ML12195A090

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2012 Prairie Island Nuclear Generating Plant Initial License Examination Proposed Scenarios
ML12195A090
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 05/22/2012
From: Mcneil D
Operations Branch III
To:
References
50-282/12-301, 50-306/12-301
Download: ML12195A090 (49)
v • d • e


Text

Appendix D Scenario Outline Form ES-D-1 Facility: Prairie Island Scenario No.:1 Op-Test No.: 2012301 Examiners: _D. McNeil_(R. Baker) _______ Operators: _____________________________

_M. Bielby_(D. Oliver) ______ _____________________________

_D. Reeser__________________ _____________________________

Initial Conditions: Power is level near 10%. Negative ITC. The main generator is synched to the grid @ 10 MWe.__________________________________________________________________

Turnover: _The Crew will prepare to perform a power ascension to 15% power and complete the remainder of 1C1.2 actions including transferring from the M to R sources, then raise power to 100%. Turbine overspeed and associated SP will not be performed during this power assention.

The Heater Drain Tank alarms have been authorized to leave flashing.

Event Malf. Event Event No. No. Type* Description 1 R (RO) Raise power to 15%

I (RO) 2 Blue Channel Pressurizer level channel fails high TS (SRO) 3 C (RO) 11 Charging Pump Trips.

I (RO/

4 BOP) N43 Power Range NI Fails Low TS (SRO) 5 M (ALL) Turbine Locks Out Initiating a Loss of All AC Power C (BOP, 6 11 TDAFW Pump Auto Start Failure SRO)

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2012301 Scenario No.: 1 Event No.: 1&2 Page 1 of 9 Event

Description:

Raise power to 15% and Transfer on-site loads from the M to R source._____

Time Position Applicants Actions or Behavior Examiner Note:

Applicants should begin the scenario at step 5.14 in 1C1.2, Unit 1 Startup Procedure, and proceed to the procedures end. The crew will have conducted the necessary briefing on the intended method with which to raise power in the following steps. 1C1.2, Unit 1 Startup Procedure does not provide specific direction as to how to raise reactor power to greater than 15%

SRO

  • Directs and supervises the crews completion of 1C1.2, Unit 1 Startup Procedure.
  • Implements 1C1.4, Unit 1 Power Operation RO/BOP Reactor power above 15%.

Examiner note:

Turbine load should be adjusted using the On Line Control screen, Manual control mode, and 5% increase/decrease (/) control .

Do not proceed to the next event until the P-7 permissive has cleared.

(PRNI > 10%)

RO

  • Perform the following to block the power range low setting high flux trip and intermediate range high flux trip:
  • Turn both power range low setting high flux trip block switches to BLOCK and release:
  • CS-46277, POWER RANGE BLOCK TRAIN A
  • CS-46278, POWER RANGE BLOCK TRAIN B
  • Turn both intermediate range high flux trip block switches to BLOCK and release:
  • CS-46275, INTERMEDIATE RANGE BLOCK TRAIN A
  • CS-46276, INTERMEDIATE RANGE BLOCK TRAIN B
  • Verify the following status lights are LIT:
  • 47014-0402, POWER RANGE LO SETTING TRIP BLOCKED
  • 47014-0302, INTERMEDIATE RANGE BLOCKED

Op-Test No.: 2012301 Scenario No.: 1 Event No.: 1&2 Page 2 of 9 Event

Description:

Raise power to 15% and Transfer on-site loads from the M to R source._____

Time Position Applicants Actions or Behavior RO

  • Verify permissive aqua status lights are NOT LIT:
  • 47014-0304, P-7 LO POWER TRIP BLOCK
  • 47014-0204, P-8 LO POWER LO FLOW TRIP BLOCKED
  • 47014-0104, P-9 REACTOR TRP BLOCKED CUE o When directed by the crew to perform SP 1005A, provide a cue that SP 1005A will be performed within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

o When directed by the crew, rack in the following breakers to the CONNECT position:

  • BKR 11-4, BUS 11 1M XFMR
  • BKR 12-4, BUS 12 1M XFMR
  • BKR 13-9, BUS 13 1M XFMR
  • BKR 14-9, BUS 14 1M XFMR BOP
  • Places EH Control in FSP control mode.

Examiner Note:

The control switch for the bus feeder breakers must be held to CLOSE for 1 second before the breaker will CLOSE. This time delay allows the breaker synch check relaying to operate.

BOP

  • For each non-safeguards bus, CLOSE the 1M Transformer breaker and observe the load transfer on the ammeter, THEN OPEN the corresponding 1R Transformer breaker:
  • Bus 14:
  • CLOSE BKR 14-9, 4.16KV BUS 14 1M XFMR, using CS-46365.
  • OPEN BKR 14-4, 4.16KV BUS 14 1R XFMR, using CS-46361.
  • Bus 13:
  • CLOSE BKR 13-9, 4.16KV BUS 13 1M XFMR, using CS-46364.
  • OPEN BKR 13-1, 4.16KV BUS 13 1R XFMR, using CS-46360.
  • Bus 12:
  • CLOSE BKR 12-4, 4.16KV BUS 12 1M XFMR, using CS-46363.
  • OPEN BKR 12-1, 4.16KV BUS 12 1R XFMR, using CS-46359.

Op-Test No.: 2012301 Scenario No.: 1 Event No.: 1&2 Page 3 of 9 Event

Description:

Raise power to 15% and Transfer on-site loads from the M to R source._____

Time Position Applicants Actions or Behavior BOP

  • Bus 11:
  • CLOSE BKR 11-4, 4.16KV BUS 11 1M XFMR, using CS-46362.
  • OPEN BKR 11-1, 4.16KV BUS 11 1R XFMR, using CS-46358.
  • Transfer the Steam Dump System to TAVG control:
  • Verify CV-31100, CONDENSER STEAM DUMP, valve CLOSED.
  • Turn CS-46338, STEAM DUMP MODE, selector to RESET.
  • Place CS-46338 in TAVG.

Verify 47014-0405, LOSS OF LOAD INTERLOCK aqua status light, is NOT LIT Examiner Note:

At the discretion of the lead examiner, proceed to the next event.

Op-Test No.: 2012301 Scenario No.: 1 Event No.: 3 Page 4 of 9 Event

Description:

Pressurizer level channel 1L-428 (Blue) fails high_______________________

Time Position Applicants Actions or Behavior CUE Annunciator 47012-0307, PRZR HI LVL CHANNEL ALERT Blue status light ON for high Pressurizer level reactor trip Examiner Note:

The RO may take manual control of charging and pressurizer heaters.

RO Identifies the failed LPZR channel, by observing one channel of LPZR off-scale high, with the other two channels slowly lowering, and charging pump speed lowering.

Stops any dilution in progress When directed by the SRO:

  • Control Pressurizer heaters manually.
  • Place charging pump speed control in "MANUAL" AND adjust Pressurizer level to setpoint.
  • Select position "2-1" (WHITE-RED) on PRZR Level Control selector switch.

o Return Pressurizer heaters to "AUTO".

o Return one charging pump speed control to "AUTO".

  • Ensure Pressurizer level recorder not selected to Blue channel.

BOP Places the turbine load ramp on hold. (If applicable.)

ANY Follow the applicable ARPs, which includes guidance to implement 1C51.

SRO Directs the crew to place the ramp on hold.

  • Implements 1C51.3, BLUE BUS (113) INSTRUMENTS FAILURE GUIDE Refers to Tech Specs:
  • Determines LCO 3.3.1 Condition A and Table 3.3.1-1 Function 9, condition K applies.

CUE o If directed as I&C to trip bistables, report that 2 I&C technicians will be available in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. (Note: bistables will not be tripped during this scenario.)

o Acknowledge reports as appropriate for the failure if contacted as Operations Management, and if asked, agree to make other notifications.

Examiner Note:

At the discretion of the lead examiner, proceed to the next event.

Op-Test No.: 2012301 Scenario No.: 1 Event No.: 4 Page 5 of 9 Event

Description:

11 CV Pump trips.__________________________________________________

Time Position Applicants Actions or Behavior CUE Annunciator 47015-0103, 11 CHARGING PUMP TRIP Takes manually control of charging RO Manually Isolate Letdown, as necessary Perform the following as directed by the SRO/ARP:

  • Start another charging pump.
  • If letdown isolation occurred then restore letdown per 1C12.1, LETDOWN, CHARGING AND SEAL WATER INJECTION.
  • Maintain Pressurizer level and seal injection flow.
  • Determine reason for charging pump trip.

