2XC deenergized SRO Time Action Notes Acknowledges report of UA-1 7 3-2 SUB E7 FDR TO MCC-2XC BKR TRIP Contacts Maintenance to investigate MCC 2XC loss.
May Evaluate TS for loss of MCC 2XC See Attachment 3 for TS impact.
RO Time Action Notes Monitors the plant BOP Time Action Notes Acknowledges & reports UA-17 3-2 SUB E7 FDR TO MCC-2XC BKR TRIP
- 1. May refer to 001-50.3 for loss of loads.
- 2. Directs Auxiliary Operator to the Reactor Building to check for fault(s) in MCC-2XC.
- 3. Directs Auxiliary Operator to Substation E7, Breaker AYO, to check for fault(s).
- 4. May contact maintenance to investigate.
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EVENT 717A RCIC STEAM BREAK I SCRAM I RHR ROOM CLR FAILURES A line rupture will develop in the RCIC steam supply which cannot be isolated due to loss of power to E51-F007 and the E51-F008 will thermally trip. OAOP-05 and SCCP will be entered and the Reactor Building temperatures and radiation levels will rise. The crew should insert a manual scram when they recognize there is an unisolable steam leak in Secondary Containment before SRHR reaches Maximum Safe Operating Temperature. After the scram is inserted the crew should enter EOP-01-RSP and EOP-01-RVCP. Reactor building pressure will go positive requiring entry into RRCP.
Objectives:
SCO Directs manual Reactor Scram Enters RSP, RVCP BOP Performs AOP-05 & SCCP actions.
RO - Diagnose RCIC steam leak Execute AOP and EOP actions as directed by SRO Perform SCRAM actions Control reactor parameters post SCRAM Success Path:
Insert a manual Scram prior to SRHR room temperature reaching Max Safe.
Simulator Operator Actions:
1 When directed by lead examiner, initiate Trigger 5 to initiate RCIC steam leak.
If contacted as l&C, Maintenance, or OS AO to investigate, acknowledge the request When Rx Bldg ARM alarms, report as RBAO steam on 20 elevation and you have left the building D If requested to close PIV-33, wait 3 minutes and report closed D If contacted as Engineering, Chem, HP, Maintenance, I&C, OSAO, acknowledge report I requests.
When directed by the lead examiner, proceed to the next event.
Required Operator Actions Major Enter OAOP-05.0, Radioactive Spills, High Radiation, And Airborne Activity and upon recognition of RCIC isolation not available insert reactor scram.
Major Enter RSP, SCCP, and RVCP, anticipate and I or ED.
SRO Time Action Notes Acknowledge alarm reports of UA-03 2-7 AREA RAD RX BLDG HIGH 3-5 PROCESS RX BLDG VENT RAD HI-HI 4-5 PROCESS RX BLDG VENT RAD HIGH UA-05 3-9 RHRFANA FAIL TO START UA- 12 3-3 RX BLDG DIFF PRESS HIGH/LOW Pacie 23 of 34
EVENT 717A (CONT) RCIC STEAM BREAK I SCRAM I RHR ROOM CLR FAILURES SRO Time Action Notes Directs entry into AOP-05.O May direct evacuation of the reactor building Enter and directs EOP-03-SCCP Direct verification of auto actions RB Vent Exh rises above 4mr/hr RB HVAC isolations and SBGT auto start.
Diagnose leak from RCIC and direct RCIC isolation Direct manual Scram prior to SRHR **CRITICAL STEP**
reaching max safe temperature. SCRAM prior to SRHR room temperature exceeding 295°F.
Direct RHR room coolers be started Direct service water aligned to the vital header Evaluate Level instrument operability using Caution I (Wide Range N026s mop with Temperature on the Reactor Building 50 above 140°F)
Contact engineering to perform EQ evaluation Enters and directs EOP-OI-RSP Determines entry into EOP-O1-RVCP is required Directs verification
. Group Isolations
. ECCS Initiations
. Diesel Generator Auto Starts Directs restoring and maintaining reactor water level between +170 and
+200 inches Paae 24 of 34
EVENT 717A (CONT) RCIC STEAM BREAK I SCRAM I RHR ROOM CLR FAILURES SRO Time Action Notes RVCP Actions continued:
Directs pressure control using EHC and pressure band of 800-1 000#
May direct starting HPCI to maintain level Contacts l&C to investigate I help isolate RCIC.
Contacts I&C to investigate RHR room cooler failures.
May direct tripping Recirc Pumps for RPV level instrument indication (if level drops below 150)
Enters RRCP upon report of Reactor Building pressure going positive (un monitored release entry condition)
Requests Unit One calculate site boundary dose per PEP-3.4.7 Directs CREV be place in service.
Directs commencing normal cooldown not to exceed 1000 F/hr Directs Anticipating Emergency **CRITI CAL STEP**
Depressurization Cautions not to close MSIVs (Gpl)
RO Time Action Notes Monitors the plant Diagnose RCIC leak and attempt to manually isolate, Paae 25 of 34
EVENT 7/7A (CONT) RCIC STEAM BREAK I SCRAM I RHR ROOM CLR FAILURES RO Time Action Notes Recognize and report RCIC inboard valve failure Loss of MCC 2XC inability to isolate RCIC Recognize and report RCIC outboard valve failure and inability to isolate RCIC A-2 5-5 OTBD NSSS VALVES MTR OVERLOAD Align service water to the vital header (SW-V1 17 or SW-V1 1 1) if not already done Inserts a manual scram as directed by **CRITICAL STEP**
SRO Performs scram immediate actions: Attachment 3 is a copy of the Hardcard.
- 1. Unit 2 Only: After steam flow is less than 3 x 106 lb/hr, PLACE the reactor mode switch to SHUTDOWN.
- 2. IF reactor power is below 2% (APRM downscale trip), THEN TRIP the main turbine.
- 3. ENSURE the master reactor level controller setpoint is +170.
- 4. IF two reactor feed pumps are running, and reactor vessel level is above +160 and rising, then trip one.
Maintains RPV level 170-200 Reports when out of band and actions to address recovery.
Places the SULCV in service lAW hard Attachment 4is a copy of the FW Control card Hardcard.
Recognizes and reports no direct RPV level indication available below 150 w/
RR pumps operating.
Trips Recirc pumps if directed by SCO Should have tripped at LL2.
Commences normal cooldown not to exceed 100° F I hr Utilizing BPVs Anticipates ED **CRITICAL STEP**
Opens BPVs with the BPV Opening Jack maintaining Steam Flow below isolation setpoint.
Does not to close MSIVs (Gpl)
Pacie26 of 34
EVENT 717A (CONT) RCIC STEAM BREAK I SCRAM I RHR ROOM CLR FAILURES BOP Time Action Notes Acknowledge and report alarms UA-03 2-7 AREA RAD RX BLDG HIGH 3-5 PROCESS RX BLDG VENT RAD HI-HI 4-5 PROCESS RX BLDG VENT RAD HIGH UA-05 3-9 RHRFANA FAIL TO START Enters and announce AOP-05.O entry Evacuates the U2 Reactor building.
Sounds RB evacuation alarm Verifies Secondary Containment and Group 6 isolation and SBGT initiation if Rx Bldg Vent exhaust Hi-Hi rad alarms Directs PIV-33 to be closed Notifies E&RC to perform the following as necessary:
- Area radiation survey
- Air sampling
- Smear survey
- Post the affected area as necessary
- Control access to reduce exposure and contamination.
Ensures the RHR room coolers are running Recognizes and reports NRHR room cooer fails to start (Auto or Manual)
May Align service water to the vital header (SW-VI 17 or SW-Vi 11) if not already done due to FAN CLG UNIT CS PUMP RMA INL PRESS LO annunciator Monitors Reactor Building pressure, (Blue bar annunciators) reports if pressure goes positive.
UA-05 6-7 RX BLDG STATIC PRESS DIFF -
LOW UA-12 3-3 RX BLDG DIFF PRESS HIGH/LOW Paae 27 of 34
EVENT 818A REACTOR DEPRESSURIZATION I SCENARIO TERMINATION If emergency depressurization is not anticipated, secondary containment temperatures will exceed maximum safe operating values in two areas, or EQ Envelopes will be reported as being exceeded, which will require emergency depressurization.
Depressurization may be Anticipated or manually performed if I when two areas exceed Max Safe.
Objectives:
SCO - Directs actions to Anticipate Emergency Depressurization or Emergency Depressurize and restore reactor water level.
RO Performs actions RPV Depressurization and restoration of reactor water level.
BOP Monitors and reports SCCP & RRCP parameters.
Success Path:
Depressurize the reactor and restore reactor water level to 170-200 inches.
Simulator Operator Actions:
Instructor Activities D If crew decides not to anticipate ED, or if SRHR room temperature lowers below Max Safe (around 450#), wait 3 minutes and report as Engineering that the EQ envelope has been exceeded for NRHR. (NOT Required if RPV pressure is rapidly lowering due to anticipating)
D When RPV level is being controlled above 170, the scenario may be terminated D When directed by the lead evaluator, place the simulator in FREEZE.
Required Operator Actions Restore and maintain RPV level above LL4 SRO Time Action Notes If two areas exceed MSOWL, direct If anticipating ED is performed, reactor emergency depressurization depressurization with BPVs will reduce building temperatures and ED is not required. (May be critical task)
Directs controlling condensate injection when RPV pressure is less than 440 psig.
Directs controlling Low Pressure ECCS injection when RPV pressure is less than 400 psig Paae 28 of 34
EVENT 818A (CONT) REACTOR DEPRESSURIZATION I SCENARIO TERMINATION SRO Time Action Notes Directs opening 7 ADS valves (ED) Not required if anticipating ED is performed. (May be critical task)
Directs restoring and maintaining **CRITI CAL STEP**
RPV level 170-200 inches.
RO/BOP Time Action Notes Places 7 ADS valve control switches Not required if anticipating ED is performed. (May be critical task)
Operates Condensate or LP ECCS to **CRITI CAL STEP**
restore and maintain RPV level 170-200 inches.
Termination Cue When RPV water level is being maintained above 170 inches with the reactor depressurized, by direction of the Lead examiner, the scenario may be terminated.
Paoe29 of 34
Simulator Operator Activities:
WHEN directed by the lead examiner, place the simulator in FREEZE.
CAUTION DO NOT RESET THE SIMULATOR PRIOR TO RECEIPT OF CONCURRENCE TO DO SO FROM THE LEAD EXAMINER Paae 30 of 34
Attachment I Control Rod Manipulations
- 1) Manipulates control rods only with CRS/SRO permission.
- 2) Verifies no other reactivity impacting manipulation is occurring.
- 3) Ensures Concurrent Verifier is available, prepared, and in place.
- 4) Selects the correct control rod using good self checking techniques.
- 5) Verifies control rod selection by observing select pushbutton lit.
- 6) Verifies control rod selection by confirming selection on RWM screen.
- 7) Verifies control rod selection using full core display.
- 8) Verifies control rod position using control rod display, confirms it matches expected position.
- 9) Communicates the following:
a) Control rod selected b) Starting position c) Movement to be taken d) Limitations on movement e) Final position to the Concurrent Verifier NOTE: The following are acceptable methods for ensuring proper control switch manipulation and should be used just prior to control rod motion:
- Placing hands above the movement switches and moving them in the direction of intent
- Placing a finger on the portion of the switch label corresponding to the movement intent (IN or NOTCH OUT)
- Use of different hand positions, depending on the direction of the intended movement of the switch f) Direction control switch manipulation
- 10) Obtains concurrence (documented by initials) of Concurrent Verifier before beginning the move.
- 11) Observes plant response to movement commands.
NOTE: The guidance of Steps C.3.i.12 & 13 is waived during emergency conditions or when the Reactor Engineer, with the Shift Manager concurrence, has determined that notch operation will result in thermal limits challenges.
- 12) When moving a control rod four notches or more, stops one notch short, then single notches to final position unless control rod is going to position 48 (full out).
- 13) When moving a control rod three notch or less, performs separate single notch moves.
- 14) When control rod movement completed, verifies settle light is extinguished and the control rod is at a settled, latched position.
- 15) Does NOT select another control rod until three seconds after control rod settle light has extinguished.
- 16) Periodically checks position on applicable Power to Flow map.
- 17) Ensures Concurrent Verifier performs duties per OPS-NGGC-1306.
- 18) Updates and signs documentation as steps are complete.
Page 31 of 34
Attachment 2 Recirculation Speed Manipulations
- 1) Manipulates recirculation speed only with SRO permission.
- 2) Ensures Concurrent Verifier is available, prepared, and in place.
- 3) Communicates to Concurrent Verifier direction of movement, component to be manipulated, amount of adjustment, and stopping point.
- 4) Obtains concurrence of Concurrent Verifier before commencing adjustments.
- 5) Operates recirculation speed controls one at a time, allows time for plant and machine response.
- 6) Observes redundant plant indications while performing adjustments.
- 7) Notifies SRO when recirculation speed adjustments are completed.
- 8) Periodically checks position on Power to Flow map.
Page 32 of 34
Attachment 3 SCRAM HARD CARD ATTACHMENT 14 Page 1 of I Unit 2 Scram Card (OEOP-O1-UG)
- 1. ENSURE SCRAM VALVES ARE OPEN BY MANUAL SCRAM OR ARI INITIATION
- 2. CONTROL REACTOR PRESSURE BETWEEN 800 AND 1000 PSIL3
- 3. CONTROL REACTOR WATER LEVEL BETWEEN +170 AND +200 INCHES
- 4. PLACE SULCV IN SERVICE
.5. INSERT NUCLEAR NSTRUMENTATION
- 6. ENSURE TURBINE OIL SYSTEM OPERATING Page 33 of 34
Attachment 4 PLACING SULCV IN SERVICE FOLLOWING SCRAM ATTACHMENT 6 Page 1 of 2.
Feedwater Level Control Followin9 a Reactor Scram Reactor Feed Pump Startup NOTE: This attachment is also applicabl to the Simulator..
NOTE: This attachment is NOT to be used for routine system operation.
FEEDWATER LEVEL CONTROL FOLLOWING A REACTOR SCRAM
- 1. IF NECESS.RY, THEN DISPATCH AN OPERATOR TO RFP A(S) TO RESPOND TO ANY LOCAL ANNUNCIATOR PANEL AlARMS
- 2. C LOSE (FW-V6 AND FW-V8) OR (FW-Vi 18 AND FW-V1 19).
- 3. ENSURE FW-FV-l 7718 CLOSED.
- 4. OPEN FW-V10.
- 5. PLACE FEEDWATER CONTROL MODE SELECT TO 1 ELEM.
- 6. IF BOTH REPs HAVE TRIPPEDT THEN ENSURE MSTR RFPT SPIRX LVL CTL, C32-$IC-R6&0, IS IN M (MANUAL) AND SET TO MAINTAIN 187 INCHE&
- 7. ENSURE SULGY, FW-LIC-3269, IN M (MANUAL) AND SULV CLOSED.
- 8. ENSURE B21-F032A AND B21-F032B ARE OPEN.
- 9. IFAN REP IS RUNNING, ThEN PLACE RFPT A (B) SP GTL, C32-SIC-R6O1A (B), IN M (MANUAL) AND ADJUST RFP A(S) SPEED UNTIL DISCHARGE PRESSURE IS APPROYIMATELY 100 PSI GREATER THAN REACTOR PRESSURE.
- 10. ADJIJSTSULcV, FW-LIc-32G9, FOR DESIRED REACTOR WATER LEVEL
- 11. IF DESIRED, THEN PLACE SULV, FW-LIC-3269, IN A (AUTO).
- 12. ADJUST FW-FV-i77 TO MAINTAIN SULGV, FW-LIC-3269, OUTPUT DEMAND SIGNAL BETWEEN 25% AND 55%.
- 13. IF SULCV. FW-LFC-3269, FAILS TO CONTROL LEVEL, THEN USE ONE OR MORE OF THE FOLLOWING VALVES TO AID IN LEVEL CONTROL:
FW-V120, (FW-Vi 18 AND FW-V6), (FW-V1 19 AND FW-V8).
2/1204 Sf1205 20P-32 Rev. 171 Page 307 of 317 Page 34 of 34
PROGRESS ENERGY CAROLINAS BRUNSWICK TRAINING SECTION SIMULATOR SCENARIO 201 0-2 NRC Exam Scenario #2
Appendix D Scenario Outline Form ES-D-1 Facility: Brunswick Scenario No.: 2010-2 #2 Op-Test No.: Draft Examiners: Operators:
Initial Conditions: Unit is operating at 75% power due to Whiteville Line 31 tripping. IA NSW Pump is under clearance for breaker refurbishment, expected to be returned to service in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. EHC Pump 2B under clearance.
Turnover: Maintain current power.
Event Maif. No. Event Event No. Type* Description KIH14A RCIC Suction Pressure Switch Failure (Failure of V8 to 1 RO close)(TS)
ZA343 2a ZUA442 N - BOP Remove RFP from service due to oil leak 2b R Lower power to allow RFP to be removed from service 3 ESOO3F C RO SRV failure RBV Rad Monitor Failure (failure of isolations/actuations) 4 RMOO3F - BOP 5 K4522A C BOP RCC Pump Failure (standby fails to auto start)
RPOO9F M EHC Pump trip I ATWS I LEP-02 6 KIHO3A C BOP Failure of ADS Inhibit Switches K2322A C RO Rod Select Power failure (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 2 of 31
SCENARIO DESCRIP11ON The plant is operating at -75 power, Middle of Cycle.
Event 1 The RCIC suction pressure switch will fail causing a trip of the RCIC turbine. The RCIC system should be declared inoperable. TS 3.5.3 condition Al, determines HPCI operable immediately and Condition A2 restore RCIC in 14 days.
Event 2 An oil leak will develop on RFP 2A oil system. A low level alarm will be received. The crew should reduce power and shutdown RFP 2A.
Event 3 SRV B will fail full open. Crew will enter OAOP-30.0. Immediate operator actions are unsuccessful in closing the SRV; pulling fuses per supplementary actions will close SRV.
Event 4 RBV Rad Monitor A will fail resulting in a Group 6 isolation. Secondary containment isolation and SBGT initiation will fail to automatically occur requiring manual action.
TS 3.3.6.2 Condition Al place the channel in trip in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (Function 3). TS 3.3.6.1 Condition Al place the channel in trip in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (Function 2d). TS 3.4.5 Condition BI Analyze grab samples of primary containment atmosphere once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and Condition B2 Restore required primary containment atmosphere radioactivity monitoring system to OPERABLE status in 30 days. TRM 3.4 Condition A Restore required channel to OPERABLE status in 31 days.
Event 5 The A RBCCW pump will trip with the standby pump failing to auto start. OAOP-16.0 should be entered and the standby pump started to recover system pressure.
Event 6 EHC pump will trip resulting in a reactor scram in which all control rods will not go in.
Bypass valves will not be available to control reactor pressure. SRVs and Main Steam Line Drains are available for pressure control. While the actions for LPC are being taken all but 3-5 rods will inserted. The key lock switches for inhibiting ADS will not work (as indicated by the ADS Inhibit lights not lighting up). Control rods will not be available for insertion using RMCS due to a failure of rod select power. Actions to reset the scram and then manually scramming per EOP-0l-LEP-02 should be taken.
When all rods have been inserted then the scenario may be terminated.
Page 3 of 31
OBJECTIVES SRO 341224B102, Determine actions required for Limiting Conditions for Operation per 01 01.8 and Technical Specifications 3412198102, Direct Actions To Lower Reactor Power From Rated to 55% Including Removal Of One Feed Pump From Service Per GP-05 & GP-12 RO 202202B101, Decrease Reactor Recirculation Pump Speed/Reactor Power Using The Manual Control Station Per OP-02 259204B101, Secure The First Reactor Feed Pump Per OP-32 2730028401, Respond To A Process Radiation Monitoring Downscale/lnop Annunciator Per The Appropriate APP Page 4 of 31
SIMULATOR SETUP Initial Conditions IC-b Event Triggers Event Trigger Trigger Description 1 1 RCIC Suction Pressure Switch Failure (Failure of V8 to close)(TS) 2 2 Annunciator for 2A RFP oil leak 3 Trips 2A REP when discharge valve FW-V3 is closed 3 4 SRVBfailure 5 Pulls fuses for SRV B 4 6 RBV Rad Monitor Failure (failure of isolations/actuations) (TS) 5 7 RCC Pump Failure (standby fails to auto start) 6 8 EHC Pump trip I ATWS I Rod Select Power failure 9 LEP-02 Section 3 Jumpers 10 MSIV LL3 Group I Isolation Jumpers 11 MVD-5005 to open Page 5 of 31
Malill) I Mull ID [Dererlution CurrentValue Target Value I Fimplime I Aciirde I Danine I Trig 13P008P y ATWS1
- True , 1ue 0EF ,rrue True 4.,
ESOQ3F ADS VALVE B FAILS OPEN Faire True ....... 4 RM3F ,. . ... FiX, BLDG VENT MON A FAILS ONSCL Fame True . OO0:08 RMOO4F FiX. BLDG. VENT MONAFAILSUPSCL Faire True 0;O8 *G RPOD5F AUTO SCRAM DEFEAT Faire True . . 5 EErJ1IJ 230KVTRAN1ISI0NUNE31 tm11 F True .
