ML072970057

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July-August Exam 50-325, 324/2007301 Final Simulator Scenarios (Scenario 3 of 4) (Section 1 of 5)
ML072970057
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 01/31/2007
From:
Progress Energy Carolinas
To:
Office of Nuclear Reactor Regulation
References
2007-301, 50-324/07-301, 50-325/07-301 50-324/07-301, 50-325/07-301
Download: ML072970057 (54)
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INITIAL LICENSE EXAM 2007 SCENARIO THREE Brunswick Steam Electric Plant, Unit No. 2 BRUNSWICK JULY-AUG EXAM - 325,324/2007-301 FINAL SIMULATOR SCENARIO (3 OF 4)

~ Progress Energy

Brunswick 2007 NRC Scenario 3 Page 1 of 3

  • Facility:

Examiners:

BRUNSWICK Scenario No.:

Operators:

3 Op Test No.: 2007 NRC (SRO)

(RO)

(BOP)

Initial Conditions:

The plant is operating at 94% power, End Of Cycle.

RHR SW Pump 20 is under clearance for motor replacement and will remain out of service for two days.

TBCCW Pump 2B is under clearance to investigate a high vibration.

TBCCW Pump 2C has been placed in service on Unit 2.

No other equipment is out of service.

Turnover: Swap Service Water Pumps for maintenance work on the operating pump.

Raise power to 100%

Critical Task: See Scenario Summary Event Malf. No. Event Event Description No. Type*

1 N/A N-SRO Swap NSW pumps N-BOP 2 N/A R-SRO Power increase to 100% for rod pattern adjustment R-RO 3 MRC021F C-SRO Recirc Pump "A" scoop tube lockup C-RO 4 ZUA2162 ON TS-SRO EDG low starting air pressure (TS) 5 CW019F (A) C-SRO NSW pump trip(AOP) and standby pump fails to auto start K4821 A-Auto C-BOP Off 6 ES27F C-SRO RCIC Mechanical Overspeed Trip C-RO 7 K4403A Open C-ALL Partial Loss of FW heating, Power reduction required (AOPs) 30 sec 8 NBOO5F M-ALL Fuel Failure, Hi MSL Rads, MSIVs closed, Manual & Auto Scram Fail, RPOO5F (EOP)(AOP) Initiates ARI (CT)

K2503A-AS IS 9 ES004F C-SRO SRV F sticks open C-BOP

  • NOTES: 1)
2) *

=

S Satisfactory;

Critical Task/Step U - Unsatisfactory;

N/O Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

Brunswick 2007 NRC Scenario 3 Page 2 of 3

  • 10 11 K1230A-AS IS RSIARHBYPB-Bypass CW071F (B)

C-SRO C-BOP C-SRO RHR Loop A SW HX outlet valve fails, F068B valve (RHR HX Service Water Outlet) will fails to auto close.

RHR SW 2B pump trip, RHR leak into service water. (CT)

CW013F C-BOP 12 CA020F M-ALL SRV F tailpipe break, ED required (CT)

  • (N)ormal, (R)eactivity, (I)nstrument, (C )om ponent, (M)ajor
  • NOTES: 1)
2) *

=

S Satisfactory;

Critical Task/Step U - Unsatisfactory;

N/O Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

Brunswick 2007 NRC Scenario 3 Page 3 of 3

  • BRUNSWICK 2007 NRC Scenario #3 SCENARIO DESCRIPTION The plant is operating at 87% power, End Of Cycle with RHR SW Pump 20 and TBCCW Pump 2B under clearance. A swap of NSW pumps is required for upcoming maintenance on the operating pump. After swapping NSW pumps, reactor power will be raised to 100%.

While power is being raised a scoop tube lockup will occur on the "A" Recirc MG Set. I&C will report a circuit breaker caused the problem and the operator can reset the scoop tube. Once the scoop tube has been reset and recirc flows are matched, the #3 EDG will have a low starting air pressure requiring a technical specification determination (TS). (The EDG #3 must be declared inoperable).

Following the TS determination for the EDG (3.8.1.0), the NSW pump previously started will trip, requiring a restart of the NSW pump originally removed from service (TS 3.7.2.B). Once the NSW pump is restarted, a RCIC overspeed trip will occur due to a field operator accidentally unlatching the mechanism

. (T.S. 3.5.3.A). The RO will respond and re-Iatch the trip mechanism.

Feedwater valve FW-V120 will partially open resulting in a loss of feedwater heating and rising reactor power. The crew will respond per AOP-03.0 and reduce reactor power. The FW-V120 valve can be manually closed by the operators.

Fuel failure will occur that causes SJAE readings to rise and MSL Rad Hi to alarm. The crew will respond by entering AOP-05.0 and OEOP-04-RRCP. Power will be reduced to clear the MSL Rad Hi alarm. The fuel failure will get worse resulting in MSL Hi-Hi alarm along with rising Main Stack readings and alarms.

Per the guidance of OEOP-04-RRCP, the crew will insert a manual reactor scram and close the Group 1 Isolation Valves ***(Critical task to Close the MSIVs and Drains). The manual scram switch for channel B will fail. The reactor can be scrammed by Mode switch or ARI initiation (Critical Task).

When the MSIVs are closed SRVs will be required for pressure control. When SRV F is opened, it will stick open. Suppression pool temperature will rise requiring initiation of suppression pool cooling per OEOP-02-PCCP. If RHR Loop "A" is started for suppression pool cooling, the E11-F068A valve (RHR HX Service Water Outlet) will fail to open and RHR Loop "A" will be unavailable for suppression pool cooling.

When RHR Loop B is started for suppression pool cooling, the RHR Heat Exchanger will develop a tube leak. The tube leak will initially result in leakage of service water into the RHR system and RHR high conductivity alarm. RHR SW Booster Pump 2B will then trip (RHR SW 20 is under clearance) and E11-F068B will fail to auto close. Without an RHR Service Water pump in operation, RHR system water will now leak into service water.

Service Water high radiation will alarm. The crew will respond to the service water release per EOP RRCP by closing E11-F068B, shutting down RHR Loop B and isolating the heat exchanger (Critical Task).

The F SRV tailpipe will fail and Emergency Depressurization will be required per OEOP-02 PCCP when the safe region of Pressure Suppression Pressure (PSP) can not be maintained (Critical Task).

When the reactor is depressurized by the Emergency Depressurization, the scenario may be terminated .