1C12.1, LETDOWN, CHARGING AND SEAL WATER INJECTION, BOP Section 5.3 Starting a second charging pump:

  • Verify the discharge desurger, for pump to be started, is pressurized in accordance with Section 5.13.
  • Transfer the inservice charging pump from AUTOMATIC to MANUAL speed control per C7, Reactor Control System.
  • Verify that the speed controller of the charging pump to be started is in MANUAL at minimum speed.
  • Reduce the speed of the inservice charging pump until the seal injection flow drops from eight (8) gpm to approximately six (6) gpm.
  • Verify charging pump discharge header pressure 1PI-133 is less than 2400 psig.
  • For the charging pump to be started, verify the control switch green light is LIT and white light is OFF.
  • Start the second charging pump.
  • Adjust the charging pump speed to maintain charging pump discharge pressure, 1PI-133 less than 2500 psig and approximately eight (8) gpm seal injection.
  • After pressure and flow have stabilized, then simultaneously adjust charging pump speed and 1C-142, CHG LINE FLOW CONT, until:

o Seal Injection flow is approximately eight (8.0) gpm.

o One (1) charging pump is in service at minimum speed, in MANUAL.

Transfer the speed control for the charging pump which is operating at greater than minimum speed from MANUAL to AUTOMATIC per C7, Reactor Control System.

  • Direct RO/BOP actions for starting another charging pump SRO o Implement 1C21.1 as necessary.

o Initiate Work Request as necessary.

o Effect necessary repairs and return system to normal.

Op-Test No.: 2012301 Scenario No.: 1 Event No.: 4 Page 6 of 9 Event

Description:

11 CV Pump trips.__________________________________________________

Time Position Applicants Actions or Behavior Examiners Note:

The 11 CV pump will not be returned to service.

CUE o If directed to investigate 11 Charging pump, after 3 minutes, report that the 11 Charging pump appears intact with no visible damage.

o If directed to log VFD faults, after 3 minutes, report that there is a VFD Overfrequency fault on 11 Charging Pump.

o If directed to verify discharge desurger is pressurized, request that the pump be taken to PTL and after 3 minutes, report that the desurger is pressurized.

o Acknowledge reports as appropriate for the failure if contacted as Operations Management, and if asked, agree to make other notifications.

Examiner Note:

At the discretion of the lead examiner, proceed to the next event.

Op-Test No.: 2012301 Scenario No.: 1 Event No.: 5 Page 7 of 9 Event

Description:

N43 Power Range NI Fails low________________________________________

Time Position Applicants Actions or Behavior CUE Annunciators:

47013-0201, NIS POWER RANGE NEGATIVE FLUX RATE CHANNEL ALERT 47013-0203, NIS POWER RANGE CHANNEL DEVIATION 47013-0303, COMPUTER ALARM DELTA I CHECK TYPER 47013-0403, COMPUTER ALARM FLUX TILT CHECK TYPER Blue status lights on for high flux low setpoints and negative rate reactor trips.

RO

  • Identifies the failed NIS channel, by observing control rods stepping out and N43 meter indication off-scale low with the other three channels slowly rising due to rods stepping out.
  • Places rods in manual upon determining that either there is an instrument malfunction or that the generator load is stable.

Examiner Note:

The crew may elect to implement 1C5 AOP 1, UNCONTROLLED ROD MOTION.

SRO Implements 1C51.3, BLUE BUS (113) INSTRUMENTS FAILURE GUIDE Refers to Tech Specs:

  • Determines LCO 3.3.1 Condition A and Table 3.3.1-1 Function 2a, 2b, 3a, 3b, 6, 16b.1, 16c, 16d, 16e; conditions D, E, Q and R apply.

Directs an operator to remove N43 from service IAW 1C51.3 Notify Nuclear Engineering to perform SP-1120.

BOP Removes N43 from service:

On the MISCELLANEOUS CONTROL AND INDICATION PANEL drawer:

  • Place ROD STOP BYPASS switch in the "N-43" position.
  • Place POWER MISMATCH BYPASS switch in the "N-43" position.
  • Place UPPER SECTION CURRENT COMPARATOR DEFEAT switch in the "N-43" position and verify the Upper Section Channel Defeat Light is LIT.
  • Place LOWER SECTION CURRENT COMPARATOR DEFEAT switch in the "N-43" position and verify the Lower Section Channel Defeat Light is LIT.

Op-Test No.: 2012301 Scenario No.: 1 Event No.: 5 Page 8 of 9 Event

Description:

N43 Power Range NI Fails low________________________________________

Time Position Applicants Actions or Behavior BOP On the COMPARATOR AND RATE drawer:

  • Place COMPARATOR CHANNEL DEFEAT switch in the "N-43" position and verify Comparator Defeat Light is LIT.
  • At N-43 POWER RANGE B drawer, remove, and concurrently verify removal of, the instrument power fuses.
  • At N-43 POWER RANGE A drawer, remove, and concurrently verify removal of, the control power fuses.

Verify the following annunciators are received:

  • 47013-0101, NIS POWER RANGE POSITIVE FLUX RATE CHANNEL ALERT
  • 47013-0102, NIS POWER RANGE HI SETPOINT CHANNEL ALERT
  • 47013-0201, NIS POWER RANGE NEGATIVE FLUX RATE CHANNEL ALERT
  • 47014-0303, N43 NUCLEAR OVERPOWER ROD STOP BYPASSED Aqua Light Verify the following status lights LIT:

44178-0306, PWR RNG LO Q-HI F NC43P 44178-0307, PWR RNG HI Q-HI F NC43R 44205-0304, PWR RNG HI F RATE NC43U/K Trip and concurrently verify the following bistables to remove channel from service (Key Hook No. 82):

IF the Thermal Power Monitor is selected to NIS input, THEN Check if TPM power is equal to the average of the remaining NIS channels.

If not equal, then change TPM "Power Source" input from "NIS" to "Calorimetric" AND notify the computer group.

Restore Tavg equal to Tref using one or two step increments with control RO rods then place rod control to "AUTO".

Verify the NR-45 recorder is selected to an operable channel.

CUE o If directed as I&C to trip bistables, report that 2 I&C technicians will be available in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

o Acknowledge reports as appropriate for the failure if contacted as Operations Management, and if asked, agree to make other notifications.

Examiner Note:

At the discretion of the lead examiner, proceed to the next event.

Op-Test No.: 2012301 Scenario No.: 1 Event No.: 6 Page 9 of 9 Event

Description:

Turbine Trip occurs - Loss of All AC Power (Station Blackout).

Time Position Applicants Actions or Behavior Annunciators:

CUE 47023-0603, SEISMIC MONITORING PANEL EVENT ALARM on the Seismic Monitoring Panel 121SR Examiner Note: Ensure the Reactor has been tripped PRIOR to inserting the SBO.

CREW Determines a reactor trip is warranted SRO Implements 1E-0, REACTOR TRIP OR SAFETY INJECTION RO/BOP Performs the first 3 Immediate action of 1E-0:

  • Verifies the Reactor is tripped
  • Verifies the Turbine is tripped
  • Determines that both Safeguard buses are de-energized SRO Implements 1ECA-0.0, LOSS OF ALL SAFEGUARDS AC POWER Examiner Note: After the SBO has occurred, the 15 EDG will have tripped, and the 16 EDG will be running unloaded. The output breaker failed to close.

Op-Test No.: 2012301 Scenario No.: 1 Event No.: 7 Page 10 of 9 Event

Description:

11 TDAFW Pump auto start failure.

Time Position Applicants Actions or Behavior BOP Starts the 11TDAFW Pump at step 2 RNO, as directed.

Op-Test No.: 2012301 Scenario No.: 1 Event No.: 8 Page 11 of 9 Event

Description:

Bus 16 EDG output breaker fails when operator attempts to close (Bus 15 EDG failed upon loss of power).

Time Position Applicants Actions or Behavior Note: At Step 6.a.2 RNO of 1ECA-0.0, the 16 EDG output breaker will catastrophically fail damaging the bus, but no fire results.

Unit 2 SI Pumps are both off and the corresponding Unit 2 bus (25) is CUE energized.