Dl Active Pending 3
10 11 J Timer PaUe . Ctearuetl Ative Pnding ii aflCltOSliflfl4 ,,._,_ ...,..__.._.,, __.....,.,,,,,.__.,__
,,,,,r r Tagrrame Override Type I OVal AVail Acilme I Daciirrre I Trig j DencripUon 43 RCiC PUMP SUCTION LO PRESS 343 ON ON OFF 4*2 RFPATURBO1LTANKLEVELH1-LO . . . zUA442 ON ON OFF 2 2-6 RCIC SYSTEM PRESS LOW ZA226 ON ON OFF 00:00:13 .
11.
r Timer Pause .
. Delete Al! ..ActNé Pending rOvenideSummay _._ :
TagID I Description I I AclualValue OvesrideVdue .Rmpirre j Acilme I Daclirne Trig K1H03 - *ADS . . - .. . INHiBIT . OFF . OFF -
KIHO4A , ADS . .- - INHIBIT OFF . OFF .
K4522A RBCCV/PMPCAIJTO . . AUTO .. ON. . . OF -
G1H0861M RCIC PUMP SUCT PRESS *29.5712 5560185 55,60105 1 Q15OBLGJ SRVVLVB21F0130 GREEN - ON)OFF ON OFF . .5 01506F1RJ SRVVLVB21-F0130 RED ON/OFF OFF OFF . . 5 J(G101 SBGTSYSA -PREF ON OW .,
OS1O1AIW SBGTSYSCONTPREFR4 ON/OFF OFF ON . ,
SBGT.SYS8CONTfEF9 ;oN/DF OFF O4 -. -
K56O8I RBVENTINBDISDLVALVESCPEN OPEN OFF ON K5605A RB VENT OTBD ISDL VALVES OPEN , OPEN OFF ON .,..
K452F1A RBCCWPMPAAUTO . . OFF OFF ON . . . .
K452 RBCcWPMPAAUTO AUTO OFF OFF . 7 K4520A RBCCWPMPAAUTO ON ON OFF , -
Q4520G4 RBCCIPMPAOFFG . ON/OFF OFF OFF . 7 04520RR4 RBCCWPMPAONR . ON/OFF ON OFF . . 7 l5417A HYDFUJIDPMPBI4FPMB OFF OFF OFF K6417A HYDFLUIDPMPBHFPMB - AUTO ON OFF 5417A . . HYD.FLUIDMPBHFPF*B . . . ON . OFF- ,,. -. OFF :- . , . .
K541Br HYD FLUID PMPAHFPM-A . OFF OFF ON , 8 K54164 HYDFLUiDPMPAHFPM -- , AUTO OFF , . 8 K5416A HYD FLUID PMPAHFPM-A . ON OFF K2322A ROD SEL POWER ON OFF OFF 8 K2322A ROD SEL POWER OFF ON ON 8 Timer Pause Delete AlI Active Pc nding Page 6 of3l
SPECIAL INSTRUCTIONS Ensure simulator exam security measures in place.
Start the 2B Stator Cooling Water Pump and Shutdown the 2A Stator Cooling Water Pump and place control switch in Auto.
Place 2B EHC Pump to off and red cap. Place an annunciator placard on the board.
Place the Auto Reclose and Supervisory control switches in Man and LocaL Advance all chart recorders to indicate steady state conditions.
Place all SPDS displays to the Critical Plant Variable display (#100).
Ensure appropriate keys have blanks in switches.
Exit shutdown screen on RWM and place the RWM key in the key locker.
Reset alarms on SJAE, MSL, and RWM NUMAC5.
Ensure reference material is in appropriate location.
Verify any log books have blank sheets only and procedures are not marked.
Load scenario file if available.
Load malfunctions/overrides if scenario file is unavailable.
Ensure OENP-24.5 for IC-lO @ P603.
Page 7 of 31
SHIFT BRIEFING Plant Status The plant is at -75% power.
Whiteville Line 31 has tripped, Load Dispatcher has requested power to remain 75%
power until Line 31 is restored. Crews have been dispatched to investigate.
Equipment Out of Service IA NSW Pump.
2B EHC Pump.
No other equipment is out of service.
Plan of the Day Maintain current power.
Page 8 of 31
SCENARIO TRAINING INFORMATION Instructor Notes This guide is designed to meet the requirements of an examination scenario for Initial License as outlined in NUREG-1 021, Rev.9, Supp.1 ES-301 and Appendix D.
During the execution of this scenario, the students should be rated on the performance of the objectives, compliance with general simulator performance standards, and for overall team skills in accordance with TAP-409 and NUREG-1 021, ES-302.
Common Student Problems/Errors None Simulator Deficiencies There are no known simulator deficiencies applicable to this scenario.
Critical Tasks (Critical Tasks are identified to ensure scenario validity and do not constitute pass/fail criteria for Initial License.)
- Insert a control rods lAW LEP-02.
- Close the SRV lAW OAOP-30.0 before reaching 110°F in the suppression pool.
Page 9 of 31
EVENT I RCIC SUCTION PRESSURE SWITCH FAILURE A3 4-3, RCIC Pump Suction Low Pressure, 13 seconds later A-02 2-6, RCIC System Press Low and A3 5-3, RCIC Turbine Tripped, annunciators are received. The RCIC suction pressure switch fails low causing the RCIC turbine to trip. The RCIC E51-V8 will not auto close and the operator should make the auto action occur. RCIC will not be available for the rest of the scenario.
Objectives:
SRO Determines Tech Spec implication.
Directs RCIC auto actions completed.
BOP Monitor plant parameters Success Path:
Tech Specs addressed and RCIC E51-V8 closed.
Simulator Operator Actions:
Li When the crew has the watch, initiate Trigger I to trip the RCIC turbine.
Li If contacted as l&C to repair the RCIC suction pressure switch acknowledge and do nothing.
LI If directed to investigate as AC report that you dont see anything wrong.
LI When directed by the lead examiner, proceed to the next event.
Required Operator Actions Component Failure Closure of RCIC V8 Tech Specs 3.5.3 Al, Verify by administrative means High Pressure Coolant Injection System is Operable immediately and Tech Specs 3.5.3 A2, Restore RCIC System to Operable status in 14 days.
Page 10 of 31
EVENT I (Contd) RCIC SUCTION PRESSURE SWITCH FAILURE SRO Time Action Notes Acknowledge report of RCIC alarms.
A-03 4-3, RCIC Pump Suction Lo Press.
After a 13 second time delay A-03 5-3, RCIC Turbine Tripped.
A-02 2-6, RCIC System Press Low Direct RO to reference APPs Direct the RO to either:
- 1. Trip RCIC by depressing the Turbine Trip pushbutton.
- 2. Close the RCIC E51-V8.
Makes TS determination.
TS 3.5.3 Condition Al, Verify by administrative means High Pressure Coolant Injection System is Operable immediately, AND Condition A2, Restore RCIC System to Operable status in 14 days.
Page 11 of 31
EVENT I (Contd) RCIC SUCTION PRESSURE SWITCH FAILURE RO Time Action Notes Announce and reference APPs.
A-03 4-3, RCIC Pump Suction Lo Press.
After a 13 second time delay A-03 5-3, RCIC Turbine Tripped.
A-02 2-6, RCIC System Press Low Determines that RCIC auto actions failed to occur and either:
- 1. Trips RCIC by depressing the Turbine Trip pushbutton.
- 2. Closes the RCIC E51-V8.
BOP Time Action Notes Plant Monitoring Page 12 of 31
EVENT 2 REACTOR FEED PUMP OIL LEAK An oil leak will develop on REP 2A oil system. A low level alarm will be received. The crew should reduce power and shutdown REP 2A. The RFP will trip when the discharge valve FW-V3 is closed.
Malfunctions required:
RFPA OIL LEVEL HI/LOWAnnunciator and REP 2A Lube Oil Leak Objectives:
SCO Determines that 2A RFP needs to be shutdown and directs power to support securing 2A RFP.
RO - Lower power to be able to remove 2A REP.
BOP Removes the 2A REP from Service Success Path:
2A RFP removed from service.
Simulator Operator Actions:
LI When directed by the lead examiner, initiate Trigger 2, to activate RFP A OIL LEVEL HI/LOWAnnunciator.
LI Verify that the 2A RFP trips when the discharge valve, FW-V3, is closed (red light out).
LI If contacted as AC report oil tank level is low. Report there is an oil leak on REP A that appears to be unisolable. The RFP should be shutdown.
LI When contacted as maintenance, report that the REP must be shutdown in an expeditiously (per the procedure) and the oil pumps must be shutdown.
Li If contacted as the Load Dispatcher, acknowledge the power reduction.
LI If contacted as the NE recommend to lower power per OENP-24.5 and thermal limits will be monitored via the computer.
LI If requested to de-energize seal water solenoids for RFP 2A, report circuits are off (2C-TBI, circuits 8 & 24).
LI If asked and the AC/DC Pumps are shutdown, report as AC the oil leak has stopped LI After the REP trips, contact the control room as MM and request that all oil pumps be shutdown and that people are in place to manually bar the REP Turbine.
LI When directed by the lead examiner, proceed to the next event.
Required Operator Actions Reactivity Manipulation to 60-65% power Normal Operation Shutdown 2A REP.
Page 13 of 31
EVENT 2 REACTOR FEED PUMP OIL LEAK SRO Time Action Notes Direct power reduction per OENP-24.5 and GP-12 to shutdown REP A (60-65%).
Direct REP A to be removed from service per 20P-32.
May direct RFP A oil pumps secured.
RO Time Action Notes Reduce power per 0ENP-24.5 as directed by the SCO.
Lower flow on one RR Pump (-2%) at a time to stay within mismatch criteria 6 Mibs jet pump flow if < than (7.5x10 6 MIbs if> than 58 58 MIbs or 3.5x10 MIbs).
Continues alternating Recirc pump decreases until core flow is -47 MIbs.
May Insert control rods using OENP-24.5 to get to 60-65% power.
Turns control rod power on.
Selects control rods in the sequence prescribed on the OENP-24.5 sheets.
26-35, 26-19, 1 8-27, and/or 34-27.
Continuously drives selected rod in using RMCS.
May maintain the Gen Voltage Regulator nulled as power is being reduced by placing the switch in the lower direction until needle is reading 12 Oclock.
(May have to perform this several times)
Page 14 of 31
EVENT 2 (Contd) REACTOR FEED PUMP OIL LEAK BOP Time Action Notes Shutdown RFP A per 20P-32. (the REP will trip when the discharge valve is closed)
Adjust level setpoint on MSTR RFPT SP/RX LVL CTL, C32-SIC-R600, to 190 inches.
Notify Radwaste Operator to monitor CDD flows and place demineralizers in service as necessary.
Ensure SJAE Condensate Recirculation Valve, CO-F V-49, is closed.
Place RFP A Recirc Vlv, FW-FV-V46, in OPEN Ensure RFPTA Sp Ctl, C32-SIC-R6OIA, is selected to BIAS and Adjust, using raise and lower push buttons, until BIAS setting is 0.
Ensure RFPTB Sp CtI, C32-SIC-R6OIB, is selected to BIAS AND Adjust, using raise and lower push buttons, until BIAS setting is 0.
Depress SEL pushbutton on both RFPTA and B SP CtI, C32-SIC-R6OIA and B, until PMP DEM is displayed on each Depress AIM pushbutton on C32-SIC-R6OIA Slowly Lower RFPT A speed, using lower pushbutton on C32-SIC-R6OIA, And Observe RFPT B increases speed to maintain reactor level between 182 and 192 inches.
Page 15 of 31
EVENT 2 (Contd) REACTOR FEED PUMP OIL LEAK BOP contd Time Action Notes Slowly Lower RFPT A speed using lower pushbutton on C32-SIC-R6OIA, until REP discharge pressure is slightly less than reactor pressure.
De-energize seal water solenoid valves.
Close RFP A Disch VIv, FW-V3. The RFP will trip when valve is closed.
Return level setpoint on MSTR RFPT SP/RX LVL CTL, C32-SIC-R600, to 187 inches Place RFPT A(B) MAN/DFCS control switch to MAN Place RFP A TURNING GEAR MTR mode selector switch in NORM Place RFP A Recirc VIv, FW-FV-V46, in AUTO.
Shuts down the Oil Pumps.
Page 16 of 31
EVENT 2 (Contd) REACTOR FEED PUMP OIL LEAK BOP contd Time Action Notes OPEN the foHowing drain valves
. RFPA HP Stop Vlv & Ln Drain, MS-V41 and MS-V42
. RFP A HP Stop Below Seat Drn, MS-V40
. RFP A LP Stop VIv & Ln Drain, RHS-V32 and RHS-V39
. RFP A LP Stop Below Seat Drn, RHS-V31
. RFP A LP Ct! V!v Chest Drn, RHS V30 and MS-V51
. RFP A LP Stm Supply Ln Drn, RHS- V40 May maintain the Gen Voltage Regulator nulled as power is being reduced by placing the switch in the lower direction until needle is reading 12 Oclock.
(May have to perform this several times)
Page 17 of 31
EVENT 3 SRV B FAILS OPEN The crew responds to an inadvertent stuck open SRV Malfunctions required:
- SRV B fails open Ob/ectives:
sco
- Direct actions in response to a stuck open SRV BOP/RO
- Respond to a stuck open SRV Success Path:
B SRV is closed by pulling fuses per the supplementary actions of AOP3O.
Simulator Operator Actions:
LI WHEN directed by the lead examiner, activate TRIGGER 4. (SRV B fails open) o If contacted as operator to pull fuses, if possible pull fuses before torus temperature reaches 95°F initiate TRIGGER 5 and immediately DELETE the SRV malfunction.
0 When directed by the lead examiner, proceed to the next event.
Required Operator Actions Critical Task Close the failed open SRV.
Page 18 of 31
EVENT 3 SRV B FAILS OPEN SRO Time Required Actions Notes Direct entry into AOP-30 Safety/Relief Valve Failure.
Direct support personnel to pull applicable fuses per Attachment 1 of OAOP-30.0.
Enter PCCP if torus temp reaches 95°F.
If Torus is greater than 95°F Determine TS 3.6.2.1 Condition Al requires verifying the Torus temperature < 110°F once per hour.
Condition A2 requires Torus to be_<_95°F_in_24_hours.
If Torus is greater than 95° F direct BOP to place torus cooling in service per PCCP (Hard Card or OP-17).
BOP Time Required Actions Notes Plant Monitoring RO Time Required Actions Notes Respond to alarms.
A-03, 1-10, Safety/Relief Valve Open A-03, 1-1, Safety or Depress Valve Leaking Page 19 of 31
EVENT 3 SRV B FAILS OPEN RO contd Time Required Actions Notes Cycle B SRV control switch several times (leaves switch in CLOSE)
Request fuses for the SRV be pulled Critical Task per Attachment 1 of OAOP-30.0.
When informed that fuses have been pulled, verify SRV is closed.
If Torus is greater than 95° F, Places SPC in service on A Loop. (Actions in parenthesis for B Loop)
Opens SW-ViOl (V105).
Closes SW-V143.
May verify adequate suction source and start a CSW (NSW)
Pump.
Adjusts El I-PDV-F068A(B) to achieve -4000 gpm per RHR SW pump running.
Supplies cooling water to vital header ensures open either SW Vill orSW-V117.
Starts RHR pump(s)
Open El I -F028A(B).
Throttles open El 1-F024A(B)
(establishes flow in green band for 1 pump or <11500 gpm for2 pump operation)
Closes El l-F048A(B).
Page 20 of 31
EVENT 4 REACTOR BUILDING VENT RAD MONITOR FAILS RBV Rad Monitor A will fail upscale then downscale resulting in a Group 6 isolation, Secondary containment isolation and SBGT initiation. The RB HVAC Dampers and SBGT will fail to automatically occur requiring manual action Malfunctions required:
- RBV Rad monitor upscale then downscale.
Objectives:
5CC
- Determine Tech Specs.
BOPIRO
Success Path:
RBV is isolated and SBGT started.
Simulator Operator Actions:
o WHEN directed by the lead examiner, activate TRIGGER 6 to fail the RBV Rad Monitor.
o If asked as l&C to investigate, acknowledge the request o When directed by the lead examiner, proceed to the next event.
Required Operator Actions Component Failure Closure of RBV Dampers and Start SBGT TS 3.3.6.2 Condition Al place the channel in trip in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (Function 3).
TS 3.3.6.1 Condition Al place the channel in trip in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (Function 2d).
TS 3.4.5 Condition Bi Analyze grab samples of primary containment atmosphere once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and Condition TS 3.4.5 Condition B2 Restore required primary containment atmosphere radioactivity monitoring system to OPERABLE status in 30 days.
TRM 3.4 Condition A Restore required channel to OPERABLE status in 31 days.
Page 21 of 31
EVENT 4 (contd) REACTOR BUILDING VENT RAD MONITOR FAILS SRO Time Required Actions Notes Acknowledge report of alarms for RBV Rad Monitor failure.
Direct verification of auto actions for rad monitor failure. Group 6 Isolation, Secondary Containment Isolation and SBGT start.
Direct failed auto action to be manually performed.
Direct l&C to investigate failure of vent rad monitor.
Determine Tech Specs:
TS 3.3.6.2 Condition Al, place the channel in trip in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (Function 3).
TS 3.3.6.1 Condition Al, place the channel in trip in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (Function 2d).
TS 3.4.5 Condition BI, Analyze grab samples of primary containment atmosphere once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and Condition TS 3.4.5 Condition B2, Restore required primary containment atmosphere radioactivity monitoring system to OPERABLE status in 30 days.
TRM 3.4 Condition A, Restore required channel to OPERABLE status in 31 days.
Page 22 of 31
EVENT 4 (contd) REACTOR BUILDING VENT RAD MONITOR FAILS RO Time Required Actions Notes Plant Monitoring BOP Time Required Actions Notes Report annunciators for RBV Rad Monitor failure and review to APP5.
Recognize and report failure of auto actions for rad monitor failure. Group 6 Isolation, Secondary Containment Isolation and SBGT start.
Manually isolate RBV dampers and manually start SBGT.
Page 23 of 31
EVENT 5 RBCCW PUMP TRIP The crew will respond to a trip of the 2A RCC pump and pressure will lower. C RCC Pump will fail to auto start and the low pressure alarm will be received. Starting the 2C RCC pump will restore pressure to normal.
Objectives:
SCO Directs BOP to enter and execute OAOP-16.O: RBCCW System Failure BOP Refers to 2-UA-3 2-5 and OACP-16.O to respond to the 2C Pump failure to start Success Path:
Starting the 2C RCC pump will restore pressure to normal.
Simulator Operator Actions:
LI At the discretion of the lead evaluator, initiate Trigger 7 to trip the 2A RCC Pump.
LI If directed as the RB AC to investigate RCC low pressure, report RCC Pump 2A Motor is hot to the touch, breaker is tripped.
LI If contacted as the RB AC, inform the control room prestart checks of the 2C RCC pump are complete.
LI If directed to investigate as l&C acknowledge the request.
LI When directed by the lead examiner, proceed to the next event.
Required Operator Actions Component failure starting 2C RCC pump.
SRO Time Action Notes Directs BOP operator to enter Annunciator response for 2-UA-3 2-5, RBCCW PUMP DISCH HEADER PRESS LOW, and refers to OAOP-16.O.
Directs start of 2C RCC pump if BOP fails to recognize auto start failure.
Directs Maintenance to investigate 2C RBCCW pump auto start failure.
Notifies Maintenance of 2A RBCCW Pump trip.
May direct the 2A RCC pump to be placed in OFF.
Page 24 of3l
EVENT 5 (Contd) RBCCW PUMP TRIP RO Time Action Notes Plant Monitoring BOP Time Action Notes Recognize the failure of the C RCC pump to auto start at 65 psig.
Manually starts 2C RBCCW Pump.
Refers to Annunciator Response UA-3 2-5, RBCCW PUMP DISCH HEADER PRESS LOW May Reference OAOP-16.O Dispatches AO to investigate cause of 2A Pump trip.
Places 2A RBCCW Pump switch to OFF.
Verifies RBCCW System is operating normally.
Page 25 of 31
EVENT 6 EHC LOSS I ATWS EHC pump will trip resulting in a reactor scram in which all control rods will not go in.
Bypass valves will not be available to control reactor pressure. SRVs and Main Steam Line Drains are available for pressure control.
While the actions for LPC are being taken all but 3-5 rods will inserted. The key lock switches for inhibiting ADS will not work (as indicated by the ADS Inhibit lights not lighting up). Control rods will not be available for insertion using RMCS due to a failure of rod select power. Actions to reset the scram and then manually scramming per EOP-01-LEP-02 should be taken.
When all rods have been inserted and pressure is being controlled then the scenario may be terminated.
Objectives:
SCO Perform LPC directing LEP-02.
BOP Control RPV pressure using Main Steam Line drains.
RD Insert control rods lAW LEP-02.
Success Path:
Inserting control rods.
Simulator Operator Actions:
LI At the discretion of the lead evaluator, initiate Trigger 8 to trip the 2A EHC Pump.
LI When the SRO enters LPC delete ATWS 2.
LI If directed as the TB AC to investigate EHC pump, report Pump Motor is hot to the touch, breaker is tripped, will not reset.
