ML12213A063

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2012 Prairie Island Nuclear Generating Plant Initial License Examination Administered Scenarios
ML12213A063
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 05/22/2012
From: Mcneil D
Operations Branch III
To:
Northern States Power Co, Xcel Energy
References
Download: ML12213A063 (44)
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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: Mode: 1; Exposure: ZBC; Power: ~13%; Boron: (CB): 1897; Temperature: ~545°F Pressure: ~2235 psig; Xenon: Building In; Rods: D @ 174 steps; Generator: 40 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 ascension. The Heater Drain Tank alarms have been authorized to leave flashing. No equipment OOS Event Malf. Event Event No. No. Type* Description 1 R (RO) Raise power to 15%

1 N (BOP) Transfer M to R power supplies 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 Page 1 of 11

2012 ILT NRC SIMULATOR EVALUATION #1 QUANTITATIVE ATTRIBUTES Malfunctions:

Before EOP Entry:

1. Blue Channel Pressurizer Level fails high
2. 11 Charging Pump trips
3. N42 PRNI fails low After EOP Entry:
1. 11 TDAFWP fails to start automatically Abnormal Events:
1. Blue Channel Pressurizer Level fails high
2. 11 Charging Pump trips
3. N42 PRNI fails low Major Transients:
1. Loss of All AC (Station Blackout)

Critical Tasks:

1. E C: energize at least one AC emergency bus before reaching step 8 of ECA-0.0 which places safeguards equipment handswitches in the pull-to-lock position.
2. ECA-0.0 - B: Establish and maintain 200 GPM AFW flow to the Steam Generators prior to Step 3 of ECA-0.0.

Page 2 of 11

2012 ILT NRC SIMULATOR EVALUATION #1 SCENARIO OVERVIEW:

SEQUENCE OF EVENTS:

Event 1: Raise power to 15% and transfer M-R sources

  • The Crew will raise reactor power to 15% per 1C1.2 Section 5.14.
  • Non-Safeguards Loads will be transferred to their M source from their R source.
  • A Surrogate may be provided to perform peer checking during these activities.

Event 2: Blue Channel Pressurizer Level fails high

  • Charging pump speed will lower.
  • The crew will respond per C47 and 1C51.3 to defeat the failed pressurizer level channel and return charging and pressurizer heaters to automatic.

Event 3: 11 Charging Pump trips

  • RCP Seal Injection flows and labyrinth seal D/P will lower.
  • The crew will respond per C47 and 1C12.1 to restore seal injection flow and return charging to automatic.

Event 4: N42 PRNI fails low

  • The crew will respond per 1C51.2 to remove N42 PRNI from service.
  • Control rods step out IF rod control is in automatic and would require restoring T ave to T ref .
  • A Surrogate may be provided for concurrent verifications, but must not perform initial component identification at any time.

Event 5: Turbine Locks Out initiating a Loss of all AC power

  • A Turbine lockout occurs accompanied by a loss of all offsite power.
  • Bus 15 and D2 lock out.
  • The crew will respond per 1E-0, and 1ECA-0.0 to restore power to Bus 16 via the cross tie to Unit 2.

Event 6: 11 TDAFWP fails to start automatically

  • The crew will respond per 1ECA-0.0 to manually start the 11 TDAFWP.

Page 3 of 11

2012 ILT NRC SIMULATOR EVALUATION #1 EVENT 1, REACTIVITY CHANGE and ELECTRICAL BUS ALIGNMENT EVENT 1 1. When the crew has assumed the duty, and at the 1C1.2, Unit 1 Startup Procedure discretion of the lead evaluator, allow the crew to raise Section 5.14 Power Increase to 15%

power to 15% and transfer loads to the M source.

  • Using the VPL pop-up screen, select the VPL Raise
a. When directed to schedule SP 1005A, NIS Power () control to raise the VPL setting to 101%.

Range Daily Calibration, within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, R(ATC)

  • Start raising reactor power to 15%.

agree to write WR and schedule the SP. (Guidance from 1C1.4 Section 5.3)

b. When directed to Rack Breakers 11-4, 12-4, 13-9 o Using the On Line Control screen, select the and 14-9 to the connected position, then enter the desired Control Mode (VPC).

remotes. (Relative Order 1, Trigger 1). When o Using the On Line Control screen, select the Trigger 1 has completed, inform the Control Room desired demand rate. (0.25%/min) a time step has occurred and Breakers 11-4, 12-4, o Set the Target setting to the desired load by 13-9 and 14-9 are in the CONNECT position. using the On Line Control screen Target increase/decrease (/) controls.

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

NOTE: Per 1C1.4 Precaution 3.2, it is desirable to maintain

  • Verify 47014-0501, P-10 NUCLEAR AT POWER T ave within 1.5°F of T ref during power changes and T ave PERMISSIVE aqua light, is LIT should not deviate by more than 5°F without Ops Manager
  • Block the power range low setting high flux trip and and Nuclear Engineering approval. intermediate range high flux trip.
  • Check CV-3 and CV-4 OPENING on program.
  • Rack in and close the following breakers:

N(BOP/ o BKR 11-4, BUS 11 1M XFMR SRO) o BKR 12-4, BUS 12 1M XFMR o BKR 13-9, BUS 13 1M XFMR o BKR 14-9, BUS 14 1M XFMR

  • Transfer the Steam Dump System to TAVG control:
  • Verify the 15% HOLD time recorded in Attachment 2 has been met. (See Step 5.14.7.)
  • Continue with 1C1.4, Power Operation, or 1C1.3, Unit 1 Shutdown.

Page 4 of 11

2012 ILT NRC SIMULATOR EVALUATION #1 EVENT 2, BLUE PRESSURIZER LEVEL INSTRUMENT FAILURE (HIGH)

EVENT 2 2. When the crew has raised power satisfactorily, and/or at I(ATC) C47012-0307, PRZR HI LVL CHANNEL ALERT the discretion of the Lead Evaluator, enter the

  • Check pressurizer level.

malfunction to fail the Blue Pressurizer Level channel

  • Control level in manual.

(LT-428) high (Relative Order 2, Trigger 2) o Reduce level to program level.

o Maintain pressurizer pressure.

a. If directed as I&C to trip bistables, report that 2 I&C
  • If channel failed, then refer to 1C51.

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 C47012-0507, PRZR LVL DEVIATION scenario.)

  • Check pressurizer level.
b. If contacted as Operations Management,
  • If actual pressurizer level deviation exists,N/A.

acknowledge the report of the failure, and if asked

  • If due to an instrument failure, then refer to 1C51.

agree to make other notifications to the NRC Resident Inspector, Duty Station Manager. C47015-0203, CHARGING PUMP IN AUTO TROUBLE

c. If contacted as the FIN team supervisor, inform the
  • If due to level channel malfunction, then switch crew that you will write a work order and assign an pressurizer level control channels. Refer to 1C51.

