Text

12-2003 - Draft Exam
	ML050480170
Person / Time
Site:	San Onofre
Issue date:	12/30/2003
From:	Gody A; Operations Branch IV
To:	Ray H; Southern California Edison Co
References
	50-361/03-301, 50-362/03-301 50-361/03-301, 50-362/03-301
	Download: ML050480170 (439)
	v • d • e

Question 1:

Given the following conditions:

Reactor Power 100%

CEA 23 LEL is lit, core mimic light for CEA 23 is lit Tave is 540F and lowering Which one of the following actions should be taken in accordance with SO23-13-13 A. Within 15 minutes of discovery initiate Rx Power reduction of 5% by inserting Gp P rods.

B. Within 15 minutes of discovery initiate Rx Power reduction of 5% by inserting Gp 6 rods.

C. Within 15 minutes of discovery initiate Rx Power reduction of 5% by boration.

D. Within 15 minutes of discovery initiate Rx Power reduction of 5% by reducing turbine load using CVOL.

Answer: C.

Reference:

SO23-13-13, Misaligned or immovable Control Element Assembly Learning Objective: _________________________ (As available)

Question Source: Bank # _______

Modified Bank # _______

New __X__

Examination Outline Cross-reference: Level RO SRO K/A # 00005 AK3.05_ 000005 AK3.05_

Importance Rating _3.7_ _3.8_

Tier # __1__ __1__

Group # __1__ __1__

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis X_

10 CFR Part 55 Content: 55.41 _____

55.43 _____

Question 2 Given the following conditions:

Unit 3 operating at 100% full power.

Reactor coolant pump 1A, RCN-P01A, has the following stable indications:

Seal #1 inlet pressure 2250 psia Seal #2 inlet pressure 585 psia Seal #2 outlet pressure 490 psia Controlled Bleedoff flow 4.9 gpm Seal #1 inlet temperature 115 degF Seal #2 inlet temperature 115 degF Seal #2 outlet temperature 120 degF Which one of the following describes the status of the RCP 1A seal system?

A. Seal #1 is degraded.

B. Seal #2 is degraded.

C. Seal #3 is degraded.

D. Nuclear cooling water flow is degraded.

Answer: B

Reference:

SO23-12-1, LOSS OF COOLANT ACCIDENT Question Source: Bank # ___X__

Modified Bank # ___ ___

New __ __

Examination Outline Cross-reference: Level RO SRO K/A # 00015G2.1.28_ 000015G2.1.28_

Importance Rating _3.2_ _3.3_

Tier # __1__ __1__

Group # __1__ __1__

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis X_

10 CFR Part 55 Content: 55.41 _____

55.43 _____

Question 3 Given the following conditions:

The plant has been operating at 100% power for the past 4 weeks.

Letdown non-regenerative heat exchanger outlet temperature is 85 F.

At the end of your shift, you notice that Circulation water inlet temperature has dropped 5 F.

Tave has increased 3 F Generator KW output has increased 2 MW Which one of the following best explains the changes in Tave and Generator output?

A. The burnout of fuel has resulted in a decrease in positive reactivity of the core.

B. The Purification Ion Exchanger's increased absorption of boron has resulted in an inadvertent reactivity addition.

C. The lower circulating water injection temperature has resulted in reduced condenser pressure (better vacuum), which improved the efficiency of the generator.

D. The continued high power operations has resulted in an increase in burnable and non-burnable poisons as well as a depletion of the fuel, this has resulted in a net increase in the positive reactivity in the core.

Answer: B

References:

Lesson Objective: 6551 Per the Emergency Boration of the RCS or Inadvertent Dilution/Boration procedure, SO23-13-11, The basis for each step, caution, or note.

The expected plant response for each step Question Source: Bank # ___ ___

Modified Bank # _______

New ___X _

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 0024AK1.02 0024AK1.02 Importance Rating 3.6 3.9 Tier # 1 1 Group # 1 1

Question 4 The following conditions exist:

Rx is at 99.3% power SWC injection temperature is 58 F.

Component Cooling Water (CCW) has been lost to the Non Critical Loop.

You have entered AOI SO23-13-7 Loss of CCW / SWC and determined you are unable to restore flow.

According to AOI SO23-13-7, "Loss of CCW/SWC, What is the required immediate action and the reason for this action?

A. Trip the reactor to prevent overheating of the CEADMs B. Trip the reactor coolant pumps to prevent overheating the RCP seals C. Trip the reactor coolant pumps to prevent overheating the RCP bearings D. Trip the reactor to prevent overheating the RCP bearings ANSWER: D

References:

AOI SO23-13-7 Question Source: Bank # ___ ___

Modified Bank # _______

New ____ X .

Question Cognitive Level: Memory or Fundamental Knowledge _X_

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # 000026AK3.03 000026AK3.03 Importance Rating 4.0 4.2 Tier # 1 1 Group # 1 1

Question 5 Given the following:

The plant is at 100% Power.

Pressurizer Pressure Controller, 2PIC-100, is in Automatic.

All other Pressurizer pressure controls are in their normal configuration.

In preparation for maintenance, the second and third point Heaters E038 and E040 are by passed.

All other systems respond as designed.

No other operator action is taken.

Considering only the effects of the above conditions on Pressurizer pressure.

Which ONE (1) of the following correctly describes the response of the plant with no operator action?

A. There is an outsurge from the Pzr, the spray valves modulate open, steam in the Pzr will expand to mitigate the pressure transient, output from the proportional heaters will increase.

B. There is an insurge into the Pzr, the spray valves modulate shut, steam in the Pzr will condense to water to mitigate the pressure transient, output from the proportional heaters will decrease.

C. There is an insurge into the Pzr, the spray valves modulate open, steam in the Pzr will condense to water to mitigate the pressure transient, output from the proportional heaters will increase.

D. There is an outsurge from the Pzr, the spray valves modulate shut, water in the Pzr will flash to steam to mitigate the pressure transient, output from the proportional heaters will increase.

Answer: D.

References:

Question Source: Bank # __ __ __

Modified Bank # __ ____

New ___X _

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 000027A1.02 000027A1.02 Importance Rating 2.8 3.1 Tier # 1 1 Group # 1 1

Question 6 Given the following plant conditions:

- Unit 2 tripped due to an ESD in the MSSS

- SIAS, CIAS, and MSIS have actuated

- SO23-12-5 Excessive Steam Demand is in progress

- S/G E089 pressure is 115 psia and TRENDING DOWN

- S/G E089 T-hot is 495 degrees F and STABLE

- S/G E089T-cold is 420 degrees F and TRENDING UP

- S/G E088 pressure is 900 psia and TRENDING DOWN

- S/G E088 T-hot is 485 degrees F and TRENDING DOWN

- S/G E088 T-cold is 472 degrees F and TRENDING DOWN

- Pressurizer Pressure is 1800 psia and TRENDING UP

- Pressurizer Level is 25% and TRENDING UP Which one of the following indicates the target S/G pressure required to stabilize RCS temperature?

A. 340 psia B. 590 psia C. 525 psia D. 650 psia Answer: C

References:

SO23-12-5 Question Source: Bank # ___X___

Modified Bank # _______

New ___ _

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # CE/A11 W/E08 EK2.2 CE/A11 W/E08 EK2.2 Importance Rating 3.6 4.0 Tier # 1 1 Group # 1 1

Question 7 Given the following:

Reactor power is 10%.

A main turbine roll to 1800 rpm is in progress.

Condenser vacuum has begun degrading.

Annunciators 99B37 VACUUM LO is actuated.

Which ONE (1) of the following immediate actions should the Crew take?

A. Reduce turbine speed to stabilize condenser vacuum.

B. Raise Tave to reduce SDBCS load.

C. Trip the turbine before exceeding 7 inches Hg absolute.

D. Observe the vacuum trend to determine if the turbine must be tripped over the next five (5) minutes.

Answer: C.

References:

Question Source: Bank # ___X___

Modified Bank # _______

New ____

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 0051AA2.02 0051AA2.02 Importance Rating 3.9 4.1 Tier # 1 1 Group # 1 1

Question 8 On Unit 2 the plant conditions are as follows:

Reactor has just tripped.

SPTA immediate operator actions have been completed.

Both 1E AC 4160 volt busses and associated Load Centers and Motor Control Centers are de-energized.

Station Blackout has been diagnosed.

During the recovery and restoration of power, Train A 1E 4 kV bus is not energized.

Which of the following Motor Control Centers is used to cross- connect the 3B04 and 2B04 busses?

A. MCC 2BE B. MCC 2BY C. MCC BQ D. MCC BS Answer: C

References:

SO23- 12-8 Question Source: Bank # ___ ____

Modified Bank # ___X __

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge _X__

Comprehension or Analysis _ __

Examination Outline Cross-reference:

Level RO SRO K/A # 000055EA1.07 000055EA1.07 Importance Rating 4.3 4.5 Tier # 1 1 Group # 1 1

Question 9 Which of the following Reactor Trip Circuit Breakers would indicate open on a loss of 120V Vital AC bus Y001?

A. Breakers 1 and 5.

B. Breakers 2 and 7.

C. Breakers 3 and 6.

D. Breakers 4 and 8.

Answer: A.

References:

Question Source: Bank # ___ ____

Modified Bank # _____ __

New __X __

Question Cognitive Level: Memory or Fundamental Knowledge __X__

Comprehension or Analysis _____

Examination Outline Cross-reference:

Level RO SRO K/A # 000057AA2.19 000057AA2.19 Importance Rating 4.0 4.3 Tier # 1 1 Group # 1 1

Question 10 Given the following conditions:

Unit is operating at 100% Power Nuclear service water pump P138 in running in manual and Nuclear Service Water Pump P139 is secured in AUTO.

Combined pump discharge header pressure on CR-61 is 137 psig Nuclear service water pressure low alarm is received on CR-61, the operator notes that Combined pump discharge header pressure on CR-61 is 70.5 psig and lowering.

Which ONE of the following indications as monitored in the control room would indicate that P-139 has started and is operating properly?

A. Nuclear service water pressure low alarm on CR-61 clears and Combined pump discharge header pressure on CR-61 indicates 137 psig.

B. Nuclear service water pressure low alarm on CR-61 starts to slow flash and Combined pump discharge header pressure on CR-61 returns to 87 psig.

C. Nuclear service water pressure low alarm on CR-61 clears and Combined pump discharge header pressure on CR-61 returns to 87 psig.

D. Nuclear service water pressure low alarm on CR-61 starts to slow flash and Combined pump discharge header pressure on CR-61 returns to 137 psig.

Answer: B

References:

SO23-450 Question Source: Bank # ___ ___

Modified Bank # _______

New ___X___

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X___

Examination Outline Cross-reference:

Level RO SRO K/A # 000062AA1.02 000062AA1.02 Importance Rating 3.2 3.3 Tier # 1 1 Group # 1 1

Question 11 A fire has occurred in the Unit 2 30' Turbine Building switchgear room. The Ops Fire Technical Advisor informs the Shift Manager in the Control Room that the Fire Department Incident Commander intends to use water to extinguish the fire. Some of the switchgear in the area is still energized.

What action should be taken?

A. Prohibit the use of water as an extinguishing agent in the vicinity of all electrical components, whether energized or deenergized.

B. Inform the Incident Commander an alternate fire suppression agent must be used if any energized switchgear is actively involved in the fire.

C. Permit the use of water as a fire suppression agent only after all switchgear in the area has been completely deenergized.

D. Ensure the Incident Commander is aware of the energized switchgear, and let the Incident Commander determine the most appropriate extinguishing agent.

Answer: D

Reference:

Question Source: Bank # ___X___

Modified Bank # _______

New _______

Question Cognitive Level: Memory or Fundamental Knowledge __X__

Comprehension or Analysis _____

Examination Outline Cross-reference:

Level RO SRO K/A # 000067AA1.08 000067AA1.08 Importance Rating 3.4 3.7 Tier # 1 1 Group # 1 1

Question 12 Given:

The following, are received in the Control Room Alarm 61A15 "FIRE",

Alarm 61A11 "FIRE PUMP P-220(E) RUNNING" Alarm 61A12 "FIRE PUMP P-221(C) RUNNING" Alarm 61A13 "FIRE PUMP P-222(W) RUNNING" A report is received from the plant operator that there is heavy black smoke in area 2-AC-30-26.

In accordance with AOI SO23-13-2 Shutdown from outside the Control Room, which is the corrsct method of shutting down the reactor?

A. Open the output breakers for the CEDM motor-generator units B. Secure the RCPs from control handswitches or by selecting the 6.9KV buses to manual and opening all feeder breakers C. Trip the reactor from either set of manual trip pushbuttons D. Open the input breakers for the CEDM motor-generator units Answer: C

References:

SO23-13-2 Question Source: Bank # __ ____

Modified Bank # _______

New __X .

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 000068AK2.02 000068AK2.02 Importance Rating 3.7 3.9 Tier # 1 1 Group # 1 1

Question 13 Given the following plant conditions:

The reactor is tripped on Steam Generator low level due to a feed line break inside containment.

186 Lockout on normal supply breaker for bus 2A04.

SIAS/CIAS were manually initiated.

Which of the following statements is correct concerning the remaining system capacity for reducing temperature and pressure in containment and Iodine removal capability?

A. Temperature and pressure reducing capability 50%, Iodine removal capability 50%

B. Temperature and pressure reducing capability 100%, Iodine removal capability 100%

C. Temperature and pressure reducing capability 150%, Iodine removal capability 200%

D. Temperature and pressure reducing capability 100%, Iodine removal capability 50%

Answer: B

Reference:

SO23-740 Question Source: Bank # __ ____

Modified Bank # _______

New __X .

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 000069EK1.2 000069EK1.2 Importance Rating 3.3 3.6 Tier # 1 1 Group # 1 1

Question 14 Given the following:

The plant tripped due to a Loss of Offsite Power 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ago.

A bus lockout occurred on Electrical Bus 2A3 and cannot be reset.