Examiner Note: The scenario may be terminated after bus 15 is powered from a Unit 2 source, and the crew is ready to transition out of 1ECA-0.0.

Appendix D Scenario Outline Form ES-D-1 Facility: PINGP Units 1 and 2 Scenario No.: 2 Op-Test No.: 2012301 Examiners: D. McNeil (R. Baker) Operators:

M. Bielby (D. Oliver)  :

D. Reeser  :

Initial Conditions: Unit 1 @ ~ 225 MWe BOL, Plant Startup in Progress. Unit 2 @ 100% power, MOL nd Equilibrium Xenon. Repairs and testing complete on 12 MFW pump. 2 Condensate pump is in service.

Turnover: Power is to be reduced < MWe to facilitate a common cause evaluation of the 11 MFP.

Crew will brief power reduction and MFP swapping prior to entering the simulator. Maintain Unit 2 @

100% power. Equipment OOS, Nothing abnormal, only equipment related to plant specific issues.

Event Malf. Event Event No. No. Type* Description R (RO) 1 Reduce power to < 200 MWe N (BOP)

N (SRO) 2 Swap Running MFP (Start 12 MFP and Secure 11 MFP)

N (BOP)

I (RO) 3 12 SG Pressure Transmitter Fails High TS (SRO)

I (RO) 4 Blue Channel Pressurizer Pressure Fails High TS (SRO) 5 M (ALL) 12 SG Tube Rupture ~ 250 gpm C (BOP) 6 12 MSIV Fails to Close C (SRO) 7 C (BOP) SI Pumps Fail to Auto Start 8 C (BOP) 12 MDAFW Pump Fails to Auto Start

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Page 2 of 17 2012 ILT NRC SIMULATOR EVALUATION #2, REV. 0 QUANTITATIVE ATTRIBUTES Malfunctions:

Before EOP Entry:

1. 12 SG Pressure fails high
2. Blue Channel Pressurizer Pressure fails high After EOP Entry:
1. 12 MSIV fails open
2. Both Safety Injection Pumps fail to auto start
3. 12 MDAFWP fails to start automatically Abnormal Events:
1. 12 SG Pressure fails high
2. Blue Channel Pressurizer Pressure fails high Major Transients:
1. 12 SG Tube Rupture Critical Tasks:
1. E F: Establish and maintain 200 GPM AFW flow to the Steam Generator(s) before transition out of E-0, unless the transition is to FR-H.1, in which case the task must be initiated before RCPs are manually tripped in accordance with step 2 of FR-H.1
2. E H: Manually start at least one Safety Injection pump before transition out of E-0.
3. E A: Isolate feedwater flow into and steam flow from the ruptured Steam Generator before a transition to ECA-3.1 occurs.
4. E B: Establish/maintain an RCS temperature so that transition from E-3 does not occur because of the inability to maintain required subcooling or such that an extreme or severe challenge to the Subcriticality and/or the Integrity CSF occurs.
5. E C: Depressurize RCS to meet SI termination criteria prior to overfilling the ruptured Steam Generator.
6. E D: Terminate SI prior to overfilling the ruptured Steam Generator.

Page 3 of 17 2012 ILT NRC SIMULATOR EVALUATION #2, REV. 0 SCENARIO OVERVIEW:

INITIAL CONDITIONS:

1. This scenario can be run from the following Specific IC set:
  • IC-292
2. The following equipment is OOS:
  • 11 TD AFW Pump SEQUENCE OF EVENTS:

Event 1: Reduce turbine load below 200 MW

  • The crew will lower turbine load to ~195 MW per 1C1.4 Event 2: Swap running MFP
  • The crew will start 12 MFP and stop 11 MFP per 1C1.4 and 1C28.2.

Event 3: 12 SG Pressure fails high

  • PT-478, 12 SG Pressure, fails high.
  • The crew will respond per C47 and 1C51 to close and manually control the 12 SG PORV.

Event 4: Blue Channel Pressurizer Pressure fails high

  • PT-431, Blue Channel Pressurizer Pressure, fails high.
  • Both Pressurizer spray valves will fully open and Pressurizer heaters will de-energize.
  • The crew will take manual control of spray valves and close them.
  • The crew will respond per C47 and 1C51.3 to change the controlling pressure channel and restore pressure.

Event 5: 12 SG Tube Rupture

  • A Steam Generator tube leak will begin to ramp in on 12 SG when Blue Channel Pressurizer Pressure is failed high.
  • The crew will respond to a Train B radiation alarm and perform 1C4 AOP2
  • The Tube Leak will grow to an ~250 GPM Tube rupture.
  • The crew will respond per 1E-0 and 1E-3 to trip the reactor and initiate safety injection.

Event 6: 12 MSIV fails open

  • During isolations in 1E-3 the 12 MSIV will NOT close.
  • The crew will respond per 1E-3 Attachment B to isolate the 12 SG.

Page 4 of 17 2012 ILT NRC SIMULATOR EVALUATION #2, REV. 0 Event 7: Both Safety Injection pumps fail to auto start

  • When Safety Injection is initiated, either manually or automatically, the 11 and 12 SI pumps will not start on the S signal.
  • The crew will respond per 1E-0 Attachment L to start the pumps manually.

Event 8: 12 MDAFWP fails to auto start

  • 12 MDAFWP fails to start automatically.
  • The crew will respond per 1E-0 to start 12 MDAFWP.

Page 5 of 17 Appendix D Required Operator Actions Form ES-D-2 SCENARIO TIME-LINE:

SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS INITIAL CONDITIONS (IC): SRO

  • If IC-292 is not available:
  • IC-292 o Reset to IC-8.
  • Mode: 1 BOP o Reduce Turbine load to 225.
  • Exposure: BOC o ~8 rod steps in and 20 gal Boration.
  • Power: 42.5% ATC
  • Boron: (CB): 1415 ppm
  • Temperature: ~552°F
  • Pressure: ~2235 psig
  • Xenon: Building In
  • Rods: D @ 170
  • Generator: ~225 MW
1. SIMULATOR SET UP
a. Set up the simulator to IC-292.
b. PRIOR TO PLACING THE SIMULATOR TO RUN, verify the FRV Patch.sch file is open and running.
c. Enter the malfunctions, remotes, and overrides, as specified by the "Simulator Input Summary."
d. Complete the "Simulator Setup Checklist.
2. Simulator Pre-brief:
a. The Simulator Pre-Brief is conducted prior to the crew entering the simulator.
1) Inform the crew that power is to be lowered to 195 Mw to swap MFPs.
2) Provide the crew a marked up copy of 1C1.4 marked up to Step 5.2.11 and 1C28.2 Section 5.7 Swapping FWPs marked up for performance.

a) Inform crew there are no fuel conditioning requirements.

b) Inform crew to lower Turbine load to 195 Mw at 0.5%/minute with rods in MANUAL with Turbine in AUTO in LOAD mode.

c) Inform the Crew to swap 12 and 11 MFPs.

3) Provide the crew a reactivity plan developed by the off going RO for the power reduction from current power to 195 Mw.
4) Inform the crew to verify the reactivity plan developed by the off going reactor operator.
5) Inform the crew that Nuclear Engineering was not available to provide a reactivity prediction.
b. An SRO candidate will perform a pre-job brief for the performance of 1C1.4 and 1C28.2 Section 5.7.

Page 6 of 17 Appendix D Required Operator Actions Form ES-D-2 SCENARIO TIME-LINE:

SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS

3. COMPLETE TURNOVER: CREW Review the following with the off-going operator:
a. UNIT 1 LPEO / PEO TURNOVER LOG.
  • Unit 1 LPEO / PEO Turnover Log
b. PRA Printout.
c. Verify crew performs walk down of control boards
  • Walk-down the control boards and ask questi and the reviews turnover checklists. appropriate

Page 7 of 17 Appendix D Required Operator Actions Form ES-D-2 SCENARIO TIME-LINE:

SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS

4. When the crew has assumed the duty, and at the BOP 1C1.4, Unit 1 Power Operation, discretion of the lead evaluator, allow the crew to Section 5.2, step 5.2.6.

reduce turbine load to ~195 MW. ATC

  • Notify Duty Chemist of the load decrease
a. When contacted, as Duty Chemist, acknowledge
  • Turn ON all pressurizer heaters SRO load change.
  • Increase letdown flow if desired (80 gpm letdo will already be established, no actions will be
  • If desired, THEN transfer Heating System to U to heating boiler (No actions will be needed si power reduction is only to 90%)
  • If desired, THEN place CS-46280, ROD BANK SELECTOR, in MANUAL. Refer to precaution
  • Start the load decrease as follows:

o Using the On Line Control screen, select desired Control Mode (VPC,FSP or LOAD o Using the On Line Control screen, select desired rate.

o Set the desired Target setting using the T increase/decrease controls using the On Control screen.

o Initiate a negative reactivity addition by us control rods or boration of the RCS per C1 o WHEN Tave shows a decrease, THEN se on the On Line Control screen to initiate decrease.

o Vary the boration rate or batch borate as necessary to maintain Tave and Tref withi desired +/- 1.5°F band.