I&C supervisor to investigate.

1C51.3, INSTRUMENT FAILURE GUIDE (1L-428 - High)

  • If the Blue channel is selected on the PRZR Level Control Selector Switch, then:

o Control pressurizer heaters manually.

o Place charging pump speed control in Manual and adjust pressurizer level to setpoint.

o Select position 2-1 (WHITE-RED) on PRZR Level Control selector switch.

o Return pressurizer heaters to AUTO if desired.

o Return one charging pump speed control to AUTO.

  • Ensure pressurizer level recorder not selected to Blue channel.

T.S.

  • Refer to TS LCO 3.3.1, Condition A and Table 3.3.1-1 (SRO) Function 9.

Page 5 of 11

2012 ILT NRC SIMULATOR EVALUATION #1 EVENT 3, TRIP OF 11 CHARGING PUMP EVENT 3 3. When the crew has restored charging and pressurizer C(ATC) 47015-0103, 11 CHARGING PUMP TRIP heaters to automatic, and/or at the discretion of the

  • Start another charging pump.

Lead Evaluator, enter the malfunction to trip 11

  • Restore letdown per 1C12.1, LETDOWN, CHARGING Charging Pump. (Relative Order 3, Trigger 3) AND SEAL WATER INJECTION.
  • Maintain Pressurizer level and seal injection flow.
a. If directed to investigate 11 Charging pump, after 3 minutes, report that the 11 Charging pump appears 1C12.1, LETDOWN, CHARGING AND SEAL WATER intact with no visible damage. INJECTION - Section 5.3 Starting a second charging
b. If directed to log VFD faults, after 3 minutes, report pump that there is a VFD Overfrequency fault on 11
  • Transfer the inservice charging pump from Charging Pump. AUTOMATIC to MANUAL speed control.
c. If directed to verify discharge desurger is
  • Verify that the speed controller of the charging pump pressurized, request that the pump be taken to PTL to be started is in MANUAL at minimum speed.

and after 3 minutes, report that the desurger is

  • Reduce the speed of the inservice charging pump until pressurized. the seal injection flow drops from eight (8) gpm to
d. If contacted as the FIN team supervisor, inform the approximately six (6) gpm.

crew that you will write a work order and assign an

  • Verify charging pump discharge header pressure Electrical Maintenance supervisor to investigate. 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 8 gpm.

o One 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.

Page 6 of 11

2012 ILT NRC SIMULATOR EVALUATION #1 EVENT 4, N42 PRNI FAILS LOW EVENT 4 4. When the crew has restored Charging and Letdown to 1C5 AOP1, UNCONTROLLED ROD MOTION normal, and/or at the discretion of the Lead Evaluator,

  • Check Generator Electrical Load - STABLE enter then malfunction to fail N42 PRNI low. (Relative
  • Place Rod Bank Selector Switch to MANUAL Order 4, Trigger 4)
  • Check Rod Motion - STOPPED
  • Check for Failed Instrument:
a. If directed as I&C to trip bistables, report that 2 I&C I(ATC) o NIS power range channels 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: o RCS loop Tavg channels bistables will not be tripped during this o Turbine impulse pressure 1PT-485 scenario.)
  • Go to 1C51, Instrument Failure Guide
b. If contacted as I&C Engineering to determine if it is necessary to energize the P-10 bistable, state that 47013-0201, NIS POWER RANGE NEGATIVE FLUX you will write a work order. RATE CHANNEL ALERT
c. If contacted as the Nuclear Engineer, state that you
  • Refer to 1C51, Instrument Failure Guide will perform a flux map and/or SP 1120.
d. If contacted as Operations Management, 47013-0203, NIS POWER RANGE CHANNEL acknowledge the report of the failure, and if asked DEVIATION agree to make other notifications to the NRC
  • Check CHANNEL DEVIATION light LIT Resident Inspector, Duty Station Manager.
  • Check Channel disagreement
e. If contacted as the FIN team supervisor, inform the
  • Check for dropped or misaligned rod crew that you will write a work order and assign an I&C supervisor to investigate.
  • If due to channel failure, refer to 1C51
f. If contacted, as the Computer Group, in reference to removing N42 from service, agree to investigate. 1C51.2, N42 PR NIS FAILS LOW
g. If desired, allow the crew to hold a crew brief.
  • Place Rod Control in MANUAL, maintain T ave at T ref .

T.S.

  • Refer to the following TS requirements:

(SRO)

  • Refer to T.S. LCO 3.3.1 Condition A and Table 3.3.1-1, Functions 2a, 2b, 3a, 3b, 6,16b.1 16c,16d,16e
  • TS LCO 3.3.1 Conditions D, E, R and Q will be entered.

I(BOP)

  • Remove N-42 from service as follows:
  • Place Rod Stop Bypass switch in the N42 position.
  • Place Power Mismatch Bypass switch in the N42 position.
  • Place Upper Section Current Comparator Defeat switch in the N42 position and verify the Upper Section Channel Defeat Light is LIT.

Page 7 of 11

2012 ILT NRC SIMULATOR EVALUATION #1 EVENT 4, N42 PRNI FAILS LOW

  • Place Lower Section Current Comparator Defeat switch in the N42 position and verify the Lower Section Channel Defeat Light is LIT.
  • On the Comparator and Rate Drawer, place Comparator Channel Defeat Switch in the N42 position and verify the Comparator Defeat Light is LIT.
  • At the N42 Power Range B drawer pull the Control and Instrument Power Fuses.
  • Verify the following annunciators are received o 47013-0101, 47013-0102 o 47013-0201, 47014-0203
  • Verify the following status lights are lit:

o 44178-0206, 44178-0207 o 44205-0204

  • Restore T ave to T ref using control rods in one or two RO step increments.
  • Verify NR-45 is selected to an operable channel.

Page 8 of 11

2012 ILT NRC SIMULATOR EVALUATION #1 EVENT 5, TURBINE LOCKS OUT INITIATING A LOSS OF ALL AC POWER EVENT 6, 11 TDAFW PUMP AUTO START FAILURE EVENT 5 5. When the crew has removed N42 PRNI from service, M(ALL) 1E-0, REACTOR TRIP OR SAFETY INJECTION and/or at the discretion of the Lead Evaluator, enter the

malfunctions to trip the turbine and initiate the Loss of

ALL AC. (Relative Order 5, Trigger 5)

  • Verify both safeguards buses energized.

o Transition to 1ECA-0.0.

a. As a Unit 2 operator, announce Unit 2 reactor trip, 1ECA-0.0, LOSS OF ALL SAFEGUARDS AC POWER Unit 2 reactor trip, SEC, SM report to the control
  • Check if RCS is isolated.

room. o PRZR PORVs - CLOSED

b. Upon hearing the announcement of reactor trip, or o Letdown isolation valves - CLOSED:

when called as Turbine Building Operator to isolate o Excess letdown isolation valve - CLOSED the Unit 1 MSRs per Attachment J, then enter

  • Verify AFW Flow - GREATER THAN 200 GPM.