LI When contacted to perform LEP-02 Section 3 jumpers, Wait 5 minutes and Initiate Trigger 9, then report action completed.
El If contacted to place jumpers for MSIVs LL3 Group I Isolation, Wait 1 minute and Initiate Trigger 10, then report action completed.
LI If contacted as the TBAO to open the MVD-5005, Main Stm Drn Hdr Isolation valve, wait 5 minutes and initiate Trigger 11.
LI If directed to investigate as I&C acknowledge the request.
LI When directed by the lead examiner, proceed to the next event.
Required Operator Actions Component failure Rod select power and ADS logic.
Critical Task Insert Control Rods lAW LEP-02.
Page 26 of 31
EVENT 6 contd EHC LOSS I ATWS SRO Time Action Notes Enter RSP and transition to LPC.
Direct mode switch to shutdown when steam flow < 3 Mlbs/hr.
Direct ARI initiation.
Direct Recirc Pump speeds reduced to 10%.
Direct Recirc Pumps Tripped.
Direct ADS inhibited.
Direct LEP-02, Alternate Rod Insertion.
(Critical task)
Direct Group 10 switches to override reset.
Direct Group I LL3 jumpers to prevent closure of MSIVs on low level.
Exit LPC and enter RVCP when all rods are in.
Page 27 of 31
EVENT 6 (Contd) EHC LOSS I ATWS RO Time Action Notes Recognize and report an ATWS.
Place mode switch to shutdown when 6 lb/hr.
steam flow < 3x10 Verifies Initiation of ARI.
Places Recirc Pump speeds reduced to 10%.
Verifies Recirc Pumps are tripped.
Performs LEP-02, Alternate Rod Insertion. (RMCS Section)
Insert IRMs.
When < range 3 on IRMs insert SRMs.
Start both CRD pumps.
Place CRD Flow Controller to Manual.
Throttle open flow controller to establish > 260 drive water psid.
Bypass RWM.
Determines Rod Select Power Failure and informs SRO.
Performs alternate rod insertion per (Critical task)
LEP-02 Section 3.
Request jumpers for LEP-02 Section 3.
Page 28 of 31
EVENT 6 (Contd) EHC LOSS I ATWS RO cont d
1 Time Action Notes Monitor APRMs for downscale.
Performs LEP-02 Section 3 after (Critical task) jumpers are installed.
Inhibit AR!
Places AR! Initiation Switch to INOP Places AR! Reset Switch to RESET and maintains for 5 seconds.
Verifies red TRIP light above AR!
Initiation is OFF Reset RPS when scram jumpers installed.
Ensures Dish Vol Vent & Drain Test switch is in Isolate.
Confirms Disch Vol Vent Valves V139 and CV-FO1O are closed Confirms Disch Vol Drain valves V140 and C V-FOIl are closed.
Resets RPS.
Place Disch Vol Vent & Drain Test switch to Normal Inserts a scram after discharge volume (Critical task) has drained for -2 minutes.
Reports all rods in.
Page 29 of 31
EVENT 6 (Contd) EHC LOSS I ATWS BOP Time Action Notes Places ADS in inhibit.
Identifies ADS failure.
Reports to SRO.
Places Group 10 switches to override I reset Controls Reactor pressure using Main Steam Line Drains lAW Hardcard.
Open Main Steam Line Drain Otbd (Inbd) Isol Vlvs, B21-F019 and B21-F016 Throttle Main Steam Line Drain Vlv, MVD-F021 as desired to maintain pressure band.
May open Main Steam Line Drain Vlv, MS-F020 with a combination of Main Steam Line Drain VIv(S), MS-F038A, F038B, F038C, F038D.
May direct TBAO to open Mn Stm Drn Hdr Isolation, MVD-5005 Page 30 of 31
Simulator Operator Activities:
WHEN directed by the lead examiner, place the simulator in FREEZE.
CAUTION DO NOT RESET THE SIMULATOR PRIOR TO RECEIPT OF CONCURRENCE TO DO SO FROM THE LEAD EXAMINER Page 31 of3l
PROGRESS ENERGY CAROLINAS BRUNSWICK TRAINING SECTION SIMULATOR SCENARIO 2010-2 NRC Exam Scenario #3
}
Appendix D Scenario Outline Form ES-D-1 Facility: Brunswick Scenario #: 2010-1 #3 OP-Test No.: Draft Examiners: Operators:
Initial Conditions: The plant is operating at -75% power following a refueling outage.
1A NSW pump is under clearance for motor replacement.
2C TCC pump is in service on Unit One.
Turnover: Following shift turnover, shift CRD pumps and continue power ascension to rated.
Event MaIf. No. Event Event No. Type* Description I N/A N-SRO Shift CRD pumps N-BOP 2 NBOO7F C-RD C32-LT-NOO4A fails Low (TS)
C-SRO 3 K4516A C-BOP 2A TCC pump trip (AOP)
C-SRO 3a N/A R-RO AOP-17 power reduction R-SRO 4 CWO21 F C-BOP 2B NSW pump shaft shear (TS) (AOP)
C-SRO 5 RDOO1M R-RO Control Rod 14-35 slow drift in. (AOP)
R-SRO 6 RDO41 F M-ALL Loss of Scram air header, multiple rod drifts, Scram ATWS 3 ATWS condition requiring entry to LPC.
7 K21 I 9A C-RD SLC pumps will not start due to switch failure.
C-SRO 8 N/A N/A ATWS Actions Terminate and Prevent 9 N/A N/A All Rods In with RPV water level restored.
(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 2 of 33
SCENARIO DESCRIPTION Unit 2 is operating at -75% power during startup following a refuel outage.
Event 1 Shift CRD pumps per 20P-08.
Event 2 Following CRD pump shift, C32-LT-N004A will fail low. The crew will reference Tech Spec 3.3.2.2 and determine a 7 day LCO exists to place the failed channel in the tripped condition. The crew should select level B per OP-32.
Event 3 TCC Pump 2B will trip and TBCCW low header pressure will alarm. The crew will respond per OAOP-17.0 and place 2A TBCCW pump in service.
Event 3a With only the 2A TCC pump in service, header pressure will remain below 42 psig requiring reactor power to be reduced with Recirc flow to the ENP-24.5 flow limit.
System pressure will recover as component TCVs throttle closed.
Event 4 The 2B NSW pump shaft will shear causing a low header pressure. 2A NSW pump will fail to AUTO start. The BOP operator should recognize the failure and manually start the 2A NSW pump. OAOP-1 8.0 will be entered and T.S. 3.7.2 will require restoring a required NSW pump to Operable status within 7 days.
Event 5 HCU 14-35 will develop an air leak causing the control rod to slowly drift inwards. The crew will enter AOP-2.0 Control Rod Malfunction/Misposition. AOP-2.0 will direct response per 2APP-A-05 (3-2) ROD DRIFT. The RO should attempt to arrest the drifting control rod.
Event 6 The scram air header leak degrades causing additional control rods to drift inward.
With scram air header low and multiple control rods drifting, a manual Scram will be inserted. Most of the control rods will fail to insert on the scram. The crew will respond to the ATWS per EOP-01-LPC.
Event 7 When SLC initiation is attempted, neither SLC pump will start due to switch failure.
RWCU will not automatically isolate requiring manual isolation of G31-F004. The crew will perform LEP-03 and align for alternate boron injection using CRD.
Event 8 The crew will terminate and prevent injection, re-injection will start when level is at 90 inches due to Table 3 conditions not met. Feedwater and HPCI will be available for level control.
Event 9 When level has been lowered and level band has been established, the scram air header leak will be isolated. Control rods can then be inserted by manual scram.
When all control rods are inserted and level is being maintained 170 to 200 inches the scenario may be terminated.
Page 3 of 33
OBJECTIVES SRO 344203B402, Direct Shift Personnel To Respond To a Control Rod Malfunction/Misposition Per AOP-02.0 344220B402, Direct Shift Response To TBCCW Failures Per AOP-17.0 344221 B402, Direct Actions For Nuclear Service Water System Failure Per AOP-1 8.0 341224B102, Determine actions required for Limiting Conditions for Operation per 0/
01.8 and Technical Specifications 344201 B502, Direct Actions To Control Reactor Power Per EOP-01-LPC 3442 14B502, Direct Actions To Control Primary Containment Pressure Per EOP PCCP 3442 15B502, Direct Actions To Control Primary Containment Temperature Per EOP 02-PCCP 3442168502, Direct Actions To Control Suppression Pool Temperature Per EOP PCCP RD 2010448401, Respond To Control Rod MalfunctionfMisposition Per AOP-02.0 2746018401, Respond to a Partial Loss of TBCCW per AOP-17.0 276602B401, Respond to a Partial loss of the Nuclear Service Water System per AOP 18.0.
202202B1 01, Decrease Reactor Recirculation Pump Speed/Reactor Power Using The Manual Control Station Per OP-02 200223B501, Control Reactor Level During An ATWS Per EOP-01-LPC 201041B501, Insert Control Rods With Reactor Manual Control System Per EOP LEP-02 203004B501, Terminate And Prevent LPCI Injection 206001B501, Terminate And Prevent HPCI Injection per EOP-01-UG 211005B501, Manually Initiate Standby Liquid Control Per OP-05 2180038501, Inhibit ADS Actuation Per EOP-01 2560078501, Terminate And Prevent Condensate System Injection To Reactor Vessel per EOP-01-LPC 2000628501, Spray The Suppression Pool Per EOP-01-SEP-03 2050148101, Start Up RHR In Suppression Pool Cooling Mode Per OP-17 Page 4 of 33
Simulator Setup Initial Conditions IC 10 (Unit 2)
RWM Sequence A2 Rx Pwr 75%
Core Age BOC Triggers Trigger Description 1 Manual C32-LT-N004B Fails Low 2 Manual 2B TCC pump trip 3 Manual 2B NSW pump shaft shear 4 Manual 1 D Air Compressor in service 5 Manual Control Rod 14-35, 22-31, 10-31 slow drift in Scram air header leak 7 Manual LEP-02 Section 3 Jumpers 8 Manual Bypass Group I LL3 Isolation per SEP-10 9 Manual MVD-5005 10 Manual DW Clr LOCA Logic bypass 11 Manual LEP-03 aligned to CRD Interventions Summary Note: Shaded entries = Active Malfunctions Summary MuIt Current Target Ramp Act. Deact Malt. ID Description Trig ID Value Value Time Time Time RPO1OF AWlS 3 True True RX LVL TRANSMITTER C32-NOO4A 61 0 1 NB 0 0 7 F FAILS CWO21F B NSWPUMPSHAFTSHEAR FALSE TRUE 3 RDOO1M 14-35 CONTROL ROD SLOW INSERT DRIFT FALSE TRUE 5 RDOO1M 22-31 CONTROL ROD SLOW INSERT DRIFT FALSE TRUE 1 Mm 5 RDOO1M 10-31 CONTROL ROD SLOW INSERT DRIFT FALSE TRUE 1.5 Mm 5 RDO4I F LOSS OF CONTROL AIR 0 40 2 Mm 2 Mm 5 RP005F Auto Scram Defeat False True 7 Page 5 of 33
Remotes Summary Mult. Current Target Remote ID Description Trig ID Value Value CC_1ACW4518 2C TBCCW PUMP UNIT ALIGNMENT I I EP_IAEOPJP1 Bypass LL3 Group I sd Off On 8 MS_VMS5005D MVD-5005 Mn Stm Drn Hdr Isolation 0 1 9 EP_IACS993U DW CLR A&D Overide Normal/Run Normal Run 10 EP_IACS994U DW CLR B&C Overide Normal/Run Normal Run 10 EP_IASW5997 SW-V106 LOCA Override Normal Bypass 10 EP_1ASW5998 SW-V103 LOCA Override Normal Bypass 10 SLIALEPO3 Alt = Sub Pump I Hose Lineup Normal Alt 11 SL_IASLCCRD SLC DISCH (NormCRD/ALT=RCIC/HPCI) Normal Normal 11 SL_IASLCSP Submersible Pump Power Off On 11 Al_IAIU1CMRSS UNIT I AIR COMPRESSER STAT IBSTBY Switches Summary Target I Actual Override Switch ID Description Trig Position Value Value K4516A TBCCW Pump A On On Off 2 Q4516LG4 TBCCW Pump A Green On/Off On/Off Off 2 K2119A SIB Liq Pump A-B Stop ON ON K2119A S/B Liq Pump A-B Pump_A OFF OFF K2119A S/B Liq Pump A-B Pump OFF OFF K21 I 9A S/B Liq Pump A-B Pump_ B OFF OFF K4B2OA NUC HDR SW PUMP A DISCH VLV AUTO ON OFF SPECIAL INSTRUCTIONS
- 1. Ensure simulator exam security measures in place.
- 2. Advance all chart recorders to indicate steady state conditions.
- 3. Place all SPDS displays to the Critical Plant Variable display (#100).
- 4. Ensure appropriate keys have blanks in switches.
- 7. Ensure reference material is in appropriate location.
- 8. Verify any log books have blank sheets only and procedures are not marked.
- 9. Load scenario file if available.
- 10. Load malfunctions/overrides if scenario file is unavailable.
- 11. Ensure 2C TCC pump in service on Unit 1.
- 12. Place in Run and verify power at -75%.
- 13. Ensure 2B Stator Cooling pump is in service.
- 14. Ensure OENP-24.5 for IC-b @ P603.
- 15. Provide marked up OGP-04 to step 5.2.31 and Attachment I marked for 70% being complete..
Page 6 of 33
Shift Briefing Plant Status The plant is operating at 75% power during startup following a refuel outage.
2C TCC pump is in service on Unit One.
Equipment Out of Service IA NSW Pump is under clearance for breaker refurbishment, expected to be returned to service in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
Plan of the Day Following shift turnover, shift CRD pumps and continue power ascension to rated lAW OGP-04 to step 5.2.31 using Reactor Recirculation Flow.
Page 7 of 33
SCENARIO INFORMATION Instructor Notes This guide is designed to meet the requirements of an examination scenario for Initial License as outlined in NUREG-1 021, Revision 8, ES-301 and Appendix D.
During the execution of this scenario, the students should be rated on the performance of the objectives, compliance with general simulator performance standards, and for overall team skills in accordance with TAP-409 and NUREG-1 021, ES-303.
Common Student Problems/Errors None Simulator Deficiencies There are no known simulator deficiencies applicable to this scenario.
Critical Tasks (Critical Tasks are identified to ensure scenario validity and do not constitute pass/fail criteria for Initial License.)
(bolded/italicized in the required operator action statements)
- Perform LEP-02, Alternate Rod Insertion using RMCS.
Page 8 of 33
EVENT I SHIFT CRD PUMPS The crew will complete shift turnover and shift CRD pumps lAW 20P-08.
Objectives:
SCO Directs shifting CRD pumps to place 2B CRD pump in service.
RO Monitors the plant.
Success Path:
CRD pump 2B placed in service with the flow controller in Auto.
Simulator Operator Actions:
ii If contacted as RBAO for CRD pump shift, report prestart checks complete SAT.
When directed as RBAO to ensure valve positions for the 2B CRD pump, report Section 8.2, Steps 1,2 & 3 are complete (Suction, Discharge, & Recirc Isolation valves are all locked open.
0 When directed as RBAO to ensure valve position for the 2A CRD pump, report Section 8.2, Step 10 is complete ( Discharge Isolation valve is locked open) and will get valves independently verified lAW Attachment 33.
0 If contacted as the RE for power increase guidance, inform crew to raise power using Reactor Recirc flow.
0 If contacted as the RE to monitor power increase, inform crew that you will monitor core performance and when plant is at 60% power inform crew Alt Power at is SAT.
0 When directed by the lead examiner, proceed to the next event.
Required Operator Actions Normal Operation Shift CRD pumps.
SRO Time Action Notes Directs 2B CRD pump be placed in service lAW 20P-08.
Acknowledges report of annunciators A-5 2-1 CR0 CHARGING WTR PRESS HI 6-1 CRD PUMP INLET FILTER z\P HIGH Acknowledges clearing of annunciators A-5 2-1 CRD CHARGING WTR PRESS HI 6-1 CRD PUMP INLET FILTER AP HIGH RO Time Action Notes Plant Monitoring Page 9 of 33
EVENT I (CONT) SHIFT CRD PUMPS BOP Time Action Notes Shifts CRD pumps LW 20P-08, Section 8.2.
Directs RBAO to ensure
- CRD PUMP 2B SUCTION ISOLATION VALVE, C12-FOI3B, is locked open.
- CRD PUMP 2B DISCHARGE ISOLATION VALVE, C12-FO14B, is locked open.
- CRD PUMP 2B RECIRCULATION LINE ISOLATION VALVE, C12-FOI4B, is locked open.
Shifts CRD FLOW CONTROL, C12-FC-R600, to BAL.
Nulls CRD FLOW CONTROL, C12-FC-R600, by adjusting the manual potentiometer.
Shifts CRD FLOW CONTROL, C12-FC-R600, to MAN.
Sets CRD flow rate to 35 gpm.
Announces and starts CRD Pump 2B Announces and stops CRD Pump 2A Directs RBAO to ensure CRD PUMP 2B DISCHARGE ISOLATION VALVE, C12-FOI4B, is locked open.
Nulls CRD FLOW CONTROL, C12-FC-R600, by adjusting the setpoint tape.
Shifts CRD FLOW CONTROL, C12-FC-R600, to AUTO.
Directs RBAO to complete Attachment 33.
Page 10 of 33
EVENT I (CONT) SHIFT CRD PUMPS BOP Time Action Notes Should verify CRD operating parameters CRD flow was initially 45 gpm, returning lAW Section 8.29 flow to this value should restore the ADJUST cooling water differential remaining parameters to pre-shift pressure, CRD flow rate and drive values.
pressure as follows:
- CRD FLOW CONTROL, C12-FC-R600, to maintain cooling water differential pressure between 10 and 26 psid.
CRD flow rate between 30 and 60 gpm.
- DRIVE PRESS, C12-PDI-R602, between 260 and 275 psid by throttling DRIVE PRESSURE VLV, C1V-F003.
Acknowledges and reports annunciators of A-S 2-1 CRD CHARGING WTR PRESS HI 6-1 CRD PUMP INLET FILTER AP HIGH Acknowledges and reports clearing of annunciators of A-5 2-1 CRD CHARGING WTR PRESS HI 6-1 CRD PUMP INLET FILTER AP HIGH Page 11 of 33
EVENT 2 C32-LT-NOO4A FAILS LOW (TS)
Following CRD pump shift, C32-LT-NOO4A will fail low. The crew will reference Tech Spec 3.3.2.2 and determine a 7 day LCO exists to place the failed channel in the tripped condition.
The crew should select level B per OP-32.
Objectives:
SCO Determine TS LCO for C32-LT-NOO4A failing low.
RO Transfer DFCS to control to B.
Success Path:
TS LCO 3.3.2.2, Condition A One feedwater and main turbine high water level trip channel inoperable. Required Action Al Place channel in trip within 7 days.
DFCS Feedwater Level Select transferred to B.
Simulator Operator Actions:
D Following CRD pump shift and at the lead evaluator direction, INITIATE TRIGGER I to fail C32-LT-NOO4A downscale.
D If contacted as I&C, acknowledge the request.
E When directed by the lead examiner, proceed to the next event Required Operator Actions Instrument Failure C32-LT-NOO4A failing low requires level selected to Level B.
Technical Specification LCO 3.3.2.2 entered.
SRO Time Action Notes Acknowledges annunciator report of A-7 4-2 FWCTL SYS TROUBLE Contacts I&C to investigate.
Directs FWCS Level control be selected to Level B.
References TS 3.3.2.2 AND TRM TS Instrument List, Appendix B TRM Table 3.3.2.2-1, Functions 1 & 2.
Page 12 of 33
EVENT 2 (CONT) C32-LT-NOO4A FAILS LOW (TS)
Feedwater and Main Turbine High Water Level Thp Instrumentation 3.3.2.2 3.3 INSTRUMENTATION 3.3.2.2 Faedwater and Main Turbine High Water Level Trip Instrumentation LCO 3.3.2.2 Three channels of feedwater and main turbine high water level trip instrumentation shall be OPERABLE.
APPLICABILITY: THERMAL POWER 23% RTP.
ATIQNS I ryrr Separate Condition entry is allowed for each channel.
CONDITION REQUIRED ACTION COMPLETION TIME A. One feedwater and main A.i Place channel in trip. 7 days turbine high water level trip channel inoperable.
B. Two or more feedwater and B.1 Restore feedwater and 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> main turbine high water level main turbine high water trip channels inoperable, level trip capability.
C. Required Action and 0.1 Reduce THERMAL 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> associated Completion Time POWER to < 23% RTP.
not met.
Brunswick Unit 2 3.3-24 Amendment No. 247 I Page 13 of 33
EVENT 2 (CONT) C32-LT-NOO4A FAILS LOW (TS)
RO Time Action Notes Acknowledges and reports annunciator report of A-7 4-2 FWCTL SYS TROUBLE Diagnose failure of the C32-NOO4A Performs 20P-32, Section 8.4 to shift level control to B.
Shifts LEVEL A/B select switch to Position B.