  • NOTES: 1)
2) *

=

S Satisfactory;

Critical Task/Step U - Unsatisfactory;

N/O Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

  • PROGRESS ENERGY CAROLINAS BRUNSWICK TRAINING SECTION 2007 NRC EXAM SCENARIO # 3
  • 2007 NRC Examination Scenario #3
  • SCENARIO DESCRIPTION BRUNSWICK 2007 NRC Scenario #3 The plant is operating at 87% power, End Of Cycle with RHR SW Pump 20 and T8CCW Pump 28 under clearance. A swap of NSW pumps is required for upcoming maintenance on the operating pump. After swapping NSW pumps, reactor power will be raised to 100%.

While power is being raised a scoop tube lockup will occur on the "A" Recirc MG Set.

I&C will report a circuit breaker caused the problem and the operator can reset the scoop tube. Once the scoop tube has been reset and recirc flows are matched, the #3 EOG will have a low starting air pressure requiring a technical specification determination (TS). (The EOG #3 must be declared inoperable).

Following the TS determination for the EOG (3.8.1.0), the NSW pump previously started will trip, requiring a restart of the NSW pump originally removed from service (TS 3.7.2.8). Once the NSW pump is restarted, a RCIC overspeed trip will occur due to a field operator accidently unlatching the mechanism (T.S. 3.5.3.A). The RO will respond and re-Iatch the trip mechanism.

Feedwater valve FW-V120 will partially open resulting in a loss of feedwater heating and rising reactor power. The crew will respond per AOP-03.0 and reduce reactor power. The FW-V120 valve can be manually closed by the operators.

Fuel failure will occur that causes SJAE readings to rise and MSL Rad Hi to alarm. The crew will respond by entering AOP-05.0 and OEOP-04-RRCP. Power will be reduced to clear the MSL Rad Hi alarm. The fuel failure will get worse resulting in MSL Hi-Hi alarm along with rising Main Stack readings and alarms. Per the guidance of OEOP RRCP, the crew will insert a manual reactor scram and close the MSIVs (Critical Task to close MSIVs and Drains) and recirc sample valves. The manual scram switch for channel 8 will fail. The reactor can be scrammed by Mode switch or ARI initiation

. (Critical Task).

When the MSIVs are closed SRVs will be required for pressure control. When SRV F is opened, it will stick open. Suppression pool temperature will rise requiring initiation of suppression pool cooling per OEOP-02-PCCP. If RHR Loop A is started for suppression pool cooling, the E11-F068A valve (RHR HX Service Water Outlet) will fail to open and RHR Loop A will be unavailable for suppression pool cooling.

When RHR Loop 8 is started for suppression pool cooling, the RHR Heat Exchanger will develop a tube leak. The tube leak will initially result in leakage of service water into the RHR system and RHR high conductivity alarm. RHR SW Pump 28 will then trip (RHR SW 20 is under clearance) and E11-F0688 will fail to auto close. Without an

2007 NRC Examination Scenario #3 2

  • Service Water high radiation will alarm. The crew will respond to the service water release per EOP-04-RRCP by closing E11-F068B, shutting down RHR Loop Band isolating the heat exchanger (Critical Task).

The F SRV tailpipe will fail and Emergency Depressurization will be required per OEOP-02 PCCP when the safe region of PSP can not be maintained (Critical Task).

When the reactor is depressurized by the ED, the scenario may be terminated .

  • 2007 NRC Examination Scenario #3 3

SIMULATOR SETUP Initial Conditions IC 183 ENP 24 for IC 14 Rx Pwr 87%

Core Age EOC EVENTS Event Trigger Trigger Description Number 1 Swap Nuclear Service Water Pumps (final alignment::: 2A NSW NA NA Pump running, 28 NSW Pump in auto) 2 Raise reactor power to -100% using Control Rods and Recirc NA NA Flow 3 1 Manual 2A Recirc Pump Scoop Tube Lock 4 2 Manual DG #3 Low Starting Air Header Pressure 5 3 Manual 2A Nuclear Service Water Pump Trip

,........6 12 Manual RCIC Overspeed Trip

)7 4 Manual Loss of Feedwater Heating (2-FW-V120 partially opening)

............. 8 5 Manual Fuel Failure 9 NA NA ATWS 10 6 Auto SRV Fails open 11 7 Auto RHR Heat Exchanger Tube Leak 12 8 Auto RHR SW Pump Trip/E11-F0688 failure to close 13 9 Manual SRV Tailpipe failure - Pressure Suppression Pressure challenge 2007 NRC Examination Scenario #3 4

  • SIMULATOR SETUP Interventions Summary (Shaded entries = Active)

Malfunctions Summary Malt ID Mult ID Description Current Target Rmptime Actime Dactime Trig Value Value RC021F RECIRC PUMP MG SET A SCOOP FALSE TRUE 00:00:30 1 TUBE FAILURE CW019F A NUC SERVICE WATER PUMP FALSE TRUE 3 MOTOR WINDING FAULT ES027F RCIC OVERSPEED TRIP FALSE TRUE 00:00:05 12 NB005F FUEL FAILURE 0.00 100.0000 00:05:00 5 ES004F ADS VALVE F FAILS OPEN FALSE TRUE 6 CW013F RHR B HX TUBE LEAK 0.00 100.0000 00:05:00 7 CW071F B RHR SW BOOSTER PUMP MOTRO FALSE TRUE 8 WINDING FAULT CA020F SRV F TAIL PIPE RUPTURE FALSE TRUE 9 RPOO5F AUTO SCRAM DEFEAT TRUE TRUE

  • Remotes Summary Remt ID EO_'AEl.KCF16 RS_IARHBYPB Mult ID Description eKR eTL DC FUSES RHRSWPUMP 2P E11-F068B AUTO-CLOSURE BYPASS Current Value OUT NORMAL Target Value OUT BYPASS Rmptime Actime Trig 8