(Relative Order 5a). o Place 12 MD AFW Pump into Manual.

c. If directed, use remotes FW134 (11 SG feed) and o Start 12 MD AFW Pump.

FW135 (12 SG feed) to throttle AFW flow as Critical Task: Establish and maintain 200 GPM directed (Relative Order 5b). C(BOP/

SRO) AFW flow to the Steam Generators prior to Step 3

d. If directed to locally investigate D2, wait 2 minutes and perform the following:

of ECA-0.0.

1) Enter the remote to acknowledge the local D2
  • Perform notifications.

alarm panel (Relative Order 6, Trigger 6).

  • Check Cooling Water Header Pressures - BOTH
2) Report that D2 is tripped and locked out on GREATER THAN 25 PSIG.

generator differential currents, and that

  • Check if Safeguards Buses are available for maintenance has been notified. Sequencer loading.
e. If directed to locally investigate Bus 16, after 3
  • Attempt to restore power to any available Safeguards minutes report that the only indication on Bus 16 is Bus from Unit 1 source.

associated with under voltage (there are no targets

  • Attempt to restore power to any available Safeguards or relays indicating any faults on the bus). Bus from Unit 2.
f. When asked status of Unit 2 SI pumps, report that o Close bus 26 Bus-Tie Breaker Unit 2 has no running SI pumps. o Close bus 16 Bus-Tie Breaker Critical Task: Energize at least one AC
g. When Bus 16 is powered from Bus 26 and/or at the emergency bus before reaching step 8 of ECA-0.0 discretion of the Lead Evaluator, place the which places safeguards equipment simulator in FREEZE. handswitches in the pull-to-lock position.
  • Start one charging pump.
  • Return to procedure and step in effect.

Page 9 of 11

QF-1075-02 Rev. 3 (FP-T-SAT-75) Page 10 of 11 2012 ILT NRC SIMULATOR EVALUATION #1, REV. 0 RETENTION: 7 Days UNIT 1 LPEO / PEO TURNOVER LOG DATE: DAY/NIGHT SHIFT: Day CAT 1 VENT OPENINGS: 0 ft2 SYSTEM CONDITION: GREEN SAFEGUARDS EQUIPMENT OOS/TECH SPEC REQUIRED ACTION STATEMENTS NONE PROTECTED EQUIPMENT NONE RAD MONITORS OOS ANNUNCIATORS OOS OUTSTANDING SPS FIRE DET / PROT EQP IMPAIRMENTS OTHER EQUIPMENT OOS / STATUS HDT Annunciators have been authorized to remain flashing.

An Extra Operator is periodically monitoring the HDT system and will inform the crew if any action is required.

MAJOR EQUIPMENT REPAIRED / RETURNED TO SERVICE OPERATIONAL PLANS FOR COMING SHIFT Raise power to 15% and commence 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> soak for engineering evaluation of secondary components.

Transfer M-R sources to M source.

10 Gallon dilutions for ~0.4°F every 15 minutes to maintain power/temperature.

NEW PROCEDURES / INSTRUCTIONS Page 10 of 11

QF-1075-02 Rev. 3 (FP-T-SAT-75) Page 11 of 11 2012 ILT NRC SIMULATOR EVALUATION #1, REV. 0 Reactivity Plan The crew has been directed to raise reactor power from 15%.

Prior to simulator:

  • verify the reactivity plan completed by the off going reactor operator
  • complete a Pre-Job Brief Current conditions are:

The Turbine is synched to the Grid.

RCS Temperature is being controlled by Steam Dumps.

Power level: 13%

Xenon: Increasing Control Rod Position: Bank D @ 174 steps Boron Concentration: 1897 ppm Core Exposure: 0 MWD/MTU (Initial Startup following refueling)

Target: VPC @ 6.2 (NI Power ~15%)

Rate: 0.25% /minute Control Mode: Valve Position Control (VPC) with Rod Control in Manual Boration/Dilution: 10 gal dilutions every 15 minutes Reactivity Prediction:

Change in Power Defect: -31 pcm Differential Boron Worth: -6.65 pcm/ppm Calculated RCS PPM change: -1.5 ppm Assumed 2/3 rods and 1/3 RMU addition Calculated Boric Acid / Reactor Makeup Water addition: 1.5 ppm change = 30 gals RMU Calculated final Control Rod Position : Bank D @ 178 steps Page 11 of 11

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: Mode: 1; Exposure: BOC; Power: 42.5%; Boron: (CB): 1415 ppm; Temperature:___

~552°F; Pressure: ~2235 psig; Xenon: Building In; Rods: D @ 170; Generator: ~225 MW_________

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

2012 ILT NRC SIMULATOR SCENARIO #2 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 2 of 17

2012 ILT NRC SIMULATOR SCENARIO #2 SCENARIO OVERVIEW:

INITIAL CONDITIONS:

The 11 TDAFW Pump is OOS.

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.

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.

Page 3 of 17

2012 ILT NRC SIMULATOR SCENARIO #2 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 4 of 17

2012 ILT NRC SIMULATOR EVALUATION #2, REV. 0 EVENT 1, REACTIVITY CHANGE - REDUCE REACTOR POWER EVENT 1 1. When the crew has assumed the duty, and at the 1C1.4, Unit 1 Power Operation, discretion of the lead evaluator, allow the crew to R(ATC) Section 5.2, step 5.2.6.

reduce turbine load to ~195 MW.