AFW Pump P-140 trips on over speed and cannot be reset.

The Loss of Feed Water SO23-12-6 has been entered.

RCS pressure is 2100 psia and rising.

RCS T-cold is rising at an uncontrolled rate.

Both Steam Generator levels are 95 inches and dropping.

The correct action to take based on these conditions would be to:

A. Establish Once Through Cooling with SI flow to remove RCS heat at this time.

B. Establish Once Through Cooling to remove RCS heat at < 70 inches in either SG.

C. Transition to the Emergency Operating Procedures to establish RCS heat removal.

D. Transition to Once Through Cooling for RCS heat removal after SGs are dry.

Answer: A.

References:

SO23-12-6 Question Source: Bank # __X____

Modified Bank # _______

New ____

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 000074EK3.11 000074EK3.11 Importance Rating 4.0 4.1 Tier # 1 1 Group # 1 1

Question 15 Given the following plant conditions:

A LOCA has been identified Pressurizer pressure is 1250 psia and steady Pressurizer level is 100% and steady HPSI injection valves are fully open Thot is 552F Tcold is 545F CET is 562F No RCPs are running Containment temperature is 195°F Containment pressure is 11 psig A cooldown is in progress using steam generators Which of the following actions should be directed by the CRS?

A. Secure HPSI pumps to allow RCS to depressurize so maximum injection flow with the LPSI system can be achieved.

B. Throttle HPSI flow to allow depressurization of the primary system and prevent pressurized thermal shock.

C. Throttle HPSI flow to restore pressurizer level to indicating range.

D. Continue maximum HPSI injection flow to ensure adequate cooling for the core.

Answer: D Handout reference material: Steam Tables Question Source: Bank # ___ ___

Modified Bank # ______

New __ X __

Question Cognitive Level: Memory or Fundamental Knowledge ____

Comprehension or Analysis _X_

Examination Outline Cross-reference:

Level RO SRO K/A # E03EK2.1 E03EK2.1 Importance Rating 3.6 4.0 Tier # 1 1 Group # 1 1

Question 16 Unit 2 has high RCS Activity and is in the process of cooling down on SDC. The SDC Purification System is in service. It has become necessary to replace CVCS Purification Filter, 2(3)F-020, cartridge.

Which of the following is used to fill and vent the CVCS Purification Filter, 2F020, following filter cartridge replacement?

A. Nuclear Service Water and returned to the VCT.

B. Primary Plant Make Up Water and returned to Radwaste.

C. Primary Plant Make Up Water and returned to the VCT.

D. Nuclear Service Water and returned to Radwaste Answer: D

References:

Question Source: Bank # ___X ___

Modified Bank # ____ ___

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge __ __

Comprehension or Analysis ___X_

Examination Outline Cross-reference:

Level RO SRO K/A # 000076G2.1.32 000076G2.1.32 Importance Rating 3.4 3.8 Tier # 1 1 Group # 1 1

Question 17 CEA Group 5 is being withdrawn from 108 inches to 123 inches.

At 112 inches on Group 5 the operator releases the CEDMCS joystick.

- CEA 14 and 15 motion stops

- CEA 16 and 17 continue to withdraw The operator terminates all CEA motion by placing CEDMCS in STANDBY mode. CEA 16 and 17 indicate 123 inches.

What action is required, and why?

A. Restore Group 5 alignment within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months by inserting CEA 16 and 17 using MANUAL INDIVIDUAL to preclude excessive power peaking.

B. Immediately open all RTCB's to preclude operation outside of design basis.

C. Reduce thermal power to limits specified in the COLR within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to preclude operation outside of DNBR limits.

D. Restore Group 5 alignment within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months by withdrawing CEAs 14 and 15 in MANUAL INDIVIDUAL to prevent exceeding AZTILT limits Answer: B

References:

Question Source: Bank # ___ ___

Modified Bank # ___X__

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge __ X_

Comprehension or Analysis _____

Examination Outline Cross-reference:

Level RO SRO K/A # 000001G2.2.25 000001G2.2.25 Importance Rating 2.5 3.7 Tier # 1 1 Group # 2 2

Question 18 The following conditions exist Unit 2 is at 85% power Group 6 is at 149 inches withdrawn Recovery of a dropped CEA (#20) is in progress CEA # 20 is at 100 inches withdrawn You notice the following indications:

Pressurizer level is dropping Pressurizer pressure is dropping slowly Thot, Tcold and Tave are lowering Reactor power is 90% and dropping Which of the following is the most likely cause?

A. An ADV on a steam generator has started leaking B. There is a small break loss of coolant accident in progress C. Another CEA has dropped D. These are expected indications during recovery of the dropped CEA.

Answer: C

References:

Question Source: Bank # ___ ___

Modified Bank # _______

New __ X __

Question Cognitive Level: Memory or Fundamental Knowledge __ __

Comprehension or Analysis ___X_

Examination Outline Cross-reference:

Level RO SRO K/A # 000003AA1.06 000003AA1.06 Importance Rating 4.0 4.1 Tier # 1 1 Group # 2 2

Question 19 Given the following plant conditions:

A small break Loss of Coolant Accident has occurred.

RCPs have been secured HPSI Pumps P018 and P019 have been secured All Three (3) charging pumps are running Pressurizer pressure is 1095 psia and steady Pressurizer level is 100%

S/G Levels are 60% and 62%

Thot is 570 F Tcold is 560 F Tave is 566 F Core exit thermocouple temperature is 575 F Which of the following is an appropriate action for these conditions?

A. Secure two (2) Charging Pumps and energize PZR heaters to restore RCS Pressure and reduce Pzr level.

B. Commence bleeding steam from the steam generators to establish natural circulation flow.

C. Start HPSI pumps P018 and P019, fully open all HPSI Injection Valves to raise RCS Pressure.

D. Restart RCPs to commence RCS cooldown and lower pressurizer level Answer: C References for student: Steam Tables

References:

SO23-12-3 Question Source: Bank # ___ ___

Modified Bank # _______

New __ X __

Question Cognitive Level: Memory or Fundamental Knowledge __ __

Comprehension or Analysis ___X_

Examination Outline Cross-reference:

Level RO SRO K/A # 000007EK1.06 000007EK1.06 Importance Rating 3.4 3.9 Tier # 1 1 Group # 2 2

Question 20 Given the following plant conditions:

Safety Injection Actuated PZR Pressure is 1800 psig and slowly DECREASING RCS Temperature is 550 F and slowly DECREASING S/G NR Levels are 1% and slowly INCREASING RDT Pressure is 3 psig and STABLE S/G Pressure's are 1000 psig and STABLE PZR Level is 28% and RISING Containment Temperature is 140°F and slowly RISING Containment Pressure is 8 psig and STEADY Containment Humidity is INCREASING Which ONE of the following could be the cause of the above conditions?

A. RCS leak from a cold leg.

B. S/G Safety Valve failed open.

C. RCS Safety Valve failed open.

D. Pressurizer steam space leak.

Answer: D Question Source: Bank # ___X___

Modified Bank # _______

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge __ __

Comprehension or Analysis ___X_

Examination Outline Cross-reference:

Level RO SRO K/A # 000008AK2.02 000008AK2.02 Importance Rating 2.7 2.7 Tier # 1 1 Group # 2 2

Question 21 Due to a common mode failure, both atmospheric dump valves, HV-8419 and HV-8421, are rendered inoperable. As a result, a unit 2 shutdown is in progress from 100% power. During the unit 2 shutdown, a reactor trip occurred due to a loss of coolant accident concurrent with a loss of offsite power.

Given the following additional information:

Emergency diesel generators are operating normally RCS Th 555 degrees F Pressurizer Pressure 1200 psia Pressurizer Level 34% and stable Reactor Vessel Upper Head Level 16%

Steam Generator #89 NR level 25% with auxiliary feedwater flow established Steam Generator #88 NR Level 26% with auxiliary feedwater flow established Containment Temperature 148 Degrees F Core Exit Temperatures are 560 degrees F Determine which parameter will NOT allow HPSI throttling with the above information:

A. Subcooling Margin.

B. Reactor Vessel Upper Head Level.

C. Pressurizer Level.

D. Steam Generator Steam / Feed Flow.

Answer: A Question Source: Bank # __X___

Modified Bank # _______

New .

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 00009EA3.26 00009EA3.26 Importance Rating 4.4 4.5 Tier # 1 1 Group # 2 1

Question 22 A reactor trip has occurred and the immediate actions of SO23-12-1, "Standard Post Trip Actions," have been completed. You are attempting to diagnose the accident.

Plant conditions are as follows:

CEA #28 indicates fully withdrawn E088 and E089 levels are 24% narrow range and rising slowly E088 and E089 pressures are 1000 psia and stable Pressurizer level is 48% and lowering Pressurizer pressure is lowering rapidly Containment pressure is 0 psig Containment area radiation monitors and Main Steam Line rad monitors are normal SELECT the proper event in progress:

A. PZR Spray valve stuck open.

B. LOCA outside Containment.

C. LOCA inside Containment.

D. Steam Line Break outside Containment.

Answer: B

References:

SO23-12-1 Question Source: Bank # ___ ___

Modified Bank # ___X___

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge __ __

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # E04EA2.01 E04EA2.01 Importance Rating 3.6 4.2 Tier # 1 1 Group # 2 2

Question 23 Unit 2 has experienced a Reactor trip from 100% power due to a fault in the turbine control system.

S/G Levels are: E088 65% NR E089 68% NR Pzr level is 48% and slowly lowering Pzr pressure is 2240 psia Letdown is secured All charging pumps are running The SBC system is operating to maintain S/G pressures at 1000 psia Quench Tank Press HI (50A01) has come in and cleared Quench Tank Level HI/LO (50A11 is locked in Quench Tank Temp HI (50A21) is locked in PZR Safety Valve outlet Temp HI (50A31) is locked in Containment pressure is 1.8 psia and increasing.

Containment temperature and humidity are increasing Attempts by the operator to shut the PZR Blocking valves have been unsuccessful.

Which of the following actions should be taken by the operator to protect the plant?

A. Initiate a manual Safety Injection to provide makeup water to the RCS B. Commence RCS cooldown using the S/Gs and the SBC system C. Commence RCS cooldown at maximum achievable rate using ADVs D. Open PZR normal and auxiliary spray valves to rapidly reduce pressure to less than 1400 psia Answer: B

References:

SO23-15-50.A1 SOSO23-360 SO23-14-3 SO23-12-11 Question Source: Bank # ___ ___

Modified Bank # _______

New __X __

Question Cognitive Level: Memory or Fundamental Knowledge __ __

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # E03EK3.3 E03EK3.3 Importance Rating 3.9 3.9 Tier # 1 1 Group # 2 2

Question 24 During mitigation of a Large Break LOCA, with HPSI and LPSI pumps injecting, a Recirculation Actuation signal actuates.

What is the impact on the long term core cooling if the safety pump minimum recirculation flow valves (HV-9306, 9307, 9347, and 9348) fail to shut?

A. No impact, system is designed with minimum flow valves to protect the pumps from overheating in a low flow condition.

B. Cooling flow through the core will be reduced by a small amount, but no other impact.

C. Cooling flow through the core will be reduced then lost as coolant inventory is lost from the containment emergency sump.

D. The parallel flow path will result in higher total flow from the pumps with no reduction in flow through the core.

Answer: C

Reference:

SO23-740 Question Source: Bank # ___ ___

Modified Bank # _______

New __X __

Question Cognitive Level: Memory or Fundamental Knowledge __ __

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # W/E11EK2.2 W/E11EK2.2 Importance Rating 3.9 4.3 Tier # 1 1 Group # 2 2

Question 25 Given the following conditions:

- Pressurizer pressure is 1250 psia.

- Pressurizer level is 100%.

- HPSI injection is 330 gpm/cold leg (acceptable flow).

- Thot is 550 F

- T cold is 510 F

- Core exit thermocouple temperature is 560 F

- Reactor vessel level monitoring system indicates 100% in plenum and 16% in upper head.

- No reactor coolant pumps are running.

- Containment temperature and pressure are 195 degrees F and 11 psig, respectively.

- SIAS, CIAS, MSIS, and CSAS have actuated.

A cooldown is in progress using steam generators.

WHICH ONE of the following identifies the action the Control Room Supervisor is to direct concerning high pressure safety injection use?

A. Continue maximum injection flow until subcooling is at least 35 degrees F.

B. HPSI flow may be throttled to restore pressurizer level in control band.

C. HPSI flow may be throttled to allow depressurization of the primary system.

D. Continue maximum injection flow until the reactor vessel level monitoring system indicates 100% in the upper head.

Answer: A

References:

Question Source: Bank # ___ ___

Modified Bank # _______

New ____ X .

Question Cognitive Level: Memory or Fundamental Knowledge ____

Comprehension or Analysis __X_

Examination Outline Cross-reference:

Level RO SRO K/A # E01/E02EK1.1 E01/E02EK1.1 Importance Rating 3.9 4.3 Tier # 1 1 Group # 2 2

Question 26 A LOCA has occurred on Unit 2. All safeguards equipment is functioning as designed.

The following conditions exist:

-RCS pressure is 850 psia and STABLE

-Highest Core Exit Thermocouple temperature is 455 degrees F and TRENDING DOWN slowly

-Containment Pressure is 9 psig and TRENDING DOWN slowly

-Containment Temperature is 168 degrees F and TRENDING DOWN slowly

-The crew is performing the action of SO23-12-3, LOSS OF COOLANT ACCIDENT The CRS directs the primary operator to trip ALL RCPs. What is the basis for this action at this time?

A. RCPs are required to be stopped when a loss of subcooling is indicated.

B. RCPs must be stopped to prevent additional RCS inventory loss.

C. RCPs must be stopped to prevent damage due to loss of cooling water.

D. RCPs must be stopped because there is insufficient NPSH to prevent cavitation of the pumps.

Answer: C

Reference:

Question Source: Bank # ___ ___

Modified Bank # _______

New ____ X .