SWITCH CF_ZVCF120T BYP 4 & 5 HTR VLV FW-V120 ON OFF 10 RUARJTURB RCIC TURB OVERSPEED TRIP RESET NORMAL RESET 13

  • 2007 NRC Examination Scenario #3 5

Override Summary TaglD Description PositionJ Actual Override Rmptime Actime Dactlme Trig Target Value Value K4517A TBCCW PMP BON OFF ON ON K4517A TBCCW PUMP BON ON OFF OFF Q4517LG4 TBCCW PUMP B OFF G ON/OFF ON OFF Q4517RR4 TBCCW PUMP BON R ON/OFF OFF OFF K4403A FW HEATER 4-5 BYPASS VLV NEUT ON OFF 00:00:30 4 CLOSE K2503A RXSCRAMB SCRAMB OFF OFF K1230A RHR SW FCV 2E11*F068A NOR ON ON K1230A RHR SW FCV 2E11-F068A CLOSE OFF OFF K1230A RHR SW FCV 2E11-F068A OPEN OFF OFF K4821A NUC HDR SW PMP B DISCH AUTO ON OFF VLV K4403A FW HEATER 4 & 5 BYPASS CLOSE OFF OFF 00:00:30 4 VLVCLOSE K4403A FW HEATER 4 & 5 BYPASS OPEN OFF ON 00:00:30 4 VALVE CLOSE Q1508LGL SRV VLV B21-F013F GREEN ONfOFF ON OFF 11 Q1508RRJ SRV VLV B21-F013F RED ON/OFF OFF OFF 11 Annunciator Summary Window Description Tagname Override Type OVal AVal Actime Dactime Trig 6-2 DG-3 LO START AIR PRESS ZUA2162 ON ON OFF 2 Batch Files II~File_1~Trigger ~~S~=.:..:....-~Ption

--r-::-=-=-::I -----II Special Instructions Load scenario file 2007 NRC Scenario 3.scn Place red cap on 2D RHR SW Booster Pump Control Switch.

Place red cap on 2B TBCCW Pump Control Switch Ensure ENP-24 and GP-12 for pulling rods for IC14 @ P603.

Null DVM 2007 NRC Examination Scenario #3 6

  • SHIFT BRIEFING Plant Status The plant is operating at 87% power, End of Cycle.

Control rods 10-43, 42-43, 42-11, and 10-11 have been inserted from position 48 to position 16 for a downpower.

Equipment Out of SeNice 20 RHR SW Booster Pump is out of seNice for lube oil change and is expected to be returned to seNice by the end of shift.

2B TBCCW Pump is out of seNice and under clearance for motor replacement and is anticipated to be returned to seNice in 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

No other equipment is out of seNice Plan of the Day Following shift turnover, place 2A Nuclear SeNice Water Pump in seNice with 2B Nuclear SeNice Water Pump in standby, in support of nuclear header flow measurement activities.

Raise reactor power by withdrawing control rods 10-43, 42-43, 42-11, and 10-11 utilizing the provided GP-12 pull sheet. Once the rods have been fully withdrawn, the NE has given approval to use Reactor Recirculation flow to raise reactor power to maximum rated.

OPT-14.1 is current for all control rods

  • 2007 NRC Examination Scenario #3 7
  • SCENARIO INFORMATION Examiner Notes Procedures Used in Scenarios:

EVENT 1

  • OGP-12
  • Technical Specifications EVENT 5
  • OAOP-18 EVENT 6
  • APP A-3 5-3 RCIC TURB TRIP
  • Technical Specifications EVENT 7
  • OAOP-03.0
  • ENP-24 (Immediate Power Reduction Guidance)
  • OGP-12 EVENT 8
  • OEOP-04-RRCP (Radioactive Release Control Procedure)

OEOP-02-PCCP (Primary Containment Control Procedure) 2007 NRC Examination Scenario #3 8

  • SCENARIO INFORMATION EVENT 9

EVENT 10

  • OAOP-30 EVENT 11/12
  • OEOP-04-RRCP EVENT 13

Critical Tasks When the Main Steam Line Rad High-High is reached (annunciator 2-UA-23 3-6), the MSIVs and MSIV drain valves are manually closed .

  • When a manual scram signal fails to complete a reactor scram due to a failure on the liB" RPS side, successfully complete control rod insertion by placing the Reactor Mode Switch to Shutdown (scram signal) or by manually initiating ARI.

When indications are observed of a radioactive leak from the liB" RHR Heat Exchanger to the environment via the Service Water system, successfully isolate the Service Water effluent from the RHR Service Water.

When containment parameters cannot be maintained within the safe region of the Pressure Suppression Pressure graph, Emergency Depressurize the reactor.

  • 2007 NRC Examination Scenario #3 9
  • EVENT 1 SHIFT TURNOVER, SWAPPING NUCLEAR SERVICE WATER PUMPS The crew will swap operating Nuclear Service Water Pumps in support of scheduled NSW flow measurement activities.

Malfunction required:

  • None Objectives:

SCO Directs BOP to start 2A Nuclear Service Water Pump and place 2B Nuclear Service Water Pump in standby per 20P-43, section 8.22.

BOP Place 2A Nuclear Service Water Pump in service and secure 2B Nuclear Service Water Pump and place it in standby per 20P-43, section 8.22.

Success Path:

Nuclear Service Water Pump 2A will be started and Nuclear Service Water Pump 2B will be secured and placed in Standby per 20P-43 .

Simulator Operator Activities:

  • WHEN asked, report that pre-start checks on 2A Nuclear Service Water Pump have been completed and all parameters/conditions are normal.
  • WHEN asked, report that 2A Nuclear Service Water Pump is running normally.
  • 2007 NRC Examination Scenario #3 10

APPLICANT'S ACTIONS OR BEHAVIOR:

  • 2007 NRC Examination Scenario #3 11
  • EVENT 2 RAISE REACTOR POWER TO -100%

The crew will raise reactor power using Reactor Recirculation flow and control rods per GP-12.

Malfunction required:

  • None Objectives:

SCO Directs RO to raise power to 100% per GP-12, using Reactor Recirculation flow and control rods.

BOP Raises reactor power per GP-12, using Reactor Recircula;ion flow and control rods.

Success Path:

Reactor Power is raised using Reactor Recirculation flow and control rods.

Simulator Operator Activities:

  • IF contacted as NE, state that continuous withdrawal of control rods is allowed .
  • 2007 NRC Examination Scenario #3 12
  • EVENT 2 RAISE REACTOR POWER TO -100%

Required Operator Actions Normal Operation - Raise Reactor Power to 100%

        • EVALUATOR NOTE: Alternate Power Verification is required at 10% power increments during power ascension and takes approximately 10 minutes to complete. If a change to the Gain Adjustment Factor (GAF) is required following Alternate Power Verification, an additional 15 minutes should be allowed.

At the evaluator's discretion, prompt may be given stating that Alternate Power Verifications are to be completed by other members of the operating crew and are satisfactory.