BOP Time Action Notes Plant Monitoring Page 14 of 33
EVENT 313a 2A TCC PUMP TRIP! AOP-17 POWER REDUCTION TCC Pump 2B will trip and TBCCW low header pressure will alarm. The crew will respond per OAOP-17.0 and place a TBCCW pump in service Objectives:
SCO Direct entry into OAOP-17.0.
RO Power reduction with Recirc flow.
BOP Restoration of TCC pressure.
Success Path:
2C TBCCW pump started and TCC pressures restored to normal with reactor power reduced to 60%.
Simulator Operator Actions:
Following TS call for LCO 3.3.2.2 and at the lead evaluator direction, initiate TRIGGER 2 to trip the 2A TCC pump.
D If contacted as the TB AC, wait one minute and report that 2B TCC pump is hot to the touch and the breaker is tripped (magnetic).
E If contacted as Unit One CRS, report Unit One is using the 2C TCC Pump.
If contacted as l&C to investigate 2B TCC Pump, acknowledge request.
If contacted as RE for power reduction or Reactivity Plan, acknowledge request.
E If contacted as Unit One for air compressor status, initiate TRIGGER 4.
E When directed by the lead examiner, proceed to the next event.
Required Operator Actions Component Failure 2A TCC pump trip.
Reactivity Manipulation Reduce Reactor Recirc flow to 47 Mlbm/hr.
SRO Time Action Notes Acknowledge report of annunciator UA-03 2-4 TBCCW PUMP DISCH HEADER PRESS LOW Direct entry into OAOP-17.0.
Direct start of a TCC Pump.
Direct power reduction lAW ENP-24.5 to 47 Mlbm/hr the Recirc flow limit.
Directs I&C to investigate loss of 2B TCC pump.
Acknowledge report of annunciator UA-03 4-8 OPRM TRIP ENABLED Briefs crew on reactor scram if TCC pressure is not restored above 42 psig within 4 minutes of reaching 47Mlbm/hr.
Page 15 of 33
EVENT 3!3a (CONT) 2A TCC PUMP TRIP! AOP-17 POWER REDUCTION RO Time Action Notes Plant Monitoring.
Reduces reactor power with Recirc Flow See Attachment 1 for power reduction to ENP-24.5 flow limit of 47 Mlbm/hr. with Recirc flow actions.
Acknowledge and report annunciator UA-03 4-8 OPRM TRIP ENABLED BOP Time Action Notes Acknowledge and Report annunciator Depending on the amount of time that no UA-03 TCC pump is operating, one pump will not 2-4 TBCCW PUMP DISCH HEADER immediately restore TCC pressure due to PRESS LOW the system load TCC temperature control valves being wide open.
Diagnose loss of 2A TCC Pump.
Enters OAOP-17.O and Starts 2B TCC pump by placing control switch to ON.
Dispatch AO to investigate 2A TCC Pump and look for system leaks.
May dispatch AO to perform prestart checks for 2B Pump.
May place 2A TCC pump control switch to OFF.
May request use of 2C TCC pump from Unit One.
May request Unit One place ID air compressor in service.
Trips the 2D air compressor if running and Unit air compressor is in service.
Report annunciator UA-03 2-4 TBCCW PUMP DISCH HEADER PRESS LOW clear.
Page 16 of 33
EVENT 4 2B NSW PUMP SHAFT SHEAR (TS)
The 2B NSW pump shaft will shear causing a low header pressure. 2A NSW pump will fail to AUTO start. The BOP operator should recognize the failure and manually start the 2A NSW pump. OAOP-18.O will be entered and T.S. 3.7.2 will require restoring a required NSW pump to Operable status within 7 days.
Objectives:
SCO Direct AOP-18 actions and Evaluate Tech Specs 3.7.2 Service Water System and Ultimate Heat Sink RO/BOP Respond to the failure of an automatic start of the 2A NSW pump.
Success Path:
2A NSW pump placed in service and TS LCO 3.7.2, 7 day LCO entry.
Simulator Operator Actions:
D When TCC parameters have stabilized and at the discretion of the lead evaluator, insert Trigger 3 to
- If asked as the OSAO to investigate, acknowledge request.
If asked as the OCSRO to initiate an impairment, acknowledge request.
If asked as I&C to investigate acknowledge the request.
When directed by the lead examiner, proceed to the next event.
Required Operator Actions SRO Time Action Notes Acknowledges report of annunciator UA-01 1-10 NUCLEAR HDR SERV WTR PRESS-LOW Directs AOP-18 entry and may direct placing 2B NSW pump in service or a CSW pump in service on the NSW header.
Acknowledges report of annunciator UA-01 1-10 NUCLEAR HDR SERV WTR PRESS-LOW Clear.
Contacts I&C / Maint to investigate 2B NSW loss and 2A NSW pump failure to auto start.
Evaluates TS 3.7.2 and determines See Attachment 2 for TS 3.7.2 Condition B requires restoration of IA or Auto start on header low pressure is not 2B NSW operability within 7 days. required for pump operability.
May direct OCSRO to initiate an impairment lAW PLP-1 .2.
Page 17 of 33
EVENT 4 (CONT) 2B NSW PUMP SHAFT SHEAR (TS)
RO Time Action Notes Plant Monitoring.
May make PA announcement for AOP-1 8 entry BOP Time Action Notes Acknowledges and reports annunciator UA-01 1-10 NUCLEAR HDR SERV WTR PRESS-LOW Identifies 2A NSW pump failure to auto start.
Enters and announces entry into AOP-1 8.
May acknowledge and report annunciators If standby pump is not started fairly quick, UA-05 vital header pressure will lower causing 1-9 FAN CLG UNIT CS PUMP RM A INL these alarms to come in. Alarms will PRESS LO clear once a SW pump is started on the 2-9 FAN CLG UNIT CS PUMP RM B INL NSW header.
PRESS LO Directs OSAD to investigate 2B NSW pump failure and to look for leaks.
Shuts down 2B NSW pump upon report of shaft shear.
Page 18 of 33
EVENT 5 SCRAM AIR LEAK! CR DRIFT HCU 14-35 will develop an air leak causing the control rod to slowly drift inwards. The crew will enter AOP-2.0 Control Rod Malfunction/Misposition. AOP-2.0 will direct response per 2APP-A-05 (3-2) ROD DRIFT. The RO should attempt to arrest the drifting control rod. The air leak start impacting surrounding HCU5 causing additional control rods to drift inward (1 minute later rod 22-31,1.5 minutes later rod 10-31, and 2 minutes later additional rods begin drifting).
Objectives:
SRO Direct actions for AOP-02 and Scram RO Perform rod drift actions, insert Manual Scram.
Success Path:
Manual Scram inserted due to multiple control rods drifting.
Simulator Operator Actions:
E At the discretion of the lead evaluator, insert Trigger 3 to cause scram air header leak.
n If asked as l&C to investigate acknowledge the request.
E If contacted as the RE to address thermal limits, inform crew that you will monitor core performance on the computer.
If asked as RBAO to investigate acknowledge the request.
D When directed by the lead examiner, proceed to the next event.
Required Operator Actions Component Failure control rod drift actions SRO Time Action Notes Acknowledges report of annunciators UA-05 3-2 ROD DRIFT 5-2 ROD BLOCK RWM/RMCS SYS TROUBLE Direct actions of APPs.
May contact l&C to investigate control rod drift.
May contact RE for control rod drift.
Acknowledges report of additional control rods drifting.
Direct manual Scram for multiple control rods drifting.
Page 19 of 33
EVENT 5 (CONT) SCRAM AIR LEAK ICR DRIFT BOP Time Action Notes Plant Monitoring.
May recognize additional control rods drifting RO Time Action Notes Acknowledge and report annunciators UA-05 3-2 ROD DRIFT 5-2 ROD BLOCK RWM/RMCS SYS TROUBLE Announce and enter AOP-2.0 Perform the actions of APP-A-05 (3-2) ROD DRIFT as follows:
Determines control rod 14-35 is drifting.
Selects control rod 14-35 and determines drifting inward.
May attempt to arrest the drift by giving a withdraw signal Monitors core parameters, main steam line radiation and off-gas activity Recognizes and reports additional control rods drifting (22-31, 10-31)
Inserts a Manual Scram by depressing both manual reactor Scram push buttons.
Page 20 of 33
EVENT 617 ATWS I SLC FAILURE I RWCU FAIL TO ISOLATE The scram air header leak degrades causing additional control rods to drift inward. With scram air header low and multiple control rods drifting, a manual Scram will be inserted. Most of the control rods will fail to insert on the scram. The crew will respond to the ATWS per EOP-01-LPC.
When SLC initiation is attempted, neither SLC pump will start due to switch failure. The crew will perform LEP-03 and align for alternate boron injection using CRD and manually isolate RWCU.
Objectives:
SCO Direct actions for a reactor scram per EOP-01-RSP.
Direct actions to control reactor power per EOP-01-LPC.
RO/BOP Perform immediate actions for a reactor scram.
Perform actions for an ATWS per EOP-01-LPC.
Success Path:
Actions of LPC performed. Recognizes failure of SLC and performs alternate boron injection and isolates RWCU. Control rods being inserted lAW LEP-02.
Simulator Operator Actions:
Li If requested to perform alternate boron injection using CRD, acknowledge the request. (will be performed after RPV injection is re-started following T&P)
Li Acknowledge request as l&C to investigate failure of SLC.
Li When directed by the lead examiner, proceed to the next event.
Required Operator Actions Major Event Reactor Scram / ATWS Component Failure SLC control switch failure Component Failure RWCU failure to isolate Performs LEP-03, Alternate Boron Injection Performs LEP-02, Alternate Rod Insertion SRO Time Action Notes Enters RSP and transitions to LPC.
Directs mode switch to shutdown when steam flow < 3 Mlbs/hr.
Directs ARI initiation.
Directs Recirc Pump speeds reduced to 10%.
Directs tripping Recirc Pumps.
Page 21 of33
EVENT 617 (CONT) SCRAM AIR HEADER LEAKIATWS ACTIONS SRO Continued Time Action Notes Directs SLC initiation.
Directs LEP-03, Alternate boron (Critical task) injection.
Directs ADS inhibited.
Directs RWCU isolation.
Directs LEP-02, Alternate Rod (Critical task)
Insertion.
Contacts I&C for SLC control switch failure.
Acknowledges request for LEP-02, Section 3 jumpers.
Directs OCSRO to perform LEP-02, Section 3 to bypass scram signals with j urn pers.
RO/BOP Time Action Notes Places mode switch to shutdown when After each action, reactor power level 6 lb/hr.
steam flow < 3x10 should be reported along with the action being completed.
Initiates ARI.
Places Recirc Pump speeds reduced to 10%.
Trips Recirc Pumps.
Places ADS in inhibit.
Page 22 of 33
EVENT 617 (CONT) SCRAM AIR HEADER LEAKIATWS ACTIONS ROIBOP Time Action Notes Initiates SLC by placing control switch to the PUMP A & B RUN position.
Recognizes failure of SLC and reports to All positions of control switch should be SCO. attempted prior to reporting failure.
Identifies RWCU fails to isolate.
Closes RWCU Outboard Isol Valve G31 -F004.
May close G31-FOO1 also.
Performs LEP-03, Alternate Boron (Critical task)
Injection.
Directs AO to perform LEP-03, Section 1, Alternate Boron Injection using CRD.
Performs LEP-02, Alternate Rod (Critical task)
Insertion. (RMCS Section)
Insert IRMs.
When < range 3 on IRMs insert SRM5.
Starts both CRD pumps.
Place CRD Flow Controller to Manual.
Throttle open flow controller to establish? 260 drive water psid.
May report failure of CRD Flow control Scram air header leak also causes loss valve, of control air to the CRD FCVs.
Bypasses RWM. Obtains key from key locker.
Selects control rods and drives in using Emerg rod in notch override.
Requests jumpers for LEP-02, Section 3.
Stabilizes RPV level and pressure.
Page 23 of 33
EVENT 8 ATWS ACTIONS TERMINATE AND PREVENT The crew will terminate and prevent injection. Re-injection will start when level is at 90 inches due to table 3 conditions not met. If RFPs are tripped they will be unavailable for level control as the Recirc Valves will fail in the closed position not allowing the RFPs to be restarted. Feedwater and HPCI will be available for level control.
Objectives:
SCO Direct actions to lower reactor vessel level when the conditions of Table 3 are not met per EOP-01 -LPC.
RO/BOP Control reactor level during an ATWS per EOP-01 LPC and insert control rods per LEP-02.
Success Path:
Continues LPC actions to shutdown the reactor by terminating & preventing injection and inserting rods using RMCS and cooling water DIP.
Simulator Operator Actions:
o If requested to defeat Group I, LL3, wait 2 minutes, initiate Trigger 8 and inform the SCO that the jumpers are installed.
0 lf requested to install LEP-02, Section 3 jumpers, wait until level has been terminated and prevented or 5 minutes whichever is longer, insert Trigger 7 and inform the SCO that the jumpers are installed.
o If directed as AO to investigate the failure of the SDV vents & drains or CRD FCV failure, acknowledge the request.
o If requested as I&C to investigate the failure of the scram discharge volume vents and drains, acknowledge the request.
0 If requested to open the MVD-5005, wait 5 minutes, initiate Trigger 9 and inform the control room that the valve is open.
0 If requested to defeat Drywell Cooler LOCA Lockout, wait three minutes, initiate Trigger 10 and inform the SCO that the jumpers are installed.
o When injection to the RPV has been re-established and if requested to line up boron to the CRD system initiate Trigger 11.
o When directed by the lead examiner, proceed to the next event.
Required Operator Actions Terminate and prevent HPCI/Feedwater (CSIRHR when LOCA signal received).
SRO Time Action Notes Directs verification of initiations and isolations.
Directs OCSRO to bypass Group 1, LL3 per SEP-10.
Directs Group 10 switches placed in override reset.
Directs terminate and prevent (Critical task)
HPCI/Feedwater (CS/RHR when LOCA signal received).
Page 24 of 33
EVENT 8 (CONT) ATWS ACTIONS TERMINATE AND PREVENT SRO Time Action Notes May direct RCIC flow be reduced to support lower level to +90 inches.
When level reaches +90 inches, Normally provides level band of 60-90 inches evaluates Table 3: to prevent reaching LL3 (LOCA signal).
. If not met, establishes a level band of LL4 to +90 inches.
Directs injection established to maintain If level is lowered to less than 45 inches (LL3)
RPV level LL4 to 90 inches then the LP ECCS pumps will start and will need to be terminated and prevented.
Directs Drywell cooling restored per SEP 10.
Evaluate TAF and LL4 indicated levels using Caution 1 graphs.
RO Time Action Notes Continues to select control rods and drive in using Emerg rod in notch override.
Monitor APRMs for downscale.
Monitors SLC tank level after report of LEP-03 is in progress.
Performs LEP-02, Section 3 after (Critical task) jumpers are installed.
Inhibit ARI Places ARI Initiation Switch to INOP Places ARI Reset Switch to RESET and maintains for 5 seconds.
Verifies red TRIP light above AR!
Initiation is OFF Reset RPS when scram jumpers installed.
Ensures Dish Vol Vent & Drain Test switch is in Isolate.
Page 25 of 33
EVENT 8 (CONT) ATWS ACTIONS TERMINATE AND PREVENT RO Time Action Notes Performs LEP-02, Section 3 Continued Confirms Disch Vol Vent Valves V139 and CV-FO1O are closed Confirms Disch Vol Drain valves V140 and C V-FOIl are closed.
Resets RPS.
Place Disch Vol Vent & Drain Test switch to Normal Recognize/report failure of scram Scram air header leak prevents opening discharge volume vents and of SDV V&Ds.
drains.
May direct OCSRO to coordinate venting CRD over pistons lAW LEP-02.
BOP Time Action Notes Places Group 10 switches to override I reset Terminate and prevents injection to RPV.
HPCI Places HPCI Aux Oil Pump to Pull to Lock.
FW - Can be performed a couple of The preferred method would be to lower ways. discharge pressure.
Trip RFP Turbines OR Trip one RFP and adjust discharge pressure of the running pump down to below RPV pressure to prevent injection.
Then Ensures SULCV lineup with MSTR RFPT SP/RX L VL CTL in manual and SULCV closed.
ECCS - Turns OFF low pressure ECCS pumps if they start.
Page 26 of 33
EVENT 8 (CONT) ATWS ACTIONS TERMINATE AND PREVENT BOP Time Action Notes May place Feedwater in service for level Controllers on P603.
control when directed by the SCO.
Raise REP discharge pressure above RPV pressure Open SULCV to obtain desired level May place HPCI in service for level control during ATWS when directed by the SCO.
Place HPCI in manual (M) and adjust output demand to approximately 40% using the manual lever.
Adjust HPCI setpoint to approximately 1000 GPM.
Start auxiliary oil pump.
When HPCI turbine speed stops increasing, then raise HPCI pump flow to approximately 1000 GPM using the manual lever on H PCI.
Ensure E41-E012 is closed when flow has increased above 800 GPM.
Transfer HPCI from Manual (M) TO Auto (A).
Adjust HPCI setpoint to maintain desired reactor water level Page 27 of 33
EVENT 9 ALL RODS IN When level has been lowered and level band has been established, the scram air header will be repaired. Control rods can then be inserted by manual scram. When all control rods are inserted and level is being maintained 170 to 200 inches the scenario may be terminated Success Path:
When actions are taken to control reactor water level during the ATWS after terminating and preventing, the SDV vents and drains will be repaired and rods can be inserted.
When all rods are inserted and level is being controlled 170 200 inches the scenario may be terminated.
Simulator Operator Actions:
D When directed by the lead evaluator, delete the following commands:
Malfunction RDO41 F, Loss of Control air to the Scram valves.
n Malfunction RPOIOF, ATVVS 3 (Make sure RPS is reset before deleting)
Inform the SCO that scram air header leak was located at 1ICU 14-35 and has been repaired.
u If contacted as the RB AO to secure Alternate Boron Injection delete remote SL_IALEPO3.
When directed by the lead evaluator, place the simulator in FREEZE.
Required Operator Actions SRO Time Action Notes Exit LPC and enter RVCP when all rods are in.
Direct securing Alternate Boron Injection.
Direct level restored to 170 200 inches after rods are all in.
Page 28 of 33
EVENT 9 (CONT) ALL RODS IN RO Time Action Notes Continues to drive rods using RMCS Confirms Disch Vol. Vent & Drains open when scram air header is reported fixed.
Inserts a scram after discharge volume has drained for 2 minutes.
Reports all rods in.
Directs AC to secure Alternate Boron Injection.
BOP Time Action Notes Maintains reactor pressure as determined by the SCO.
Maintains level as directed by the SCO.
Restores level to 170 200 inches after all rod inserted using any of the following:
Increases RCIC controller to 500 gpm.
Increases HPCI controller to raise reactor water level.
Raises feedwater flow to raise reactor water level, if RFPs were not tripped.
Page 29 of 33
Simulator Operator Activities:
WHEN directed by the lead examiner, place the simulator in FREEZE.
CAUTION DO NOT RESET THE SIMULATOR PRIOR TO RECEIPT OF CONCURRENCE TO DO SO FROM THE LEAD EXAMINER Page 30of33
Attachment I Recirculation Speed Adjustments
- 1) Manipulates recirculation speed only with SRO permission.
- 2) Ensures Concurrent Verifier is available, prepared, and in place.
- 3) Communicates to Concurrent Verifier direction of movement, component to be manipulated, amount of adjustment, and stopping point.
- 4) Obtains concurrence of Concurrent Verifier before commencing adjustments.
- 5) Operates recirculation speed controls one at a time, allows time for plant and machine response.
- 6) Observes redundant plant indications while performing adjustments.
- 7) Notifies SRO when recirculation speed adjustments are completed.
- 8) Periodically checks position on Power to Flow map.
Page 31 of 33
Attachment 3 Reactor Water Level Graphs SW System and UHS 3.7.2 3.7 PLANT SYSTEMS 31.2 Service Water (SW) System and Ultimate Heat Sink (UI-IS>
LCO 3.7.2 SW System and UHS shall be OPERABLE APPLICABILITY: MODES 1,2, and 3.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. ---------NOTE-------------- Al ----------NOTE-------
Only applicable when Unit 1 Enter applicable Conditions is in MODE 4 or 5. and Required Actions of
- -------------------- LCO3.8.i,ACSources Operating, for diesel One required nuclear generators (DGs) made service water (NSW) pump inoperable by NSW.
inoperable due to an inoperable Unit 1 NSW header. Restore required NSW 14 days pump to OPERABLE status.
(continued)
ACTIONS (continued)
OND[TION REQUIRED ACTION COMPLETION TIME B. One required NSW pump B. 1 --------
inoperable for reasons other Enter applicable Conditions than Condition A. and Required Actions of LCO 3.8.1 for DOs made inoperable by NSW.
Restore required NSW 7 days pump to OPERABLE status.
14 days from discovery of failure to meet LCO C. One required conventional C. 1 Verify the one OPERABLE Immediately service water CSW) pump CSW pump and one inoperable. OPERABLE Unit 2 NSW pump are powered from separate 4.16 kV emergency buses.
AND C.2 Restore required CSW 7 days pump to OPERABLE status. AND IA frnm Page 32 of 33
Attachment 3 Reactor Water Level Graphs SW System and UHS 6 3.7..2 BASES APPLICABLE analyses include the evaluation of the long term primary containment SAFETY ANPLYSES response after a design basis LOCA.