  • Turn ON all pressurizer heaters
a. When contacted as Duty Chemist, acknowledge
  • Increase letdown flow if desired (80 gpm letdown flow load change. will already be established, no actions will be needed)
  • If desired, place CS-46280, ROD BANK SELECTOR, in MANUAL.
  • Start the load decrease as follows:

Page 5 of 17

2012 ILT NRC SIMULATOR EVALUATION #2, REV. 0 EVENT 2, NORMAL EVOLUTION - SWAP 11 AND 12 MFP EVENT 2 2. When the crew has reduced turbine load below 195 MW N(BOP, 1C28.2 UNIT 1 FEEDWATER SYSTEM and returned Rod Control to automatic, and/ or at the SRO) 5.7 Swapping FWPs discretion of the Lead Evaluator, direct the crew to

  • Reduce turbine load to approximately 200 MWe proceed with swap of 12 and 11 MFP, if necessary.
  • Verify two (2) condensate pumps are running or start a second condensate pump per 1C28.3.
  • 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 FW pump:

o F-22-3, 11 FW PMP WARMUP LINE Page 6 of 17

2012 ILT NRC SIMULATOR EVALUATION #2, REV. 0 EVENT 3, FAILURE OF 12 STEAM GENERATOR PRESSURE INSTRUMENT HIGH EVENT 3 3. When the crew has swapped 11 and 12 Main Feed Note: Per rules of usage, reference use actions may Pumps, and/or at the discretion of the Lead Evaluator, be used prior to consulting procedure as follows:

enter the malfunction to fail 12 SG pressure high. I(ATC)

  • Manual control of B SG PORV (Relative Order 3, Trigger 3)

Note: If 1C5 AOP1 is entered it should be exited on

a. If directed as I&C to trip bistables, report that 2 I&C step 1 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 47011-0405. FW CONTROL SYSTEM TROUBLE scenario.)

b. If contacted as Operations Management, properly in automatic acknowledge the report of the failure, and if asked
  • Control level in manual for any Steam Generator agree to make other notifications to the NRC which has shifted to manual N/A Resident Inspector, Duty Station Manager.
  • Refer to 1C51, Instrument Failure Guide
c. If contacted as the FIN team supervisor, inform the crew that you will write a work order and assign an 1C51.3 12 STEAM GENERATOR PRESSURE 1P-478 I&C supervisor to investigate. HIGH
  • Take manual control of 12 SG PORV and ensure valve is closed
  • Verify SG Level Control operating properly in automatic
  • Refer to T.S. LCO 3.3.2 Condition A and Table 3.3.2-1 T.S. Function 1e (SRO)
  • T.S. LCO 3.3.2 Condition D will be entered Page 7 of 17

2012 ILT NRC SIMULATOR EVALUATION #2, REV. 0 EVENT 4, FAILURE OF PT-431, BLUE PRESSURIZER PRESSURE INSTRUMENT HIGH EVENT 4 4. When the crew has recovered SG pressure control, Note: Per rules of usage reference use actions and/or at the discretion of the Lead Evaluator, enter the may be used prior to consulting procedure as malfunction to fail PT-431, Blue Channel Pressurizer follows:

Pressure high. (Relative Order 4, Trigger 4) I(ATC)

  • Manual Control of Pressurizer Spray Valves 5.
a. If directed as I&C to trip bistables, report that 2 I&C 47012-0408 PRZR HI/LO PRESS CHANNEL ALERT 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:
  • Check pressure high or low.

bistables will not be tripped during this

  • If necessary then control pressure in manual.

scenario.)

  • If due to channel failure, then refer to 1C51,
b. If contacted as Operations Management, INSTRUMENT FAILURE GUIDE - UNIT 1.

acknowledge the report of the failure, and if asked agree to make other notifications to the NRC C51.3 Pressurizer Pressure 1P-431 High Resident Inspector, Duty Station Manager.

c. If contacted as the FIN team supervisor, inform the
  • Place Pressurizer Pressure Controller in MANUAL and crew that you will write a work order and assign an stabilize pressure.

I&C supervisor to investigate.

  • Select position 2-1 (WHITE-RED) on channel selector switch.

Note: If not diagnosed and responded to quickly enough

  • When pressure returned to normal with no deviation this failure will result in a Reactor Trip and, potentially, from setpoint, then return pressure control to a Safety Injection. If this should occur proceed automatic.

immediately to Event 5 where the SGTR will be

  • Verify Pressurizer Pressure Recorder not selected to diagnosed during performance of 1E-0 or 1ES-0.1. Blue channel.

T.S.

  • Refer to the following Technical Specifications:

Note: If RCS Pressure lowers below DNB (2175 psig) (SRO) o T.S. LCO 3.3.1 Condition A & Table 3.3.1-1 T.S. LCO 3.4.1 Condition A should be entered.. Functions 6, 8a, 8b.

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

o T.S. LCO 3.4.1.a o T.S. LCO 3.3.1 Conditions E and K will be entered o T.S. LCO 3.3.2 Condition D will be entered o T.S. LCO 3.4.1 Condition A might be entered Page 8 of 17

2012 ILT NRC SIMULATOR EVALUATION #2, REV. 0 EVENT 5, SGTR ON 12 STEAM GENERATOR EVENT 5 6. When the crew has recovered Pressurizer pressure M(ALL) C47022-0108, HI RADIATION TRAIN B PANEL ALARM control, and/or at the discretion of the Lead Evaluator,

  • Determine the initiating alarm and respond to the enter the malfunction to cause a SGTR on 12 SG which alarm as specified in C47048, TRAIN B RADIATION will ramp in over the next 15 minutes. (Relative Order MONITORING SYSTEM ALARM RESPONSE 5, Trigger 5) PROCEDURES.
a. If directed to perform cation column frisks C47048: 1R-15 acknowledge the order and, after 1 minute, report
  • If primary-to-secondary leakage is confirmed by 12 Steam Generator cation column has elevated sampling or other indication, then:

activity, 11 Steam Generator cation column is o Enter 1C4 AOP2, STEAM GENERATOR TUBE reading background. LEAK.

b. If asked to take primary or secondary samples per T.S.

RPIP 4503, state that the samples are in progress. (SRO)

  • Refer to T.S. 3.7.14, and T.S. 3.4.14
c. If contacted as Operations Management, acknowledge the report of the failure, and if asked Note: Letdown may be isolated to aid in maintaining agree to make other notifications to the NRC pressurizer level.

Resident Inspector, Duty Station Manager.

d. If directed to turn on all turbine building roof 1C4 AOP2, STEAM GENERATOR TUBE LEAK exhausters, wait 3 minutes and report all turbine
  • IF at any time RCS inventory can not be maintained by building roof exhausters are running. available charging flow, THEN perform the following:

o Manually trip the reactor - enter 1E-0, Reactor Trip or Safety Injection.

o WHEN reactor is verified tripped, THEN initiate Safety Injection.

o Exit this procedure CREW

  • Continuously monitor 1R15 and 1R19 in the Control Room for further increase.

Page 9 of 17

2012 ILT NRC SIMULATOR EVALUATION #2, REV. 0 EVENT 5, SGTR ON 12 STEAM GENERATOR EVENT 5 7. When the crew has determined tube leakage exceeds RO/ 1E-0, REACTOR TRIP OR SAFETY INJECTION cont the available charging they will perform a reactor trip BOP

and initiate Safety Injection per 1C4 AOP2.