SRO

  • Direct RO to raise reactor power to 100% per OGP-12 using Recirc Flow and control rods RO
  • Raise Reactor Power to 100% per OGP-12 using Recirc Flow and control rods APPLICANT'S ACTIONS OR BEHAVIOR:
  • 2007 NRC Examination Scenario #3 13
  • EVENT 3 2A Reactor Recirc Pump Scoop Tube Lock (Spurious)

The crew responds to a spurious lock of the 2A Reactor Recirc Pump Scoop Tube Malfunctions required:

  • Circuit 2 on Panel 2A-TB for the 2A Reactor Recirc MG set will trip resulting in a locking of its scoop tube, preventing any controlled changing of speed of the affected machine Objectives:

SCO Directs actions to stop power changes and evaluates plant conditions to verify the initiating cause.

Contacts I&C to request support in issue resolution.

RO Refers to annunciator procedure and identifies/reports indications of scoop tube status and related plant conditions.

2-A-6 2-4, Fluid Drive A Scoop Tube Lock Success Path:

Scoop Tube lock is successfully identified, diagnosed, and recovered from, with the final condition being that the scoop tube is restored to an unlocked condition and reactor power is approximately 100%.

Simulator Operator Activities:

  • WHEN directed by lead examiner, activate TRIGGER 1 (2A Recirc Pump Scoop Tube Lock).
  • WHEN asked, as TBAO, report that 2A-TB circuit 2 is tripped
  • WHEN asked, as I&C, to assist in the investigation of the failure, acknowledge the request and, after 3 minutes, inform the SCO that the faulty breaker has been repaired.
  • WHEN directed, as TBAO, to reclose the breaker, then acknowledge the request and report the breaker has been reclosed.
  • WHEN asked, as I&C, provide assistance in matching speed demand versus actual in support of unlocking the scoop tube using the Instructor Aid for Recirc MG Set Bailey Position error.

2007 NRC Examination Scenario #3 14

  • EVENT 3 2A Reactor Recirc Pump Scoop Tube Lock Required Operator Actions SRO
  • Directs actions to stop power changes and evaluates plant conditions to verify the initiating cause.
  • Contacts I&C to request support in issue resolution.
  • Approves resetting the circuit breaker after repairs have been made.
  • Following correction of problem, directs RO to unlock the scoop tube per 20P-02, Section 8.4.

RO

  • Refers to annunciator procedure 2-A-6 2-4, Fluid Drive A Scoop Tube Lock and identifies/reports indications of scoop tube status and related plant conditions.

Directs AO to investigate potential scoop tube lock causes.

When directed, unlocks the scoop tube per 20P-02, Section 8.4

  • 2007 NRC Examination Scenario #3 15
  • EVENT 3 2A Reactor Recirc Pump Scoop Tube Lock APPLICANT'S ACTIONS OR BEHAVIOR:
  • 2007 NRC Examination Scenario #3 16

Malfunction required:

Objectives:

SCO Correctly evaluates the condition of the Diesel Generator Low Starting Air Header Success Path:

SCO obtains information from the Diesel Generator and determines the affected Diesel Generator is inoperable (Technical Specifications).

Simulator Operator Activities:

WHEN directed by Lead Examiner, activate TRIGGER 2 (# 3 Diesel Generator Starting Air Low Pressure)

WHEN asked, report that the #3 Emergency Diesel Generator starting air header pressure and air receiver pressure is 220 psig and the air compressors breakers are closed, but the compressors are not running.

  • WHEN contacted as Maintenance requesting help to adjust the pressure, acknowledge the request.

2007 NRC Examination Scenario #3 17

  • EVENT 4 DG #3 Low Starting Air Header Pressure Required Operator Actions Normal Plant Operation - Assessing Technical Specifications due to a parameter outside of established bands (DG #3 Starting Air Header Pressure)

SRO

NOTE: Per OP-39 "DG Operating Procedure" Precaution/Limitation step 3.17.3, the.

DG is inoperable when air receiver pressure is below 230 psig.

      • EVALUATOR NOTE: As necessary, prompt SRO that the opposite unit will perform required surveillances.

Refers to Tech Specs:

Tech Spec 3.8.1.0: One diesel generator inoperable for reasons other

  • 0.1 AND than planned maintenance Perform surveillance 3.8.1.1 within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter 0.2 Declare required features supported by inoperable DG inoperable when redundant required features are inoperable AND 0.3.1 Determine Operable DGs are not inoperable due to common cause failure (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />)

Or 0.3.2 Perform SR 3.8.1.2 for Operable DGs (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />)

AND 0.4 Restore DG to Operable status (7 days)

  • Tech Spec 3.7.1.C.1 2007 NRC Examination Scenario #3 Both RHRSW subsystems inoperable (8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />) 18
  • Notifies AO to investigate problem at #3 EDG
  • 2007 NRC Examination Scenario #3 19
  • EVENT 4 DG #3 Low Starting Air Header Pressure APPLICANT'S ACTIONS OR BEHAVIOR:
  • 2007 NRC Examination Scenario #3 20
  • EVENTS 2A NUCLEAR SERVICE WATER PUMP TRIP The crew will respond to the failure of an operating Nuclear SeNice Water Pump per OAOP-18.0 and take action to restore Nuclear SeNice Water to within normal operating limits.

Malfunctions required:

2A Nuclear SeNice Water Pump will trip on electrical fault, and the 2B Nuclear SeNice Water Pump will fail to start on a low pressure demand signal.

Objectives:

SCO Reference/Enter OAOP-18.0 and directs the actions of the BOP to facilitate restoration of the Nuclear SeNice Water System to within normal limits Evaluates Technical Specifications for the inoperability of the 2A Nuclear SeNice Water Pump. TS 3.7.2. Ultimate Heat Sink - Tracking LCO- LCO conditions are still met BOP Reference/Enter OAOP-18 and manually starts the 2B Nuclear SeNice Water Pump to restore Nuclear SeNice Water parameters within normal limits.

  • Success Path:

Nuclear SeNice Water header is restored to operating within normal ranges with the 2B Nuclear SeNice Water Pump operating.