(continued)
The ability of the SW System to provide adequate coaling to the identified safety equipment is an implicit assumption for the safety analyses evaluated in References 1 and 2. During the first 10 minutes of a design basis LOCA. the ability to provide onsite emergency AC power is dependent on the ability of the SW System to cool the DGs. Ten minutes following a LOCA, the long term cooling capability of the RHR, core spray, and RHRSW subsystems is dependent on the cooling provided by the SW System.
The SW System, together with the UHS. satisfy Criterion 3 of 10 CFR 50.36(c)(2)Qi) (Ref. 4).
LCO In the event of a DBA, the NSW header and associated components are adequate to provide the minimum heat removal capability assumed in the safety analysis for the systems to which it supplies cooling water.
However, the SW header and assodated components are required to ensure maximum reliability in the event of a single failure. To ensure this requirement is met, the appropriate equipment to supply the unit NSW and CSW headers must be OPERABLE. In addition, at least three site NSW pumps are required to ensure adequate NSW pump redundancy is available to ensure cooling to the DGs in the event of an active single failure.
The SW System is considered OPERABLE wten it has two OPERABLE CSW pumps (specifically the CSW 2A and CSW 2C pumps), three site NSW pumps (any combination of Unit I and Unit 2 NSW purnps, and an OPERABLE flow path capable of taking suction from the intake structure and transferring the water to the ECCS equipment and the DGs. In addition, for a site NSW pump to be considered OPERABLE, it must be capable of supplying its associated unit NSW header. For a CSW pump to be considered OPERABLE, it must be capable of supplying the CSW header and the NSW header. The CSW 2A and CSW 2C pumps must be OPERABLE to ensure that two pumps can supply the CSW header with one specific postulated single failure, toss of Division II power. This failure disables both the flow path from the NSW header to the RHRSW pumps and it disables the CSW 26 pump.
The OPERABILITY of the UHS is based on having a minimum water level in the pump well of the intake structure of -6 ft mean sea level and a rnaxmun UHS 24-hour average water temperature of 90.5cF with the maximun UHS actual water temperature not to exceed 92°F.
(continued)
Brunswick Unit 2 B 3.7.2-3 Revision No. 5 Page 33 of 33
PROGRESS ENERGY CAROLINAS BRUNSWICK TRAINING SECTION SIMULATOR SCENARIO 2010-2 NRC Exam Scenario #5
Appendix D Scenario Outline Form ES-D-1 Facility: Brunswick Scenario No.: 2010-2 #5 Op-Test No.: Draft Examiners: Operators:
Initial Conditions: Unit Two is operating at 94% power, end of cycle power.
APRM Channel 2 failed downscale and bypassed.
2C TCC pump is in service on Unit One Turnover: Perform Main Turbine Stop Valve Testing.
Event MaIf. No. Event Event No. Type* Description 1 N/A N-BOP Main Turbine Stop Valve Test N-SRO 2 ESOI3F 1-RO HPCI Logic Bus A Auto Start Fails (TS) l-SRO 3 CFO39F C-BOP Heater Drain Deaerator Controller Failure C-SRO R-RO AOP-23 Power Reduction 3a N/A R-SRO 4 1-RO APRM 4 Failure (TS)
NIO3IF l-SRO ZUA1321O C-BOP UAT Ground C-SRO 6 M-AII Loss of Offsite Power, Scram EEO2OF 6a DGOO5F C-BOP DG 4 Failure to Start C-SRO 7 NBOO9F M-All Small break LOCA 7a ESO44F ESO45F C-RO LP ECCS initiation logic failure ESO46F C-SRO 8 N/A N/A Emergency depressurization (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Page 2 of 37
SCENARIO DESCRIPTION The plant is operating at -94% power, end of cycle. Core Spray Pump 2A is out of service and APRM Channel 2 is failed downscale and bypassed. 2C TCC pump is aligned to Unit One.
Event I 20P-26, Section 8.6 (Main Turbine Stop Valve Test) is complete up to Step 8.6.2.7 with feedwater level control transferred to single element lAW 20P-32. MTSV Testing will continue testing MSVs 1 through 4. DFCS will be transferred to 3-element when complete.
Event 2 The HPCI logic power fuse will blow requiring HPCI to be manually isolated per the APP and declared Inoperable perTS 3.5.1, Condition D and also Condition E (HPCI &
CS Inop) which requires restoration of one of the two within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
Event 3 The Heater Drain Deaerator level control system will fail causing the HDP discharge valves to fail full open. The crew will respond per AOP-23.O, lower reactor power, stop I HD pump before HDD level goes <24, and then open the HD-V57 to control HDD level.
Event 3a Reactor power will be reduced with Recirc Flow to within the capacity of I HDP per AOP-23.
Event 4 APRM 4 will fail upscale resulting in a rod block. The APRM will be declared Inoperable per TS 3.3.1.1, Condition A and placed in trip within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. WCCSRO will request APRM TS Actions be taken in order to troubleshoot which requires the APRM mode selector switch to be place in INOP lAW 001-1 8.
Event 5 A UAT ground alarm will be received. The crew will respond lAW the APP.
Investigation by I&C will indicate the alarm is valid requiring Buses 2C & 2D to be transferred to the SAT.
Event 6 Prior to transferring the second Bus to the SAT, the SAT will trip and lock out. Off-site power will be lost. The crew will respond per AOP-36.1 and EOP-01-RSP. SRVs will be available for pressure control. RCIC and CRD will provide inventory makeup to the RPV.
Event 6a Diesel Generator 4 will fail to auto start. DG4 will be manually started in Control Room Manual and Emergency Bus E4 re-energized.
Event 7 A small Recirculation line break will occur. Available injection sources will be unable to stabilize RPV level. RPV level will drop to LL3 resulting in actuation of ADS timers.
ADS will not automatically initiate due to ECCS logic failure but may be manually initiated when level drops below TAF.
Event 7a Low pressure ECCS initiation logic will fail at LL3 requiring manually starting available pumps and aligning injection when RPV pressure drops below 400 psig.
Event 8 When the RPV has been depressurized and RPV level restored to the normal band, the scenario may be terminated.
Page 3 of 37
OBJECTIVES SRO 341224B102, Determine actions required for Limiting Conditions for Operation per 01-01.8 and Technical Specifications 344227B402, Direct Action For Condensate/Feedwater System Failures Per AOP-23.0 344237B402, Direct Actions For A Loss of Any 4KV Buses Per AOP-36. 1 344231 B502, Direct Actions For A Reactor Scram With MSIVs Closed And Reactor Power Less Than 4% Per EOP-O1-RSP 344217B502, Direct Actions To Control RPV Level Per EOP-01-RVCP 344218B502, Direct Actions To Control Reactor Pressure Per EOP-01-RVCP 344220B502, Direct Actions To Emergency Depressurize The RPV Per EOP-01-RVCP 3442 14B502, Direct Actions To Control Primary Containment Pressure Per EOP PCCP 344215B502, Direct Actions To Control Primary Containment Temperature Per EOP PCCP 3442 16B502, Direct Actions To Control Suppression Pool Temperature Per EOP PCCP RO 259001 B401, Respond to a Condensate/Feedwater System Failure Per AOP-23.0 202202B1 01, Decrease Reactor Recirculation Pump Speed/Reactor Power Using The Manual Control Station Per OP-02 21 5204B401, Respond To An APRM Failure Per APP A-06 2-7, 2-8, 3-7, And/Or 3-8 262002B401, Respond To A Loss Of Off-Site Power Per AOP-36.1 264009B401, Manually Start A DG With An Auto Start Signal Present With A Failure Of The DG To Start 209007B501, Manually Operate Core Spray To Maintain Reactor Water Level 203006B501, Manually Operate LPCI To Control Reactor Water Level 200049B501, Spray The Drywell Per EOP-01-SEP-02 200062B501, Spray The Suppression Pool Per EOP-01-SEP-03 205014B101, Start Up RHR In Suppression Pool Cooling Mode Per OP-17 Page 4 of 37
SIMULATOR SETUP Initial Conditions IC-25 Sequence BI Triggers Trigger Description 1 Manual HPCI Bus A Logic Failure 2 Manual HDD Controller Failure 3 Manual APRM 4 Fail Upscale 4 Manual UAT Ground 5 Auto SATTrip(K4101B08) 7 Manual Small Break LOCA 8 Manual RCC Aligned to CSW 9 Manual CRD Flow Max F034 Charging Water Isolation valve 10 Manual DW Cooler Stop 11 Manual E41-F041 BreakerOff 12 Manual E41-F042BreakerOff 13 Manual SLC to DW (LEP-Ol) 14 Manual CRD Maximize 2 pumps (SEP-09) 15 Manual Place 1 D Air Compressor in service Interventions Summary Note: Shaded entries = Active Malfunctions Summary Current Target Ramp Act. Deact MaIf. ID Mult ID Description Thg Value Value Time Time Time DGOO5F DG4 AUTO START FAIL
[ TRUE TRUE ESO43F CORE SPRAY A AUTO START FAIL TRUE TRUE ESO44F CORESPRAYBAUTOSTARTFAIL ITRUE TRUE ESO45F_f_______ RHR A AUTO START FAIL TRUE TRUE I_____
ESO46F RHR B AUTO START FAIL TRUE TRUE NIO32F APRM 2 APRM FAILS LO TRUE TRUE Page 5 of 37
Malfunctions Summary Current Target Ramp Act. Deact MaIf. ID Mult ID Description Trig Value Value Time Time Time ES013F HPCI LOGIC BUS A AUTO START FAIL FALSE TRUE 1 ESO14F INADVERANT HPCI SYS INITIATION FALSE TRUE 1 CFO39F HTR DRN DEAER LVL CNTRLR FAILS FALSE TRUE 2 NIO31F APRM4 APRM FAILS HI FALSE TRUE 3 EEO2OF SAT RELAY FAILURE FALSE TRUE 5 NBOO9F SMALL RECIRC LINE RUPTURE 10% 5 Mm 7 Remotes Summary
. . Current Target Remote ID Mult. D Description Trig Value Value CC_IACW45I8 2CTBCCWPUMP UNIT ALIGNMENT 1 1 VHSWI46L CSW TO RBCCW HXS V146 SHUT OPEN 8 1.0 over 5 RDVFO34 CHARGING WATER ISOL VALVE F034 .25 sec 1AC5993P DW CLR AID OVERRIDE NORMAL/STOP NORM STOP 10 IACS994P DW CLR B/C OVERRIDE NORMAL/STOP NORM STOP 10 HP_ZVHPO41M SUPPSUCTIONVLVE4I-F041 ON OFF 11 HP_ZVHPO42M TORUS SUCTION VLV E41-F042 ON OFF 12 SL_IASLCRCR SLC TST TNK SOURCE (NORM=DW/ALT=FP) NORM NORM 13 SL_IASLCCTST SLC SUCT LINEUP (ALT=TEST TANK) ALT ALT 13 BV707/
RD_RDSUCTF SUCTION FILTER ISOL VALVES OPEN OPEN 14 RDRDSUCTB SUCTION FILTER BYPASS VLV C0-V306 OPEN OPEN 14 RD_RDDRIVF DRIVE WATER FILTER ISOL VALVES OPEN OPEN 14 IA_IAIU1CMPRSS UNIT 1 AIR COMPRESSOR STATUS 15 lB STDBY lB STDBY Page 6 of 37
Switches Summary 1 Position / Actual Override Switch ID Description Trig j Target Position Value QI D23SWN RHR A mit Sig White ON/OFF OFF OFF Q1J39SWN RHR 2 mit Sig White ON/OFF OFF OFF QIC22SWL mit Sig Seal In White ON/OFF OFF OFF QIJ32SWL mit Sig Seal In White ON/OFF OFF OFF ZUAI32IO UATWINDINGYGRDCURRENT ON/OFF OFF ON 4 SPECIAL INSTRUCTIONS
- 1. Ensure simulator exam security measures in place.
- 2. Provide 20P-26, Section 8.6, marked up completed to Step 8.6.2.7.
- 3. Advance all chart recorders to indicate steady state conditions.
- 4. Place all SPDS displays to the Critical Plant Variable display (#100).
- 5. Ensure appropriate keys have blanks in switches.
- 8. Ensure reference material is in appropriate location.
- 9. Verify any log books have blank sheets only and procedures are not marked.
- 10. Load scenario file if available.
- 11. Load malfunctions/overrides if scenario file is unavailable.
- 12. Ensure 2C TCC pump in service on Unit 1.
- 13. Place in Run and verify power at -94%.
- 14. Place Equipment Control Tag on and Bypass APRM 2.
- 15. Ensure 2B Stator Cooling pump is in service.
- 16. Place DFCS in 1-element.
- 17. Ensure SIMULATOR CONTROL ROOM KEY INDEX is next to key locker. (Hide actual CR Index)
- 18. Ensure OENP-24.5 for IC-25 @ P603.
Page 7 of 37
SHIFT BRIEFING Plant Status Unit Two is operating at 94% power, end of cycle.
Equipment Out of Service Core Spray Pump 2A is under clearance for breaker repair and is expected to be returned to service in two hours.
APRM Channel 2 failed downscale and bypassed.
2C TCC pump is supplying Unit One cooling.
No other equipment is out of service Plan of the Day 20P-26, Section 8.6 (Main Turbine Stop Valve Test) is complete up to Step 8.6.2.7 with feedwater level control transferred to single element lAW 20P-32.
When shift turnover is complete, perform Main Turbine Stop Valve testing.
Page 8 of 37
SCENARIO TRAINING INFORMATION Instructor Notes This guide is designed to meet the requirements of an examination scenario for Initial License as outlined in NUREG-1 021, Rev.9, Supp.1 ES-301 and Appendix D.
During the execution of this scenario, the students should be rated on the performance of the objectives, compliance with general simulator performance standards, and for overall team skills in accordance with TAP-409 and NUREG-1 021, ES-302.
Common Student Problems/Errors None Simulator Deficiencies There are no known simulator deficiencies applicable to this scenario.
Critical Tasks (Critical Tasks are identified to ensure scenario validity and do not constitute pass/fail criteria for Initial License.)
- Emergency Depressurize
- Restore and maintain RPV level above LL4.
Page 9 of 37
EVENT I MAIN TURBINE STOP VALVE TESTING 20P-26, Section 8.6 (Main Turbine Stop Valve Test) is complete up to Step 8.6.2.7 with feedwater level control transferred to single element lAW 20P-32. MTSV Testing will continue testing MSVs I through 4. DFCS will be transferred to 3 element when testing is complete.
Objectives:
SCO Directs performance of Main Turbine Stop valve testing lAW 20P-26, Section 8.6.
RO Monitors the plant.
BOP Performs Main Turbine Stop valve testing lAW 20P-26, Section 8.6.
Success Path:
Main Turbine Stop valve testing completed.
Simulator Operator Actions:
If requested to verify back panel relay positions, report complete lAW 20P-26.
D If contacted as Load Dispatcher, acknowledge request or information.
D If contacted as System Engineer (any discussion about fast closure), inform crew fast closure of MTSVs is satisfactory matches previous performances.
E When 20P-26, Section 8.6 is complete and when directed by the lead examiner, proceed to the next event.
Required Operator Actions Normal Operations Main Turbine Stop valve testing.
SRO Time Action Notes Direct performance of Main TSV testing.
Acknowledges Annunciator A-7 4-2 FW CTL SYS TROUBLE during TSV testing May allow discontinuing further reports of expected alarms lAW OPS-NGGC-1 000.
May contact System Engineer regarding Stop Valve testing abnormalities.
Page 10 of 37
EVENT 1(Cont) MAIN TURBINE STOP VALVE TESTING RD Time Action Notes Monitors the plant during Stop Valve 5-10 MWE Generator output change and possible standby EHC pump auto start.
testing.
Acknowledges Annunciator A-7 4-2 FW CTL SYS TROUBLE during TSV testing.
May request discontinuing further reports of May place a green placard under Annunciator A-7 expected alarms lAW OPS-NGGC-1 000.
on Panel P603.
BOP Time Action Notes Verifies DFCS is in Single Element.
DEPRESS AND HOLDs MSV NO I TEST push button AND ENSURE the following:
- a. Valve travel is smooth from 100% to 10% open.
- b. Valve travel is fast from 10% open to 0% open.
RELEASE MSV NO 1 TEST push button AND ENSURE the valve opens smoothly to the full open position.
ALLOWs plant parameters to stabilize before testing stop valve number 2.
ENSURE TURB STOP VLV CLOS TRIP (A-05 5-7) annunciator is clear.
DEPRESS AND HOLDs MSV NO 2 TEST push button AND ENSURE the following:
- a. Valve travel is smooth from 100% to 10% open.
- b. Valve travel is fast from 10% open to 0% open.
RELEASE MSV NO 2 TEST push button AND ENSURE the valve opens smoothly to the full open position.
ALLOWs plant parameters to stabilize before testing stop valve number 3.
ENSURE TURB STOP VLV CLOS TRIP (A-OS 5-7) annunciator is clear.
Page 11 of 37
EVENT I (Cont) MAIN TURBINE STOP VALVE TESTING BOP Time Action Notes DEPRESS AND HOLDs MSV NO 3 TEST push button AND ENSURE the following:
- a. Valve travel is smooth from 100% to 10% open.
- b. Valve travel is fast from 10% open to 0% open.
RELEASE MSV NO 3 TEST push button AND ENSURE the valve opens smoothly to the full open position.
ALLOWs plant parameters to stabilize before testing stop valve number 4.
ENSURE TURB STOP VLV CLOS TRIP (A-05 5-7) annunciator is clear.
DEPRESS AND HOLDs MSV NO 4 TEST push button AND ENSURE the following:
- a. Valve travel is smooth from 100% to 10% open.
- b. Valve travel is fast from 10% open to 0% open.
RELEASE MSV NO 4 TEST push button AND ENSURE the valve opens smoothly to the full open position.
PLACEs feedwater level control in three element in accordance with 20P-32.
- a. ENSUREs steam flow and feedwater flow Any of the following may be utilized:
have negligible mismatch using multiple C32-FR-R6o7 (SF/FE Recorder P603) indications. C32-R603 (SF) to C32-R604A & B (FE)
- b. ENSUREs vessel level has been at Plant Process Computer (PPC) or ERFIS steady state for approximately 5 minutes.
C32-R608 (NR Level recorder)
- 1. Depresses SEL button on SULCV, FW LIC-3269, until LVL ERROR is displayed AND CHECK level error is less than approximately 2 inches.
- 2. SHIFTs FEEDWATER CONTROL MODE SELECT control switch to 3-element position.
Reports results of testing and DFCS alignment to SRO.
Page 12 of 37
EVENT 2 HPCI LOGIC BUS A FAILURE The HPCI logic power fuse will blow requiring HPCI to be manually isolated per the APP and declared Inoperable per TS 3.5.1.
Objectives:
SCO Declare HPCI Inoperable
- Recognize logic failure and Isolate HPCI.
Success Path:
HPCI declared inoperable lAW TS 3.5.1 and isolated lAW APP.
Simulator Operator Actions:
U When directed by lead evaluator, INITIATE TRIGGER I to activate HPCI fuse failure.
LI If asked as AO to investigate, report all circuit breakers in DC SWBD 2A & Panel 4A are closed.
U If asked as I&C to investigate, wait 2 minutes and report fuse E41A-F1 in panel P620 is blown (blows again if replaced).
If asked as WCC/OC SRO for clearance or Equipment Control tags, acknowledge request.
U If requested to open breakers for E41-F041 and F042 (MCC 2XDA) when valves are shut, monitor valve positions on panel mimic (P601 Section A2).
o When E41-F041 indicates closed, INITIATE TRIGGER 11 o When E41-F042 indicates closed, INITIATE TRIGGER 12.
Required Operator Actions Instrument /Component Failure Isolate HPCI steam supply.
Technical Specification TS 3.5.1 Conditions D & E.
SRO Time Action Notes Direct annunciator response for A-I 5-5 HPCI LOGIC BUS A PWR FAILURE 6-4 HPCI COND STORAGE TNK WTR LVL LO May identify requirement to initiate an HPCI is considered a Train A system for impairment lAW OPLP-OI .5. ASSD.
(This action may be directed to Ops Center SRO)
Directs BOP to monitor the plant.
Determines depressurization of steam supply is NOT required.
Contacts l&C to investigate HPCI LOGIC BUS A PWR FAILURE Page 13 of 37
EVENT 2 (Cont) HPCI LOGIC BUS A FAILURE SRO Time Action Notes Refers to Tech Spec 3.5.1 ECCS Operating and Determines: Condition A existed at turnover with CONDITION A. One low pressure ECCS Core Spray Pump 2A under clearance.
injection/spray subsystem inoperable.
REQUIRED ACTION A.1 Restore low pressure ECCS injection/spray subsystem to OPERABLE status within 7 days.
CONDITION D REQUIRED ACTION:
Di Verify by administrative means RCIC System is OPERABLE.
Immediately AND D.2. Restore HPCI System to OPERABLE status.
14 days CONDITION E REQUIRED ACTION:
E.1 Restore HPCI System to OPERABLE status.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OR E.2 Restore low pressure ECCS injection/spray subsystem to OPERABLE status.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> May request equipment control tags to support abnormal HPCI system alignment.