Question Cognitive Level: Memory or Fundamental Knowledge _X___

Comprehension or Analysis __ _

Examination Outline Cross-reference:

Level RO SRO K/A # 000022AK3.06 000022AK3.06 Importance Rating 3.2 3.3 Tier # 1 1 Group # 2 2

Question 27 Given the following plant conditions:

The reactor is shutdown Cooldown of the reactor is in progress at 40F/hr.

RCS Temperature is 280F RCS pressure is 300psia,

- Loop II CCW Surge Tank Level increased from 40% to 55% in 20 minutes.

- Pressurizer Level is 60% and stable.

- VCT level decreased from 77% to 73% in 20 minutes.

Select which of the following components could be causing the CCW Surge Tank Level increase.

(Assume normal equipment conditions)?

A. Spent fuel pool heat exchanger.

B. Shutdown cooling heat exchanger C. Startup and Blowdown Demineralizer Sample Cooler.

D. Steam Generator sample cooler Answer: B

Reference:

Question Source: Bank # ___ ___

Modified Bank # _______

New ____ X .

Question Cognitive Level: Memory or Fundamental Knowledge _X___

Comprehension or Analysis __ _

Examination Outline Cross-reference:

Level RO SRO K/A # 000025AA2.02 000025AA2.02 Importance Rating 3.4 3.8 Tier # 1 1 Group # 2 2

Question 28 WHICH ONE (1) of the following describes how the ATWS Diverse Scram System trips the reactor?

A. Outputs from logic channels 1 and 3 or 2 and 4 are required to open both M-G set contactors to trip the reactor.

B. Outputs from logic channels 1 and 2 or 3 and 4 are required to activate the undervoltage relay to trip the M-G set contactors to trip the reactor C. Outputs from logic channels 1 or 3 and 2 or 4 are required to open both M-G set contactors to trip the reactor.

D. Outputs from logic channels 1 or 3 and 2 or 4 are required to activate the undervoltage relay to trip the M-G set contactors to trip the reactor .

Answer: C

Reference:

SO23-520 Question Source: Bank # ___ ___

Modified Bank # _______

New ____ X .

Question Cognitive Level: Memory or Fundamental Knowledge _X___

Comprehension or Analysis __ _

Examination Outline Cross-reference:

Level RO SRO K/A # 000029EA1.08 000029EA1.08 Importance Rating 4.5 4.5 Tier # 1 1 Group # 2 2

Question 29 Which of the following describes the effect on the Excore Nuclear Instrumentation (NI) Log Safety Channel response if the voltage applied to the fission chamber is too high?

A. The Excore NIs shift from a count rate circuit to a Campbelling circuit at a lower indicated power level.

B. The Excore NIs shift from a Campbelling circuit to a count rate circuit at a higher actual nuclear power.

C. The Excore NIs shift from a count rate circuit to a Campbelling circuit at a lower actual nuclear power level.

D. The Excore NIs shift from a Campbelling circuit to a count rate circuit at a higher indicated nuclear power.

Answer: C

Reference:

SO23-470 Question Source: Bank # ___ ___

Modified Bank # _______

New ___X _

Question Cognitive Level: Memory or Fundamental Knowledge ____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 000032AK1.01 000032AK1.01 Importance Rating 2.5 3.1 Tier # 1 1 Group # 2 2

Question 30 The following conditions exist:

-The reactor has tripped

-CEA's 23 and 24 are not inserted

- Boration is in progress at 41gpm

-Reactor power 1X10-2% and dropping

- SUR is negative

-Standard Post Trip Actions (SPTA) procedure is in progress The reactivity control safety function acceptance criteria ....

A. will not be satisfied until the boration is increased to >44 gpm.

B. are currently satisfied however boration should continue until adequate shutdown margin is established..

C. are currently satisfied and boration may be terminated.

D. will not be satisfied until at least one (1) of the CEA's stuck out is inserted..

Answer: B

Reference:

Question Source: Bank # ___ ___

Modified Bank # __X___

New ___ _

Question Cognitive Level: Memory or Fundamental Knowledge __ __

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 000033AA2.07 000033AA2.071 Importance Rating 3.9 4.2 Tier # 1 1 Group # 2 2

Question 31 Given:

Unit 2 has been operating at 97% power for the last 54 hours6.25e-4 days 0.015 hours 8.928571e-5 weeks 2.0547e-5 months after completing maintenance on the MFW pump.

Turbine load is 1176 MW and steady Pzr level is 53% and lowering slowly Pressurizer pressure is 2140 psia and lowering slowly Thot is 588F Tcold is 538F Tave is 563F Steam Generator E088 parameters are:

Pressure: 805psig FW Flow: 15,360 gpm Stm Flow: 7.7 x 10 6th lbm/hr Steam Generator E089 parameters are:

Pressure: 805psig FW Flow: 15,360 gpm Stm Flow: 7.5 x 10 6th lbm/hr FW Temperature is 445F Containment pressure is 0 psig, temperature and humidity are stable.

Which of the following events is taking place?

A. A steam generator tube rupture is in progress on E088 B. Plant is responding to Xenon buildup following the up power.

C. There is a steam leak on steam generator E088 D. Plant is responding to Xenon burnout following the up power.

Answer: A

References:

Question Source: Bank # ___ ___

Modified Bank # _______

New ___X _

Question Cognitive Level: Memory or Fundamental Knowledge ____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 000038EA1.01 000038EA1.01 Importance Rating 3.5 3.9 Tier # 1 1 Group # 2 2

Question 32 Given the following conditions:

The plant had been operating at full power conditions for three months.

The CRS has completed the Standard Post Trip Actions and entered the Station Blackout procedure.

MSIS has been initiated.

Auxiliary Feedwater pump P-140 started, NO AC power has been restored.

Steaming is being controlled by the ADVs E088 level is 22% NR and lowering E089 level is 21% NR and lowering Thot is 556 F and steady Tcold is 495 F and steady Core exit thermocouple temp is 585 F Which one of the following is the correct actions in accordance with SO23-12-8 STATION BLACKOUT.

A. Single flow natural circulation has been established, continue steaming on the ADVs to maintain RCS in hot standby. Use the AFW pump to feed S/Gs as necessary until main feedwater can be restored.

B. Single flow natural circulation has been established, secure steaming on the ADVs to maintain S/G inventory until normal source of feedwater can be restored C. Single flow natural circulation has not been established. Raise at least one S/G level to maximum allowable level but less than 80% NR or feedwater flow rate of at least 200 GPM and increase the steaming rate on the ADVs D. Two-phase flow natural circulation has been established. Maintain the AFW system in automatic to control S/G levels, increase the steaming rate on the ADVs Answer: C

References:

SO23-12-8 SO23-14-8 Question Source: Bank # ___ ___

Modified Bank # _______

New __X __

Question Cognitive Level: Memory or Fundamental Knowledge __ _ _

Comprehension or Analysis __X___

Examination Outline Cross-reference:

Level RO SRO K/A # E04G2.4.14 E04G2.4.14 Importance Rating 3.0 3.9 Tier # 1 1 Group # 2 2

Question 33 Which ONE (1) of the following describes the effect of a loss of green DC Bus, 2D26 will have on the operation of Emergency Feed water Pump 2P7A?

A. All P-140 discharge valves to both Steam generators will fail open.

B. All P-140 discharge valves to both Steam generators will fail closed.

C. P-140 will over speed.

D. P-140 will go to minimum speed.

Answer: C.

References:

SO23-140 125 and 250 VDC system SO23-6-15 SO-23-12-6 SO23-2-4 Question Source: Bank # ___X___

Modified Bank # _______

New ____

Question Cognitive Level: Memory or Fundamental Knowledge __X__

Comprehension or Analysis _____

Examination Outline Cross-reference:

Level RO SRO K/A # 000058AA2.03 000058AA2.03 Importance Rating 3.5 3.9 Tier # 1 1 Group # 2 2

Question 34 The Unit Three was initially operating at 100% power.

A complete loss of off-site power occurred 5 minutes ago.

Buses have been re energized from the emergency diesel generators.

There are no RCPs running Letdown flow has been restored Pzr Level is 68% and slowly lowering PZR Pressure is 2320psia and slowly lowering MSIVs are open Condenser vacuum is 20 inches In accordance with SO23-12-7,Loss of forced circulation/Loss of off-site power, which of the following is the appropriate action for the operator to take?

A. Operate the AFW system to establish 200gpm flow rate to each S/G for at least 5 minutes B. Operate AFW system to establish at least one intact S/G level between 40% and 80% on the narrow range indication.

C. Operate MFW system to establish at least one intact S/G level between 40% and 80% on the narrow range indication.

D. Operate the MFW system and use main steam Safety valves to steam the S/Gs to establish natural circulation and decay heat removal.

Answer: B Reference SO 23-12-7 step 9 Question Source: Bank # ___ ___

Modified Bank # ___ __

New __ X _

Question Cognitive Level: Memory or Fundamental Knowledge __ __

Comprehension or Analysis __X___

Examination Outline Cross-reference:

Level RO SRO K/A # 000056A3.02 000056A3.02 Importance Rating 4.4 4.7 Tier # 1 1 Group # 3 3

Question 35 Given the following plant conditions:

The reactor is tripped following a Steam Generator Tube Rupture.

RCS pressure is 970 psia.

Thot is 490F Steam Generator #1 pressure is 890 psia.

RU-4 is in high alarm.

Steam generator E089 is isolated.

Steam Generator E089 level is 78% NR and rising slowly.

Steam Generator E088 level is 50% NR and steady.

WHICH ONE of the following is the preferred method to control level in the isolated steam generator?

A. Bypass the MSIV and steam #1 Steam Generator to the condenser.

B. Lower RCS pressure below #1 Steam Generator pressure and allow backflow to the RCS.

C. Steam #1 Steam Generator to atmosphere via the ADVs.

D. Lineup high rate blowdown to the condenser from #1 Steam Generator.

Answer: B

Reference:

Question Source: Bank # __X___

Modified Bank # ___ __

New __ _

Question Cognitive Level: Memory or Fundamental Knowledge __X __

Comprehension or Analysis __ ___

Examination Outline Cross-reference:

Level RO SRO K/A # W/E13G2.3.11 W/E13G2.3.11 Importance Rating 2.7 3.2 Tier # 2 2 Group # 1 1

Question 36 During mitigation of a Large Break LOCA, with HPSI and LPSI pumps injecting, a Recirculation Actuation signal actuates.

What is the expected impact on the running Safety Injection pumps?

A. LPSI pumps stopped, HPSI pumps recirculating RCS to the RWT.

B. LPSI pumps recirculating the RCS, HPSI pumps injecting from RWT.

C. HPSI pumps stopped, LPSI pumps recirculating the RCS to the containment sump.

D. LPSI pumps stopped, HPSI pumps recirculating the RCS to the containment sump.

Answer: D

Reference:

Question Source: Bank # __X___

Modified Bank # ___ __

New __ _

Question Cognitive Level: Memory or Fundamental Knowledge __X __

Comprehension or Analysis __ ___

Examination Outline Cross-reference:

Level RO SRO K/A # W/E15EA1.3 W/E15EA1.3 Importance Rating 2.8 3.0 Tier # 1 1 Group # 3 3

Question 37 Given the following plant conditions:

The plant has just experienced a trip due to grid instabilities Charging pump 2P191 has been tagged out for maintenance.

Charge pump 2P193 is in auto and Charging Pump 2P192 is in standby CEA 23 is stuck fully withdrawn, CEA 24 is stuck at 110 steps withdrawn Power has been lost to 480 Volt Load center 2B06 Charging pump 2P193 trips on loss of suction pressure In accordance with SO23-13-11 Emergency Boration of Reactor Coolant System / Inadvertent Dilution or Boration, which of the following operator actions are required under these conditions?

A. Borate via gravity feed suction path B. Lower RCS pressure and borate via HPSI C. Initiate RCS cooldown and initiate SIAS to borate the reactor D. Stabilize RCS temperature and pressure until at least one charging pump can be restored to operation, then borate.

Answer: B.

References:

SO23-13-11 Emergency Boration of Reactor Coolant System / Inadvertent Dilution or Boration Question Source: Bank # ___ ___

Modified Bank # ___X__

New __ _

Question Cognitive Level: Memory or Fundamental Knowledge __ __

Comprehension or Analysis __X___

Examination Outline Cross-reference:

Level RO SRO K/A # 001A2.03 001A2.03 Importance Rating 3.5 4.2 Tier # 2 2 Group # 1 1

Question 38 Given the following conditions:

- Reactor startup is in progress.

- Critical data has just been recorded.

A 20-second continuous rod withdrawal event now occurs due to the RAISE/LOWER rod control switch being inadvertently stuck in RAISE. NO operator action is taken other than to unstick the control switch and return it to neutral.

WHICH ONE of the following parameters will stabilize at a value greatly different from what it was before the event?

A. Pressurizer level B. Steam generator pressures C. Nuclear instrumentation power E. RCS Hot and Cold leg Temperatures Answer: C

References:

Question Source: Bank # ___ ___

Modified Bank # ___ ___

New ___X .

Question Cognitive Level: Memory or Fundamental Knowledge __ __

Comprehension or Analysis __X___

Examination Outline Cross-reference:

Level RO SRO K/A # 001A3.06 001A3.06 Importance Rating 3.9 3.9 Tier # 2 2 Group # 1 1

Question 39 Given the following plant conditions:

Reactor is shutdown with no Reactor Coolant Pumps running following a Station blackout.

Power has been restored and preparations are under way to restore forced circulation in the Reactor.

Tave is 530F Tcold is 525F Thot is 535F Pressurizer level is 45%

Pressurizer pressure is 2200psia Steam Generator level is: A 51%

B 48%

Steam Generator pressures are 1000 psia being controlled by SBCS.

In accordance with the appropriate operating procedures and instructions, which of the following actions must be taken before starting reactor coolant pumps.