Simulator Operator Activities:

  • WHEN directed by the lead examiner, activate TRIGGER 3 (2A Nuclear SeNice Water Pump trip with failure of 2B Nuclear SeNice Water Pump to auto start)
  • IF asked to investigate in the SeNice Water Building, wait 3 minutes and then report an acrid smell in the vicinity of the 2A Nuclear SeNice Water Pump motor, but that there are no signs of smoke and/or fire
  • IF asked to investigate in the Diesel Generator Building, wait 3 minutes and report that there are overcurrent trips on all three phases of the 2A Nuclear SeNice Water Pump 4KV Breaker.
  • IF contacted as I&C and requested to help with the investigation of the failure of the 2A Nuclear SeNice Water Pump, acknowledge the request.
  • 2007 NRC Examination Scenario #3 21
  • EVENTS 2A NUCLEAR SERVICE WATER PUMP TRIP Required Operator Actions Abnormal Operating Procedures - Nuclear Service Water Failure SCO
  • Reference/Enter OAOP-18.0 and directs the actions of the BOP to facilitate restoration of the Nuclear Service Water System to within normal limits
  • Evaluates Technical Specifications:

Tech Spec 3.7.2.B (Tracking - required number of nuclear service water pumps remain Operable)

UA-17 6-1, Bus E3-4KV MTR OVLD UA-1 1-10, NUCLEAR SERV WTR HDR PR LO UA-1 2-10, NUCLEAR SERV WTR PMP A TRIP RO/BOP

  • Dispatches an AO to the Service Water building and Diesel Generator building to investigate cause of 2A NSW Pump trip .
  • 2007 NRC Examination Scenario #3 22
  • EVENT 5 2A NUCLEAR SERVICE WATER PUMP TRIP APPLICANT'S ACTIONS OR BEHAVIOR:
  • 2007 NRC Examination Scenario #3 23

Malfunctions required:

  • None Objectives:

SCO Directs response to Annunciator A-3 5-3, RCIC TURB TRIP Directs contacting auxiliary operator to investigate Evaluates Tech Specs for RCIC Inoperability Directs re-Iatch of trip device RO Reviews APP A-3 5-3, RCIC TURB TRIP

  • Re-Iatches RCIC mechanical overspeed per OP-16, sections 8.3. & 5.1 RO/BOP Dispatches AO to investigate the cause of the RCIC trip Success Path:

RCIC mechanical overspeed re-Iatched with RCIC in a standby alignment.

Simulator Operator:

  • WHEN called to investigate, report back in 3 minutes that the problem occurred because an auxiliary operator accidentally bumped the overspeed latch. Report that at all personnel are clear and the device can be re-Iatched.

WHEN contacted to relatch RCIC overspeed trip, activate TRIGGER 13. then report that the overspeed latch mechanism has been reset.

  • 2007 NRC Examination Scenario #3 24

SRO

  • Directs contacting field operator to investigate
  • Evaluates Technical Specifications:

Tech Spec 3.5.3.A RCIC Inoperable A.1 Verify by administrative means HPCI Operability AND A.2 Restore RCIC to Operable status (14 days)

  • Directs re-Iatch of trip device
  • Directs re-opening of the RCIC TRIP THROTTLE VALVE to restore RCIC operability.

RO

  • Reviews APP A-3 5-3, RCIC TURB TRIP
  • Notes that APP states to refer to OP-16 to reset the mechanical overspeed

THROTTLE VALVE E51-V8

  • Directs the AO to perform the steps of OP-16 Step 8.3.1. to locally reset RCIC mechanical overspeed device.
  • When informed by the AO that the device is re-Iatched, re-opens TURBINE TRIP

& THROTTLE VALVE E51-V8 per SCO direction.

      • EVALUATOR NOTE: IF requested by RO, state that another operator will perform necessary independent verification steps.
  • 2007 NRC Examination Scenario #3 25
  • RO/BOP
  • Dispatches AO to investigate cause of trip
  • 2007 NRC Examination Scenario #3 26
  • EVENT 7/8 LOSS OF FEEDWATER HEATING/FUEL FAILURE.

The crew will observe and respond to a spurious opening of the 2-FW-V120 (loss of feedwater heating) and resultant fuel failure due to the cold water injection overpower.

Malfunctions required:

  • 2-FW-V120 (High Pressure Feedwater Heater String) will receive a spurious "Open" signal for 30 seconds, resulting in a loss of feedwater heating and companion power increase.

Objectives:

SCO Directs the actions of the crew per 2AOP-03.0, Positive Reactivity Addition, in response to the opening of the 2-FW-V120 to limit the power excursion resulting from the cold water addition.

Directs the actions of the crew per OAOP-05.0, Abnormal Rad Conditions, in response to the indications of fuel failure resulting from the overpower event caused by the loss of feedwater heating.

Lowers reactor power, when directed, to mitigate the overpower resulting from the loss of feedwater heating.

Continues lowering power, as directed, in response to increases in radiological conditions in the plant resulting from fuel failure.

Inserts a manual scram, when directed .

  • 2007 NRC Examination Scenario #3 27
  • EVENT 7/8 BOP LOSS OF FEEDWATER HEATING/FUEL FAILURE Recognizes and reports the abnormal position of the 2-FW-V120 and takes action to close the valve Observes and reports annunciators relating to fuel failure, specifically as relating to changing radiological conditions Success Path:

The crew will correctly diagnose the spurious opening of the 2-FW-V120 and take actions to close the valve and manage power level to limit the overpower condition and subsequent fuel failure.

Simulator Operator Activities:

  • WHEN directed by the lead examiner, activate TRIGGER 4 (FW-V120 spurious opening to provide cold water injection)

NOTE: Fuel failure will ramp to 100% severity over 5 minutes. IF a scram is inserted prior to fuel failure reaching 100%, THEN TRIGGER 14 will automatically actuate to ramp fuel failure to 100% when control rods begin to insert.

  • IF asked as an auxiliary operator, standby and open the breaker for the 2-FW-V120 when it is moved to a "Closed" position by activating TRIGGER 10.
  • WHEN directed by the lead examiner, activate TRIGGER 5 (Fuel Failure).
  • WHEN asked as E&RC, acknowledge the request to perform area radiological surveys.
  • 2007 NRC Examination Scenario #3 28
  • EVENT 7/8 LOSS OF FEEDWATER HEATING/FUEL FAILURE Required Operator Actions:

seo

  • Direct actions to close the 2-FW-V120 and entry into OAOP-03.0: Positive Reactivity Addition
  • Enter and direct actions of 0"AOP-05.0 Abnormal Rad Conditions, based on the fuel failure.
  • Enter and direct actions of OEOP-04-RRCP (Radiological Release Control Procedure) o When UA-23, 2-6 (MSL Rad Hi) is in alarm, Enters EOP-04-RRCP (Rad Release Control Procedure) o Request Unit 1 or Ops Center to Perform PEP 3.4.7 (site boundary dose) o Ensure/direct BOP to place CREV in service
  • o o