  • Verify both safeguards buses energized.
a. Upon hearing the announcement of reactor trip, or
  • Check if SI is actuated.

when called as Turbine Building Operator to isolate

  • Perform Attachment L. (See page 23 for Att. L actions) the Unit 1 MSRs per Attachment J, then enter Critical Task: Manually actuate at least one train of SI-Relative Order 7 (Schedule file E-0_Att-J.sch). C(BOP) actuated safeguards equipment before transition out
b. When called as the Turbine Building Operator to of 1E-0.

verify the status of Turbine Building Roof

  • Check AFW Status.

Exhausters, report that the Turbine Building Roof o 12 MD AFW Pump placed in Manual Exhausters are all secured. o 12 MD AFW Pump started

c. When directed to perform sampling after 3 minutes report 12 SG Cation frisk had elevated counts and Note: AFW to the ruptured SG may be isolated at this 11 SG Cation frisk read background. point, but appropriate Heat Sink must be maintained.
d. If Unit 2 is requested to support performance of Att L and/or Att B, decline to assist until at least one SI Critical Task: Establish and maintain 200 GPM AFW pump is running and the SRO has prioritized Att L flow to the Steam Generator(s) before transition out of and Att B. Upon completion of these two events, E-0, unless the transition is to FR-H.1, in which case personnel may be provided to complete Att L, but the task must be initiated before RCPs are manually no assistance will be given to perform Att B. tripped in accordance with step 2 of FR-H.1.
  • Verify total AFW flow greater than 200 gpm.
  • Verify AFW pumps discharge pressure greater than 1000 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 547°F.
  • 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.

Page 10 of 17

2012 ILT NRC SIMULATOR EVALUATION #2, REV. 0 EVENT 5, SGTR ON 12 STEAM GENERATOR EVENT 5 1E-3, STEAM GENERATOR TUBE RUPTURE cont

  • Check if RCPs should be stopped.
  • Identify Ruptured SG.
  • Isolate flow from ruptured SG.

o Set ruptured SG PORV in auto at 75%

o Check Ruptured SG PORV - CLOSED o Close steam supply from ruptured to 11 TDAFWP 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.

C(BOP, Critical Task: Isolate feedwater flow into and steam SRO) flow from the ruptured Steam Generator before a transition to ECA-3.1 occurs.

Perform ATT B while continuing in 1E-3.

(NOTE: Attachment B actions are on page 22)

  • Check ruptured SG level.
  • Check ruptured SG pressure - Greater than 210 psig Critical Task: 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.
  • Initiate RCS Cooldown o Determine required core exit temperature.

o Check one condensate pump running.

o Establish steam dump to condenser.

o Dump steam from intact SG until below core exit Note: During the cooldown, the SS must continue with step 8 to prepare the plant for depressurization.

  • Check intact SG level
  • Check PRZR PORVs and Block Valves
  • Reset SI Page 11 of 17

2012 ILT NRC SIMULATOR EVALUATION #2, REV. 0 EVENT 5, SGTR ON 12 STEAM GENERATOR EVENT 5

  • Reset Containment Isolation cont
  • Establish Instrument Air to containment
  • Check if RHR pumps should be stopped
  • Establish Charging flow
  • Check if RCS Cooldown should be stopped
  • Check Ruptured SG pressure - Stable or increasing
  • Check RCS subcooling based on core exit T/Cs -

greater than 40°F Critical Task: Depressurize RCS to meet SI termination criteria prior to overfilling the ruptured Steam Generator.

  • Depressurize RCS to minimize break flow and refill PRZR
  • Check if SI flow should be terminated:

o Subcooling > 20 [35F].

o Secondary Heat Sink exists.

o RCS Pressure is stable or increasing.

o PRZR Level > 7%.

Critical Task: Terminate SI prior to overfilling the ruptured 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 isolation valves (CY-1-1 and CY-1-4)
  • Dispatch personnel to locally close air ejector suction valves (AR-5-1 and AR-5-2)
  • Verify turbine stop valves - CLOSED
  • Verify MSR steam isolation valves - CLOSED:

o CV-31096 o CV-31097 o CV-31094 o CV-31095 Page 12 of 17

2012 ILT NRC SIMULATOR EVALUATION #2, REV. 0 EVENT 5, SGTR ON 12 STEAM GENERATOR EVENT 5

  • WHEN air ejector suction valves are closed, THEN cont close normal and secondary air ejector steam supply valves (MV-32327 and MV-32355)
  • Verify standby air ejector suction valves (MV-32346 and MV-32347) - CLOSED
  • Verify standby air ejector steam supply valves (MV-32328) - CLOSED
  • Verify 11 and 12 hogging jet suction valves (MV-32308 and MV-32309) - CLOSED
  • Verify 11 and 12 hogging jet steam supply valves (MV-32316 and MV-32317) - CLOSED
  • Verify steam dumps selected to OFF
  • Evaluate the need to transfer gland steam to heating steam Page 13 of 17

2012 ILT NRC SIMULATOR EVALUATION #2, REV. 0 EVENTS 6, 7, 8, MSIV FAILURE TO CLOSE, SI PUMP FAILURE, 12 MDAFP FAILURE

8. 1E-0 Attachment L actions 1E-0 Attachment L: SI Alignment Verification
  • Verify Safeguards Component Alignment:
  • Verify both trains of SI actuated:

o Both RHR pumps - RUNNING

-OR-o Both SI pumps - RUNNING

  • RNO Manually actuate SI.
  • "SI NOT READY" lights - NOT LIT
  • "SI ACTIVE" lights - LIT FOR PLANT CONDITIONS
  • "CONTAINMENT ISOLATION" lights - LIT FOR PLANT CONDITIONS
  • Check Category 1 Vent Zone Boundary:
  • Close MV-32117, 121 SFP HX INLT HDR MV A
  • Check Cooling Water Header Pressures - BOTH GREATER THAN 65 PSIG
  • Verify Plant Announcements Complete:
  • Check If Main Steamlines Are Isolated:
  • MSIVs and bypass valves - CLOSED
  • Containment instrument air valves - CLOSED:
  • Verify SI Flow:
  • Verify RHR Flow
  • Check RCP Cooling
  • Verify Local Actions Complete
  • Verify Generator Breakers - OPEN
  • Verify All Heater Drain Pumps - STOPPED
  • Check Turbine Valves:

o Turbine reheat and intercept valves - CLOSED o Open turbine drain valves

o Both main feedwater pumps - STOPPED o Main and bypass FRVs - CLOSED

  • Verify All Condensate Pumps - STOPPED:
  • Place Steam Dump In "STM PRESS" Mode
  • Verify Unit 1 Cooling Water/Chilled Water Alignment:

Page 14 of 17

2012 ILT NRC SIMULATOR EVALUATION #2, REV. 0 EVENTS 6, 7, 8, MSIV FAILURE TO CLOSE, SI PUMP FAILURE, 12 MDAFP FAILURE o CFCU control switches - "SLOW".

o CFCU dampers - ALIGNED TO DOME o Unit 1 cooling water/chilled water valves closed o Unit 1 CRDM shroud cooling supply and return valves - CLOSED o CFCU cooling water supply and return valves -

OPEN o CFCU chilled water supply and return valves -

CLOSED

  • Verify Control Room Ventilation Alignment:

o Chillers and fans - RUNNING o Control room chiller suction/discharge tie closed -

STATUS LIGHT LIT

  • Verify Unit 1 Cooling/Chilled Water Alignment
  • Check Status Of Notifications
  • Notify SS Of Any Discrepancies
9. 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.