  • To suspend the load decrease, perform the fo o Select Hold on the On Line Control scr o Stop the boration per C12.5, if necessary o If reduced power steady state operation is anticipated, THEN, change ERCS TPM Po
4. Turbine Load reduction to ~195 MW cont Source from NIS to calorimetric (LEFM pre source) when steady state conditions are o Place CS-46300, MAKE-UP MODE SELE in AUTO.

o Momentarily turn CS-46457, BORIC ACID UP CONTROL, to START.

o Verify CS-46280, ROD BANK SELECTOR returned to AUTO.

Page 8 of 17 Appendix D Required Operator Actions Form ES-D-2 SCENARIO TIME-LINE:

SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS

5. When the crew has reduced turbine load below 195 MW BOP 1C28.2 UNIT 1 FEEDWATER SYSTEM and returned Rod Control to automatic, and/ or at the 5.7 Swapping FWPs discretion of the Lead Evaluator, direct the crew to ATC
  • Reduce turbine load to approximately 200 MW proceed with swap of 12 and 11 MFP, if necessary.
  • Verify two (2) condensate pumps are running SRO
a. When contacted to perform Turbine building actions second condensate pump per 1C28.3.

for starting 12 MFP perform the following:

  • Verify the FWP warmup line for the pump to b
1) Follow along in 1C28.2 Step 5.7 and report is OPEN:

actions complete after 2 minutes for o F-22-4, 12 FW PMP WARMUP LINE unmodeled actions.

2) The following outplant actions are modeled on o 47010-0501, 11 FEEDWATER PUMP SEA the simulator: WATER LO PRESS.

a) When directed to unblock 12 MFP Recirc o 47010-0503, 12 FEEDWATER PUMP SEA valve, CV-31875, 12 FW PMP Recirc, wait WATER LO PRESS.

3 minutes and enter the remotes to o 47010-0101, 11 FEEDWATER PUMP LOC unblock CV-31875 (Relative Order 1a, OUT.

Event Trigger 10) and report completion. o 47010-0103, 12 FEEDWATER PUMP LOC b) When directed to close F-22-4 and open OUT.

F-22-3 wait 3 minutes enter remotes to

  • Verify oil levels in 12 FWP motor are approxim align the warm-up lines (Relative Order 1/4 to 1/2 sight glass.

1b, Event Trigger 1) and report

  • Place the computer points, listed in Attachmen completion. trend, Operations Group Display:
3) When asked to report Combined AFW flow as o OP6 for 12 FWP indicated on FI-26601, wait 1 minute, and
  • Verify the following:

report combined AFW flow as observed on NOTE: 1T2821A on 12 FWP should approximate ERCS screen FW1 in the booth. 1T2826A and 1T2827A.

o The difference between 1T2826A and 1T2 12 FWP is less than 40°F.

o 1P2449A 11/12 FW PMPS SUCT HDR P, approximately 400 psig.

  • IF the FWP recirc valve is blocked OPEN, TH restore it to normal as follows:

o CLOSE the vent on the bottom of the strai

5. Swap 11 and 12 MFPs continued. the desired recirc valve (located just down of the air isolation valve).

CV-31875, 12 FW PMP RECIRC, Air S Vent o OPEN the air isolation valve to the desired valve:

CV-31875 A/S, 12 FW PMP RECIRC C 31875 AIR SPLY VLV o Attach block to the air isolation valve for th desired recirc valve:

CV-31875 A/S, 12 FW PMP RECIRC C 31875 AIR SPLY VLV o Rotate the desired FW pump recirc valve b device handwheel COUNTER-CLOCKWIS

Page 9 of 17 Appendix D Required Operator Actions Form ES-D-2 SCENARIO TIME-LINE:

SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS the blocking device is fully backed off:

CV-31875, 12 FW PMP RECIRC, Bloc Device NOTE: Feedwater pump suction pressure and Condensate System flow should be closely monito during performance of the following steps.

  • OPEN the recirc valve on the running FWP:

o CS-46416, 11 FWP RECIRC CV-31874 NOTE: The recirc valve on the pump to be started open until the FW Pump switch is placed in the S position.

  • Place the recirc valve control switch for the pu started to the OPEN position:

o CS-46417, 12 FWP RECIRC CV-31875 NOTE: Bearing temperatures rise quickly and the stabilize within the following limits:

5. Swap 11 and 12 MFPs continued.
  • Pump journal bearing temperatures 130-180°F Maximum of 220°F.
  • Pump thrust bearing temperatures 130-180°F Maximum of 200°F.
  • Motor sleeve bearing temperatures 130-180°F Maximum of 194°F.

Continuously rising bearing temperatures or an ab temperature rise is an indication of a condition req immediate remedial action to prevent serious dam

  • Start the second FWP.

o CS-46419, 12 FW PMP

  • Stop the first running FWP.

o CS-46418, 11 FW PMP

  • CLOSE the in-service FWP warm up line:

o F-22-4, 12 FW PMP WARMUP LINE

  • OPEN the FWP warmup valve for the stopped pump:

o F-22-3, 11 FW PMP WARMUP LINE

  • Check vibration on Vibration Monitoring Panel the running FWP, step-up gear, and motor wit requirements of Limitation 4.5.
  • Increase plant load until the second FWP disc flow is steady and exceeds 5000 gpm as indic locally near 15A FW Heater.

o FI-26601, 12 FW PMP DISCH FI

  • Place the second FWP recirc valve in AUTO o CS-46417, 12 FWP RECIRC VLV
  • Stop the second condensate pump per 1C28.

Page 10 of 17 Appendix D Required Operator Actions Form ES-D-2 SCENARIO TIME-LINE:

SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS required.

Page 11 of 17 Appendix D Required Operator Actions Form ES-D-2 SCENARIO TIME-LINE:

SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS

6. When the crew has reduced turbine load below 200 MW BOP Note: Per rules of usage, reference use ac and returned Rod Control to automatic, and/or at the may be used prior to consulting procedure discretion of the Lead Evaluator, enter the malfunction ATC follows:

to fail 12 SG pressure high. (Relative Order 3, Trigger

a. If directed as I&C to trip bistables, report that 2 I&C Note: If 1C5 AOP1 is entered it should be exite technicians will be available in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (Note: step 1 bistables will not be tripped during this scenario.) 47011-0405. FW CONTROL SYSTEM TROUBLE
b. If contacted as Operations Management,
  • Verify Steam Generator Level Control operatin acknowledge the report of the failure, and if asked properly in automatic agree to make other notifications to the NRC
  • Control level in manual for any Steam Genera Resident Inspector, Duty Station Manager.

which has shifted to manual

c. If contacted as the FIN team supervisor, inform the
  • Refer to 1C51, Instrument Failure Guide crew that you will write a work order and assign an I&C supervisor to investigate.

1C51.3 12 STEAM GENERATOR PRESSURE 1P

d. If desired, allow the crew to hold a crew brief.

HIGH

  • Take manual control of 12 SG PORV and ens valve is closed
  • Verify SG Level Control operating properly in automatic
  • Refer to T.S. LCO 3.3.2 Condition A and Tabl Function 1e

Page 12 of 17 Appendix D Required Operator Actions Form ES-D-2 SCENARIO TIME-LINE:

SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS

7. When the crew has recovered SG pressure control, BOP Note: Per rules of usage reference use act and/or at the discretion of the Lead Evaluator, enter the may be used prior to consulting procedure malfunction to fail PT-431, Blue Channel Pressurizer ATC follows:

Pressure high. (Relative Order 4, Trigger 4)

  • Manual Control of Pressurizer Spray Valve SRO
a. If directed as I&C to trip bistables, report that 2 I&C technicians will be available in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (Note: 47012-0508 PRZR HI/LO PRESS bistables will not be tripped during this
  • Check pressure high or low.

scenario.)