Determine if annunciator UA-3, 5-4 (Stack Rad Hi Hi) is in alarm

  • If yes, ensure/direct BOP to verify SBGTs in service, RB ventilation isolated Ensures AOG is in service o Directs RO to reduce power to clear UA-23, 2-6 (MSL Rad Hi) o Notify E&RC to obtain off-gas and coolant samples o Assess if annunciator UA-3, 4-2 (SJAE Rad Hi Hi) has been in alarm o Assess if Main Stack Rad is rising o Ensures AOG bypass (AOG-HCV-102) is closed o Directs reactor shutdown per GP-05 o Determine if UA-23, 3-6 (MSL Rad Hi Hi) is in alarm When Yes
  • Directs BOP to close Group 1 isolation valves o (B21-F022A-D, B21-F028A-D, B21-F016/F019, B32-F019/F020)
  • 2007 NRC Examination Scenario #3 29
  • EVENT 7/8 LOSS OF FEEDWATER HEATING/FUEL FAILURE Required Operator Actions:

SRO (cant.)

      • CRITICAL TASK***(MSIVs and Drains are Critical) When Main Steam Line Rad High High has been exceeded, Directs actions to manually scram and close Group 1 isolation valves.
  • Determines Reactor Power is >2% (ATWS) goes to Level-Power Control
  • Directs BOP to control reactor pressure 800 psig to 1000 psig using SRVs
  • Directs reactor water level control using HPCI/RCIC RO
  • When directed lowers reactor power to keep main steam line high rad alarm clear lAW ENP-24 o Lowers Recirc Flow to 47 Mlbm/hour o Inserts Control Rods lAW ENP-24 established emergency power
  • BOP reduction When directed, insert a manual scram based on radiological conditions.

Recognizes and reports failure of controls to insert (ATWS)

Places ARI to Trip lAW the Scram Hard Card

  • Identify and report the position of the 2-FW-V120 and take action to close the valve.

o Recognizes and reports Radiological Conditions from annunciators and rad monitors

  • When directed closes Group 1 isolation valves (B21-F022A-D, B21-F028A-D, B21-F016/F019, B32-F019/F020)
  • ***CRITICAL TASK***(MSIVs and Drains are Critical) Following scram closes Group 1 isolation valves.
  • Following scram, maintains reactor water level 170" to 200" using HPCI and/or RCIC.
  • Following scram, maintains reactor pressure 800 psig to 1000 psig with HPCI and/or SRVs.
  • 2007 NRC Examination Scenario #3 30
  • EVENT 7/8 LOSS OF FEEDWATER HEATING/FUEL FAILURE APPLICANT'S ACTIONS OR BEHAVIOR:
  • 2007 NRC Examination Scenario #3 31
  • EVENT 9 ATWS The crew will observe and respond to an ATWS when a reactor scram is attempted.

Malfunctions required:

  • The manual scram pushbutton will be overridden to prevent a scram from being successful via depressing of the manual scram pushbuttons.

Objectives:

SCO Directs actions of the crew in response to the failure of the reactor to scram.

Enters 2EOP-01-RSP, Reactor Scram Procedure and 2EOP-01-LPC, Level Power Control.

RO Inserts a manual scram, when directed, and takes the appropriate actions in response to the failure of the RPS system to complete a scram.

  • BOP Maintains vessel level 170" to 200: using HPCI and RCIC.

Maintains vessel pressure 800 psig to 1000 psig using SRVs and/or HPCI in pressure control mode.

  • 2007 NRC Examination Scenario #3 32
  • EVENT 9 Success Path:

ATWS The crew will correctly diagnose the ATWS condition and effect control rod insertion by placing the mode switch in Shutdown or by ARI initiation.

Simulator Operator Activities:

  • NONE Required Operator Actions:

SCO

  • Enters and directs actions of OEOP-01-RSP (Reactor Scram Procedure)
  • Enters and directs actions of OEOP-01-LPC (Level-Power Control) o ***CRITICAL TASK***Directs mode switch placed to Shutdown and ARI initiation.
  • When all control rods are inserted, go to Reactor Vessel Control Procedure (EOP-01-RVCP) o Direct RO/BOP to use SRVs to maintain reactor pressure 800 psig to 1000 psig o Direct RO/BOP to control Reactor Water Level 170" to 200" using HPCI/RCIC

o Direct RO/BOP to maximize Suppression Pool Cooling when Suppression Pool temperature is > 95°F.

RO

o Initiates ARI (per scram hard card or as directed by SRO).

o Places Recirc Contr. to 10% (per scram hard card or as directed by SRO) 2007 NRC Examination Scenario #3 33

  • EVENT 9 ATWS Required Operator Actions (cont.):

RO (cont.)

o Places Reactor Mode Switch to shutdown (immediate operator action or as directed by SRO)

    • CRITICAL TASK*** Initiates ARI and places mode switch to shutdown.
  • When directed, perform LEP-02, Alternate Control Rod Insertion RO/BOP
  • When directed, establishes and controls reactor pressure in a band 800 psig to 1000 psig using SRVs
  • When directed, maintain reactor water level 170" to 200" using HPCIIRCIC RCIC
  • Open E51-F046
  • Start Barometric Vacuum Pump Open E51-F045 Open E51-F013 Adjust RCIC flow controller to establish desired flowrate (pre-set value is 500 gpm)

HPCI

  • Open E41-F059
  • Start Vacuum Pump
  • Open E41-F001
  • Start Aux Oil Pump
  • Open E41-F006 (auto open on valve is failed, but valve will open when control switch is operated.
  • Adjust Flow Controller to desired injection rate .
  • 2007 NRC Examination Scenario #3 34
  • EVENT 9 ATWS Required Operator Actions (cont.):

RO/BOP (cont.)

  • When directed places "A" and liB" loops of RHR in Suppression Pool Cooling per the Hard Card.
  • Opens SW-V105 (liB" Loop) and SW-V101 ("A" Loop)
  • Starts RHRSW Booster Pump (places control switch to Start
  • Throttles Open E11-F068AJB
  • Recognizes and Reports Failure of E11-F068A to Open.
  • If E11-F015A(B) is Open, closes E11-F017A(B)
  • Starts Loop A(B) RHR Pump using control switch
  • Opens E11-F028A(B)
  • Throttles Open E11-F024A(B)
  • Throttles closed E11-F048A(B)
  • 2007 NRC Examination Scenario #3 35
  • EVENT 9 ATWS APPLICANT'S ACTIONS OR BEHAVIOR:
  • 2007 NRC Examination Scenario #3 36
  • EVENT 10 SRV F STUCK OPEN The crew will respond to a failure of SRV F to close following the placing of its control switch to the "AUTO" position following its manual actuation in support of reactor pressure control.