Page 15 of 17

2012 ILT NRC SIMULATOR EVALUATION #2, REV. 0 RETENTION: 7 Days UNIT 1 LPEO / PEO TURNOVER LOG DATE: DAY/NIGHT SHIFT: Day CAT 1 VENT OPENINGS: 0 ft2 SYSTEM CONDITION: GREEN SAFEGUARDS EQUIPMENT OOS/TECH SPEC REQUIRED ACTION STATEMENTS 11 TDAFWP is OOS for Corrective Maintenance on the Woodward Governor.

T.S. 3.7.5 Condition B was entered at 0400 today.

11 TD AFWP is expected to return to service tonight at midnight.

PROTECTED EQUIPMENT 12 MDAFWP RAD MONITORS OOS ANNUNCIATORS OOS OUTSTANDING SPS FIRE DET / PROT EQP IMPAIRMENTS OTHER EQUIPMENT OOS / STATUS 12 MFP Recirc Valve is blocked open HDT Annunciators have been authorized to remain flashing.

An Extra Operator is periodically monitoring the HDT system and will inform the crew if any action is required.

MAJOR EQUIPMENT REPAIRED / RETURNED TO SERVICE OPERATIONAL PLANS FOR COMING SHIFT 10 gal dilutions every 15 mins for ~0.25°F temp change.

Lower power to 195 MW.

Start 12 MFP and Stop 11 MFP for common cause evaluation of 11 MFP.

11 and 12 Condensate pumps are to remain running in anticipation of returning 11 MFP to service.

NEW PROCEDURES / INSTRUCTIONS Page 16 of 17

2012 ILT NRC SIMULATOR EVALUATION #2, REV. 0 Reactivity Plan The crew has been directed to reduce reactor power from 220 Mw to 195 Mw.

Prior to simulator:

  • verify the reactivity plan completed by the off going reactor operator
  • complete a Pre-Job Brief of:

o 1C28.2 Section 5.7 o 1C1.4 Section 5.2 Current conditions are:

11 MFP is running.

12 MFP has just been returned to service following emergent repairs.

12 MFP recirc valve is blocked open.

11 and 12 condensate pumps are running.

Power level: 43% (220 Mw)

Xenon: Increasing (Power reduced from 50% and stable to 43% over last hour)

Control Rod Position: Bank D @ 170 steps Boron Concentration: 1411 ppm Core Exposure: 150 MWD/MTU Target: Turbine Load: 195 MW Rate: 0.25% /minute Control Mode: LOAD control with Rod Control in Manual Boration/Dilution: 10 gal dilutions every 15 minutes Reactivity Prediction:

Change in Power Defect: 63 pcm Differential Boron Worth: 6.5 pcm/ppm Calculated RCS PPM change: 4.7 ppm Assumed 1/2 rods and 1/2 RMU addition Calculated Boric Acid addition: 4.7 ppm change = 8 gallon Boration Calculated final Control Rod Position : Bank D @ 163 steps Page 17 of 17

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: Mode: 1; Exposure: MOC; Power: ~91.7%; Boron: (CB): 635 ppm; Temperature: ~ 559°F; Pressure: ~2235 psig; Xenon: Building in; Rods: D @ 200; Generator:

530 MWe, stable Turnover: Power is to be lowered to 90% upon TSO request due to grid loading. The crew has a 1C1.4 Section 5.3 marked up for performance. There are no fuel conditioning requirements. Lower Reactor Power to 90% at 0.25%/minute with rods in MANUAL with Turbine in AUTO in FSP mode.

A reactivity plan developed by the off going RO for the power reduction from current power to 90% is provided. Verify the reactivity plan developed by the off going reactor operator. Nuclear Engineering was not available to provide a reactivity prediction.

Event Malf. Event Event No. No. Type* Description I (RO) 1 Tcold Instrument Fails High TS (SRO) 2 R (RO) Restore Tave to Tref (Power reduction per TSO) 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 1 of 16

2012 ILT NRC SIMULATOR EVALUATION #3 QUANTITATIVE ATTRIBUTES Malfunctions:

Before EOP Entry:

1. T cold 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. T cold 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 2 of 16

2012 ILT NRC SIMULATOR EVALUATION #3 SCENARIO OVERVIEW:

INITIAL CONDITIONS:

1. No equipment is OOS.

SEQUENCE OF EVENTS:

Event 1: T cold instrument fails high

  • T cold instrument fails high causing auctioneered T avg 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 T avg to T ref 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.

Event 7: Main Feedwater line break inside containment

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

Page 3 of 16

2012 ILT NRC SIMULATOR EVALUATION #3 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 4 of 16

2012 ILT NRC SIMULATOR EVALUATION #3 EVENT 3, SWAP 11 AND 13 CONDENSATE PUMPS - NORMAL EVOLUTION EVENT 1. When the crew has assumed the duty, and at the I(RO) 1C5 AOP1, UNCONTROLLED ROD MOTION 1&2 discretion of the lead evaluator, enter the malfunction to

  • Check Generator Electrical Load - STABLE cause the Blue Channel T cold to fail high. (Relative
  • Place Rod Bank Selector Switch to MANUAL Order 1, Trigger 1)
  • Check Rod Motion - STOPPED
  • Check for Failed Instrument:
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: C47012-0104, REACTOR COOLANT SYSTEM HI TAVG bistables will not be tripped during this
  • Check RCS Tavg scenario.)
  • If due to an instrument malfunction:
b. If contacted as Operations Management, o Place rod control in manual and adjust as needed acknowledge the report of the failure, and if asked o Shift charging pumps to manual and adjust as agree to make other notifications to the NRC needed Resident Inspector, Duty Station Manager. o Verify steam dumps not armed
c. If contacted as the FIN team supervisor, inform the o Refer to 1C51 crew that you will write a work order and assign an I&C supervisor to investigate. 1C51.3, TAVG LOOP 1B 1T-403 - HIGH
d. If desired, allow the crew to hold a crew brief.
  • 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
  • Select blue channel on the Tavg defeat switch and pull out
  • Return the following to auto:

o Rod control o Charging pump speed control T.S. o Steam dumps (SRO)

  • Refer to T.S:

o LCO 3.3.1 condition A, table 3.3.1-1 function 6, 7 o T.S. LCO 3.3.1 Condition E will be entered o LCO 3.3.2 condition A, table 3.3.2-1 function 4d o T.S. LCO 3.3.2 Condition D will be entered o TRM TLCO 3.3.3 condition A

  • Trip bistables Page 5 of 16

2012 ILT NRC SIMULATOR EVALUATION #3 EVENT 3, SWAP 11 AND 13 CONDENSATE PUMPS - NORMAL EVOLUTION EVENT 2 2. When the crew has restored Tave to Tref, and/or at the 1C1.4 UNIT 1 POWER OPERATION discretion of the Lead Evaluator, deliver the direction for R(ATC) 5.3 Small Turbine Load Adjustment the crew to reduce power to 90%.