Acknowledge and report annunciators A-I:
5-5 HPCI LOGIC BUS A PWR FAILURE 6-4 HPCI COND STORAGE TNK WTRLVLLO Report HPCI Suction is aligned to both the CST and Suppression Pool.
Page 14 of 37
EVENT 2 (Cont) HPCI LOGIC BUS A FAILURE RO Time Action Notes Performs APP A-I 5-5 (HPCI LOGIC BUS A PWR FAILURE) actions:
I. Close the Condensate Storage Tank Suction Valve, E41-F004.
I) CLOSE STEAM SUPPLY INBOARD ISOL VLV, E41-F002.
- 2) CLOSE STEAM SUPPLY OUTBOARD ISOL VLV, E41-F003.
- 3) Depressurizing steam supply is NOT required, but if performed will require performance of OPT-02.3.lb, Suppression Pool to Drywell Vacuum Breaker Position Check, within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />
- 3. Close the Turbine Exhaust Vacuum Breaker Valve, E41 -F075.
Informs SRO of expected alarm A-I 1-1 HPCI VAC BKR VLVFO75/F079 NOT FULL OPEN Contact RBAO to standby for opening breakers on MCC 2XDA when the following valves indicate Full Closed.
- 4. Close the Torus Suction Valve, E41-F041.
- 5. Close the Torus Suction Valve, E41-F042.
Notifies SRO APP actions are complete and No impact to TRM 3.6 BUS POWER to reference TS 3.5.1 and TRM 3.6. MONITORS (HPCI Inop).
BOP Time Action Notes Monitors the plant and reports CST at normal level.
Page 15 of 37
EVENT 3!3a HDD CONTROLLER FAILURE! AOP-23 POWER REDUCTION The Heater Drain Deaerator level control system will fail causing the HDP discharge valves to fail full open. The crew will respond per AOP-23.O, lower reactor power, stop 1 HD pump before HDD level goes <24, and then open the HD-V57 to control HDD level.
Reactor power will be reduced with Recirc Flow to within the capacity of 1 HDP per AOP 23.
Objectives:
SCO Direct AOP-23 actions.
RO - Reduce reactor power with Recirc flow.
BOP Trip a HDP and control HDD level manually.
Success Path:
Reactor power reduced to within the capacity of I HDP and HDD level being controlled manually with the HD-V57.
Simulator Operator Actions:
Li When directed by lead evaluator, INITIATE TRIGGER 2 to activate HDD controller failure.
Li If asked as AO to investigate, acknowledge request.
Li If asked as I&C or MM to investigate, acknowledge request.
Li If contacted as RE to monitor thermal limits, acknowledge request.
Li When plant conditions have stabilized with HDD level being manually controlled, DELETE HDD malfunction (CFO39F) and call the control room as l&C and report Level controller output air line was discovered separated and has been reconnected.
Required Operator Actions Component Failure HDD Level Controller.
Reactivity Manipulation Lower reactor power with Recirc flow.
SRO Time Action Notes Direct entry into AOP-23.0 Direct lowering reactor power I HDP should maintain HDD Level with Main Generator output between 200 &
550 MWe.
Direct trip of I HD pump and HDD level control with HD-V57 Direct l&C to investigate HDD level control problem Direct OGP-12 or GP-05 performance May contact RE to monitor thermal limits due to reduced feedwater temperature or a reactivity management plan for recovery.
Page 16 of 37
EVENT 313a (Cont) HOD CONTROLLER FAILURE! AOP-23 POWER REDUCTION RO Time Action Notes Reduce power per OENP-24.5 as directed by the SCO.
Lower flow on one RR Pump (2%) at a time to stay within mismatch criteria 6 MIbs jet pump flow if < than (7.5x10 58 MIbs or 3.5x10 6 Mlbs if> than 58 MIbs).
Continues alternating Recirc pump decreases until core flow is 43 MIbs.
BOP Time Action Notes May Diagnose HD pump discharge valves full open prior to low level alarm.
Acknowledges and reports annunciator UA-4 2-10 HD DEAERA TOR LEVEL HIGH -
LOW.
Dispatches an operator to local HDD controller.
Enters and announces AOP-23.0 Trips 1 HD pump prior to HDD level reaching +24 inches.
Opens HD-V57 to control HDD level Monitors main condenser vacuum.
Maintains heater drain deaerator level less than 60 inches indicated on HEATER DRAIN DEAERATOR LEVEL, HD-Ll-97 MONITORs final feedwater temperature (FFWT) lAW 201-03.2.
Ensures plant is compatible with GP-12 or GP-05 Page 17of37
EVENT4 APRM4FAILURE APRM 4 will fail upscale resulting in a rod block. The APRM will be declared Inoperable per TS 3.3.1.1, Condition A and placed in trip within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. WCCSRO will request APRM TS Actions be taken in order to troubleshoot which requires the APRM mode selector switch to be place in INOP lAW 001-1 8.
Objectives:
SCO Determine LCO for APRM 4 inoperability and direct placing channel in trip.
RO - Diagnose APRM 4 failure and place in INC P.
BOP Monitor the plant.
Success Path:
ARPM 4 declared inoperable lAW TS 3.3.1 .1 and placed in trip condition lAW 001-18.
Simulator Operator Actions:
O With the HDD level being controlled automatically and directed by lead evaluator, INITIATE TRIGGER 3 to activate APRM 4 failure.
0 If asked as l&C to investigate, acknowledge the request.
0 If asked to pull fuses (for TRM 3.3 actions) acknowledge the request.
0 After LCD entries have been determined and SRO is waiting for l&C, call as WCCSRO and request APRM 4 be placed in tripped condition to support I&C trouble shooting.
Required Operator Actions Component Failure APRM 4 will be required to be placed in INOP.
Technical Specification TS 3.3.1.1 Condition A, TRM 3.3.
SRO Time Action Notes Direct actions of APPs Direct l&C to investigate Evaluate Tech Spec 3.3.1.1 Reactor Protection System Instrumentation Determine APRM 4 and 2 are inoperable.
Determine 2 of 4 the available channels are operable for Function 2.
Condition A, Required Action with one or more required channels inoperable, place in trip condition in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Evaluate TRM 3.3 Control Rod Block Instrumentation Determine one of the required channels is not operable for Function I 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to restore to operable.
Page 18 of 37
EVENT 4 (Cont) APRM 4 FAILURE RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 (paBe I of 3 Reactor Faction Sysleni Instnwactation APPLICABLE CONOI1ONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNQTIO[4 CONOcI0NS SYSTEM ACTION 0.1 REOUREMENTS VALUE
- 2. Avera11e Powa Raoe Monbors
- a. Nautcn FIuoHh (Setdown) 2 0 SR 3.3,1.1,2 22.7% FTP SR 3.3.1.1.5 SR 3.3.1.1.7 SR 3,3.1.1.8 SR 3.31.1.11 SR 3.31.1.13
- b. Simulated Themial PoarHh 1 F SR 3.3.1.1.2 0.55W + 82.61 RTP SR 3.3.1.1.3 and SR 3.3.1.1.5 117.1% RIP CR 3.3.1.1.8 SR 3.31.1.11 SR 3.3.1.1.13 SR 3.3.1.1.18 tioed)
(a) WIth any conirol rod v.i:hdrawn from a core tal contanin one or moan fuel assaribes.
(b) E65 (w SW) + 82.8% RT9 ethan react for o4c loop operation per LEO 3.4.1, Reciron .alion Loopa Operadnçj The value of LW is deSried in plant procedwes.
(c) Each APR%1 ohamoel provden puio ta both nip sens.
RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 f,page 2 of 3)
Reactor Pfolaction System lowlIenladon APPUCABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SP3ClFED ?ERTR? RECUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION 11.1 REQUiREMENTS VALUE
- 2. Average Power Range Monlors (oon1hcted>
- c. NeutronFluxHiBh 1 F SR 3.3.1.1.2 118.7%RTP SR 3.3.1.1.3 SR 3.31.1.5 SR 3.3.1.1.8 S.R 3.3.1.1.11 SR 3.3.1.1.13 d.. lnop 1.2 0 SR 3.3.1.1.5 NA SR 3.3.1.1.11 Page 19 of 37
EVENT 4 (Cont) APRM 4 FAILURE 3.3 INSTRUMENTATION 3.3.1.1 Reactor Protection System (RPS) Instrumentation LCO 13.1.1 The RPS instrumentation for each FunctIon in Table 33.1.1-1 shall be OPERABLE.
APPLICABILITY: According to Table 13.11-1.
ACTIONS Separate Condition entry is allowed for each channel.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required Al Place channel in trip. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> channels inoperable.
OR A2 -------------NOTE------------- 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Not applicable for Functions Ia, 2.b, Ic, ld, or 21 Place associated trip system in trip..
SRO Time Action Notes Refers to OOI-18 for actions to place APRM 4 in a tripped condition.
Direct APRM 4 mode selector switch placed n INOP to allow l&C troubleshooting.
BOP Time Action Notes Monitors the plant.
May check back panel APRM indications.
Page 20 of 37
EVENT 4 (Cont) APRM 4 FAILURE RO Time Action Notes Acknowledges, refers to & reports annunciators A-6 2-8 APRM UPSCALE 3-7 APRM TROUBLE 3-8 APRM UPSCALE TRIP/INOP A-5 2-2 ROD OUT BLOCK Determines ARPM 4 has a critical fault (CPU Failure) and cannot be bypassed (APRM 2 already bypassed).
Obtains Key #114 from Control room Key locker.
Places APRM 4 in the tripped condition If APRM I or 3 is placed in INOP, a Full by placing APRM OPER/INOP mode reactor SCRAM will occur.
selector switch in INOP on Panel P608.
Page 21 of 37
EVENT 5 UAT GROUND A UAT ground alarm will be received. The crew will respond lAW the APP. Investigation by l&C will indicate the alarm is valid requiring Buses 2C & 2D to be transferred to the SAT.
Objectives:
SCO Direct BOP Buses transferred to the SAT.
RD - Monitors the plant.
BOP Transfers BOP Bus 2C to the SAT.
Success Path:
BOP Bus 2C transferred to the SAT.
Simulator Operator Actions:
D When directed by lead evaluator, INITIATE TRIGGER 4 to activate UAT ground alarm.
D If asked as AD to investigate, wait 1 minute and report no ground targets visible on Buses 2C or 2D.
II If asked as l&C to investigate, wait 2 minutes and report UAT Y winding ground is valid.
fl Monitor BOP bus transfers and ensure TRIGGER 5 automatically initiates when Bus 2D synch switch is placed to DN (Do not allow the crew to transfer BOTH BOP Buses)
Required Operator Actions Component Failure Ground fault on UAT Y winding requiring BOP bus transfer to SAT.
SRO Time Action Notes Acknowledges report of UA-1 3 2-10 UAT WINDING YGRD CURRENT Informs l&C verify UAT ground alarm is valid.
Directs BOP Buses(2C & 2D) be transferred to the SAT per OP-50 May reference TS 3.8.1 for UAT Degraded but not INOP.
inoperability.
RO Time Action Notes Monitors the plant.
Page 22 of 37
EVENT 5 (Cont) UAT GROUND BOP Time Action Notes Acknowledges, refers to & reports annunciator 2-10 UAT WINDING Y GRD CURRENT Directs TBAO to walk down Buses 2C &
2D looking for ground targets.
May direct OSAO to walk down the UAT.
Notifies SRO that no ground targets If a second ground fault should occur before the present on Buses 2C or 2D and that initial ground fault is cleared, loss of equipment and severe equipment damage may result.
these buses should be transferred to the SAT if valid.
Transfers BOP Bus 20 to the SAT Plant announcements for bus transfers utilizing 20P-50, Section 7.1 should be made.
- 1. Places SAT TO BUS 2C SYNCHRONIZING SWITCH in ON.
- 2. Confirms synchroscope is at 12 oclock, AND CLOSEs SAT TO BUS 2C BREAKER, AC6.
- 3. CONFIRMs SAT TO BUS 20 BREAKER, AC6, has closed using the breaker indicating lights.
- 4. Confirms UAT TO BUS 20 BREAKER, AC4, has opened using the breaker indicating lights.
- 5. Places SAT TO BUS 20 SYNCHRONIZING SWITCH in OFF.
- 6. Places SAT TO BUS 2D SYNCHRONIZING This causes a loss of the SAT SWITCH in ON. Loss of both the RR Pumps Page 23 of 37
EVENT 6!6a LOSS OF SAT! SCRAM I DG4 FAILURE Prior to transferring the second Bus to the SAT, the SAT will trip and lock out. Off-site power will be lost. The crew will respond per AOP-36.1 and EOP-01-RSP. SRVs will be available for pressure control. RCIC and CRD will provide inventory makeup to the RPV.
Diesel Generator 4 will fail to auto start. DG4 will be manually started in Control Room Manual and Emergency Bus E4 re-energized.
Objectives:
SCO Directs actions for a Reactor Scram, RVCP, and OAOP-36.1.
RO Insert a reactor scram with no recirc pumps running.
BOP Starts DG4, ties to E4 and perform OAOP-36.1 actions.
Success Path:
Manual SCRAM inserted with DG4 manually started and tied to E4.
Simulator Operator Actions:
LI Ensure Trigger 5 automatically initiates prior to Bus 2D transfer to the SAT.
LI If contacted as load dispatcher, report line crews are being dispatched to investigate.
LI If asked as Outside AO, acknowledge request to monitor DGs.
LI If asked to perform actions to maximize CRD flow with 2 pumps per SEP-09, wait 4 minutes, initiate Trigger 14 and report the actions complete.
LI If requested to open CRD charging header isolation valve, initiate Trigger 9, wait 2 minutes and report actions complete.
LI If asked as Unit 1 for status of the air system, initiate Trigger 15 and report 1 D air compressor is in service.
LI If asked to transfer RCC to CSW, wait 5 minutes, initiate Trigger 8 and report actions complete.
LI If requested to perform field actions for UAT back-feed, acknowledge the request.
LI When directed by the lead examiner, proceed to the next event.
Required Operator Actions Major event Loss of offsite power, reactor Scram.
Component Failure DG4 auto start failure requiring manual start.
SRO Time Action Notes Direct insertion of manual scram due to loss of the recirc pumps.
Enter and direct EOP-01-RSP.
Direct entry into OAOP-36.1 for Loss of Off-Site Power.
Page 24 of 37
EVENT 616a (Contd) LOSS OF SAT I SCRAM I DG4 FAILURE SRO Time Action Notes Announces entry into RVCP Directs a pressure band of 800-1000#
Direct reactor water level band of 170-200 inches.
CRD (SEP-09)
RCIC Announces entry into PPCP Suppression Pool Temp Above 95°F OR Drywell Average Air Temp Above 150°F OR Suppression Pool Water Level Above 27 inches Direct RHR Loops be placed in suppression pool cooling.
RO Time Action Notes Announces Unit 2 reactor SCRAM.
Performs immediate actions for Reactor scram Depresses both manual Scram pushbuttons.
6 After steam flow is less than 3 x I lb/hr, place the reactor mode switch to shutdown When APRM downscale trip, then Tripping the main turbine causes a loss of Trip the main turbine offsite power to Unit Two.
Ensures the master reactor level controller setpoint is +170 inches Operates SRVs as directed to stabilize pressure and control pressure as directed by the SCO.
Manually Starts RCIC or maximizes RCIC flow to 500 gpm following auto initiation to maintain reactor water level.
Page 25 of 37
EVENT 616a (Contd) LOSS OF SAT I SCRAM I DG4 FAILURE RO Time Action Notes Maximizes CRD flow lAW SEP-09 Hard card I CRD pump should be in service and
- 2. ENSURE CRD FLOW CONTROL, C12-FC- hard card only supports this alignment.
R600, is in MAN position.
- 3. THROTTLE the following valves, as necessary, to maintain charging water header pressure greater than or equal to 1000 psig but as low as possible.
A. In-service FLOW CONTROL VLV, C12-FOO2A.
B. DRIVE PRESSURE VLV, C12-PCV-F003.
- 4. IF the CRD pump trips on low suction pressure due to high CRD suction filter dP, THEN PERFORM the following:
A. CLOSE the in-service FLOW CONTROL VLV, C12-F002A.
B. START a CRD pump.
C. THROTTLE OPEN the in-service FLOW CONTROL VLV, C12-FOO2A, to maintain charging water header pressure above the pressure at which the CRD pump tripped, but as low as possible.
- 5. As time permits refer to OEOP-01-SEP-09 for additional actions.
SEP-09 Procedure Actions Dispatch AO to perform SEP-09 for two CRD pumps with the Reactor Building Accessible.
When AC reports field actions for SEP-09 complete for 2 pump operation, the RO performs the following:
- d. STARTs the second CRD pump.
- e. ENSUREs CRD FLOW CONTROL, C12-FC-R600, is in MAN.
- f. Throttles the following valves to maintain charging water header pressure greater than or equal to 950 psig but as low as possible:
- In-service Flow Control Vlv, C12- FOO2A
- Drive Pressure Vlv, C12-PCV-F003
- Charging Water Header Throttle Valve, C12-F034 F034 throttling is performed by RBAO in the field.
Operates RCI C/CRD to restore/maintain Reactor water level +170-200 inches Page 26 of 37
EVENT 616a (Contd) LOSS OF SAT I SCRAM I DG4 FAILURE RO (Contd)
Time Action Notes Place RHR Loop B into suppression pool cooling.
Open SW-V105 Close SW-V143 If LOCA signal is present place RHR LOCA signal may or may not be present SW Booster Pumps B & D LOCA when aligning this loop for SPC.
override switch to manual override Start RHR SW Pmp Adjust Eli -PDV-F068B (I pump 2000 4000 gpm)
(2 pumps 5000 8000 gpm)
Supply CIg Wtr to Vital Hdr Opens either SW-VI 11 or SW-Vi 17 Verify cooling logic is made up Start Loop B RHR Pmp Open Eil-F028B Throttle OPEN Ell-F024B (1 pump 6000-10000 gpm)
(2 pumps 6000 11500 gpm)
Throttle El l-F048B CLOSED Places MSIV control switches to CLOSED.
Page 27 of 37
EVENT 616a (Contd) LOSS OF SAT I SCRAM I DG4 FAILURE BOP Time Action Notes Diagnose failure of DG4 to auto start Manually Start and tie DG4 to E4. DG4 failure to auto start and control room manual mode of operation should be Depresses the AUTO Start pushbutton. reported to the SRO and may be done utilizing Crew Update.
Depresses the Control Room Manual pushbutton.
Manually starts DG4 Verifies DG4 ties E4 (DG4 output bkr closes, E4 undervoltage clears).
Dispatches OSAO to monitor DG operation locally.
Announce and enter OAOP-36.1.
Verifies the following systems are DG4 loading should be periodically operating as required for current plant monitored to ensure over load conditions conditions: do not occur.
- CRD System
- CSW System
- NSW System
- RBCCW System
- Service/Instrument Air System Momentarily Places DIV I NON-INTRPT RNA, SV-5262 control switch to OVERRIDE/RESET, THEN to OPEN, AND ENSURE DIV I NON-INTRPT RNA, SV-5262 opens Momentarily Places DIV II NON-INTRPT RNA, SV-5261 control switch to OVERRIDE/RESET, THEN to OPEN, AND ENSURE DIV II NON-INTRPT RNA, SV-5261 opens.
Determines UAT back-feed available and direct field actions.
Page 28 of 37
EVENT 6!6a (Contd) LOSS OF SAT I SCRAM I DG4 FAILURE BOP Time Action Notes Starts all available NSW & CSW pumps.
Starts Control Room HVAC.
Ensures at least one of the following Control Room A/C and Supply Fan units is operating:
- CTL ROOM A/C & SUPPLY FAN, ID-CU-CB and 1D-SF-CB
- CTL ROOM A/C & SUPPLY FAN, 2D-CU-CB and 2D-SF-CB
- CTL ROOM A/C SPARE FAN, 2E-SF-CB.
Starts Battery Room HVAC.
- BATTERY ROOM IA VENT FANS, 1C-SF-CB and 1C-EF-CB
- BATTERY ROOM I B VENT FANS, I B-SF-CB and 1 B-EF-C8
- BATTERY ROOM 2A VENT FANS, 2C-SF-CB and 2C-EF-CB
- BATTERY ROOM 28 VENT FANS, 28-SF-CB and 2B-EF-CB.
Restores Drywell cooling Dispatches an AC to transfer RCC to CSW header by Opening SW-V146.
Verifies all available DW Coolers in operation Proper aligns RCC pumps
- a. IF three RBCCW pumps are running, THEN STOP one RBCCW pump, AND PLACE its control switch in AUTO.
- c. IF no RBCCW pump is running, THEN PLACE all RBCCW pump control switches in OFF Direct RPS to be restarted.
Verifies Group Isolations Group 1,2,3,6,8 & lOon LOOP.
Page 29 of 37
EVENT 7/7A SMALL BREAK LOCA I ECCS LOGIC FAILURE A small Recirculation line break will occur. Available injection sources will be unable to stabilize RPV level. RPV level will drop to LL3 resulting in actuation of ADS timers. The crew may allow ADS to automatically initiate (only if Low Pressure ECCS pumps are manually started), or manually initiate ADS when level drops below TAF. Low pressure ECCS initiation logic will fail at LL3 requiring manual actions to start available pumps and align injection when RPV pressure drops below 400 psig.