Malfunctions required:

  • SRV "Fit will fail in the OPEN position following its use to maintain reactor pressure.

Objectives:

SCO Enter and direct actions associated with 2EOP-02-PCCP (Primary Containment Control Procedure) due to heating of the Suppression Pool.

Directs actions for OAOP-30.0 (SRV Failure)

Directs RO/BOP to place all available loops of RHR in Suppression Pool Cooling

  • RO Recognizes and communicates failure of SRV "Fit to close when it's switch is taken to the AUTO position.

Takes actions as directed by the OAOP-30, to attempt to close the SRV When directed, places RHR in Suppression Pool Cooling to mitigate the heat addition due to the failed open SRV BOP When directed, supports placing RHR in Suppression Pool Cooling to mitigate the heat addition due to the failed open SRV Success Path:

Crew recognizes the failed open SRV and takes the actions as directed by the AOP and EOP relating to the failure.

  • 2007 NRC Examination Scenario #3 37
  • EVENT 10 SRV F STUCK OPEN Simulator Operator Activities NOTE: When SRV F is opened (Red Lamp ON) TRIGGER 6 will automatically initiate activating SRV F Fails Open Malfunction.

WHEN requested pull SRV fuses by initiating TRIGGER 11 (SRV will remain open)

Required Operator Actions SCO

  • Directs entry into OAOP-30.0 (stuck open relief valve).

o Directs OAOP-30.0 actions to attempt to achieve reclosure of SRV F by cycling control switch and leaving in the Auto/Closed position.

o Directs OAOP-30.0 actions to have fuses removed lAW AOP guidance.

  • Contacts Maintenance personnel for assistance in the stuck open SRV
  • When Suppression Pool Temperature reaches 95°F enters OEOP-02-PCCP (Primary Containment Control Procedure) and directs actions associated with the heating of the suppression pool resulting from the stuck open SRV.

o Direct RO/SOP to maximize Suppression Pool Cooling when Suppression Pool temperature is > 95°F.

RO/BOP

  • Recognizes and Reports failure of SRV F to close.

o Enters and executes OAOP-30.0 as directed to attempt to re-c1ose SRV F.

o Cycles SRV several times, leaves switch in Auto/Close position (immediate operator actions of AOP) o Contacts I&C for assistance in removal of fuses lAW AOP-30.0.

o After fuses are removed, determines and notifies SRO that the relief valve is still open.

  • EVENT 10 SRV F STUCK OPEN 2007 NRC Examination Scenario #3 38
  • Required Operator Actions (cont.):

RO/BOP (cant.)

  • When directed places "A" and liB" loops of RHR in Suppression Pool Cooling per the Hard Card.
  • Opens SW-V105 (liB" Loop) and SW-V101 ("A" Loop)
  • Starts RHRSW Booster Pump (places control switch to Start
  • Throttles Open E11-F068A1B
  • Recognizes and Reports Failure of E11-F068A to Open.
  • If E11-F015A(B) is Open, closes E11-F017A(B)
  • Starts Loop A(B) RHR Pump using control switch
  • Opens E11-F028A(B)
  • Throttles Open E11-F024A(B)
  • Throttles closed E11-F048A(B)
  • 2007 NRC Examination Scenario #3 39
  • EVENT 10 SRV F STUCK OPEN APPLICANT'S ACTIONS OR BEHAVIOR:
  • 2007 NRC Examination Scenario #3 40
  • EVENT 11!12 RHR HEAT EXCHANGER TUBE LEAK/SERVICE WATER FAILURE TO ISOLATE! RHR SW BOOSTER PUMP TRIP The crew will respond to an RHR Heat Exchanger tube leak accompanied by an RHR Service Water Booster Pump trip and subsequent failure of the outflow isolation valve to automatically close (Radioactive Release).

Malfunctions required:

An RHR Heat Exchanger tube failure will occur (indicated by a rising conductivity of the RHR system). The supporting RHR Service Water Booster Pump will, subsequently, trip accompanied by the Service Water Loop effluent valve (2-E11-F068B) failure to automatically close.

Objectives:

SCO Will direct the actions of OEOP-04-RRCP (Radioactive Release Control Procedure) associated with the Service Water Leg of the procedure

      • CRITICAL TASK*** Will recognize the failure of the 2-E11-F068B to close and provide direction! oversight to ensure the valve is closed by operator action.

BOP Will recognize and report the failure of the RHR Service Water Booster Pump and the accompanying failure of the 2-E11-F068B (RHR Service Water Loop Effluent) to automatically close.

      • CRITICAL TASK*** Will take action to manually manipulate the 2-E11-F068B to close the valve and stop the radiological effluent path from the heat exchanger via the Service Water effluent.

Examiner Note: Closure of the E11-F003 and E11-F047 would also isolate the source of the leak.

Success Path:

The crew will recognize the indications of the RHR Heat Exchanger tube leak.

Following the tripping of the RHR Service Water Booster Pump and the failure of the 2-E11-F068B to close, the crew will take action to achieve isolation of the radioactive effluent via the Service Water system by closing the 2-E11-F068B.

  • 2007 NRC Examination Scenario #3 41
  • EVENT 11/12 RHR HEAT EXCHANGER TUBE LEAK/SERVICE WATER FAILURE TO ISOLATE/ RHR SW BOOSTER PUMP TRIP Simulator Operator Activities:

NOTE: WHEN E11-F024B is opened (Red Lamp ON) by the operator, TRIGGER 7 will automatically initiate activating RHR B HX tube leak malfunction.

NOTE: WHEN E11 F024B is opened (Red Lamp ON) AND RHR SW ~ flow is greater than 1000 gpm, TRIGGER 8 will automatically initiate activating RHR SW Booster Pump B motor winding fault malfunction, tripping the 2B RHR SW pump.

  • IF requested as the building auxiliary operator to check the 2-E11-F068B or manually close the 2-E11-F068B, acknowledge the request.

Required Operator Actions:

SRO When notified of RHR HX outlet conductivity Hi (A-3, 2-10) directs RO/BOP to take actions lAW APP.