  • If high, then perform the following actions:
b. If contacted as Operations Management, o Verify both pressurizer sprays are OPEN.

acknowledge the report of the failure, and if asked o Verify all pressurizer heaters are OFF.

agree to make other notifications to the NRC

  • If necessary then control pressure in manual.

Resident Inspector, Duty Station Manager.

c. If contacted as the FIN team supervisor, inform the
  • If due to channel failure, then refer to 1C51, crew that you will write a work order and assign an INSTRUMENT FAILURE GUIDE - UNIT 1.

I&C supervisor to investigate.

d. If desired, allow the crew to hold a crew brief. C51.3 Pressurizer Pressure 1P-431 High
  • Place Pressurizer Pressure Controller in MAN NOTE: If not diagnosed and responded to quickly stabilize pressure.

enough this failure will result in a Reactor Trip and,

  • Select position 2-1 (WHITE-RED) on channe potentially, a Safety Injection. If this should occur selector switch.

proceed immediately to Event 5 where the SGTR will be

  • When pressure returned to normal with no dev diagnosed during performance of 1E-0 or 1ES-0.1. from setpoint, then return pressure control to automatic.

NOTE: The SGTR take ~1.5 Minutes to generate an

  • Verify Pressurizer Pressure Recorder not sele alarm. Enter the trigger accordingly. Blue channel.
  • Refer to the following Technical Specifications o T.S. LCO 3.3.1 Condition A & Table 3.3.1-Functions 6, 8a, 8b.

o T.S. LCO 3.3.2 Condition A & Table 3.3.2-Function 1d.

o T.S. LCO 3.4.1.a

  • Trip bistables.

Page 13 of 17 Appendix D Required Operator Actions Form ES-D-2 SCENARIO TIME-LINE:

SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS

8. When the crew has recovered Pressurizer pressure BOP C47022-0108, HI RADIATION TRAIN B PANEL ALAR control, and/or at the discretion of the Lead Evaluator,
  • Determine the initiating alarm and respond to the a enter the malfunction to cause a SGTR on 12 SG which ATC specified in C47048, TRAIN B RADIATION MONIT will ramp in over the next 15 minutes. (Relative Order SYSTEM ALARM RESPONSE PROCEDURES.

SRO

  • If malfunction of radiation monitor N/A 5, Trigger 5)
a. If directed to perform cation column frisks acknowledge the order and, after 1 minute, report C47048: 1R-15 12 Steam Generator cation column has elevated
  • If primary-to-secondary leakage is confirmed by sa other indication, then:

activity, 11 Steam Generator cation column is o Enter 1C4 AOP2, STEAM GENERATOR TUB reading background. -AND-

b. If asked to take primary or secondary samples per o Turn on all turbine building roof exhausters.

RPIP 4503, state that the samples are in progress.

  • If radiation monitor malfunctioned N/A
c. If contacted as Operations Management,
  • Refer to T.S. 3.7.14, and T.S. 3.4.14 acknowledge the report of the failure, and if asked agree to make other notifications to the NRC 1C4 AOP2, STEAM GENERATOR TUBE LEAK Resident Inspector, Duty Station Manager.
  • IF at any time RCS inventory can not be maintaine
d. If directed to turn on all turbine building roof available charging flow, THEN perform the followin exhausters, wait 3 minutes and report all turbine o Manually trip the reactor - enter 1E-O, Reactor building roof exhausters are running. Safety Injection.

o WHEN reactor is verified tripped, THEN initiate Injection.

o Exit this procedure

  • Continuously monitor 1R15 and 1R19 in the Contr for further increase.
  • If the only indication of a SG tube leak is a radioch analysis greater than 5 GPD N/A
  • Notify the Operations Manager of the following:

o Entry into this AOP per SWI O-28.

o To determine if additional training on SG tube rupture is desired.

  • Notify NRC Resident Inspector of entry into this AO SWI O-28.
  • Perform the following steps while continuing on in
8. Response to Tube Leak continued. procedure:

o Direct the duty chemist to:

Perform RPIP 4503.

Repeat Radiochemistry analysis

  • At least every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
  • Whenever a 50% increase in count ra
e. When directed to perform sampling required in 1C4 occurs.

AOP2 agree to perform samples and inform the

  • Whenever process flows are changed control room the samples are being drawn. After 3 Inform the Control Room when each SG s minutes report 12 SG Cation frisk had elevated drawn.

Inform the Control room when the leaking counts and 11 SG Cation frisk read background.

identified (11 or 12 SG)...

o When the duty chemist reports sample time o Stop Steam generator blowdown to the river u approval for release is given by Radiation Prot

Page 14 of 17 Appendix D Required Operator Actions Form ES-D-2 SCENARIO TIME-LINE:

SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS and Chemistry Manager.

o Continuously monitor rate of change and GPD on ERCS using Tabular Display\Load Group\SGLeak_U1.

o Determine the appropriate Procedure Section.

Page 15 of 17 Appendix D Required Operator Actions Form ES-D-2 SCENARIO TIME-LINE:

SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS

9. When the crew has determined tube leakage exceeds BOP 1E-0, REACTOR TRIP OR SAFETY INJECTION the available charging they will perform a reactor trip

and initiate Safety Injection per 1C4 AOP2. ATC

a. Upon hearing the announcement of reactor trip, or
  • Verify both safeguards buses energized.

SRO when called as Turbine Building Operator to isolate

  • Check if SI is actuated.

the Unit 1 MSRs per Attachment J, then enter

  • Perform Attachment L.

Relative Order 7 (Schedule file E-0_Att-J.sch). Critical Task: Manually actuate at least one train o

b. When called as the Turbine Building Operator to actuated safeguards equipment before transition o verify the status of Turbine Building Roof 0.

Exhausters, report that the Turbine Building Roof

  • Check AFW Status.

Exhausters are all secured. Critical Task: Establish and maintain 200 GPM AFW

c. When directed to perform sampling after 3 minutes the Steam Generator(s) before transition out of E-0 report 12 SG Cation frisk had elevated counts and the transition is to FR-H.1, in which case the task m 11 SG Cation frisk read background. initiated before RCPs are manually tripped in accor with step 2 of FR-H.1.
  • Verify total AFW flow greater than 200 gpm.
  • Verify AFW pumps discharge pressure greater tha psig.
  • Check NR SG levels greater than 5% in any SG.
  • Maintain NR SG level between 5% and 50%.
  • Check RCS temperatures stable at or trending to 5
  • Check PRZR PORVS and Spray Valves closed
  • Check if RCPs should be stopped.
  • Check if SGs are not faulted.
  • Check if SG tubes are not ruptured.

o Transition to 1E-3.

1E-3, STEAM GENERATOR TUBE RUPTURE

  • Check if RCPs should be stopped.
  • Identify Ruptured SG.
9. Response to Steam Generator Tube Rupture
  • Isolate flow from ruptured SG.

continued. o Set ruptured SG PORV in auto at 75%

o Check Ruptured SG PORV - CLOSED o Close steam supply from ruptured to 11 TDAF o Verify Ruptured SG blowdown isolated.

o Close Ruptured SG MSIV. ->RNO Close 11 MSIV.

Set 11 SG PORV to 71.8%.

Place Steam Dumps to off.

Critical Task: Isolate feedwater flow into and steam from the ruptured Steam Generator before a transit ECA-3.1 occurs.

Perform ATT B while continuing in 1E-3.

Attachment B actions are listed below)

  • Check ruptured SG level.