Objectives:
SCO Directs actions for RVCP and PCCP.
RO Aligns and maximizes flow from available injection sources (RCIC, CRD, SLC).
BOP Monitors DG4 loading while continuing OAOP-36.1 actions.
Success Path:
Align alternate coolant injection from SLC and manually start low pressure ECCS systems when level lowers below 45 inches (LL3).
Simulator Operator Actions:
L When RPV level and pressure have been stabilized and as directed by the lead evaluator, initiate Trigger 7 to activate small break LOCA.
LI If requested to transfer SLC suction to demin water, initiate Trigger 13, wait two minutes and report actions complete.
LI If requested to stop drywell coolers, initiate Trigger 10.
u If asked as I&C to investigate ECCS logics, acknowledge request LI When directed by the lead examiner, proceed to the next event.
Required Operator Actions Major Event Small Break LOCA Component Failure ECCS logic failure requiring manual start of ECCS pumps and manual alignment of injection valves SRO Time Action Notes Recognize rising drywell temperature and pressure, diagnose as LOCA.
Enter and direct EOP-01-RVCP, if not already in.
Direct reactor water level band of 170-200 inches.
CRD (SEP-09)
Direct initiation of suppression chamber spray.
Page 30 of 37
EVENT 717A (Contd) SMALL BREAK LOCA I ECCS LOGIC FAILURE SRO Time Action Notes Direct drywell spray when suppression chamber pressure >1 1.5 psig.
Informs crew on decision of inhibiting or not inhibiting ADS Directs verification of Isolations and Actuations for LLI, LL2, LL3, & High DW Pressure Directs Low Pressure ECCS pumps be started RO Time Action Notes Recognize rising drywell temperature and pressure, diagnose as LOCA Perform LEP-Ol for SLC injection with demin water Dispatch an AC to perform infield actions.
When in field actions complete, starts Both SLC Pumps.
Page 31 of37
EVENT 7/7A (Contd) SMALL BREAK LOCA I ECCS LOGIC FAILURE RO Time Action Notes Initiate suppression chamber spray per SEP-03.
If necessary, then place Loop B 2/3 CORE HEIGHT LPCI INITIATION OVERRIDE SWITCH, E11-CS-Sl8B, in Manual Overrd.
If the CTMT SPR OVRD light for the Loop B CONTAINMENT SPRAY VALVE CONTROL SWITCH, El1-CS-SI7B is not on, then momentarily place Loop B CONTAINMENT SPRAY VALVE CONTROL SWITCH, Eil-CS-SI7B, to Manual Ensure at least one RHR Loop B Pump is operating Ensure TORUS DISCHARGE ISOL VLV, Ell-F028B, is open Open TORUS SPRAY ISOL VLV, Eli -F027B.
Page 32 of 37
EVENT 717A (Contd) SMALL BREAK LOCA I ECCS LOGIC FAILURE RO (Contd)
Time Action Notes Initiate drywell spray per SEP-02 Ensure WELL WATER TO VITAL HEADER VLV, SW-V141, is closed Ensure both reactor recirculation pumps are tripped Place all drywell cooler control switches to OFF (LIO)
May request Drywell Cooler override switches to STOP.
Confirm the following:
- Drywell pressure and drywell temperature are in the SAFE region of the DSIL graph.
- Suppression pool water level is below +21 inches.
Open Loop B DRYWELL SPRAY INBD ISOLVLV, Ell-FO2IB Throttle open Loop B DRYWELL SPRAY OTBD ISOL VLV, Eli FOI6B, to obtain between 8,000-10,000 gpm flow Inhibits ADS if directed by 5CC Start all available low pressure ECCS pumps at 400 psig in reactor:
2ACS 2B CS 2A RHR 2B RHR 2C RHR 2D RHR Page 33 of 37
EVENT 717A (Contd) SMALL BREAK LOCAl ECCS LOGIC FAILURE BOP Time Action Notes Monitors DG loading Performs verification of Group Isolations See attached Group and System actuations for LLI, LL2, LL3 and High Drywell pressure.
Page 34 of 37
EVENT 8 REACTOR DEPRESSURIZATION Depressurization may be automatic or manually performed when level drops below TAF.
Objectives:
SCO Directs Emergency Depressurization and restoration of reactor water level.
RO Performs action for emergency Depressurization and restoration of reactor water level.
Success Path:
Emergency depressurize the RPV and restore RPV level to 170 200 inches.
Simulator Operator Actions:
LI If requested to re-align SLC to the boron tank, wait 4 minutes and modify Remote Function SL_IASLCTST, NORM Li When RPV level is being controlled >+170, the scenario may be terminated Li When directed by the lead evaluator, place the simulator in FREEZE.
Required Operator Actions Restore and maintain RPV level above LL4 SRO Time Action Notes Determine ED is required.
Direct placing 7 ADS valve ***CRITICAL TASK***
switches to open.
Direct re-alignment of RHR for LPCI injection Direct low pressure ECCS injection valves opened Direct RPV level be restored and ***CRITICAL TASK***
maintained +170-200 inches Direct Alternative Source Term actions (SLC, GREy, SEP-li)
Page 35 of 37
EVENT 8 (Contd) REACTOR DEPRESSURIZATION ROIBOP Time Action Notes Places 7 ADS valve control switches ***CRITICAL TASK***
Re-align RHR for LPCI injection.
Ensures Drywell Sprays I SP Sprays I Torus Cooling removed from service Manually perform any failed LPCI initiation actions Open 2A CS injection valve Open 2B CS injection valve Open 2A RHR Loop Injection Valve Open 2B RHR Loop Injection Valve Close Recirc Discharge and Discharge Bypass valves Operate LP ECCS to restore and ***CRITICAL TASK***
maintain RPV level 170-200 inches.
Re-align SLC for SLC Tank Injection (Alternate Source Term Action)
Start CREV (Alternate Source Term Action)
Perform SEP-Il (Alternate Source Term Action)
Page 36 of 37
Simulator Operator Activities:
WHEN directed by the lead examiner, place the simulator in FREEZE.
CAUTION DO NOT RESET THE SIMULATOR PRIOR TO RECEIPT OF CONCURRENCE TO DO SO FROM THE LEAD EXAMINER Page 37 of 37
PROGRESS ENERGY CAROLINAS BRUNSWICK TRAINING SECTION SIMULATOR SCENARIO 201 0-2 NRC Exam Scenario #6
Appendix D Scenario Outline Form ES-D-1 Facility: Brunswick Scenario No.: 2010-2 #6 Op-Test No.: Draft Examiners: Operators:
Initial Conditions: Plant is operating at -70% power (IC-b). 2B EHC pump under clearance.
Turnover: Swap Condensate Booster Pumps.
Event MaIf. No. Event Event No. Type* Description I N BOP
- Swap Condensate Booster Pumps MCC 2TD trip I Standby Stator Water Cooling Pump fails 2 EEO3OM C BOP to auto start MG Lube Oil Pump B3 trips I 2B Recirc Pump fails to trip 3a RCO29F C - RO (TS)
Insert control rods to exit scram avoidance region of the 3b R-RO power to flow map.
4 ZUA5I 10 C BOP RB Exhaust Fan trip RDOO1M C RO Rod Drift (TS)
(22-11)
NBOO5F M All Fuel Failure I Enter RRCP I SCRAM (failure of Rx Scram 6
NBO1OF C RO-B Pushbutton) 7 C - BOP PCCP I Initiate SPC (failure of F024A valve)
(N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Page 2 of 35
SCENARIO DESCRIPTION The plant is operating at -70 power. 2B EHC pump under clearance.
Event I Normal Operations Swap from 2A CBP to 2C CBP. Unit /LOCA Load Shed switches will have to be swapped also.
Event 2 MCC 2TD will trip and the standby stator cooling water will fail to auto start. The standby stator cooling water pump can be manually started. The 2D air compressor will also be lost and OAOP-20.0 may be entered. Unit One may be contacted to start the 1D Air Compressor.
Event 3a MG Lube Oil Pump B3 trips and with the loss of 2TD this only leaves I oil pump.
Recirc MG Set 2B oil pressure drops below the trip setpoint but fails to trip the 2B Recirc Pump. The MG Set must be manually tripped. Determine TS 3.4.1 condition Al applies to satisfy the requirements of the LCO in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
Event 3b OAOP-04.0 will be entered. The plant will be in the Scram Avoidance Region of the power to flow map. Recirc flow must be increased or control rods must be inserted to exit this region. With only one recirc pump in operation reactor power must be less than 50% also.
Event 4 RB Exhaust fan will trip on overload. The APP will be addressed which will have the standby fan started. I&C should be contacted before the overload reset and the fan restarted.
Event 5 Control Rod 22-1 1 will start to drift in. The crew will enter OAOP-02.0 and take action lAW 2APP-A-05 (3-2). When the high temperature alarm is received Engineering will report that scram times cannot be assured based on past history of the control rod.
Determine TS 3.1.3 condition Cl to insert the control rod in 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> and C2 to disarm the control rod within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
Event 6 Fuel failure will occur. RRCP will be entered and charts executed. When Process Off gas Hi Hi alarm with the Main Stack rising a scram will be inserted and Group I valves closed. Reactor Scram Pushbutton B is failed, other methods are available i.e. mode switch, ARI, etc.
Event 7 With MSIVs isolated and fuel damage indicated SRVs will be used to control pressure thereby adding heat to the suppression pool. PCCP will direct SPC to be placed in service on all available loops.
Event 8 After the reactor scram and MSIV closure, when SPC has been placed in service on B loop, and the failure of the SPC valves on the A loop has been identified then the scenario may be terminated.
Page 3 of 35
OBJECTIVES SRO 344218B502, Direct Actions To Control Reactor Pressure Per EOP-01-RVCP 344209B402, Direct Shift Response To Recirculation Pump Trip Per OAOP-04.0 3412198102, Direct Actions To Lower Reactor Power From Rated to 55% Including Removal Of One Feed Pump From Service Per GP-05 & GP-12 344227B502, Direct Actions To Control An Unmonitored Radioactive Release With The Release Rate Less Than That Requiring An Alert Declaration Per EOP RRCP RO 259204B1 01, Secure The First Reactor Feed Pump Per 2OP-32 20201 7B401, Respond To Recirc Pump Trip(s) Per OAOP-04.0 201201B401, Respond To A Control Rod Drift Per APP A-05 3-2 205014B101, Start Up RHR In Suppression Pool Cooling Mode Per OP-17 272201 B401, Respond To An Area Radiation Annunciator Per APP UA-03 200601 B401, Respond to radioactive spills, high radiation and airborne activity per OAOP 05.0 200603B501, Perform immediate actions for a reactor scram Page 4 of 35
SIMULATOR SETUP Initial Conditions IC-b Event Triggers Event Trigger Trigger Description 1 1 Normal Ops (Disable Unit/LOCA Load Shed for 2C CBP) 2 Normal Ops (Enable Unit/LOCA Load Shed for 2A CBP) 11 HWCH-SV-5719 to open 2 3 Manually Initiated (2TD trip) 10 Manually Initiated (Start ID Air Compressor) 3 4 Manually Initiated (B3 Oil Pump trip) 4 5 Manually Initiated (RB Exhaust Fan overload) 5 6 Manually Initiated (Control Rod Drift) 6 7 Manually Initiated (Fuel Failure) 8 Auto Initiated (Gross Fuel Failure)(on manual scram A pushbutton, K2501PP7) 7 9 Auto Initiated (SPC valve failures)(on the F024 switch in auto, K12O7JNN)
Page 5 of 35
Malfunction Summary MaIIID I MtMD I Descr6orr I CurrentValuej Taiget Value I Rmprine Aclime j Daliee I Trig EEO3OM 2TD INDMDUAL. BUS FAILURE False flue .
RECIRCPLJMPBAUTO TRIP FAILURE True True IE 0.00 100.0000 00:07:30 7 coo 1.200800 00:05:00 8
. T r TimerPause ,DeiedaAii U Pending Remotes Samtnary .
Real ID I. Mull ID I Description .
I Current Value I TaigetValue I Rrnplkee Alfroe Trig EE_LSHEDB LOCA LOAD SHED SEL SW. 2C COHDENSATE BOOSTER PUMP ENABLE DISABLE 1 EE_IJTSHEDS UNIT TRIP LOAD SHED SELSW,2CCOND BOOSTER PUMP ENABLE DISABLE 1 EE_LSHED4 LOCALDADSHEDSELSW.2ACONDENSATEBDOSTERPUMP DISABLE ENABLE . 2 EE_UTSHED4 UNIT TRIP LOAD SHED SEL SW 24 COND BOOSTER PUMP DISABLE ENABLE 2 CF_ZVCFS71B . HWC-SV5718442INJECTION OPEN VLV NORM AL . OPEN 11 MUAEFTPD . TB VENT MODE (RECIRC/ONCE TH.R.U.I.:UNIT 2 ONLr ONCE THRU REDRC 13 MUACBLRM1 UNIT 1 4BLE SPREAD ROOM VENT FANS AUTO 14 AJIAIU1CMPRSS UNIT 1 AIR bOMPRESSOR STATUS 1D OFF DISARM 1D ON in -
RD_RDELDIS 2211 ELECTRICAL DISARM OF ROD ARM ARM 12 RD_RDHYDIS 2211 HYDRAUUCDISARMDFROD . ARM ARM 12 MLZVACS8181 UNIT 1 CB MECHANICAL EQUIP ROOM VENT FANS CS NEUT STOP 16 Annunciator Snmmaw Window J Descriplb, 1 Tagoerne I Override Twe OVal I AVaI I Aclkr I Dec8rae I Trig 1.10 RXBLDGEXI-IFANAOVLDTRIP ZUA511O ON ON OFF 5 50 RHRA VALVES OVERLOAD ZtilSS ON ON OFF 8 1*2 CRD HYD TEMP HIGH 2A512 ON ON OFF *15 .1 uvernoeummaw Tao ID I Descriglion Pounion / Taroet Actual Value I DverddoVelue Rrrrpfiroe I/Active I Daclime I Trio K54-12A STATLODL4NTPMPA AUTD OFF 13FF .
G2709EGB LURE OIL PMP 03 GREEN ON/OFF ON OFF . 4 G2709FAB LUBE OIL PMP B3AMBER ON/OFF . OFF OFF .. 4 (27054 LUOEOILPUMPB3STDPRESET AUTO ON OFF 4 K2705A LUBE OIL PUMP B3 STOP RESET RESET OFF ON 4 (27854 LUBE DILPUMP B3STDPRESET . START OFF OFF KS6O1A RBEXHUASTFANASTART . : NORMAL ON OFF . 5 K5681A RBSGIUASTFANASTART START OFF OFF 5 :
K5601A RBE)GIUASTFANASTART . STOP OFF ON 5 05681 EGG RB E>8IUASTFANA DIS. DAMPERS ON/OFF OFF OFF . . 5 Q5601AGG RBEXHUAST FANA FAN S .
ON/OFF OFF OFF . P 05601 FRG PB EXHUAST FAN A DIS DAMPER 9 ON/OFF ON 056810RG BEXI-IUAST FANA FAN R ON/OFF ON OFF . 5 K1287A FULLFLDWVLVE11.F024A - - AUTO ON OFF . .
8 X1207A FULL FLOW VLV Eli F024A CLOSE OFF OFF S K1207A FULLFLDWVLVE11F024A OPEN OFF OFF . S 01207R20i FULLFLOWE11 FO24ARED JJH/OFF tFF -, OFF 01287LGN FULLFLOWE11-FO24AGREEN ON/OFF ON OFF 9 Wno OIL PMPO2 RED ON ON Q2708UR6 ON/OFF K2708A LU000ILPMPO2STOPRESET AUTO ON OFF 4 k2780A -. LUBE OIL PMP B2 STOP RESET RESET OFF H ON . - 4 -.
K2788A LUBE OIL PMP 02 STOP RESET START OFF OFF . . 4.
OFF 5
. 1(25034 B .. - - - SI3WIIG - . . -OFF - - - - - -
Page 6 of 35
SPECIAL INSTRUCTIONS Ensure simulator exam security measures in place.
Start the 2B Stator Cooling Water Pump and Shutdown the 2A Stator Cooling Water Pump and place control switch in Auto.
Reduce reactor power to -70% power using recirc.
Place 2B EHC pump to off and red cap. Place an annunciator placard on the board.
Advance all chart recorders to indicate steady state conditions.
Place all SPDS displays to the Critical Plant Variable display (#100).
Ensure appropriate keys have blanks in switches.
Exit shutdown screen on RWM and place the RWM key in the key locker.
Reset alarms on SJAE, MSL, and RWM NUMACs.
Ensure reference material is in appropriate location.
Verify any log books have blank sheets only and procedures are not marked.
Load scenario file if available.
Load malfunctions/overrides if scenario file is unavailable.
Ensure OENP-24.5 for IC-b @ P603.
Page 7 of 35
SHIFT BRIEFING Plant Status The plant is operating at -70% power.
Equipment Out of Service 1A NSW Pump is under clearance for breaker refurbishment.
No other equipment is out of service.
Plan of the Day When the shift turnover is complete swap the Condensate Booster Pumps for maintenance. (Secure 2A CBP, Start 2C CBP)
Page 8 of 35
SCENARIO TRAINING INFORMATION Instructor Notes This guide is designed to meet the requirements of an examination scenario for Initial License as outlined in NUREG-1021, Rev.9, Supp.1 ES-301 and Appendix D.
During the execution of this scenario, the students should be rated on the performance of the objectives, compliance with general simulator performance standards, and for overall team skills in accordance with TAP-409 and NUREG-1 021, ES-302.
Common Student Problems/Errors None Simulator Deficiencies There are no known simulator deficiencies applicable to this scenario.
Critical Tasks (Critical Tasks are identified to ensure scenario validity and do not constitute pass/fail criteria for Initial License.)
- Insert a manual reactor scram and close the Group I Isolation Valves when Process Off gas Hi Hi annunciator is received and Main Stack Rad is rising.
- Initiate SPC when the suppression pool is greater than 95°F to remain in the safe region of the HCTL graph.
Page 9 of 35
EVENT I SWAPPING CBPs The crew will complete shift turnover and Swap from 2A CBP to 2C CBP. Unit /LOCA Load Shed switches will have to be swapped also.
Objectives:
SCO Directs performance of 20P-32, Section 8.6.
RO - Completes 20P-32, Section 8.6.
Success Path:
Condensate Booster pumps swapped lAW 20P-32, Section 8.6.
Simulator Operator Actions:
LI Acknowledge requests as the RW Operator.
LI When requested, initiate Trigger I to disable the 2C CBP LOCA/Unit Trip Load Shed switches.
LI When requested to check oil level of 2C CBP, report proper oil levels have been verified.
Li When requested to perform step 9 (venting the mechanical seals) report that it has been completed.
LI When requested to open HWCH-SV-5719, initiate Trigger II, and report that the valve is open.
LI When requested, initiate Trigger 2 to enable the 2C CBP LOCA/U nit Trip Load Shed switches.
LI When requested to close the HWC condensate H2 injection isolation solenoid valve report that the valve is closed.
Required Operator Actions Normal Ops Perform 2OP-32, Section 8.6 to swap CBPs.
SRO Time Action Notes Direct 2OP-32, Section 8.6 to be performed.
RO Time Action Notes Plant Monitor May be asked to perform IV for steps from the operating procedure.
Page 100f35
EVENT I (Contd) SWAPPING CBPs BOP Time Action Notes Verifies Initial conditions in 20P-32, Section 8.6. Verifies a condensate booster pump is in service.
Per note three condensate pumps must be operation if condensate flow is greater than or equal to 14,400 gpm.
Verifies 3 condensate pumps are not needed.
Flow indication of CO-FV-49 is <14,400 gpm.
NOTIFY Radwaste operator to perform the following:
- 1. Place an additional CFD in service to prevent override or bypass condition during condensate pump transfer
- 2. Place an additional CDD in service as necessary.
Determines step 2 & 3 are N/A.
PLACE standby condensate booster pump mode selector switch in MAN AND CHECK its discharge valve closes.
Direct an AC to place the following switches in DISABLED for the 2C Condensate Booster Pump:
- Unit Trip Load Shed Selector Switch
- LOCA Load Shed Selector Switch.
Page 11 of 35
EVENT I (Contd) SWAPPING CBPs BOP Contd Time Action Notes Direct an AC to ensure proper level in associated condensate booster pump oil reservoir Determines step 7 & 8 are N/A.
Directs an AC to perform step 9.
START 2C condensate booster pump AND OBSERVE its discharge valve opens.
NOTE:
The start/stop control switch for a condensate booster pump must be held in START until the recirculation valve is full open.
Direct an AO to OPEN HWC condensate H2 injection isolation solenoid valve at HWC local Panel H2J, for condensate booster pump just started.
CONDENSATE BOOSTER PUMP 2C H2 INJECTION ISOLATION VALVE, HWCH-SV-571 9 WHEN condensate booster pump discharge pressure stabilizes, THEN STOP selected condensate booster pump AND PLACE its mode switch in AUTO Direct an AC to place the following switches in ENABLED for the 2A Condensate Booster Pump:
- Unit Trip Load Shed Selector Switch
- LOCA Load Shed Selector Switch.