When notified of Service Water Effluent Rad High (UA-3, 5-5) o Directs actions associated with the Service Water leg of OEOP-04-RRCP, Radioactive Release Control Procedure.

o Contacts E&RC to sample SW outlet per OEOP-04-RRCP to determine source of radioactivity.

o Directs RO/BOP to isolate RHR Heat Exchanger lAW APP or EOP RRCP

      • CRITICAL TASK*** Provides oversight and direction, as applicable, to the BOP to take individual action to attempt to close the 2-E11-F068B.

BOP

  • Recognizes and communicates the indications of the RHR Heat Exchanger tube leak to the crew.

o Recognizes and reports RHR HX Outlet Conductivity Hi (A-3 2-10, RHR Ht Exh B Outlet Condo High).

2007 NRC Examination Scenario #3 42

  • EVENT 11/12 RHR HEAT EXCHANGER TUBE LEAK/SERVICE WATER FAILURE TO ISOLATE/ RHR SW BOOSTER PUMP TRIP Required Operator Actions (cont.):

BOP (cant.)

  • Recognizes and reports the tripping of the RHR Service Water Booster Pump and accompanying failure of the 2-E11-F068B to automatically close.

o Closes E11-F068B and reports to the SRO.

o If directed, closes E11-F003B and E11-F047B to isolate the RHR Heat Exchanger.

o Refers to annunciator procedure UA-3 5-5, Service Water Effluent Rad High.

      • CRITICAL TASK*** Takes action, as directed, to isolate the source of the radioactive release by either closing the E11-F068B or by isolating the heat exchanger by closing the E11-F003 (HX Outlet isolation) and E11-F047 (HX Inlet isolation).
  • 2007 NRC Examination Scenario #3 43
  • EVENT 11/12 RHR HEAT EXCHANGER TUBE LEAK/SERVICE WATER FAILURE TO ISOLATE/ RHR SW BOOSTER PUMP TRIP APPLICANT'S ACTIONS OR BEHAVIOR:
  • 2007 NRC Examination Scenario #3 44
  • EVENT 13 SRV F TAILPIPE BREAK/EMERGENCY DEPRESSURIZATION REQUIRED The crew will respond to indications of a failure of the SRV "F" tailpipe in the air space of the suppression chamber, resulting in entry of the Unsafe region of the Pressure Suppression Pressure graph, requiring an Emergency Depressurization of the reactor.

Malfunctions Required:

The SRV "F" tailpipe will experience a failure in the air space of the Suppression Chamber, resulting in a loss of the pressure suppression function of the suppression pool.

Objectives:

SCO Diagnose the SRV tailpipe failure based on the rapid increase in containment pressure and the accompanying loss of differential pressure between the Drywell and Suppression Chamber air space.

Assess the changing conditions in the containment, specifically the approach to and entry into the Unsafe region of the Pressure Suppression Pressure curve, requiring Emergency Depressurization of the reactor.

      • CRITICAL TASK*** Successfully direct the actions prescribed in OEOP-02-PCCP (Primary Containment Control Procedure) to Emergency Depressurize the reactor.

RO/SOP Identify and report the changes in containment pressure.

Observe and report the lowering differential pressure between the air spaces and participate in the diagnosis of the loss of pressure suppression function.

      • CRITICAL TASK*** When directed, take the actions necessary to Emergency Depressurize the reactor and control injection sources to prevent overfilling of the reactor pressure vessel.

Success Path:

The crew will correctly diagnose the loss of pressure suppression function of the containment and complete an Emergency Depressurization of the reactor.

  • 2007 NRC Examination Scenario #3 45
  • EVENT 13 SRV F TAILPIPE BREAK/EMERGENCY DEPRESSURIZATION REQUIRED Simulator Operator Activities:
  • WHEN directed by the lead examiner, after the F068B valve closes, initiate TRIGGER 9 (SRV Tailpipe Failure).

Required Operator Actions:

SCO

  • Correctly diagnoses the SRV tailpipe failure and subsequent entry into the Unsafe region of the Pressure Suppression Pressure graph.

o Recognizes changes in primary containment pressure o Prior to Suppression Chamber Pressure Exceeding 11.5 psig

  • Directs RO/BOP to perform Suppression Pool Spray per SEP-03 o When Suppression Chamber exceeds 11.5 psig,
  • o o
  • Directs RO/BOP to perform Drywell Sprays per SEP-02 Determines Anticipation of Emergency Depressurization is not permitted because of the failed fuel (EOP-01-RVCP guidance)

Determines Pressure Suppression Pressure cannot be maintained in the safe region of the graph and directs Emergency Depressurization of the reactor

      • CRITICAL TASK*** Direct the actions prescribed in OEOP-02-PCCP to Emergency Depressurize the reactor when Pressure Suppression Pressure cannot be maintained in the SAFE region.

RO/BOP

  • Observe and report the changes in containment parameters associated with the SRV tailpipe failure o Support the diagnosis of the loss of pressure suppression function of the containment.
  • When directed, Sprays the Suppression Chamber per SEP-03 o Places 2/3 Core Height Override Position to ON 2007 NRC Examination Scenario #3 46
  • o o

o Place Containment Spray Valve Control Switch to Manual If E11-F015A(B) is open and RHR injection is not necessary, close E11-F017A(B)

Start/Ensure a loop RHR Pump is running o Open E11-F028A(B) o Open E11-F027A(B) o Ensure Loop is aligned to one of the following: LPCI, Suppression Pool Cooling, or drywell spray.

  • When directed to spray the drywell per SEP-02 o Ensure Recirc Pumps are tripped o Ensure Drywell Coolers not running o Close E11-F024A(B) o Verify in Safe region of Drywell Spray Initiation Graph o Ensure liB" Loop RHR Pump running o Open E11-F021A(B) o Open E11-F016A(B)
  • When directed, open 7 ADS valves by taking control switches to Open
      • CRITICAL TASK*** When directed, Emergency Depressurize by opening 7 ADS valves.

NOTE: During Emergency Depressurization, coolant swell will cause Reactor Water Level to be out-of-band high

  • Control Injection to establish post depressurization water level 170" to 200"
  • 2007 NRC Examination Scenario #3 47
  • EVENT 13 SRV F TAILPIPE BREAK/EMERGENCY DEPRESSURIZATION REQUIRED APPLICANT'S ACTIONS OR BEHAVIOR:
  • 2007 NRC Examination Scenario #3 48
  • 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

  • 2007 NRC Examination Scenario #3 49
  • ATTACHMENT 1
  1. Title - 2007 NRC Scenario 3
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  • 2007 NRC Examination Scenario #3 50
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