3.
  • IF desired, THEN place CS-46280, ROD BANK
a. When directed by the Lead Evaluator contact the SELECTOR, in MANUAL. Refer to Precaution 3.7.

control room as the TSO and direct power

  • Reduce load to 90%

reduction to 90% power.

b. When contacted, as Duty Chemist, acknowledge load change.

Note: This event only needs to be performed if, in the opinion of the Lead Evaluator, adequate performance of reactivity manipulations has not been observed for the ATC operator.

Page 6 of 16

2012 ILT NRC SIMULATOR EVALUATION #3 EVENT 3, SWAP 11 AND 13 CONDENSATE PUMPS - NORMAL EVOLUTION EVENT 3 4. When the crew has restored Tavg to Tref, and/or at the 1C28.3, UNIT 1 CONDENSATE SYSTEM discretion of the Lead Evaluator, notify the control room N(BOP, Section 5.6 Swapping Condensate Pumps of abnormal noise in the 11 Condensate pump SRO)

  • Local prestart checks (Relative Order 3)
  • Check condensate pump gland seal water flow using the following:
a. As the Shift Manager, contact the control room and o Following annunciators NOT LIT:

inform the Shift Supervisor the Condensate system 47009-0402, 11 CONDENSATE PUMP SEAL engineer, over the course of a system walk-down, WATER LO PRESS discovered an abnormal noise coming from the 11 47009-0403, 12 CONDENSATE PUMP SEAL Condensate pump and has recommended WATER LO PRESS swapping the 11 and 13 Condensate pumps due to 47009-0404, 13 CONDENSATE PUMP SEAL concern of imminent failure and that you agree with WATER LO PRESS this course of action. Indicate the System Engineer

  • Place the desired condensate pump selector switch in will be writing a CAP and WR to address the pump MANUAL.

and will contact the FIN team.

  • Start the desired condensate pump by placing the
b. Follow along in 1C28.3 step 5.6 and report back all control switch to the START position.

local actions and checks are complete as

  • Check the bearing temperatures and motor stator requested after 2 minutes. None of the local checks temperatures on ERCS are modeled in the simulator.
  • Stop the desired condensate pump by placing the
c. If contacted as the SM and/or the Condensate control switch to the STOP position.

system engineer for a recommendation on the Note: 11 Condensate may be placed in Pullout due to auto/manual selector for 11 Condensate pump then concerns with imminent failure.

recommend placing the 11 Condensate pump into

  • If desired, then place a condensate pump selector pullout. switch in STANDBY.
d. If contacted as the Duty Chemist, acknowledge
  • Open the discharge vent valve of the condensate condensate pumps will be swapped.

pump that was stopped - local.

Note: While operating 3 condensate pumps, Heater Drain Tank alarms are likely to be received.

Page 7 of 16

2012 ILT NRC SIMULATOR EVALUATION #3 EVENT 4, PRESSURIZER PORV PCV-431C LEAKAGE EVENT 4 5. When the crew has swapped running Condensate C(RO) 47012-0109 PRZR SAFETY/RELIEF VALVE FLOW Pumps, and/or at the discretion of the Lead Evaluator,

  • Check flow monitor light to determine which valve enter the malfunction to cause Pressurizer PORV PCV- opened.

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

  • Depress individual flow monitor lights to reset alarm
a. If contacted as Operations Management, and lights.

acknowledge the report of the failure, and if asked

  • Check safety/relief line temperatures, they should agree to make other notifications to the NRC decrease after valves reseat.

Resident Inspector, Duty Station Manager.

  • Determine cause for opening of valve.
b. If contacted as the FIN team supervisor, inform the
  • If PORV fails to seat, then close PORV block valve crew that you will write a work order and assign a with power maintained to the valve.

Mechanical Maintenance supervisor to investigate. T.S.

  • Evaluate T.S. 3.4.10.
c. If desired, allow the crew to hold a crew brief. (SRO)
  • Evaluate T.S. 3.4.11.
  • Evaluate T.S. 3.4.14
  • 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 8 of 16

2012 ILT NRC SIMULATOR EVALUATION #3 EVENT 5, FEEDWATER PUMP LOCK OUT EVENT 6, AUTOMATIC SCRAM FAILURE EVENT 5 6. When the crew has closed the leaking PORVs C(ATC) C47010:0101, 11 Feedwater Pump Locked Out

&6 associated block valve, and/or at the discretion of the

  • If reactor power is greater than 85%, then manually Lead Evaluator, enter the malfunction to trip the 12 trip the reactor and go to 1E-0, Reactor trip or Safety Condensate Pump. (Relative Order 5, Trigger 5) Injection.

C(BOP) C47017:0304 11 STM GEN LO LO LVL Reactor Trip NOTE: When the reactor is tripped proceed immediately

to Event 7.

Page 9 of 16

2012 ILT NRC SIMULATOR EVALUATION #3 EVENT 7, MAIN FEEDLINE BREAK INSIDE CONTAINMENT EVENT 8, TRAIN A SAFEGUARDS EQUIPMENT FAILS TO AUTO-START EVENT 7 7. When the crew has recognized the need to trip the M(ALL) 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 control room before transition out of E-0.

Feedline break inside containment. (Relative Order 7,

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 C(BOP)

  • Perform Attachment L. (see page 20 for Att. L actions)

(Relative Order 7a).

  • Check AFW Status
b. If directed to open reactor trip breakers, wait 1 minute and delete malfunctions RP02A and RP02B
  • Verify total AFW flow greater than 200 gpm.

and then report completion (Relative Order 7b).

  • Verify AFW pumps discharge pressure greater than
c. If directed to perform cation column frisks 900 psig.

acknowledge the order and, after 1 minute, report

  • Check SG levels NR >5% [WR > 50%] in any SG.