A. Adjust SBCS setpoint to reduce steam generator pressures to less than 920psia.

B. Energize Pressurizer heaters to raise RCS Pressure to greater than 2235psiapsia.

C. Start a charging pump and raise pressurizer level to greater than 53%.

D. Place both lift oil pumps in normal until at least one Reactor Coolant Pump is running in each loop and RCS temperatures have stabilized.

Answer: A Student Reference Material required:

Attachments 4 and 5 of OPERATING INSTRUCTION SO23-3-1.7 Steam Tables

Reference:

OPERATING INSTRUCTION SO23-3-1.7 Question Source: Bank # ___ ___

Modified Bank # _______

New ___X .

Question Cognitive Level: Memory or Fundamental Knowledge __ __

Comprehension or Analysis __X___

Examination Outline Cross-reference:

Level RO SRO K/A # 003K6.14 003K6.14 Importance Rating 2.6 2.9 Tier # 2 2 Group # 1 1

Question 40 Given the following conditions:

Plant is at 99% power RCP 1B seal cavity pressures are approximately equal to reactor coolant system pressure.

A calculation of the RCS leak rate has just been completed and is the same as the previously calculated rate.

Radiation levels are normal What is the most likely cause of the following indications?

A. Inadvertent closure of a RCP Controlled bleed-off isolation valve(s).

B. Failure of the vapor seal.

C. Excessive Control Bleed-Off flow.

D. Failure of RCP middle seal.

Answer A Question Source: Bank # ___ ___

Modified Bank # _______

New __X __

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 003K1.03 003K1.03 Importance Rating 3.3 3.6 Tier # 2 2 Group # 1 1

Question 41 Given the following conditions on Unit 3:

Reactor is at 100% power Pressurizer level is at 43%

Tave is 566F Power is lost to 480V Bus B0413 Which of the following is the expected condition of the CVCS system?

A. Charging pumps P-190, P-191, and P-192 running with letdown flow at minimum.

B. Charging pumps P-190 and P-191running with letdown flow at maximum.

C. Charging pumps P-191 and P-192 running with letdown flow at minimum.

D. Charging pumps P-191 and P-192 running with letdown flow at maximum.

Answer: C Question Source: Bank # ___ ___

Modified Bank # _______

New ___X .

Question Cognitive Level: Memory or Fundamental Knowledge __ __

Comprehension or Analysis __X___

Examination Outline Cross-reference:

Level RO SRO K/A # 004K2.03 004K2.03 Importance Rating 3.3 3.5 Tier # 2 2 Group # 1 1

Question 42 During normal 100% power operations, the instrument air containment isolation valve, IAA-UV-2, closes and cannot be opened. WHICH ONE of the following describes the affect of this failure on the reactor coolant pumps?

A. Seal cooler inlet temperatures will rise requiring a manual trip of the reactor and securing all four RCPs.

B. Seal bleedoff flow will drop however, no RCP trip setpoints will be exceeded.

C. Seal injection flow will rise, however, no RCP trip setpoints will be exceeded.

D. Seal bleedoff flow will rise and the High Pressure Seal Cooler outlet temperature will rise requiring a manual reactor trip and securing all four RCPs.

Answer: C

Reference:

Question Source: Bank # ___X__

Modified Bank # _______

New ___ .

Question Cognitive Level: Memory or Fundamental Knowledge _X __

Comprehension or Analysis __ ___

Examination Outline Cross-reference:

Level RO SRO K/A # 004K1.04 004K1.04 Importance Rating 3.4 3.8 Tier # 2 2 Group # 1 1

Question 43 Given the following plant conditions:

E088 S/G Pressure is 725 psia E089 S/G pressure is 1000psia Pressurizer pressure is 1600psia Pressurizer Level is 42%

Containment pressure is 12 psig Containment Hi Range radiation monitor reads 13 R/hr and is increasing Which of the following ESFAS actuations should NOT have automatically initiated?

A. CRIS B. SIAS C. MSIS D. CSAS Answer: D Question Source: Bank # __X____

Modified Bank # _______

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 013A1.03 013A1.03 Importance Rating 2.6 2.6 Tier # 2 2 Group # 1 1

Question 44 The following plant conditions exist:

An ESFAS actuation has occurred.

S/G-E089 Level = 15% NR S/G-1 Pressure = 580 psia S/G-E088 Level = 20% NR S/G-2 Pressure = 710 psia Which of the following describes the automatic operation of the ESFAS System.

A. AFW is feeding BOTH S/Gs.

B. AFW is isolated to BOTH S/Gs.

C. AFW is feeding S/G-E089 ONLY.

D. AFW is feeding S/G-E088 ONLY.

Answer: D Question Source: Bank # ___X___

Modified Bank # .

New _______

Question Cognitive Level: Memory or Fundamental Knowledge __ ___

Comprehension or Analysis __ X __

Examination Outline Cross-reference:

Level RO SRO K/A # 013A3.02 013A3.02 Importance Rating 4.1 4.2 Tier # 2 2 Group # 1 1

Question 45 The plant is operating at 85% power. Surveillance testing is in progress on the Excore Nuclear Instruments when the following groups of channel trips are received.

High LPD and Low DNBR The most likely cause of this is:

A. Placing the Linear Calibrate Switch to "Zero" on one of the Excore Nuclear Instrumentation channels B. Placing the Rate Calibrate Switch to "Zero" on one of the Excore Nuclear Instrumentation channels C. Placing the Log Calibrate Switch to "Zero" on one of the Excore Nuclear Instrumentation channels D. Placing the Linear Calibrate Switch to "125%" on one of the Excore Nuclear Instrumentation channels Answer: C Question Source: Bank # _______

Modified Bank # X .

New _______

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 015K6.04 Importance Rating 3.1 Tier # 2 Group # 1

Question 46 The following plant conditions exist:

- Large Loss of Coolant Accident has occurred.

- All Reactor Coolant Pumps are secured.

- No Safety Injection Flow is available.

- Reactor Coolant in the core region is at saturated conditions.

SELECT the expected response of the Excore Nuclear Instrumentation System Startup Channels as the coolant in the core region is initially boiled off and level in the core drops.

A. Count rate lowers because there are fewer neutrons generated.

B. Count rate rises because there are more neutrons generated C. Count rate rises because the level in the down comer drops.

D. Count rate lowers because the level in the down comer rises.

Answer: C

References:

Question Source: Bank # __ ____

Modified Bank # __ X___

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 015G2.2.2 015G2.2.2 Importance Rating 4.0 3.5 Tier # 2 2 Group # 1 1

Question 47 A Loss of Coolant Accident has occurred in unit 2 and the following conditions exist:

Pzr Pressure is 1100 psia Pzr level is 12% and slowly increasing Thot is 561F Tcold is 557F What additional indications would alert the Control Room Operators that Core uncovery is occurring and where could they obtain them?

A. Core Exit Thermocouple (CET) temperatures increasing. They can be obtained from CFMS page 311.

B. Core Exit Thermocouple (CET) temperatures increasing. They can be obtained from QSPDS page 311.

C. Core Exit Thermocouple (CET) temperatures steady. They can be obtained from QSPDS page 411.

D. Core Exit Thermocouple (CET) temperatures steady. They can be obtained from CFMS page 411.

Answer: A

References:

SO23-12-8 Question Source: Bank # __ ____

Modified Bank # __ _____

New __ X __

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 017A4.01 017A4.01 Importance Rating 3.8 4.1 Tier # 2 2 Group # 1 1

Question 48 Given the following conditions:

Unit 2 operating at 100% full power.

One Core Exit Thermocouple failed to 0 output.

Which of the following describes the effect of this failure on the Qualified Safety Parameter Display System (QSPDS) Representative CET (REPCET) reading?

A. Indicates lower, since 0 temp indication is averaged into calculation.

B. Does not change, input not used in calculation.

C. Indicates lower, flagged as invalid.

D. Indication will flash indicating failure of input. Operator can manually delete failed input to restore display.

Answer: B

Reference:

Question Source: Bank # __ _ ___

Modified Bank # __ _X___

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge ___X__

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # 017K3.01 017K3.01 Importance Rating 3.5 3.7 Tier # 2 2 Group # 1 1

Question 49 Given the following plant conditions:

- RCS pressure, temperature, power, and inventory stable.

- Steam Generator pressure and levels stable.

- Containment temperature, pressure, and humidity rising rapidly.

- Containment Sump increasing at a rate of 150 gpm.

Which ONE (1) of the following events is in progress?

A. RCS leak in Containment.

B. Main Steam Leak in Containment.

C. CCW leak in Containment.

D. Main Feed water leak in Containment.

Answer: D.

References:

Question Source: Bank # __ ____

Modified Bank # __ _____

New __ X __

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 022A4.05 022A4.05 Importance Rating 3.8 3.8 Tier # 2 2 Group # 1 1

Question 50 Given the following plant conditions:

The reactor is tripped.

SIAS is actuated.

Pressurizer level is 10% and lowering.

CSAS is NOT initiated.

Containment pressure is rising slowly on all channels.

Containment pressure is 9.0 psig on Channel 'A'; 8.5 psig on Channel 'B', 8.0 psig on Channel 'C, and 8.0 psig on Channel 'D'.

WHICH ONE of the following should be performed?

A. Manually initiate CSAS due to the CSAS setpoint being met or exceeded.

B. When Channels C or D reach 8.5 psig, then manually initiate CSAS.

C. When channel B, C or D reach 9 psig, then verify CSAS automatically initiates.

D. CSAS may be initiated now based on trend, but is NOT required.

Answer: A

Reference:

Question Source: Bank # __X____

Modified Bank # _______

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge __X__

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # 022A1.02 022A1.02 Importance Rating 3.6 3.8 Tier # 2 2 Group # 1 1

Question 51 The plant has suffered a loss of feed water accident. E089 Steam Generator level is 0% on the narrow range level indication, E088 Steam Generator level is 38% on the narrow range level indication, AFW pump P-141 has been started.

Which ONE (1) of the following describes the correct sequence of actions for the conditions given?

A. Commence feeding both SGs; maintain AFW flow < 150 gpm to each SGs (Total AFW flow 300gpm). When increases in SG level observed or continuous AFW flow to the SG has been maintained for > 5 minutes, control AFW flow as necessary.

B. Commence feeding E089 SG; maintain AFW flow < 130 gpm. When increases in SG level observed or continuous AFW flow to the E089 SG has been maintained for > 5 minutes, control AFW flow as necessary.

C. Commence feeding the E088 SG; maintain AFW flow between 130gpm and 150 gpm.

When increases in SG level observed or continuous AFW flow to the E088 SG has been maintained for > 5 minutes, control AFW flow as necessary.

D. Commence feeding the SGs; maintain AFW flow between 130gpm and 150 gpm to both SGs (Total AFW flow <150gpm). When increases in SG level observed or continuous AEFW flow to the SG has been maintained for > 15 minutes, control AFW flow as necessary.

Answer: C

References:

SO23-12-6 Question Source: Bank # __X____

Modified Bank # _______

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 059G2.4.49 059G2.4.49 Importance Rating 4.0 4.3 Tier # 2 2 Group # 1 1

Question 52 Given the following conditions:

Unit 3 is at 100% power Pzr Level is 53%

Pzr Pressuse is 2250 psia Steam generator levels are 65% NR Breaker 480 VAC BB 51 (44) power supply to HV-4011 trips on fault Feedwater Control System #1 receives a High Level Override in #1 Steam Generator (E089)

Which of the following correctly identifies the effects on the plant?

A. Main Feed Pump Speed will not be affected, Main Feed Reg Valve will go fully closed, and Main Feed Bypass Valve will not be affected.

B. Main Feed Pump Speed will go to 3600 rpm, Main Feed Reg Valve will go fully closed, and Main Feed Bypass Valve will go fully closed.

C. Main Feed Pump Speed will go to 3600 rpm, Main Feed Reg Valve will go fully closed, and Main Feed Bypass Valve will close to 50%.

D. Main Feed Pump Speed will not be affected, Main Feed Reg Valve will remain in its current position and Main Feed Bypass Valve will go fully closed.

Answer: D

References:

SO23-250 Question Source: Bank # _ .

Modified Bank # ___X___

New ___ __

Question Cognitive Level: Memory or Fundamental Knowledge __ __

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 059A2.12 059A2.12 Importance Rating 3.1 3.4 Tier # 2 2 Group # 1 1

Question 53 The following plant events occur:

-A plant heatup is in progress.

-Steam generator pressure is 400 psia.

-A large steam leak occurs in the turbine building.

-The MSIVs do not close.

-Both steam generators start to blow down uniformly.

Which one of the following describes the expected response of the AFW system to these events?

A. All AFW pumps will start when either steam generator level decreases to 32% WR.

B. The AFW system will not respond to these events.

C. Only the motor driven AFW pumps will start when either steam generator level decreases to 32% WR.

D. Only the motor driven AFW pump will start when either steam generator level decreases to 32% WR.

Answer: B

Reference:

SO23-780 Question Source: Bank # _ .

Modified Bank # ___X___

New ___ __

Question Cognitive Level: Memory or Fundamental Knowledge __ __

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 061K4.06 061K4.06 Importance Rating 4.0 4.2 Tier # 2 2 Group # 1 1

Question 54 Given the following conditions:

Unit 2 tripped from 100% power 20 minutes ago.

P-140 tripped on overspeed at cannot be reset Both S/G levels lowered to 17% NR and recovered to 27%NR The ACO has depressed the override pushbuttons for the AFW valves and is feeding each S/Gs at 450 gpm.

Subsequently, 1E 4KV bus is de-energized due to an overcurrent condition S/G E088 pressure decreases to 700psia with level at 25% NR S/G E089 pressure decreases to 850psia with level at 27% NR Which of the following describes the status of the AFW system? (Assume no other operator actions have occurred)

A. Both S/Gs E088 and E089 are being fed B. S/G E088 is being fed and S/G E089 is not being fed C. Both S/Gs E088 and E089 are isolated D. S/G E089 is being fed and S/G E088 is not being fed Answer: B

Reference:

SO23-780 Auxiliary Feedwater System Question Source: Bank # _ .