Page 16 of 17 Appendix D Required Operator Actions Form ES-D-2 SCENARIO TIME-LINE:

SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS

  • Check ruptured SG pressure - Greater than 210 p Critical Task: Establish/maintain an RCS temperatu that transition from E-3 does not occur because of inability to maintain required subcooling or such th extreme or severe challenge to the Subcriticality an Integrity CSF occurs.
  • Initiate RCS Cooldown Note: During the cooldown, the SS must continue w 8 to prepare the plant for depressurization.
  • Check intact SG level
  • Check PRZR PORVs and Block Valves
  • Reset Containment Isolation
  • Establish Instrument Air to containment
  • Check if RHR pumps should be stopped
  • Establish Charging flow
  • Check if RCS Cooldown should be stopped
9. Response to Steam Generator Tube Rupture
  • Check Ruptured SG pressure - Stable or increasin continued.
  • Check RCS subcooling based on core exit T/Cs -

than 40°F Critical Task: Depressurize RCS to meet SI termina criteria prior to overfilling the ruptured Steam Gene

  • Depressurize RCS to minimize break flow and refil
  • Check if SI flow should be terminated Critical Task: Terminate SI prior to overfilling the ru Steam Generator.
  • Stop SI pumps
  • Establish Charging flow
  • Verify SI flow not required 1E-3 Attachment B, Main Steamline Isolation
  • Dispatch personnel to locally close cylinder heating valves (CY-1-1 and CY-1-4)
  • Dispatch personnel to locally close air ejector suct (AR-5-1 and AR-5-2)
  • Verify turbine stop valves - CLOSED

Page 17 of 17 Appendix D Required Operator Actions Form ES-D-2 SCENARIO TIME-LINE:

SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS

  • Verify MSR steam isolation valves - CLOSED:

o CV-31096 o CV-31097 o CV-31094

9. Response to Steam Generator Tube Rupture o CV-31095 continued.
  • WHEN air ejector suction valves are closed, THEN
d. When directed to perform local actions of 1E-3 normal and secondary air ejector steam supply val 32327 and MV-32355)

Attachment B, Main Steamline Isolation, follow along with the procedure and after 2 minutes report

  • Verify standby air ejector suction valves (MV-3234 MV-32347) - CLOSED completion of directed step(s).
  • Verify standby air ejector steam supply valves (MV CLOSED
  • Verify 11 and 12 hogging jet suction valves (MV-32 MV-32309) - CLOSED
  • Verify 11 and 12 hogging jet steam supply valves (

32316 and MV-32317) - CLOSED

  • Verify steam dumps selected to OFF
  • Evaluate the need to transfer gland steam to heati
10. When SI has been verified to not be required and has been terminated and/or at the discretion of the Lead Evaluator, place the simulator in FREEZE.

Emergency Plan Classification - Classify the event per F3-2 SM Classify the event as follows:

a. The SM may delegate ED duties to the Unit 2 SS if
  • Alert - EAL FA1 declared a Unit 2 SS is participating as part of the crew

Appendix D Scenario Outline Form-ES-D-1 Facility: Prairie Island Scenario No.: 3 Op-Test No.: 2012301 Examiners: _D. McNeil__(R. Baker)___________ Operators: _____________________________

_M. Bielby__(D. Oliver)___________ _____________________________

_D. Reeser____________________ _____________________________

Initial Conditions: 93% Power and stable_________________________________________________

Turnover: _TSO is waiting to direct a reduction to 90% power. When directed, the crew is expected to reduce power to ~ 90% power and then perform a condensate pump swap.

Event Malf. Event Event No. No. Type* Description I (RO) 1 Tcold Instrument Fails High TS (SRO)

R (RO) 2 Restore Tave to Tref (Power reduction per TSO)

N (BOP) 3 N (BOP) Swap Condensate Pumps C (RO) 4 Pressurizer PORV significant leakage PCV-431C TS (SRO) 5 C (BOP) 12 Condensate Pump Trip - 11 Condensate Pump Locks Out 6 C (RO) Reactor Fails to Auto Trip 7 M (ALL) Main Feedwater Line Break Inside Containment 8 C (BOP) A Train Safeguards Equipment Fails to Auto Actuate

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Page 2 of 20 2012 ILT NRC SIMULATOR EVALUATION #3, REV. 0 Guide Requirements During all plant operating conditions, the crew will demonstrate the ability to monitor and operate the plant within the limits of the Operations Manuals and Technical Specifications.

Goal of Training: When presented with various scenario events, the crew will demonstrate the ability to respond to the events using appropriate operating and administrative procedures to return the plant to stable conditions.

1. During all plant operating conditions, demonstrate the ability to perform communications, verification practices (STAR and peer checks), procedure use, alarm response, reactivity control, and crew briefs in accordance with Operations Standards and Expectations.
2. Diagnose and perform corrective actions for Tcold instrument failing high per 1C5 AOP1, C47 and 1C51.3.
3. Restore Tavg to Tref following inadvertent rod movement per 1C51.3.

Learning 4. Diagnose and perform corrective actions for Pressurizer PORV Objectives: leakage per C47 and 1C4 AOP1.

5. Perform power reduction to ~90% power per 1C1.4.
6. Swap running condensate pumps per 1C28.3.
7. Diagnose and perform corrective actions for Main Feedwater break inside containment per 1E-0, 1E-2 and 1E-1.
8. Diagnose and perform corrective actions for failure of the Reactor to trip automatically when required per 1E-0.
9. Diagnose and perform corrective actions for A Train Safeguards equipment failing to actuate per 1E-0.
10. Apply Technical Specifications to specific scenario events.

Prerequisites: None

1. Full Scope Simulator Training 2. Lead Evaluator Resources: 3. Booth Operator (Primary communicator)
4. Backup Communicator
1. 1C4 AOP1
2. 1C5 AOP1
3. 1C28.3
4. C47

References:

5. 1C51.3
6. 1E-0
7. 1E-1
8. Tech Specs Commitments: None

Page 3 of 20 2012 ILT NRC SIMULATOR EVALUATION #3, REV. 0 Evaluation This is an evaluation scenario.

Method:

Operating None - This is an evaluation scenario.

Experience:

Initiating Event with Core Damage Frequency:

LOSS OF MAIN FEEDWATER (4%)

Related PRA Important Components:

Information: REACTOR PROTECTION Important Operator Actions with Task Number:

None

Page 4 of 20 2012 ILT NRC SIMULATOR EVALUATION #3, REV. 0 TASKS ASSOCIATED WITH SIMULATOR EXERCISE(S):

None. This is an evaluation scenario and no credit will be taken for tasks performed.

GENERAL EXPECTATIONS Over the duration of the scenario, monitor

  • Communications crew performance for adherence to the
  • Verification Practices (STAR and Peer conduct of operations standards and Checks)

Operations department Standards and

  • Procedure Use Expectations:
  • Alarm Response
  • Reactivity Control
  • Crew Briefs Performance for adherence to
  • Reportability of the malfunction or event administrative procedural requirements
  • Notifications to the Operations Manager and operations management and NRC Resident Inspector per SWI-O-expectations: 28
  • Notification to the Duty Station Manager per operations management request
  • Tech Spec implementation; interpretation; and documentation of decision made, actions taken, and the basis for decisions made and actions taken

Page 5 of 20 2012 ILT NRC SIMULATOR EVALUATION #3, REV. 0 QUANTITATIVE ATTRIBUTES Malfunctions:

Before EOP Entry:

1. Tcold fails high
2. Leaking Pressurizer PORV PCV-431C
3. 12 Condensate pump trips/11 Condensate pump locks out
4. Reactor fails to trip automatically After EOP Entry:
1. Main Feedwater line break inside containment
2. A Train safeguards equipment fails to auto actuate Abnormal Events:
1. Tcold fails high
2. Leaking Pressurizer PORV PCV-431C
3. 12 Condensate pump trips/11 Condensate pump locks out Major Transients:
1. Main Feedwater line break inside containment Critical Tasks:
1. E A: Manually trip the reactor from the control room before transition out of E-0.
2. E A: Isolate the faulted STEAM GENERATOR before transition out of E-2.

Page 6 of 20 2012 ILT NRC SIMULATOR EVALUATION #3, REV. 0 SCENARIO OVERVIEW:

INITIAL CONDITIONS:

1. This scenario can be run from the following Specific IC sets:
  • IC-293
2. The following equipment is OOS:
  • None SEQUENCE OF EVENTS:

Event 1: Tcold instrument fails high

  • Tcold instrument fails high causing auctioneered Tavg to indicate high.
  • Charging pump speed rises.
  • The crew will respond per 1C5 AOP1, C47 and 1C51 to defeat the failed channel and restore Rod Control to automatic.

Event 2: Restore Tavg to Tref and/or Power Reduction to 90% power

  • The crew will reduce power per 1C1.4.

Event 3: Swap Condensate pumps

  • The crew will receive a report from the condensate system engineer of abnormal noise on the 11 condensate pump and recommendation to remove it from service.
  • The crew will start 13 condensate pump and place 11 condensate pump in standby per 1C28.3.