BOTH 11 and 12 Steam Generator cation columns

  • Control feed flow to maintain SG level NR 5% to 50%

are reading background. [WR between 50% and 59%].

d. If Unit 2 is requested to perform Attachment L,
  • Check RCS temperatures stable at or trending to inform the crew Unit 2 has no available personnel. 547°F.
  • Check PRZR PORVS and Spray Valves:
  • PRZR Spray Valves closed.
  • Check if RCPs should be stopped:

o Injection flow into the RCS o RCS Pressure less than 1250 [1575] psig o Operator Controlled cooldown NOT in progress

  • 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 11 SG.
  • Check if either SG is NOT faulted:
  • Identify faulted SG.

Page 10 of 16

2012 ILT NRC SIMULATOR EVALUATION #3 EVENT 7, MAIN FEEDLINE BREAK INSIDE CONTAINMENT EVENT 8, TRAIN A SAFEGUARDS EQUIPMENT FAILS TO AUTO-START EVENT 7

  • Isolate faulted SG.

&8 o Isolate main feedline cont o Isolate AFW flow o Close steam supply valve to TD AFW pump o Verify SG PORV - CLOSED o Verify SGB isolation valve - CLOSED Critical Task: Isolate the faulted STEAM 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 [35°F].

o Total feed flow to intact SGs - greater than 200 GPM

- OR -

Narrow range level in at least one intact SG -

Page 11 of 16

2012 ILT NRC SIMULATOR EVALUATION #3 EVENT 7, MAIN FEEDLINE BREAK INSIDE CONTAINMENT EVENT 8, TRAIN A SAFEGUARDS EQUIPMENT FAILS TO AUTO-START EVENT 7 greater than 5% [WR 50%]

&8 o RCS pressure:

cont Pressure - GREATER THAN 2000 PSIG.

Pressure - STABLE OR INCREASING.

o PRZR level - GREATER THAN 7% [27%].

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

1ES-0.2, SI TERMINATION

  • Reset Containment Isolation.
  • Establish instrument air to containment.
  • Stop Safeguards Pumps.
  • Check if charging flow has been established.
  • Verify SI flow is not required.

Page 12 of 16

2012 ILT NRC SIMULATOR EVALUATION #3 ATTACHMENT L ACTION/VERIFICATIONS

8. 1E-0 Attachment L actions 1E-0 Attachment L: SI Alignment Verification
  • Verify Safeguards Component Alignment:
  • Verify both trains of SI actuated:

o Both RHR pumps - RUNNING

-OR-o Both SI pumps - RUNNING

  • RNO Manually actuate SI.
  • "SI NOT READY" lights - NOT LIT
  • "SI ACTIVE" lights - LIT FOR PLANT CONDITIONS
  • "CONTAINMENT ISOLATION" lights - LIT FOR PLANT CONDITIONS
  • Check Category 1 Vent Zone Boundary:
  • Close MV-32117, 121 SFP HX INLT HDR MV A
  • Check Cooling Water Header Pressures - BOTH GREATER THAN 65 PSIG
  • Verify Plant Announcements Complete:
  • Check If Main Steamlines Are Isolated:
  • MSIVs and bypass valves - CLOSED
  • Containment instrument air valves - CLOSED:
  • Verify SI Flow:
  • Verify RHR Flow
  • Check RCP Cooling
  • Verify Local Actions Complete
  • Verify Generator Breakers - OPEN
  • Verify All Heater Drain Pumps - STOPPED
  • Check Turbine Valves:

o Turbine reheat and intercept valves - CLOSED o Open turbine drain valves

o Both main feedwater pumps - STOPPED o Main and bypass FRVs - CLOSED

  • Verify All Condensate Pumps - STOPPED:
  • Place Steam Dump In "STM PRESS" Mode
  • Verify Unit 1 Cooling Water/Chilled Water Alignment:

Page 13 of 16

2012 ILT NRC SIMULATOR EVALUATION #3 ATTACHMENT L ACTION/VERIFICATIONS o CFCU control switches - "SLOW".

o CFCU dampers - ALIGNED TO DOME o Unit 1 cooling water/chilled water valves closed o Unit 1 CRDM shroud cooling supply and return valves - CLOSED o CFCU cooling water supply and return valves -

OPEN o CFCU chilled water supply and return valves -

CLOSED

  • Verify Control Room Ventilation Alignment:

o Chillers and fans - RUNNING o Control room chiller suction/discharge tie closed -

STATUS LIGHT LIT

  • Verify Unit 1 Cooling/Chilled Water Alignment
  • Check Status Of Notifications
  • Notify SS Of Any Discrepancies
9. 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 Page 14 of 16

RETENTION: 7 Days UNIT 1 LPEO / PEO TURNOVER LOG DATE: DAY/NIGHT SHIFT: Day CAT 1 VENT OPENINGS: 0 ft2 SYSTEM CONDITION: GREEN SAFEGUARDS EQUIPMENT OOS/TECH SPEC REQUIRED ACTION STATEMENTS NONE PROTECTED EQUIPMENT NONE RAD MONITORS OOS ANNUNCIATORS OOS OUTSTANDING SPS FIRE DET / PROT EQP IMPAIRMENTS OTHER EQUIPMENT OOS / STATUS MAJOR EQUIPMENT REPAIRED / RETURNED TO SERVICE OPERATIONAL PLANS FOR COMING SHIFT Maintain 92% power.

Reduce power if/when requested by the TSO.

Dilute 25 gallons every 15 minutes for a ~0.1°F temperature change.

NEW PROCEDURES / INSTRUCTIONS Page 15 of 16

Reactivity Plan The crew has been informed of potential need to reduce turbine load from 530 Mw to 520 Mw.

Prior to simulator:

  • verify the reactivity plan completed by the off going reactor operator
  • complete a Pre-Job Brief of:

o 1C1.4 Section 5.3 Current conditions are:

In the last hour the TSO has requested multiple small (<2%) power reductions due to grid loading.

Power level: 529 MW (91.7%)

Xenon: Building in (100% to ~92% power reduction over last hour)

Control Rod Position: Bank D @ 200 steps Boron Concentration: 635 ppm Core Exposure: 10000 MWD/MTU Target: Turbine load 520 Mw (Power Level: ~90%)

Rate: 0.25% /minute Control Mode: Load Control with Rod Control in Manual Boration/Dilution: 25 gal dilutions every 15 minutes Reactivity Prediction:

Change in Power Defect: 28 pcm Differential Boron Worth: -7.2 pcm/ppm Calculated RCS PPM change: 1.9 ppm Assumed 1/2 rods and 1/2 RMU addition Calculated Boric Acid / Reactor Makeup Water addition: 1.9 ppm change = 3 gals Boric Acid Calculated final Control Rod Position : Bank D @ 197 steps Page 16 of 16

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