Modified Bank # ___ ___

New ___X __

Question Cognitive Level: Memory or Fundamental Knowledge __ __

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 061K2.02 061K2.02 Importance Rating 3.7 3.7 Tier # 2 2 Group # 1 1

Question 55.

The liquid radwaste system and boron management system are designed to provide controlled collection, handling, treatment, and disposal of radioactive wastes from plant operation.

Which ONE (1) of the following describes the principle design criteria of these systems?

A. Allow processing the various potentially radioactive liquid wastes for long term storage on site.

B. Limit releases due to anticipated operational occurrences to annual liquid activity release quantity (five Ci) with an average annual liquid activity release concentration of 2 x 10-8 mCi/cc (excluding tritium and dissolved fission product gases).

C. Provide the removal of radioactivity as soon as feasible in the process, thus preventing the buildup of excessive activity in the remainder of the systems.

D. Ensure protection of general public from exposure by keeping release levels as low as possible.

Answer: D.

References:

STM-2-52 Section 1.4 Lesson Plan ASLP-RO-RADP Question Source: Bank # _ X .

Modified Bank # _______

New ___ __

Question Cognitive Level: Memory or Fundamental Knowledge __X__

Comprehension or Analysis _____

Examination Outline Cross-reference:

Level RO SRO K/A # 068K5.04 068K5.04 Importance Rating 3.2 3.5 Tier # 2 2 Group # 1 1

Question 56 Given the following conditions:

- Gaseous radwaste lined up for receiving gas from surge header.

- Oxygen content in the Volume Control Tank is 1.8% and rising.

-Oxygen content in the surge header is 1.8% and rising.

WHICH ONE of the, following, describe the action(s) which occur as oxygen content continues to rise?

A. All input into the gaseous radwaste header isolates.

B. Technical Specification limits on oxygen are exceeded followed by automatic nitrogen dilution of gaseous radwaste surge header C. Volume Control Tank to gaseous radwaste header isolates automatically.

D. Automatic nitrogen dilution of gaseous radwaste surge header prior to exceeding Technical Specification limits on oxygen.

Answer: B

Reference:

Question Source: Bank # __X ___

Modified Bank # _______

New _ ___

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 071K5.04 071K5.04 Importance Rating 2.5 3.1 Tier # 2 2 Group # 1 1

Question 57 Given the following conditions:

A planned release of waste gas decay tank T086 is in progress.

A high spike occurs on WRGM 2 RI-7865 The spike causes a HIGH alarm, which subsequently clears.

Which of the following describes the automatic action due to the high spike on the radiation monitor?

A. Stops all waste gas compressors.

B. Closes 2/3HV-7202, waste gas discharge isolation valve.

C. Starts all auxiliary building supply and exhaust fans.

D. Initiates Control Room Isolation System Actuation.

Answer: B

Reference:

Question Source: Bank # __X ___

Modified Bank # _______

New _ ___

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 071K3.04 071K3.04 Importance Rating 2.7 2.9 Tier # 2 2 Group # 1 1

Question 58 Unit 3 is in MODE 6. Irradiated Fuel movement is in progress.

A spent fuel assembly is damaged while being transported to the spent fuel racks.

The following conditions exist:

- Fuel Pool area radiation monitor: High Trip exceeded

- Fuel Building air exhaust monitor: High Trip exceeded Which of the following describes the expected ventilation alignment?

A. Fuel Building normal supply and exhaust fans are tripped. Fuel Building Essential AFUs take suction from the Fuel Building intake dampers and discharge downstream of the Fuel Building normal exhaust fan.

B. Fuel Building normal supply fan trips. Fuel Building normal exhaust fan remains running.

Fuel Building Essential AFUs take suction from the Fuel Building and Aux building intake dampers and discharge downstream of the Fuel Building normal exhaust fan.

C. Fuel Building normal supply fan trips. Fuel Building normal exhaust fan remains running.

Fuel Building Essential AFUs take suction from Fuel Building Intake dampers and discharge upstream of the Fuel Building normal exhaust fan.

D. Fuel Building normal supply and exhaust fans are tripped. Fuel Building Essential AFUs take suction from the Aux Building intake dampers and discharge downstream of the Fuel Building normal exhaust fan.

Answer: A

Reference:

Question Source: Bank # __X ___

Modified Bank # _______

New _ ___

Question Cognitive Level: Memory or Fundamental Knowledge __X__

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # 072K4.03 072K4.03 Importance Rating 3.2 3.6 Tier # 2 2 Group # 1 1

Question 59 Unit 2 is operating at 98% power The Hotwell Sampling System detects a leak from the saltwater cooling system.

The Overboard System is in automatic and all four Condensate Pumps are running.

Which of the following best describes the effects on the plant.

A. The condensate pump on the affected quadrant is automatically secured. The Overboard System dumps the affected quadrant until correct chemistry is restored. A manual bypass valve is opened to "quick fill" the hotwell quadrant to aid in correcting chemistry during overboarding. Power must be reduced to less than 95%.

B. The affected quadrant is automatically isolated. The Overboard System dumps the affected quadrant until correct chemistry is restored. A manual bypass valve is opened to "quick fill" the hotwell quadrant to aid in correcting chemistry during overboarding. Power must be reduced to less than 75%.

C. The affected quadrant is automatically isolated. The Overboard System dumps the affected quadrant until correct chemistry is restored. A bypass valve automatically opens to "quick fill" the hotwell quadrant to aid in correcting chemistry during overboarding Power must be reduced to less than 75%.

D. The affected quadrant is automatically isolated. The Overboard System dumps the affected quadrant until correct chemistry is restored. A bypass valve automatically opens to "quick fill" the hotwell quadrant to aid in correcting chemistry during overboarding Power must be reduced to less than 85%.

Answer: B

Reference:

SD-SO23-240 Question Source: Bank # ___ ___

Modified Bank # _______

New _ X___

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 056A2.04 056A2.04 Importance Rating 2.6 2.8 Tier # 2 2 Group # 1 1

Question 60 Unit 2 has experienced a Loss of Coolant accident.

RCS pressure is at 600 psia and dropping slowly.

Pzr level is 12% and lowering slowly S/G levels are 21% slowly increasing The expected safety injection flow indications would be:

A. Maximum HPSI flow with no LPSI flow.

B. Increasing HPSI flow with no LPSI flow.

C. Constant HPSI and LPSI flow.

D. Constant HPSI and increasing LPSI flow.

Answer: B

References:

Question Source: Bank # ___ ___

Modified Bank # ___X___

New _ ___

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 002K1.08 002K1.08 Importance Rating 4.5 4.6 Tier # 2 2 Group # 2 2

Question 61 The following conditions exist:

A small break Loss of Coolant Accident has occurred.

High Pressure Safety Injection (HPSI) Pump P017 has tripped on over current.

The crew aligned and started HPSI Pump P018.

Two charging pumps are running.

Pressurizer pressure is 1500 psia and steady.

HPSI Pumps P018 and P019 were secured upon meeting SI Termination Criteria.

The CBOR reports that Pressurizer Level is now 20% and slowly dropping. Determine which one (1) of the following actions is appropriate.

A. Start HPSI Pump P018 and throttle open enough HPSI Injection valves to raise Pressurizer level to greater than 28%.

B. Start HPSI Pump P018 and the third Charging Pump and fully open all HPSI Injection valves.

C. Start HPSI Pumps P018 and P019 and fully open enough HPSI Injection valves to raise Pressurizer level to greater than 28%.

D. Start HPSI Pumps P018 and P019 and fully open all HPSI Injection valves.

Answer: D

Reference:

Question Source: Bank # ___ ___

Modified Bank # ___X___

New _ ___

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 006K6.03 006K6.03 Importance Rating 3.6 3.9 Tier # 2 2 Group # 2 2

Question 62 Given the following conditions:

Unit 2 in Mode 3 LV-0110A, letdown flow control valve in service PV-0201A, letdown back pressure control valve in service Pressurizer Level Control System master controller in "MANUAL" with letdown flow at 28 gpm.

Charging pump P-190 is in service, pulsation dampener adjustment in progress on pumps P-191 and P-192.

Backpressure controller PIC-0201A output fails to zero while in "AUTO".

Pressurizer level is observed to slowly drop.

Which of the following identifies the reason for the observed pressurizer level change?

A. A small void in the reactor vessel upper head is now being compressed.

B. Zero output from PIC-0201A in "AUTO" corresponds to 30 gpm flow.

C. A small break has developed in the pressurizer steam space.

D. A pressure relief valve is lifting to the miscellaneous waste tank, T063.

Answer: D

Reference:

Question Source: Bank # __X ___

Modified Bank # ___ ___

New _ ___

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 010K4.03 010K4.03 Importance Rating 3.8 4.1 Tier # 2 2 Group # 2 2

Question 63 Given the following:

-Unit 2 is at 70% power.

-A fault in the SBCS results in the bypass valves opening to 10%.

WHICH ONE (1) of the following is the response of the Pressurizer Level Control System?

A. Both backup charging pumps will be running with minimum letdown flow.

B. Only the first backup charging pump will be running with minimum letdown flow..

C. Only the first backup charging pump will be running with letdown flow reduced but still greater than minimum.

D. No change in the Pzr Level control system, the SBCS is designed to accommodate up to 45% change in Rx Power.

Answer: A Question Source: Bank # ___ ___

Modified Bank # _______

New _ X ___

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 011A3.02 011A3.02 Importance Rating 2.6 2.8 Tier # 2 2 Group # 2 2

Question 64 The Unit 2 is operating at 100% power.

The shaft on RCP 2B shears Due to a fault in the Reactor Protection system circuitry, the Turbine Trip coils fail to energize If left unresolved this malfunction will cause:

A. An uncontrolled cool down of the RCS, resulting in less shutdown margin.

B. A High Linear power trip limit to be exceeded which will scram the reactor.

C. High local power density limits to be exceeded resulting in fuel damage.

D. An increase in RCS pressure, possibly resulting in the Pressurizer safety valves lifting.

Answer: A Question Source: Bank # ___ ___

Modified Bank # ___X___

New _ ___

Question Cognitive Level: Memory or Fundamental Knowledge __X__

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # 012K3.02 012K3.02 Importance Rating 3.2 3.3 Tier # 2 2 Group # 2 2

Question 65 Group 5 CEA's have just been withdrawn to 100 inches when the following alarms and indications occur:

- Group deviation alarm on PMS

- Reactor power decrease

- CEA 16 Lower Electrical Limit (LEL) light on the CEDMCS Panel is illuminated

- Pulse counter indicates group 5 and CEA 16 at 100 inches

- Both CEACs indicate CEA 16 at 0 inches

- CEA bottom light on the core mimic is not illuminated CEA 16 has:

A. dropped/slipped and actual position cannot be determined..

B. not dropped/slipped however, one 0 inch Reed Switch Position Transmitter (RSPT) has failed closed.

C. not dropped/slipped however, both 0 inch Reed Switch Position Transmitter's (RSPT's) have failed closed.

D. dropped/slipped to position 0 inches..

Answer: D

Reference:

Question Source: Bank # ___X ___

Modified Bank # ___ ___

New ___ _

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 014K5.04 014K5.04 Importance Rating 2.8 3.3 Tier # 2 2 Group # 2 2

Question 66 Given the following plant conditions:

- Unit 3 is at 100% power

- The S/G level selection for both FWCS is in the "Higher Level" position

- Control channel level transmitter LT-1111 for FWCS #1 fails to 100%

Which ONE of the following describes the plant response without operator action?

A. A Reactor Trip on high E089 S/G level.

B. A Reactor Trip on low E089 S/G level.

C. No impact, since selected to the "Higher Level" position.

D. Level initially decreases in E089 S/G, but stabilizes above the Reactor Trip Setpoint.

Answer: B

Reference:

SO23-250 Question Source: Bank # ___ ___

Modified Bank # ___X___

New ___ _

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 016A2.03 016A2.03 Importance Rating 3.0 3.3 Tier # 2 2 Group # 2 2

Question 67 Given the following plant conditions:

The reactor is tripped.

SIAS is actuated.

A steam line break is occurring in the containment.

Containment pressure is 10 psig and rising.

A loss of Bus 2A0403 has occurred.

WHICH ONE of the following is correct concerning the Containment Spray (CS) System?

A. CS Pump, P-012 is on. CS Pump, P-013 is on. HV-9367 open. HV-9367 open.

B. CS Pump, P-012 is off. CS Pump, P-013 is on. HV-9367 open. HV-9367 closed.

C. CS Pump, P-012 is off. CS Pump, P-013 is on. HV-9367 closed. HV-9367 open.

D. CS Pump, P-012 is off. CS Pump, P-013 is on. HV-9367 open. HV-9367 open.

Answer: C

References:

SO23-740 Question Source: Bank # ___ ___

Modified Bank # ___X___

New ___ _

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 026A3.01 026A3.01 Importance Rating 4.3 4.5 Tier # 2 2 Group # 2 2

Question 68 Given the following conditions:

It is currently 0830 8 December 2003 Unit 2 is at 100% power Preparations for commencing a Mini Purge of containment are in progress.

An entry into containment is planned for 10 December 2003 at 1030.

When the Wide range gas monitor, (WRGM) 2RE-7865 is aligned to the Containment Purge Stack, Annunciator alarm 61A08, "Airborne Radiation Hi" is received due to a fault in the circuitry.

In accordance with SO 23-3-2.34, what is the latest that the purge can commence without impacting the containment entry?

A. 2230 9 December 2003.

B. 1030 8 December 2003 C. 0030 10 December 2003 D. 1030 9 December 2003.

Answer: D

References:

SO 23-3-2.34 Containment access control, Inspections and airlocks operation Question Source: Bank # __ ___

Modified Bank # ___ __

New __X _

Question Cognitive Level: Memory or Fundamental Knowledge __X__

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # 029K3.02 029K3.02 Importance Rating 2.9 3.5 Tier # 2 2 Group # 2 2

Question 69 Unit 2 is in MODE 6. During fuel inspection activities, the fuel inspection device was raised out of the Spent Fuel Pool.