Page 12 of 35
EVENT I (Contd) SWAPPING CBPs BOP Contd Time Action Notes Determines steps 14, 15 and 16 are N/A.
NOTIFY Radwaste operator to remove the additional CFD or CDD placed in service in Step 8.6.2.1.
Direct an AO to CLOSE HWC condensate H2 injection isolation solenoid valve for the 2A condensate booster pump.
CONDENSATE BOOSTER PUMP 2A H2 INJECTION ISOLATION VALVE, HWCH SV-571 7 NOTIFY Radwaste operator to monitor CDD effluent conductivity for each demin in service.
Page 13 of 35
EVENT 2 TRIP OF MCC 2TD The crew will respond to a trip of MCC 2TD with the standby stator cooling water pump failure to auto start. The standby stator cooling water pump can be manually started. The 2D air compressor will also be lost and OAOP-20.O may be entered.
Objectives:
SCO Direct the standby Stator Cooling Water pump to be started.
BOP Start the standby Stator Water Cooling pump with an automatic initiation signal present.
Success Path:
Standby Stator Cooling Water Pump started and actions of OAOP-20.O addressed.
Simulator Operator Actions:
D When the directed by the lead examiner, initiate Trigger 3 to trip the feeder breaker to MCC 2TD.
E When asked as the TB AC to investigate the 2F feeder breaker trip, report a trip of the feeder breaker to MCC 2TD, (ATO) on 480V Substation 2F is tripped with the white overcurrent indicating flag protruding from the breaker.
U If asked as l&C to investigate, acknowledge any requests. If asked do not recommend re-energizing 2TD until an investigation can be completed.
O If asked to investigate/acknowledge the 2B REP alarm, acknowledge the local panel alarm and report that the alarm on the local panel is HPU Pump 2 Running in Stby. If asked the standby pump is operating with no problems noted.
0 If dispatched to verify proper operation of the standby Stator Water Cooling Water Pump or the 2B air Compressor, report no problems with the operation of the pump/compressor are noted.
0 If contacted as UI, report that the ID air compressor is not running. If asked to start the ID Air Compressor initiate Trigger 10, and report ID air compressor is running. After air pressure returns to normal the I B will auto shutdown (go into standby).
O When directed by the lead examiner, proceed to the next event.
Required Operator Actions Component Failure Start the standby Stator Cooling Water pump when the auto action did not occur.
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EVENT 2 (Contd) TRIP OF MCC 2TD SRO Time Action Notes Acknowledges report of alarms received/cleared for the BOP/RO.
Directs BOP operator to start the standby stator water cooling pump.
May ask for I&C to investigate
- 1) The trip of the feeder breaker to 2TD
- 2) The failure of the standby Stator Water Cooling pump to auto-start.
May direct entry into OAOP-20.0.
May review the load list for MCC 2TD (001-50.1 1).
RO Time Action Notes Plant Monitor Report alarms to the SCO. RFP alarm may be addressed by the BOP.
UA-13, 6-6 RFP B Control Trouble A-7, 6-4 Fluid Drive B Lube Oil Press Lo (In and then cleared on standby pump auto starting)
May Dispatch an AO to investigate the REP alarm may be addressed by the BOP.
alarm on the 2B REP.
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EVENT 2 (Contd) TRIP OF MCC 2TD BOP Time Action Notes Report alarms to the SCO.
UA-6, 2-5 Sub 2F 480V Feeder Bkr Trip UA-13, 6-6 REP B Control Trouble UA-1, 3-2 Air Compr D Trip UA-2, 1-8 Stat coolant Inlet Flow-Low UA-2, 1-9 Loss of Stat Coolant Trip Ckt Ener UA-2, 2-8 Stat Coolant Press-Low UA-2, 6-9 Exciter Coolant Flow-Low Start the standby Stator Water Cooling Action to start the pump is in the APPs, or Pump. an auto action that did not occur.
UA-2, 4-9 Stator Cool Reserve Pump Running will annunciate on starting of the standby pump and then will clear when the 2A pump is placed in off.
Dispatch an AO to investigate the Sub 2F Feeder Breaker Trip.
May dispatch an AC to investigate the Stator Water Cooling pump that was started.
May enter and announce OAOP-20.O for Actions for starting the ID are also in the APP.
the trip of 2D Air Compressor.
Verifies that the 2B Air Compressor auto starts.
May ask Unit One to start the 1 D Air If 1 D Air Comp. is started the 2B and 1 B air comp.
will go back into a standby condition when the air Compressor and verify 2B returns to header pressure is returned to normal.
standby.
May place the 2D A/C is Stop.
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EVENT 3a MG LUBE OIL PMP TRIPS I 2B RECIRC PUMP FAILS TO TRIP The crew will respond to a trip of MG Lube Oil Pump B3 in which the 2B Recirc Pump fails to trip.
Objectives:
SCO Direct tripping of the 2B Recirc Pump.
RO Trips the 2B Recirc Pump.
Success Path:
Recirc Pump is tripped.
Simulator Operator Actions:
D When the directed by the lead examiner, initiate Trigger 4 to trip the B3 MG Lube Oil Pump.
If asked as l&C to investigate, acknowledge any requests.
D If requested as the AC to investigate the MG Set, report that the B3 MG Lube Oil Pump is tripped and lube oil pressure is 15 psig with the Emergency and B2 pumps running.
D When directed by the lead examiner, proceed to the next event.
Required Operator Actions Component Failure Recognizes failure (B3 oil pump) and that the 2B Recirc Pump should have tripped and make the action occur.
SRO Time Action Notes Acknowledge the report of alarms due to the loss of B3 Lube Oil Pump.
Direct tripping of the 2B Recirc Pump.
Direct BOP to enter and announce 2AOP-04.O.
Contact l&C to investigate failure of Lube Oil System and Recirc Pump trip failure.
BOP Time Action Notes Plant Monitor Page 17 of 35
EVENT 3a contd MG LUBE OIL PMP TRIPS I 2B RECIRC PUMP FAILS TO TRIP RO Time Action Notes Report alarms to the SCO.
A-7, 1-6, Fluid Drive B Scoop Tube Lock A-7, 6-4, Fluid Drive B Lube Oil Press Lo Recognize failure of the B3 Lube Oil Pump.
Recognize failure of the 2B Recirc Pump to trip on low oil pressure.
Trips the 28 Recirc Pump.
A-7, 5-5, Pump B Seal Staging Flow Hi/La A-7, 4-6, Recirc Loop B Only Out Of Service A-5, 4-8, OPRM Trip Enabled Announce and enter 2AOP-04.O.
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EVENT 3b INSERT CONTROL RODS TO EXIT SCRAM AVOIDANCE REGION The crew will respond to the tripping of the 2B Recirc Pump which puts the Unit in the scram avoidance region of the power to flow map requiring the crew to insert control rods to exit the region.
Objectives:
SCO Direct the RO to exit the Scram Avoidance Region lAW 2AOP-04.O.
RO Inserts control rods to exit the Scram Avoidance Region.
Success Path:
Scram avoidance region of the power to flow map exited.
Simulator Operator Actions:
Li If contacted as the RE for power reduction guidance, Ask for the SROs recommendation for the power reduction and then concur with the recommendation given.
Li If contacted as the RE to monitor power reduction, inform crew that you will monitor core performance on the computer.
Li When directed by the lead examiner, proceed to the next event.
Required Operator Actions Reactivity Inserts control rods to exit the scram avoidance region of the power to flow map.
SRO Time Action Notes Notify RE of 2B RR Pump Trip.
Direct power reduction to exit scram avoidance region lAW 2AOP-04.O and OENP-24.5.
BOP Time Action Notes Plant Monitor May maintain the Gen Voltage Regulator nulled as power is being reduced by placing the switch in the lower direction until needle is reading 12 Oclock.
(May have to perform this several times)
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EVENT 3 (Contd) INSERT CONTROL RODS TO EXIT SCRAM AVOIDANCE REGION RD Time Action Notes Request peer checker I reactivity team.
May maintain the Gen Voltage Regulator nulled as power is being reduced by placing the switch in the lower direction until needle is reading 12 Oclock.
(May have to perform this several times)
Inserts control rods using OENP-24.5 to exit the Scram Avoidance Region.
Turns control rod power on.
Selects control rod in accordance with OENP-24.5 sheet.
(See attachment 1 for the rods to insert, Page 34)
Continuously drives selected rod in using RMCS.
Repeats steps as needed to insert rods to exit the scram avoidance region.
May Raise recirc flow on the 2A RR Pump to exit the Scram Avoidance Region.
Adjusts the potentiometer clockwise to raise the flow on the A recirc loop.
Must stay below 45 Mlbs/Hr and greater than 30.8 MlbsIHr while maintaining power less than 50%.
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EVENT 4 RB EXHAUST FAN TRIP The crew will respond to a trip of the 2A Reactor Building Exhaust Fan.
Objectives:
SCO Directs Standby RB Exhaust Fan to be started BOP Refers to 2-UA-5 1-10 and starts standby RB Exhaust Fan Success Path:
Starting the 2D RB Exhaust Fan.
Simulator Operator Actions:
u At the discretion of the lead evaluator, initiate Trigger 5 to trip the 2A RB Exhaust Fan.
If directed as the RB AC to investigate fan trip, report RB Exhaust fan breaker is tripped on an overload. If asked to attempt to reset report that the breaker will not reset.
D If contacted as the RB AC, inform the control room p restart checks of the 2D RB Exhaust Fan are complete.
D If directed to investigate as I&C acknowledge the request.
D When directed by the lead examiner, proceed to the next event.
Required Operator Actions Component failure Trip of the 2A RB Exhaust Fan requiring a start of the 2D RB Exhaust Fan.
SRO Time Action Notes Directs BOP operator to enter Annunciator response for 2-UA-5, 1-10.
Directs start of 2D RB Exhaust Fan.
Directs Maintenance to investigate 2A RB Exhaust Fan Trip.
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EVENT 4 (Contd) RB EXHAUST FAN TRIP RO Time Action Notes Plant Monitoring BOP Time Action Notes Recognize the failure of the 2A RB Exhaust Fan.
Reports and refers to Annunciator Response UA-5 1-10.
Manually starts 2D RB Exhaust Fan.
Dispatches AO to investigate cause of fan trip.
Verifies RB pressure is maintained negative during evolution.
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EVENT 5 DRIFTING CONTROL ROD The crew responds to a drifting control rod.
Objectives:
SCO Direct actions in response to a drifting control rod and evaluate Tech Specs.
BOP Respond to a drifting control rod Success Path:
The drifting control rod is fully inserted, valved out of service and electrically disarmed.
Simulator Operator Actions:
Li When directed by the lead evaluator, initiate Trigger 6 to activate the control rod drift of rod 22-11.
Li If contacted as the RE to address thermal limits, inform crew that you will monitor core performance on the computer.
Li When the control rod is inserted to 00, initiate Trigger 15 to activate CRD high temperature alarm.
Li If asked as the RBAO to investigate HCU for control 22-11, report that the HCU scram outlet riser is hot to the touch.
Li When contacted as the RBAO report that the CRD temperature is 390°F.
Li When contacted as the System Engineer report that based on past history of this rod (22-11) scram times cannot be guaranteed.
Li If asked as the RBAO to valve out accumulator and disarm control rod, activate TRIGGER 12 and delete the rod drift malfunction.
Required Operator Actions Insert and disarm control rod 22-11.
Tech Spec 3.1.3 Control Rod Operability Condition C. One or more control rods inoperable for reasons other than Condition A or B Reciuired Action C.1 Fully insert inoperable control rod (3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />)
C.2 Disarm the associated CRD (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />)
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EVENT 5 (Contd) DRIFTING CONTROL ROD SRO Time Action Notes Direct actions of 2APP-A-05 (3-2) ROD DRIFT.
Direct entry into OAOP-02.O According to Note 2 in TS Table 3.1.4-1 the rod must be declared inoperable.
Tech Spec 3.1.3 Control Rod Operability Condition C. One or more control rods inoperable for reasons other than Condition A or B Required Action C.1 Fully insert inoperable control rod (3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />)
C.2 Disarm the associated CRD (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />)
Contact System Engineer on high temperature condition of control rod.
BOP Time Action Notes Plant Monitoring Page 24 of 35
EVENT 5 (Contd) DRIFTING CONTROL ROD RO Time Action Notes Acknowledge and ROD OUT BLOCK alarm Announce and enter AOP-2.O Perform the actions of APP-A-05 (3-2)
ROD DRIFT as follows:
Determine which control rod is drifting Select the drifting control rod and determine direction of drift Attempt to arrest the drift by giving a withdraw signal If rod continues to drift in, apply an RMCS insert signal and fully insert to position 00.
Attempt to locate and correct the cause of the rod malfunction as follows:
Check and adjust cooling water header pressure if required Direct AC to check for leaking scram valve Monitor core parameters, main steam line radiation and off-gas activity Page 25 of 35
EVENT 6a FUEL FAILURE I RRCP I SCRAM Fuel failure will occur. When the Main Stack Rad indication is rising then a reactor scram and Group I isolation is inserted. Reactor Scram Pushbutton B is failed, other methods are available (i.e. ARI).
Objectives:
SCO Directs actions for a Reactor Scram, and RRCP.
RO Insert a reactor scram when directed lAW RRCP.
BOP Ensure CREV is initiated.
Success Path:
Rods inserted with ARI.
Simulator Operator Actions:
El When directed by the lead evaluator, initiate Trigger 7 to activate Fuel failure.
El When the ramp timer for trigger 7 is timed out and the lead evaluator is ready initiate Trigger 8 to activate the Gross Fuel Failure.
El When directed as AC to align TB HVAC form once through to recirc alignment wait 15 minutes, initiate Trigger 13 and report alignment to Control Room.
El When requested as Unit 1 to stop Unit I Cable Spread Vent Fans, initiate Trigger 14.
El When requested as Unit I to stop CB Mechanical Equipment Room Vent Fan initiate Trigger 16.
El Monitor MSL Rad and as power is reduced, adjust Fuel Failure and Gross Fuel Failure to ensure MSL Hi-HI is received. (If NBOO5F reaches 100, Manually initiate Trigger 8)
El If PEP-3.4.7 is requested, acknowledge the request.
El If asked as E&RC, acknowledge the request to obtain actual/projected off site dose rates.
El If asked as E&RC, acknowledge the request to sample off gas and reactor coolant for potential fuel damage.
El If asked as E&RC, acknowledge the request to obtain noble gas dose rates.
El When fuel failure reaches 100%, proceed to the next event.
Required Operator Actions Insert control rods. (critical task)
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EVENT 6a (Contd) FUEL FAILURE I RRCP I SCRAM SRO Time Action Notes May direct BOP to announce and enter OAOP-05.O.
(May evacuate areas)
Enters RRCP on report of UA-03 5-2.
Asks Unit One to calculate site boundary dose per PEP-3.4.7.
Direct BOP to place CREV in service Ensure AOG in service Notify E&RC to sample off- gas and reactor coolant for potential fuel damage.
When UA-03 4-2 is received:
Verifies Main Stack Rad levels rising.
Ensures AOG bypass valve is closed.
May direct a power reduction When UA-23 3-6 is received, Directs Critical Task the insertion of a manual scram.
Directs the closure of Group I valves (MSIVs, Steam Line Drains (B21-F016 and F019) and Recirc Sample Valves (B32-F019 and F020)
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EVENT 6a (Contd) FUEL FAILURE I RRCP I SCRAM RO Time Action Notes Recognize failure of manual scram channel B Initiates ARI per the Scram Hard Card. Critical task Perform immediate actions for Reactor scram 6
After steam flow is less than 3 x 1 lb/hr, place the reactor mode switch to shutdown When APRM downscale trip, then Trip the main turbine Ensure the master reactor level controller setpoint is +170 inches Close Group I Isolation valves. Critical Task Closes MSIVs Closes Main Steam Line Drain valves B21-F016 and F019.
Closes Reactor Recirc Sample Valves B32-F019 and F020 Operate SRVs as directed to stabilize pressure and control pressure as directed by the SCO.
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EVENT 6a (Contd) FUEL FAILURE I RRCP I SCRAM BOP Time Action Notes Report Annunciators when received UA-03 5-7 UA-03 5-2 UA-23 2-6 UA-23 3-6 May announce and enter OAOP-05.O.
May evacuate turbine building Manually start CREV per the Hard Card.
Place one of the CB Emerg Recirc Fans, 2A(B)-ERF-CB, in ON.
Ensure CTL Rm Norm MU Air Dmpr, 2L-D-CB, closes.
Ensure CB Emerg Recirc Damper, VA-2J-D-CB, opens.
Stop CB Washroom Exhaust Fan, 2D-EF-CB, and ensure associated damper closes.
Stop CB Mechanical Equip Room GB Mechanical Equip Room Vent Fans Vent Fans 2F-SF-CB and 2E-EF-CB, can be stopped only by simultaneously and ensure associated supply and placing both Units control switches in exhaust dampers close. OFF Stop Cable Spread Room 2 Vent Fans 2A-SF-CB-and 2A-EF-CB, and ensure associated supply and exhaust dampers close.
Direct Unit One to Stop Cable Spread Room I Vent Fans lA-SF-GB and 1A-EF-CB, and ensure associated supply and exhaust dampers close Page 29 of 35
EVENT 7 PCCP Entry SRVs will be used to control reactor pressure raising the temperature of the suppression pool. PCCP will be entered and Suppression Pool cooling placed in service. The Eli F024A valve will fail not allowing SPC on A Loop to be placed in service.
Objectives:
SCO Directs PCCP actions and establish a cooldown.
Success Path:
Suppression Pool Cooling is in service.
Simulator Operator Actions:
If asked as l&C to investigate E11-F024A failure, acknowledge request When suppression pool cooling has been established and F024A valve failure recognized the scenario may be terminated.
Required Operator Actions Recognize valve failure (El l-F024A)
SRO Time Action Notes Recognize rising suppression pool temperature and enter PCCP.
Direct initiation of suppression pool cooling (Hardcard)
Enter and direct RVCP.
Direct reactor water level band of 170-200 inches.
Direct reactor pressure band of 800 -
1000 psig.
Direct a cooldown, not to exceed 1 00°F/hr.
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EVENT 7 (Contd) SMALL BREAK LOCA RO Time Action Notes Place RHR Loop A into suppression pool cooling.
- Open SW-ViOl
. Close SW-V143
. If LOCA signal is present place RHR No LOCA signal present SW Booster Pumps A & C LOCA override switch to manual override
. Start RHRSW Pump (may start both)
. Adjust Ell-PDV-F068A (1 pump 2000 4000 gpm) (2 pumps 5000 8000 gpm)
. Supply CIg Wtr to Vital Hdr
. Verify spray logic is made up
- Start Loop A RHR Pmp (may start both)
. Open Eli-F028A
. Throttle El l-F024A (Valve will get a overload when attempted to open)
Inform SRO of overload on F024A valve Place RHR Loop B into suppression pool cooling.
. Open SW-ViOl
. Close SW-Vl43
. If LOCA signal is present place RHR No LOCA signal present SW Booster Pumps B & D LOCA override switch to manual override
- Start RHRSW Pump (may start both)
. Adjust Ell-PDV-F068B (1 pump 2000 4000 gpm) (2 pumps 5000 8000 gpm)
. Supply GIg Wtr to Vital Hdr
. Verify spray logic is made up
. Start Loop A RHR Pmp (may start both)
. Open Ell-F028B
. Throttle Ell-F024B.
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EVENT 7 (Contd) SMALL BREAK LOCA BOP Operate SRVs to maintain reactor pressure in the established pressure band.
Establishes a cooldown not to exceed 100°F/hr Maintain reactor water level 170 200 inches.
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Simulator Operator Activities:
WHEN directed by the lead examiner, place the simulator in FREEZE.
CAUTION DO NOT RESET THE SIMULATOR PRIOR TO RECEIPT OF CONCURRENCE TO DO SO FROM THE LEAD EXAMINER Page 33 of 35
Attachment I ENP-24.5 Form FORM 2 Immediate Reactor Power Reduction Instructions Sheet I of 2 (Control Rod Insertions ONLY) SRO Control Correct Rod Control Rod Licensed Second Approximate Rod Selected and Position Operator Licensed % CTP Verified* Operator 26-35 / 08 to 00 26-19 I 08to00 18-27 I 08to00 34-27 I 08 to 00 59%
I 18-35 I l2toOO 34-19 I 12 to 00 34-35 I 12 to 00 18-19 I l2t000 56%
I 26-27 / 16 to 00 55%
I 18-43 I l6t000 34-11 I l6toOO 34-43 I l6toOO 18-11 I l6toOO 51%
I 10-35 I 16 to 00 42-19 I l6t000 42-35 I l6t000 10-19 I l6toOO 48%
I I
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Attachment I ENP-24.5 Form FORM 2 Immediate Reactor Power Reduction Instructions Sheet 2 of 2 (Control Rod Insertions ONLY) SRO Control Correct Rod Control Rod Licensed Second Approximate Rod Selected and Position Operator Licensed % CTP Verified* Operator 26-43 I 48 to 00 26-Il I 48t000 10-27 I 48t000 42-27 I 48 to 00 37%
I 10-43 I 48t000 42-11 I 48t000 42-43 I 48 to 00 10-11 I 48to00 30%
I I
I I
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