Event 4: Leaking Pressurizer PORV PCV-431C

  • A small leak will develop on Pressurizer PORV PCV-431.
  • The crew will respond per C47 and 1C4 AOP1 to identify and isolate the leaking PORV.

Event 5: 12 Condensate pump trips and 11 Condensate pump locks out

  • 12 Condensate pump will trip.
  • 11 Condensate pump will restart, if in standby, but immediately lockout.
  • 11 MFP will trip in response to loss of 12 Condensate pump.
  • A first out will be generated on low low SG level if the reactor is not manually tripped earlier.
  • The crew will respond per C47 and 1E-0, to manually trip the reactor.

Event 6: Reactor Fails to automatically trip

  • The reactor will not trip automatically.
  • The crew will respond per 1E-0 to manually trip the reactor.

Page 7 of 20 2012 ILT NRC SIMULATOR EVALUATION #3, REV. 0 Event 7: Main Feedwater line break inside containment

  • The crew will respond per 1E-2 to isolate the faulted SG.

Event 8: A Train safeguards equipment fails to auto actuate

  • A train safeguards equipment will fail to actuate automatically.
  • The crew will respond per 1E-0 to manually actuate the A Train safeguards equipment using the control switch in the control room.

Page 8 of 20 Appendix D Required Operator Actions Form ES-D-2 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS INITIAL CONDITIONS (IC): SRO

  • If IC-293 is not available:
  • IC-293 o Reset to IC-10.
  • Mode: 1 BOP o Reduce power to 530 Mw.
  • Exposure: MOC o ~18 rod steps in and 15 gal Boration.
  • Power: ~91.7% ATC
  • Boron: (CB): 638 ppm
  • Temperature: ~ 559°F
  • Pressure: ~2235 psig
  • Xenon: Building in
  • Rods: D @ 200
  • Generator: 530
1. SIMULATOR SET UP
a. Set up the simulator to IC-293.
b. Enter the malfunctions, remotes, and overrides, as specified by the "Simulator Input Summary."
c. Complete the "Simulator Setup Checklist.

Page 9 of 20 Appendix D Required Operator Actions Form ES-D-2 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS

2. Simulator Pre-brief:
a. The Simulator Pre-Brief is conducted prior to the crew entering the simulator.
1) Inform the crew that power is to be lowered to 90% upon TSO request due to grid loading.
2) Provide the crew a marked up copy of 1C1.4 Section 5.3 marked up for performance.

a) Inform the crew there are no fuel conditioning requirements.

b) Inform crew to lower Reactor Power to 90% at 0.5%/minute with rods in MANUAL with Turbine in AUTO in FSP mode.

3) Provide the crew a reactivity plan developed by the off going RO for the power reduction from current power to 195 Mw.
4) Inform the crew to verify the reactivity plan developed by the off going reactor operator.
5) Inform the crew that Nuclear Engineering was not available to provide a reactivity prediction.
b. An SRO candidate will perform a pre-job brief for the performance of 1C1.4 Section 5.3.
3. COMPLETE TURNOVER: CREW Review the following with the off-going operator:
a. UNIT 1 LPEO / PEO TURNOVER LOG.
  • Unit 1 LPEO / PEO Turnover Log
b. PRA Printout.
c. Verify crew performs walk down of control boards
  • Walk-down the control boards and ask questions as and the reviews turnover checklists. appropriate

Page 10 of 20 Appendix D Required Operator Actions Form ES-D-2 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENT 1 4. When the crew has assumed the duty, and at the BOP Note: Per rules of usage reference use actions

&2 discretion of the lead evaluator, enter the malfunction to may be used prior to consulting procedure as cause the Blue Channel Tcold to fail high. (Relative ATC follows:

Order 1, Trigger 1)

  • Place Rod Control in manual SRO
a. If directed as I&C to trip bistables, report that 2 I&C
  • Manually control Charging technicians will be available in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. (Note:

bistables will not be tripped during this 1C5 AOP1, UNCONTROLLED ROD MOTION scenario.)

  • Check Generator Electrical Load - STABLE
b. If contacted as Operations Management,
  • Place Rod Bank Selector Switch to MANUAL acknowledge the report of the failure, and if asked agree to make other notifications to the NRC
  • Check Rod Motion - STOPPED Resident Inspector, Duty Station Manager.
  • Check for Failed Instrument:
c. If contacted as the FIN team supervisor, inform the o NIS power range channels - ALL IN AGREEMENT crew that you will write a work order and assign an o RCS loop Tavg channels - ALL IN AGREEMENT I&C supervisor to investigate. o Turbine impulse pressure 1PT-485 - NORMAL
d. If desired, allow the crew to hold a crew brief. FOR POWER
  • If due to an instrument malfunction:

o Place rod control in manual and adjust as needed o Shift charging pumps to manual and adjust as needed o Verify steam dumps not armed o Refer to 1C51 1C51.3, TAVG LOOP 1B 1T-403 - HIGH

  • Place rod control in manual and maintain Tavg
  • Place charging pump speed in manual and maintain pressurizer level
  • If necessary, take manual control of steam dumps

Page 11 of 20 Appendix D Required Operator Actions Form ES-D-2 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENT 1 4. Response to TAVG failing high continued.

  • Select blue channel on the Tavg defeat switch and pull

&2 out cont

  • Return the following to auto:

o Rod control o Charging pump speed control o Steam dumps

  • Refer to T.S:

o LCO 3.3.1 condition A, table 3.3.1-1 function 6, 7 o LCO 3.3.2 condition A, table 3.3.2-1 function 4d o TRM TLCO 3.3.3 condition A

  • Trip bistables

Page 12 of 20 Appendix D Required Operator Actions Form ES-D-2 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENT 2 5. When the crew has restored Tave to Tref, and/or at the BOP 1C1.4 UNIT 1 POWER OPERATION discretion of the Lead Evaluator, deliver the direction for 5.3 Small Turbine Load Adjustment the crew to reduce power to 90%. ATC NOTE: IF the load change will be performed in conjunction

a. When directed by the Lead Evaluator contact the with rod movement and/or boron concentration change, SRO THEN 1C5 and/or C12.5 will also be used.

control room as the TSO and direct power reduction to 90% power.

  • Verify Pre-Job Brief completed, as necessary.
b. When contacted, as Duty Chemist, acknowledge
  • Notify the Duty Chemist of the load change.

load change.

  • IF desired, THEN place CS-46280, ROD BANK SELECTOR, in MANUAL. Refer to Precaution 3.7.
  • Start the load change as follows:

Note: This event only needs to be performed if, in o Using the On Line Control screen, select the the opinion of the Lead Evaluator, adequate desired Control Mode (VPC, FSP, or LOAD).

performance of reactivity manipulations has not o Using the On Line Control screen, select the been observed for the ATC operator. desired demand rate.

o Verify the VPL control is not Red. IF the VPL control is Red, THEN using the On Line Control screen, lower the Target setting to a value slightly less than the Actual value using the decrease () control.

o Select the Go control to initiate the load decrease. Continue to reduce load until the VPL control is no longer Red.

o Raise the VPL as necessary using the Valve Limiter pop-up screen.

o Set the Target setting to the desired load by using the On Line Control screen Target increase/decrease (/) controls.

o Select the Go control using the On Line Control screen.

o To suspend the load change, select turbine control Hold on the On Line Control screen.

5. Power reduction continued. o Verify the load change stops when desired load is

Page 13 of 20 Appendix D Required Operator Actions Form ES-D-2 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENT 2 obtained.

cont o Lower the VPL until the Valve Position Limit signal is at or close to the Current Valve Demand signal. This will prevent unexpected turbine load increases due to grid transients.

o Verify CS-46280, ROD BANK SELECTOR, in AUTO

Page 14 of 20 Appendix D Required Operator Actions Form ES-D-2 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENT 3 6. When the crew has restored Tavg to Tref, and/or at the BOP 1C28.3, UNIT 1 CONDENSATE SYSTEM discretion of the Lead Evaluator, notify the control room Section 5.6 Swapping Condensate Pumps of abnormal noise in the 11 Condensate pump ATC

  • Check condensate pump oil cooling water flow using (Relative Order 3) cooling water return sight glass.