Airborne radiation levels as sensed by the Fuel Handling Building Vent Airborne Monitors RE-7822 & RE-7823 have exceeded the alarm/trip setpoint.

RE-7822 is in bypass RE-7823 is in normal operation Based on these conditions, which of the following statements represents correct system response?

A. FHIS actuation, Trains 'A' and 'B'.

B. FHIS actuation, Train 'A'.

C. FHIS actuation, Train 'B'.

D. No FHIS actuation occurs.

Answer: C

References:

Question Source: Bank # ___X___

Modified Bank # ___ ___

New ___ _

Question Cognitive Level: Memory or Fundamental Knowledge __X_

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # 033A1.02 033A1.02 Importance Rating 2.8 3.3 Tier # 2 2 Group # 2 2

Question 70 Given the following plant conditions:

Reactor Trip.

Steam Generator (S/G) E089 Level 28% WR.

S/G E088 Level 36% WR.

S/G E089 Pressure 890 psia.

S/G E088 Pressure 1100 psia.

Annunciator "SG 2 > SG 1 PRESS CH TRIP".

If both S/G Levels DECREASED to < 25% WR, which ONE of the following statements would be correct?

Auxiliary feed would automatically feed...

A. only S/G E089.

B. only S/G E088.

C. both S/Gs because of low S/G levels.

D. only S/G E089 until S/G E088 pressure equals 950 psia, then both.

Answer: B Question Source: Bank # ___ ___

Modified Bank # ___X___

New ___ _

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 035K1.01 035K1.01 Importance Rating 4.2 4.5 Tier # 2 2 Group # 2 2

Question 71 All of the following are functions of the Main and Reheat Steam System except:

A. Increase Turbine cycle efficiency by preheating the feedwater.

B. Remove heat from the Reactor coolant System C. Prevent the release of radioactive materials from the reactor coolant system.

D. To provide temperature control fort eh reactor coolant system during plant heat up, at operating conditions, and during cooldown.

Answer: A

Reference:

S)23-160 Question Source: Bank # ___ ___

Modified Bank # ___ ___

New _ X___

Question Cognitive Level: Memory or Fundamental Knowledge __X__

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # 055K3.01 055K3.01 Importance Rating 2.5 2.7 Tier # 2 2 Group # 2 2

Questions 72 Given the following plant conditions:

The plant is at 100% power.

Condenser Vacuum Pump hand switch HS-3331A (CR-53) is in AUTO.

Condenser Vacuum starts to degrade.

Which ONE (1) of the following describes the design of the Condenser Vacuum System that will prevent continued degradation of Condenser vacuum.

A. PV3335B will open and PV3335A will close at < 7.5 Hg Absolute vacuum in the condenser placing the Air Assisted Air Ejectors in service..

B. Condenser Vacuum Pump will shift to the "Holding" mode of operation at < 6" Hg Absolute vacuum in the condenser and prevent further loss of vacuum.

C. Condenser Vacuum Pump will startup at < 22.5" Hg vacuum in the condenser and will be operating in the "Hogging" mode after the inlet diaphragm valves are opened.

D. PV3335B will open and PV3335A will close at < 26.5 Hg vacuum in the condenser placing the Air Assisted Air Ejectors in service.

Answer: A.

References:

SO23-190 Question Source: Bank # ___ ___

Modified Bank # ___X___

New _ ___

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 055K3.01 055K3.01 Importance Rating 2.5 2.7 Tier # 2 2 Group # 2 2

Question 73 The following plant conditions exist:

-A station blackout has occurred.

-The diesel generators have both failed to start.

-SO23-12-1 Standard post trip Actions steps 1 through 10 have been completed

-Diagnosis of Station Blackout has been verified

-Actions have been taken to notify the Shift manager and Operations leader of the situation

-The Emergency plan has been initiated In accordance with SO 23-12-8, which one of the following courses of action should be taken by the operators?

A. Initiate SO23-12-11, Attachment 6, Diesel Generator Failure Followup actions B. Restore and maintain at least one (1) S/G level between 30% and 80% NR C. Bleed steam as necessary to maintain S/G pressure 1000 psia using ADVs D. Attempt to energize 1E 4KV bus A04 or A06 from the other unit.

Answer: A

References:

SO23-12-8 Station Blackout Step 4 Question Source: Bank # ___ ___

Modified Bank # ___ ___

New _ X ___

Question Cognitive Level: Memory or Fundamental Knowledge __X__

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # 062G2.4.16 062G2.4.16 Importance Rating 3.0 4.0 Tier # 2 2 Group # 2 2

Question 74 Unit 3 is operating at 100% power.

Pzr Level is 52%

Maintenance is in progress in the B001 Battery room.

SWC pumps 3P112 and 3P113 are running Breaker D101, the 1E 125 VDC bus D1battery breaker is inadvertently opened by the maintenance worker.

What effect will this have on the Unit 3 SWC system?

A. SWC pump 3P112 breaker will trip on loss of control power and the standby SWC pump P307 will start.

B. SWC pump 3P112 breaker will remain shut, but there will be no remote operation or automatic tripping available.

C. SWC pump 3P113 breaker will trip on loss of control power and the standby SWC pump P114 will start.

D. SWC pump 3P113 breaker will remain shut, but there will be no remote operation or automatic tripping available.

Answer: B

Reference:

SO23-6-15 Attachment 13 SO23-140 125 and 250 VDC Systems Question Source: Bank # ______

Modified Bank # ___X__

New ___ _

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 063K2.01 063K2.01 Importance Rating 2.9 3.1 Tier # 2 2 Group # 2 2

Question 75 A plant trip has occurred and offsite power to both vital 4.16kv buses has been lost. During standard post trip actions the primary operator at B01 observes the following:

The `A' Diesel Generator has tripped on overspeed.

The `B' Diesel Generator has started but its output breaker has not closed.

The `B' Diesel Generator voltage is 3.98KV All other indications appear normal.

According to procedural guidance, the CRS would expect the operator to:

A. Emergency stop the `B' Diesel Generator.

B. Adjust the output voltage to 4.36KV and close the output breaker.

C. Reset the 86 Lockout, adjust voltage and close the output breaker.

D. Direct an Auxiliary Operator to reset 'A' Diesel Generator.

Answer: B

Reference:

SO23-11 Attachment 6 step 6a Question Source: Bank # ______

Modified Bank # ___X __

New ___ _

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 064A1.03 064A1.03 Importance Rating 3.2 3.3 Tier # 2 2 Group # 2 2

Question 76 The Process Radiation Monitoring System generates an alarm signal in the control room to perform specific isolation functions.

Which of the following isolation signals are generated by the Process Radiation Monitoring System?

A. Containment isolation.

B. Containment purge isolation.

C. CCW Non Critical Loop Isolation.

D. Radwaste building ventilation isolation.

Answer: B

Reference:

Question Source: Bank # ___X___

Modified Bank # ___ __

New ___ _

Question Cognitive Level: Memory or Fundamental Knowledge __X__

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # 073A4.01 073A4.01 Importance Rating 3.9 3.9 Tier # 2 2 Group # 2 2

Question 77 Which of the following describes the power supplies for the Nuclear Service Water Pumps P-138 and P-139?

A. 480V Bus 2B0711 and 480V 2B1403 B. 480V Bus A0606 and 480V A0605 C. 480V Bus A0406 and 480V A0405 D. 480V Bus 2B0703 and 480V 2B1411 Answer: D

Reference:

SO23-450 Question Source: Bank # ___X__

Modified Bank # ___ __

New ___ _

Question Cognitive Level: Memory or Fundamental Knowledge __X__

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # 075K2.03 075K2.03 Importance Rating 2.6 2.7 Tier # 2 2 Group # 2 2

Question 78 The purpose/function of the Service Air system includes all of the following except:

A. To provide compressed air to service outlets throughout the plant and Make-up Demineralizer area for operation of pneumatic tools and other service requirements.

B. To inflate and maintain the spent fuel pool seals.

C. Provides compressed air at a normal pressure of 115psig and meets OSHA Class D breathing air requirements.

D. Provides a backup source of compressed air for the safe shutdown of the plant in the event of a failure of the Instrument air system.

Answer: D

Reference:

SO23-570 Question Source: Bank # ___ ___

Modified Bank # ___ __

New ___X _

Question Cognitive Level: Memory or Fundamental Knowledge __X__

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # 079G2.1.27 079G2.1.27 Importance Rating 2.8 2.9 Tier # 2 2 Group # 2 2

Question 79 Given:

Unit 2 is at 100% power, Unit 3 is at 60% power increasing to 100%.

Maintenance is in progress that has resulted in Panel L-191 being de-energized.

There is a leak in the wet fire protection main that exceeds the capacity of the running and standby jockey pumps to maintain pressure.

Which of the following statements describes the sequence of events that will occur to maintain fire protection header pressure.

A. Pressure switch PSL-5661 senses a system pressure of 107.5 psig for a ten (10) second period and fire pump P-221 starts B. Pressure switch PSL-5668 senses a system pressure of 107.5 psig for a ten (10) second period and fire pump P-222 starts C. Pressure switch PSL-5668 senses a system pressure of 104 psig for a twenty (20) second period and fire pump P-222 starts D. Pressure switch PSL-5661 senses a system pressure of 100 psig for a thirty (30) second period and fire pump P-220 starts Answer: C

Reference:

SO23-590 Fire Protection System Question Source: Bank # ___ ___

Modified Bank # ___ __

New ___X _

Question Cognitive Level: Memory or Fundamental Knowledge __X__

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # 086A2.02 086A2.02 Importance Rating 3.0 3.3 Tier # 2 2 Group # 2 2

Question 80 The following conditions exist:

- MODE 5

- LPSI Train A is providing Shutdown Cooling using HX ME-003

- Shutdown Cooling Heat Exchanger inlet temperature indicates 152 degrees F on TR-8148

- A 10 degrees F/hr cooldown is in progress.

The CRS directs that RCS temperature be stabilized.

Which of the following describes the preferred action(s) to stop the cooldown?

A. Throttle CLOSED the SDC HX ME-003 outlet to RCS Loops lA/1B (HV-9322)

B. Adjust the SDC HX ME-003 outlet valve (HV-8150)

C. Fully OPEN the bypass valve (HV-8160) to bypass SDC HX ME-003 D. Adjust CCW temperature to SDC HX ME-003 using CCW-HCV-6547 Answer: B

References:

SO23-3-2.6 SO23-5-1.5 Question Source: Bank # __X___

Modified Bank # ___ __

New ___ _

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 005A1.01 005A1.01 Importance Rating 3.5 3.6 Tier # 2 2 Group # 3 3

Question 81 Given the following plant conditions:

Component Cooling Water (CCW) Pumps P-024 and P-026 are operating CCW Pump P-025 is aligned to Train A and is in STANDBY Grid instabilities result in a loss of off site power The reactor has tripped Pzr level is 15% and increasing Pzr Pressure is 1580 psia and increasing slowly The Emergency Diesels have started normally.

Without any other operator action, which of the following correctly describes the status of the component cooling water pumps?

A. All CCW pumps are running B. CCW Pumps P-024 and P-026 are running, P-025 is off C. CCW Pumps P-024 and P-025 are running, P-026 is off D. CCW Pumps P-025 and P-026 are running, P-024 is off Answer: D Question Source: Bank # ______

Modified Bank # ___X__

New ___ _

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 008K4.09 008K4.09 Importance Rating 2.7 2.9 Tier # 2 2 Group # 3 3

Question 82 While in Mode 1 at full power, it was determined that the Trisodium Phosphate baskets in containment had been inadvertently emptied during the last outage.

The consequences of this action would be increased:

A. containment pressure during a LOCA.

B. Formation of oxygen during a LOCA.

C. containment iodine levels during a LOCA.

D. formation of hydrogen during a LOCA.

Answer: C Question Source: Bank # __X__

Modified Bank # ___ __

New ___ _

Question Cognitive Level: Memory or Fundamental Knowledge __X__

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # 027K1.01 027K1.01 Importance Rating 3.4 3.7 Tier # 2 2 Group # 3 3

Question 83 Given the following conditions:

- Core reload is in progress.

- Refueling machine over core with fuel assembly grappled.

- Spent Fuel Handling Machine losses power

-Core reload is suspended.

WHICH ONE of the following states the safe location for placement of the assembly suspended on the refueling machine grapple?

A. In designated core location.

B. In most easily accessible core location.

C. Up-ender in horizontal position.

D. Lowered into deep area of refueling pool.

Answer: A Question Source: Bank # __ X __

Modified Bank # __ ___

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge _ X __

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # 034A2.03 034A2.03 Importance Rating 3.3 4.0 Tier # 2 2 Group # 3 3

Question 84 Given the following:

-Unit 2 is at 100% power.

-Ppzr is 2250 psia

-Tave is 566F

-The selected loop Tcold instrument input into RRS fails HIGH.

The reactor subsequently tripped.

WHICH ONE (1) of the following is the response of the atmospheric dump valves and Steam Bypass Control valves over the next ten (10) minutes? ASSUME no operator actions.

A. Atmospheric dump valves OPEN.

Steam Bypass Control valves OPEN.

B. Atmospheric dump valves OPEN.

Steam Bypass Control valves CLOSE.

C. Atmospheric dump valves CLOSE Steam Bypass Control valves CLOSE.

D. Atmospheric dump valves CLOSE.

Steam Bypass Control valves OPEN.

Answer: D

References:

SO23-175 Question Source: Bank # __ ___

Modified Bank # __ X___

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge _ __

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 041K6.03 041K6.03 Importance Rating 2.7 2.9 Tier # 2 2 Group # 3 3

Question 85 Unit 3 is at 100% power. All control systems in AUTO.

The Main Turbine Generator trips on a voltage regulator card failure.

Assuming no operator action, describe the expected set of secondary plant conditions immediately following the occurrence.

A. Main Steam safeties lift and modulate. FWCS 1 and 2 CLOSE the feedwater isolation valves.

B. SBCS QUICK OPEN, FWCS 1 and 2 control feedwater isolation valves in Reactor Trip Override. (RTO).

C. Main Steam Safety valves lift, FWCS 1 and 2 feed the S/Gs to high level override setpoint.

D. SBCS QUICK OPEN, then modulate, FWCS l and 2 throttle the feedwater regulating valves Answer: D

References:

Question Source: Bank # __ ___

Modified Bank # __ X___

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge _ __

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 045K3.01 045K3.01 Importance Rating 2.9 3.2 Tier # 2 2 Group # 3 3

Question 86 Given the following conditions:

The MSIVs must be tagged in the OPEN position for repacking in MODE 6.

The Instrument Air supply isolation valve will be tagged CLOSED.

Which one (1) of the following items should be included in the MINIMUM Personnel Protective equipment tagging requirements?

A. Lift the leads on the MSIS solenoid valves.

B. Install locking pins for MSIVs C. Place the Control Room handswitches from the MSIVs to OPEN.

D. Open the vent on the valve operator.

Answer: B

References:

Question Source: Bank # __X___

Modified Bank # __ ___

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge _X__

Comprehension or Analysis ____

Examination Outline Cross-reference:

Level RO SRO K/A # 078K1.05 078K1.05 Importance Rating 3.4 3.5 Tier # 2 2 Group # 3 3

Question 87 Given the following conditions:

Reactor has tripped from 100% power.

Reactor coolant system pressure is 1650 psia and dropping.

Pressurizer level is 10% and dropping.

Steam generator levels have turned at 21% NR and are recovering.

Steam generator pressures are 980 psia and rising.

Containment pressure is 7.4 psig and rising.

Safety Injection and Emergency Feedwater actuations have occurred.

Which of the following states the additional Engineered Safety Features actuation(s) present assuming all systems functioned as designed?

A. Containment Spray Actuation.

B. Containment Isolation actuation C. Main Steam Isolation.

D. Containment Isolation Actuation and Main Steam Isolation.

Answer: B

References:

Question Source: Bank # __ _ __

Modified Bank # __ X ___

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 103 A3.01 103 A3.01 Importance Rating 3.9 4.2 Tier # 2 2 Group # 3 3

Question 88 Operating Instruction S023-2-8, "Saltwater Cooling System Operation," cautions against running a saltwater cooling (SWC) pump without its associated component cooling water loop pressurized.

Which of the following is the reason for this caution?

A. Prevent thermal shock of the CCW heat exchanger.

B. Prevent saltwater from entering the CCW system in the event of a tube leak.

C. CCW system provides cooling for the SWC pump motor.

D. Ensures the CCW radiation monitor is in service in the event of CCW leakage into the SWC system.

Answer: B

Reference:

Question Source: Bank # __X___

Modified Bank # __ ___

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge _X__

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # 2.1.7 2.1.7 Importance Rating 3.7 4.4 Tier # 3 3 Group # 1 1

Question 89 The following plant condition exists:

Toxic gas ingress to the Control Room requires a control room evacuation and plant shutdown from outside the control room The reactor has been manually tripped.

The turbine has been manually tripped.

Which of the following identifies the ORDER in which the "IMMEDIATE ACTIONS" for AOI SO23-13-2, "Shutdown From Outside the Control Room" are to be completed?

A. 1) Stop all RCPs.

2) Manually initiate MSIS.

3) Select manual and stop all Charging Pumps.

B. 1) Stop all RCPs.

2) Manually initiate MSIS.

3) Select manual and stop all backup Charging Pumps.

C. 1) Select manual and stop ALL backup Charging Pumps.

2) Manually initiate MSIS.

3) Stop all RCPs.

D. 1) Manually initiate MSIS.

2) Stop all RCPs.

3) Select manual and stop all Charging Pumps.

Answer: A

Reference:

AOI SO23-13-2, "Shutdown From Outside the Control Room" Question Source: Bank # __ ___

Modified Bank # __ X___

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 2.1.12 2.1.12 Importance Rating 2.9 4.0 Tier # 3 3 Group # 1 1

Question 90 Given the following plant conditions:

15 minutes post trip from full power operation.

"A" Main Steam Radiation Monitor reads 2 R/Hr.

RCS pressure is 1500 psia and stable.

RCS temperature is 550 degrees F and stable.

Which One (1) of the following actions will minimize the off-site release for the given conditions?

A. Restore CCW to RCPs.

B. Restore SW to ACW.

C. Isolate SG Blowdown.

D. Isolate both S/Gs.

Answer: B.

References:

Question Source: Bank # ___ ___

Modified Bank # __X___

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 2.1.23 2.1.23 Importance Rating 3.9 4.0 Tier # 3 3 Group # 1 1

Question 91 Unit 2 is in MODE 6. Swapping to a Containment Spray Pump for Shutdown Cooling per SO23-3-2.6, Att.

25 is in progress.

Step 2.1.10 of Att. 25 requires SDC flow to be adjusted to less than 2750 gpm.

Which one of the following explains why SDC flow is reduced?

A. To prevent Containment Spray Pump runout when off-going SDC pump is stopped.

B. To prevent excessive Shutdown Cooling Heat Exchanger flow rate when starting the Containment Spray Pump.

C. To prevent voiding in the Shutdown Cooling Heat Exchanger when stopping the off-going SDC pump.

D. To prevent loss of off-going SDC Pump NPSH when Containment Spray Pump is started.

Answer: A Question Source: Bank # ___X___

Modified Bank # _______

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge __X_

Comprehension or Analysis ____

Examination Outline Cross-reference:

Level RO SRO K/A # 2.1.32 Importance Rating 3.4 Tier # 3 Group # 1

Question 92 For a Surveillance Test that was aborted, the...

A. Paperwork can be immediately discarded.

B. Acceptance review will be completed, noting that the ST is incomplete.

C. Acceptance review will be completed only after the complete performance of the ST.

D. Paperwork is maintained, however, the acceptance review is not required to be performed.

Answer: B Question Source: Bank # ___X___

Modified Bank # _______

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge __X_

Comprehension or Analysis ____

Examination Outline Cross-reference:

Level RO SRO K/A # 2.2.12 Importance Rating 3.0 Tier # 3 Group # 2

Question 93 Given the following:

Technical Specification 3.4.7 restricts starting a RCP when Tcold is less than 256 degrees F and steam generator secondary water temperature is more than 100 degrees F. above each RCS Tcold.

Which of the following is the reason for this limit?

A. Minimize RCS pressure transient caused by additional heat transfer from the core B. Prevent core lift from excessive differential pressure across the core.

C. Minimize RCS pressure transient caused by reverse heat transfer from a hot S/G.

D. Prevent excessive RCP starting current due to increased density of the coolant.

Answer: C Question Source: Bank # ___ ___

Modified Bank # ___X___

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge __X_

Comprehension or Analysis ____

Examination Outline Cross-reference:

Level RO SRO K/A # 2.2.25 Importance Rating 2.5 Tier # 3 Group # 2

Question 94 Which of the following evolutions would be considered a "Core Alteration" by Technical Specifications?

A. Removing the Upper Guide Structure from the Reactor Vessel.

B. Removing the incore detectors from the Reactor vessel.

C. Transferring a control rod between the Reactor vessel and Spent Fuel Pool.

D. Uncoupling all control rods in Shutdown Rod Group "B".

Answer: C

Reference:

Tech. Spec, Question Source: Bank # ___X___

Modified Bank # _______

New ___ _

Question Cognitive Level: Memory or Fundamental Knowledge __X_

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # 2.2.27 Importance Rating 2.6 Tier # 3 Group # 2

Question 95 A Waste Control Operator is required to complete a valve lineup in an area where the radiation level is 50 mrem/hour. The operator's current Total Effective Dose Equivalent (TEDE) is 1730 mrem.

What is the maximum time he can work in this area and not exceed his Administrative Dose Control Level (ADCL)?

A. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

B. 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months .

C. 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months .

D. 25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months .

Answer: B.

References:

Question Source: Bank # ___ ___

Modified Bank # ___X___

New ___ _

Question Cognitive Level: Memory or Fundamental Knowledge __X__

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # 2.3.1 2.3.1 Importance Rating 2.6 3.0 Tier # 3 3 Group # 3 3

Question 96 Given the following plant conditions:

The radioactive effluent release permit for a containment refueling purge is current.

Core alterations are in progress.

Containment refueling purge is stopped.

It is desired to restart the containment refueling purge.

The current time is within the time constraints of the release permit.

Which ONE of the following identifies the requirement(s) to restart the containment refueling purge?

A. Re-verify Containment Integrity is established per LCO 3.9.9.

B. Re-perform the channel functional tests for RU-37 and RU-38.

C. Perform ASME Section XI tests on refueling purge isolation valves.

D. Notify Radiation Monitoring Group to evaluate the restart of the purge.

Answer: D Question Source: Bank # ___X___

Modified Bank # _______

New __ _

Question Cognitive Level: Memory or Fundamental Knowledge __X __

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # 2.3.9 Importance Rating 2.5 Tier # 3 Group # 3

Question 97 Unit 2 was operating at 100% power when a tube rupture occurred on E089. In order to cool down the RCS for SG maintenance the operators should:

A. dump steam to the condenser using the E088 SG to minimize radiological releases.

B. dump steam through the E088 SG's ADVs to minimize contamination of the secondary system for ALARA reasons.

C. dump steam through the E089 SG's ADVs to reduce the contamination in the condensate.

D. dump steam to the condenser using the E089 SG to minimize radiological releases.

Answer: A Question Source: Bank # ___ ___

Modified Bank # _______

New __X _

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 2.3.11 Importance Rating 2.7 Tier # 3 Group # 3

Question 98 Given the following conditions A small break LOCA is occurring.

PZR pressure 1750 psia.

Thot is 570F Tcold is 552F Core exit thermocouple temperature is 570F 1B and 2B RCP's have been manually tripped.

Two RCP's were left operating under these conditions because:

A. Maintaining forced circulation is desirable and the potential for RCP seal failures is reduced.

B. Maintaining 2 pumps running minimizes RCP journal bearing wear/damage.

C. Maintaining 2 pumps running minimizes the potential for the formation of boron crystals in the core.

D. Maintaining forced circulation is desirable and the plant can remain in a safe condition under these conditions.

Answer: D Question Source: Bank # ___ ___

Modified Bank # __X___

New __ _

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 2.4.6 Importance Rating 3.1 Tier # 3 Group # 4

Question 99 Unit 2 is at 15% power with power accession in progress when Component Cooling Water (CCW) is lost to the Non Critical Loop.

It is determined that flow cannot be restored.

According to AOI SO23-13-7, "Loss of CCW/SWC," what is the required action?

A. Trip the reactor and then secure the RCP(s).

B. Cross connect the component cooling water loops, perform a normal plant shutdown and then secure the RCP(s).

C. Perform a Rapid Plant Shutdown and then secure the RCP(s).

D. Cross connect the component cooling water loops, perform a Rapid Plant Shutdown and then secure the RCP(s).

Answer: A Question Source: Bank # __ ___

Modified Bank # __ X __

New __ _

Question Cognitive Level: Memory or Fundamental Knowledge __X__

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # 2.4.24 Importance Rating 3.3 Tier # 3 Group # 4

Question 100 SO23-13-21, "Fire" describes the duties and responsibilities of personnel during a fire. A fire is reported inside the protected area of San Onofre Unit 2.

Which of the following correctly describes the duties of the Common Control Operator, after obtaining a copy of the zone evaluation?

A. Remain in the control room, and coordinate the fire fighting effort.

B. Remain in the control room, and act as technical advisor.

C. Proceed to the scene, and act as technical advisor.

D. Proceed to the scene, and act as fire brigade leader.

Answer: C

Reference:

Question Source: Bank # __ X__

Modified Bank # __ __

New __ _

Question Cognitive Level: Memory or Fundamental Knowledge __X__

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # 2.4.27 Importance Rating 3.0 Tier # 3 Group # 4

Given the following:

-Unit 2 is at 100% power.

-Ppzr is 2250 psia

-Tave is 566F

-2Q0612, non-class 1E instrument bus # 2, de-energizes.

If no operator action is taken, what will be the response of the plant and why?

A. Plant will trip and all CEAs will be on the bottom because the Control Element Drive Mechanism Control System loses power.

B. Tave will begin to lower C.

D.

(CHARGING PUMP SUCTION SHIFTS TO RWST, BORATING)

2PIC-0100 PZR PRESSURE CONTROL MEASUREMENT SELECTED VIA 2HS0100 (2PT100X OR 2PT100Y)

OPERATOR 2500 PSIA SETPOINT VALVE PIC-0100 (1500-2500 PSIA)

OSP 2263 2500 PSIA LOCAL ALARM/REMOTE (1500-2500 PSIA) ACTUATION AT:

HA = MEAS < 2275 PSIA (77.5%)

RESETS AT 2265 PSIA (76.5%)

CONTROLLER OUTPUT OUT 100.0 (0-100.0%)

AM E

A/M SEL ACK 100%

CONTROLLER OUTPUT 0%

33.3% 66.7% 100%

PROPORTIONAL SPRAY HEATERS VALVES 100% TO 0% 0-100%

FIGURE III-6: PRESSURIZER PRESSURE CONTROLLER PIC-0100

NUCLEAR ORGANIZATION OPERATING INSTRUCTION SO23-3-1.7 UNITS 2 AND 3 REVISION 24 TCN 24-1 PAGE 103 OF ATTACHMENT 4 RCP MINIMUM PRESSURE FOR OPERATION

NUCLEAR ORGANIZATION OPERATING INSTRUCTION SO23-3-1.7 UNITS 2 AND 3 REVISION 24 TCN 24-1 ATTACHMENT 5 RCP MINIMUM PRESSURE FOR OPERATION - LOW TEMPERATURE/PRESSURE

SONGS 2003 SRO ONLY EXAM QUESTIONS Q-1 (Q-4)

After an Excess Steam Demand Event, one of the concerns is the overpressurization of the RCS which could result in a large break LOCA. Which of the following actions will minimize the chance of this type of loss of pressure control?