SRO

  • Check condensate pump gland seal water flow using the
a. As the Shift Manager, contact the control room and inform the Shift Supervisor the Condensate system following:

engineer, over the course of a system walkdwon, o Flow through the gland seal water sight glass - local.

o Seal water pressure is 18-24 psig - local.

discovered an abnormal noise coming from the 11 o Following annunciators NOT LIT:

Condensate pump and has recommended 47009-0402, 11 CONDENSATE PUMP SEAL swapping the 11 and 13 Condensate pumps due to WATER LO PRESS concern of immenent failure and that you agree 47009-0403, 12 CONDENSATE PUMP SEAL with this course of action. Indicate the System WATER LO PRESS Engineer will be writing a CAP and WR to address 47009-0404, 13 CONDENSATE PUMP SEAL the pump and will contact the FIN team. WATER LO PRESS

b. Follow along in 1C28.3 step 5.6 and report back all
  • Ensure the motor bearing of the condensate pump have the local actions and checks are complete as proper oil level - local.

requested after 2 minutes. None of the local checks

  • Verify all condensate pump suction valves are open - local.

are modeled in the simulator.

  • Notify the duty chemist that a condensate pump is being
c. If contacted as the SM and/or the Condensate started and secondary chemistry may be affected.

system engineer for a recommendation on the

  • Place the desired condensate pump selector switch in auto/manual selector for 11 Condensate pump then MANUAL.

recommend placing the 11 Condensate pump into

  • Start the desired condensate pump by placing the control pullout. switch to the START position.
  • Check the pump visually for excessive vibration or seal leakage.
  • Check the bearing temperatures and motor stator temperatures on ERCS
  • Close the discharge vent of the running condensate pump -

local.

  • Verify pump gland seal water pressure is 18-24 psig - local.
  • Verify heat removal fans have started - local.
  • Check condensate header pressure approx. 440 psig on

Page 15 of 20 Appendix D Required Operator Actions Form ES-D-2 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENT 3 6. Swapping 13 and 11 Condensate Pumps continued. 4122101, 11/12/13 CD PMP DISCH HDR PI.

cont

  • Stop the desired condensate pump by placing the control switch to the STOP position.
  • If desired, Then place a condensate pump selector switch in STANDBY.
  • Open the discharge vent valve of the condensate pump that was stopped - local.

Page 16 of 20 Appendix D Required Operator Actions Form ES-D-2 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENT 4 7. When the crew has swapped running Condensate BOP Note: Per rules of usage, reference use actions Pumps, and/or at the discretion of the Lead Evaluator, may be used prior to consulting procedure as enter the malfunction to cause Pressurizer PORV PCV- ATC follows:

431C leakage. (Relative Order 4, Trigger 4)

  • Manually close EITHER Pressurizer Block Valve.

SRO

a. If contacted as Operations Management, acknowledge the report of the failure, and if asked 47012-0109 PRZR SAFETY/RELIEF VALVE FLOW agree to make other notifications to the NRC
  • Check flow monitor light to determine which valve Resident Inspector, Duty Station Manager. opened.
b. If contacted as the FIN team supervisor, inform the
  • Depress individual flow monitor lights to reset alarm crew that you will write a work order and assign a and lights.

Mechanical Maintenance supervisor to investigate.

  • Check safety/relief line temperatures, they should
c. If desired, allow the crew to hold a crew brief.

decrease after valves reseat.

  • Determine cause for opening of valve.
  • If PORV fails to seat, then close PORV block valve with power maintained to the valve.
  • Effect necessary repairs and return system to normal.

1C4 AOP1, REACTOR COOLANT LEAK

  • Determine charging pumps can maintain pressurizer level.
  • Table 1: Close PORV isolation valves one at a time to try to determine which PORV is leaking
  • Make notifications per SWI O-28

Page 17 of 20 Appendix D Required Operator Actions Form ES-D-2 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENT 5 8. When the crew has closed the leaking PORVs BOP Note: Per rules of usage reference use actions

&6 associated block valve, and/or at the discretion of the may be used prior to consulting procedure as Lead Evaluator, enter the malfunction to trip the 12 ATC follows:

Condensate Pump. (Relative Order 5, Trigger 5)

  • Manually Trip the Reactor SRO C47010:0101, 11 Feedwater Pump Locked Out NOTE: When the reactor is tripped proceed immediately
  • If reactor power is greater than 85%, then manually to Event 7. trip the reactor and go to 1E-0, Reactor trip or Safety Injection.

C47017:0304 11 STM GEN LO LO LVL Reactor Trip

Page 18 of 20 Appendix D Required Operator Actions Form ES-D-2 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENT 7 9. When the crew has recognized the need to trip the BOP 1E-0, REACTOR TRIP OR SAFETY INJECTION

&8 reactor and performed a manual trip, and/or at the Critical Task: Manually trip the reactor from the discretion of the Lead Evaluator, enter the Main ATC control room before transition out of E-0.

Feedline break inside containment. (Relative Order 7,

SRO Trigger 7)

a. Upon hearing the announcement of reactor trip, or
  • Verify both safeguards buses energized.

when called as Turbine Building Operator to isolate

  • Check if SI is actuated.

the Unit 1 MSRs per Attachment J, then enter

  • Perform Attachment L.

(Relative Order 7a).

  • Check AFW Status
b. If directed to open reactor trip breakers, wait 1
  • Verify total AFW flow greater than 200 gpm.

minute and delete malfunctions RP02A and RP02B

  • Verify AFW pumps discharge pressure greater than 900 and then report completion (Relative Order 7b). psig.
c. If directed to perform cation column frisks
  • Check WR SG levels greater than 50% in any SG.

acknowledge the order and, after 1 minute, report

  • Control feed flow to maintain wide range SG level between BOTH 11 and 12 Steam Generator cation column 50% and 59%.

has are reading background.

  • Check RCS temperatures stable at or trending to 547°F.
  • Check PRZR PORVS and Spray Valves:
  • PRZR Spray Valves closed.
  • Check if RCPs should be stopped:
  • Check if SGs are not faulted.
  • Check no SG pressure decreasing in an uncontrolled manner.
  • Check no SG completely depressurized.

1E-2. FAULTED STEAM GENERATOR ISOLATION

  • Check MSIV and Bypass Valve closed on 12 SG.
  • Check if either SG is NOT faulted:
  • Identify faulted SG.

Page 19 of 20 Appendix D Required Operator Actions Form ES-D-2 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENT 7 9. Main Feedline break inside containment continued.

  • Isolate faulted SG.

&8 Critical Task: Isolate the faulted STEAM cont GENERATOR before transition out of E-2.

  • Check CST level - Greater than 10,000 Gallons.
  • Check Secondary Radiation.
  • Go To 1E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1.

1E-1, LOSS OF REACTOR OR SECONDARY COOLANT.

NOTE: The crew may transition to 1ES-0.2, SI TERMINATION, from 1E-1 info page once conditions are met.

  • Check if RCPs should be stopped.
  • Check if SGs are not faulted.
  • Check intact SG levels.
  • Check secondary radiation - Normal.
  • Check PRZR PORVs and block valves.
  • Reset Containment Isolation
  • Establish Instrument Air to Containment
  • Check power supply to Charging Pumps - OFFSITE POWER AVAILABLE.
  • Check if SI flow should be terminated:

o RCS subcooling based on core exit T/Cs -

GREATER THAN 20°F.

o Secondary heat sink.

o RCS pressure:

Pressure - GREATER THAN 2000 PSIG.

Pressure - STABLE OR INCREASING.

o PRZR level - GREATER THAN 7%.

  • Go to 1ES-0.2, SI TERMINATION, Step 1.

Page 20 of 20 Appendix D Required Operator Actions Form ES-D-2 SCENARIO TIME-LINE:

SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EVENT 7 9. Main Feedline break inside containment continued.

&8 1ES-0.2, SI TERMINATION cont

  • Reset Containment Isolation.
  • Establish instrument air to containment.
  • Stop Safeguards Pumps.
  • Check if charging flow has been established.
  • Verify SI flow is not required.
10. When SI has been verified to not be required and has been terminated and/or at the discretion of the Lead Evaluator, place the simulator in FREEZE Emergency Plan Classification - Classify the event per F3-2 SM Classify the event as follows:
a. The SM may delegate ED duties to the Unit 2 SS if *  ??? - EAL ??? declared a Unit 2 SS is participating as part of the crew
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