A. Initiate Safety Injection Throttle/Stop B. Establish maximum Safety Injection flow C. Ensure Main Steam isolation Signal is actuated D. Secure at least 2 Reactor Coolant Pumps Answer: A Ref.: SO23-12-5 KA: 000011 EA2.14 Source: SONGS Bank Question Source: Bank # __X___

Modified Bank # __ ___

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge _X__

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # 000011 EA2.14 000011 EA2.14 Importance Rating Tier #

Group #

Q-2 (Q-8)

Which of the following is an indication that effective single phase Natural Circulation cooling may be lost?

A. Reactor Vessel Plenum level equal to 82%

B. Delta-T (T-hot minus T-cold) of 28EF C. Core Exit Thermocouple minus T-hot equal to 10EF D. CET Saturation Margin equal to 25EF Answer: A Ref.: SO23-12-7 KA: CE EPE A13 AK2.2 Source: SONGS Bank Question Source: Bank # __X___

Modified Bank # __ ___

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge _X__

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # CE/A11;W/E08 EA2.14 CE/A11;W/E08 EA2.14 Importance Rating Tier #

Group #

Q-3 (Q-37)

Given the following conditions:

Unit 2 in Mode 3, 500 degrees F and 2250 psia 3 Reactor Coolant Pumps are operating Auxiliary Feedwater pump P-141 is supplying feedwater to maintain Steam Generator levels Auxiliary Feedwater pump P-504 is out of service Reserve Auxiliary Transformer (Unit 2) trips on ground fault on class 1E 4.16KV bus 2A04 Emergency diesel generator "2G002" trips, after successfully starting Auxiliary Feedwater pump P-140 trips when started All other systems are operating as designed Which of the following correctly identifies the success path for plant stabilization?

A. SO23-12-6, "Loss of All Feedwater".

B. SO23-12-7, "Loss of Forced Circulation / Loss of Offsite Power".

C. SO23-12-9, "Functional Recovery Procedure".

D. SO23-12-2, "Reactor Trip Recovery".

Answer: A Ref.: SO23-12-6 KA: APE 054 AA1.01 Source: Bank Question Source: Bank # __X___

Modified Bank # __ ___

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge _X__

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # CE/A11;W/E08 EA2.14 CE/A11;W/E08 EA2.14 Importance Rating Tier #

Group #

Q-4 (Q-100)

The fire suppression system is required to be operable:

A. In Modes 1-2 B. In Modes 1-4 C. In Modes 1-6 D. At all times Answer: D Ref.: SO23-7-1, Technical Specifications KA: GKA 2.4.25 Source: SONGS Bank Question Source: Bank # __X___

Modified Bank # __ ___

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge _X__

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # CE/A11;W/E08 EA2.14 CE/A11;W/E08 EA2.14 Importance Rating Tier #

Group #

Q-5 (Q-67)

The following conditions are present: Channel "A" Low DNBR trip is bypassed, RCP P001 (Loop 1A) flow input to Channel "B" has failed LOW.

Which of the following conditions will result in a reactor trip?

A. Pressurizer pressure input to Channel "C" CPC fails low B. Pressurizer Pressure input to Channel "B" CPC fails high C. Loop 1 Hot Leg temperature input to Channel "A" CPC fails low D. Loop 1 Hot Leg temperature input to Channel "B" CPC fails high Answer: A Ref.: SO23-3-2.12 KA: 012 K5.01 Source: SONGS Bank Replacement question WHICH ONE (1) of the following conditions will result in an INCREASE of the Thermal Margin/Low Pressure (TM/LP) Trip setpoint? The plant is at 100% power.

A. Tcold (safety channel) Loop A1 fails LOW.

B. ASI changes from 0.0 to -0.1.

C. RCS pressure increases 25 psia D. Delta-T power is reduced via the Calibrate pot.

Answer: B Question Source: Bank # __X___

Modified Bank # __ ___

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge _X__

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # CE/A11;W/E08 EA2.14 CE/A11;W/E08 EA2.14 Importance Rating Tier #

Group #

Q-6 (Q-35)

Given the following Plant Conditions:

-Unit 2 tripped 25 minutes ago

-A Steam Generator Tube Rupture has been diagnosed and RCS cooldown has been initiated

-Hot leg temperature is 529EF

-RCPs 2P001 and 2P004 have been secured

-S/G levels are 27% and slowly rising

-Pressurizer level is 20% and slowly rising

-Pressurizer pressure is 1480 psia Which of the following actions should be performed at this time?

A. Isolate the affected steam generator B. Perform HPSI throttle stop C. Override and feed both steam generators D. Secure 2 charging pumps Answer: A Ref.: SO23-12-4 KA: GAPE 037 2.1.2 Source: SONGS Bank Question Source: Bank # __X___

Modified Bank # __ ___

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge _X__

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # CE/A11;W/E08 EA2.14 CE/A11;W/E08 EA2.14 Importance Rating Tier #

Group #

Q-7 (Q-91)

You are preparing a Procedure Modification Permit which could potentially change the intent of the Operating Instruction. Which of the following is true?

A. A 50.59 Safety Evaluation must be performed prior to implementation B. A 50.59 Safety Evaluation must be performed within 14 days of completion C. The Manager Operations approval is required prior to implementation D. The Manager Operations approval is required within 14 days of completion Answer: C Ref.: SO123-0-20 KA: GKA 2.2.6 Source: SONGS Bank Question Source: Bank # __X___

Modified Bank # __ ___

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge _X__

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # CE/A11;W/E08 EA2.14 CE/A11;W/E08 EA2.14 Importance Rating Tier #

Group #

Q-8 (Q-95)

Given the following plant conditions: The plant is operating in a normal 100% power alignment; Radwaste Secondary Tank, 2/3T-057, is being released through the Unit 2 Outfall; two circulating water pumps trip causing dilution flow to be less than required per the Release Permit How is the release affected?

A. The release must be terminated and may proceed once Chemistry issues a new Release Permit B. The release may proceed provided the Shiftly FLow Estimate for dilution flow verification is performed C. The release may proceed as long as two independent samples are analyzed and the release rate calculations are within ODCM limits D. The release must be terminated and may resume only when all four circulating water pumps are running Answer: A Ref.: SO23-8-7 KA: GKA 2.3.6 Source: SONGs Bank Question Source: Bank # __X___

Modified Bank # __ ___

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge _X__

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # CE/A11;W/E08 EA2.14 CE/A11;W/E08 EA2.14 Importance Rating Tier #

Group #

Q-9 (Q-99)

The Reactor has tripped and four (4) CEAs are stuck out. After opening the Reactor Trip circuit breakers locally, two (2) CEAs fall in.

Which one (1) of the following would be the correct actions?

A. Emergency Borate the RCS, finish the Standard Post Trip Actions and diagnose a Reactor Trip Recovery event B. Emergency Borate the RCS, and immediately go to the Reactor Trip Recovery C. Emergency borate the RCS, and immediately go to the Functional Recovery D. Emergency borate the RCS, finish the Standard Post Trip Actions and diagnose a Functional Recovery entry Answer: A Ref.: SO23-12-1; SO23-12-10; SO23-12-9, Attach. FR-1 KA GKA 2.4.1 Source: SONGS Bank Question Source: Bank # __X___

Modified Bank # __ ___

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge _X__

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # CE/A11;W/E08 EA2.14 CE/A11;W/E08 EA2.14 Importance Rating Tier #

Group #

Q-10 (Q-12)

A Main Steam line break has occurred and both steam generators have gone dry. When reinitiating core cooling, what are the implications of feedwater introduction to a dry steam generator?

A. Both steam generators must be fed at an equal flow rate B. One steam generator is fed but excessive thermal stresses in the tubes may occur C. Overpressure in the steam generators may occur from the feedwater flashing to steam D. Feedwater must be introduced at a very low flowrate to prevent exceeding the shutdown cooling margin Answer: B Ref.: SO23-12-9, HR-1 KA: GAPE 0040 AK1.07 Source: NEW Question Source: Bank # __X___

Modified Bank # __ ___

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge _X__

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # CE/A11;W/E08 EA2.14 CE/A11;W/E08 EA2.14 Importance Rating Tier #

Group #

Q-11 (Q-40)

Units 2 & 3 are operating in Mode 1. A significant leak is occuring from the instument air system. Location and isolation of leaks has been unsuccessful. Air and nitrogen header pressure is rapidly lowering with no sign of recovery. When do you commence a plant shutdown?

A. When an ESFAS signal is received B. When header pressures are less than 40 psig C. When header pressures are less than 60 psig D. Plant shutdown is not required Answer: C Ref.: SO23-13-5 KA: APE 065 AA2.05 Source: NEW Question Source: Bank # __X___

Modified Bank # __ ___

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge _X__

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # CE/A11;W/E08 EA2.14 CE/A11;W/E08 EA2.14 Importance Rating Tier #

Group #

Q-12 (Q-17)

Given the following plant conditions: A Waste Gas Decay Tank release using 2/3 RT-7808, Plant Vent Stack Airborne Radiation Monitor, is in progress; Rad monitor 3RT-7865, Containment/Plant Vent Stack Radiation Monitor, becomes inoperable.

What additional action must be performed to allow the release to continue?

A. Process flow rate must be estimated at least once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months B. Two independent samples must be drawn at least once every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months C. Reverify valve alignment, sample and recalculate release rate calculations D. Verify composite samplers are operational for the gaseous radwaste system Answer: A Ref.: SO23-8-15 KA: GKA 2.1.20 Source: SONGS Bank Question Source: Bank # __X___

Modified Bank # __ ___

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge _X__

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # CE/A11;W/E08 EA2.14 CE/A11;W/E08 EA2.14 Importance Rating Tier #

Group #

Q-13 (Q-45)

During a reactor coolant system heatup the control room operator performs the first start of the fourth reactor coolant pump (RCP). Five minutes after this start the pump is shutdown to perform minor maintenance.

Which of the following describes the starting duty limits which apply for a subsequent restart of this RCP?

A. A restart may be attempted immediately after the motor coasts to a stop B. An interval of 20 minutes must elapse prior to a restart attempt to ensure RCP seal integrity when RCS temperature is above 500EF C. An interval of 10 minutes must elapse prior to a restart attempt to ensure proper thrust bearing lubrication D. An interval of 10 minutes must elapse prior to a restart attempt to allow loop temperatures to stabilize Answer: A Ref.: SO23-3-1.7; (N56419) RCP starting duty limits KA: 003 K6.14 Source: SONGS Bank Replacement Question A Reactor Coolant Pump is started in an idle loop.

What is the proper response to a unexpected rapid rise in excore power indication?

A. Immediately stop the RCP and emergency borate the RCS per SO23-13-11.

B. Stop the RCP and continue monitoring the NI's for approximately one minute following the transient.

C. Ensure all CEAs are fully inserted into the core and then wait five (5) seconds and trip the RCP.

D. Immediately stop the RCP and implement Loss of Boron Concentration Control/Inadvertent Dilution procedure.

Answer: A Question Source: Bank # __X___

Modified Bank # __ ___

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge _X__

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # CE/A11;W/E08 EA2.14 CE/A11;W/E08 EA2.14 Importance Rating Tier #

Group #

Q-14 (Q-47)

After a reactor trip a secondary safety lifts and an uncontrolled cooldown commences.

Automatic Safety Injection Actuation and Main Steam Isolation Signals fail to actuate and are initiated manually by the PNPO. All of the following occur except:

A. Containment Isolation B. The Containment Cooling system realigned C. Letdown isolation D. The Safeguards Pump Room coolers started Answer: A Ref.: SO23-3-2.22 KA: 013 A3.02 Source: INPO Bank Replacement Question Given the following:

-Unit 2 has tripped from full power.

-The following S/G level conditions exist IMMEDIATELY following the reactor trip:

Level Channel A B C D E089 S/G 33% 12% 18% 10%

E088 S/G 10% 4% 65% 0%

WHICH ONE (1) of the following describes the ESFAS response and the reason for that response?

A. An ESFAS 2 signal would be generated, but NOT an ESFAS 1 because ESFAS logic uses the auctioneered low level.

B. ESFAS 1 and ESFAS 2 signals would NOT be generated because both S/Gs EFAS circuitry senses the failed channels, thus sensing both S/Gs as faulted.

C. An ESFAS 2 signal would be generated, but not an ESFAS 1 because the setpoint is not exceeded on the E089 S/G.

D. ESFAS 1 and ESFAS 2 signals would be generated because both S/Gs have met the logic requirement on low level.

Answer: D Question Source: Bank # __X___

Modified Bank # __ ___

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge _X__

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A #

Importance Rating Tier #

Group #

Q-15 (Q-49)

Given the following conditions: Unit 2 is in MODE 6. The Operator on the Refueling Machine has just grappled a Fuel Assembly. The Fuel Assembly is to be transferred immediately to the Spent Fuel Pool.

Which ONE of the following conditions WOULD allow the Operator to continue and complete removal of the Fuel Assembly from the core?

A. Only one (1) Wide Range NI becomes inoperable B. The Control Room Source Range audible malfunctions and is inaudible C. Only one (1) Criticality Monitor becomes inoperable D. The Spent Fuel Pool low level alarm annunciates Answer: A Ref.: SO23-X-7 KA: 015 A3.03 Source: INPO Bank (Modified)

Replacement Question Given the following:

-Unit 1 is at 100% power.

-CPS/W Power Channel B indicates one (1) CPS.

-RTGB 104% Power Recorder is selected to "A" and indicates 100%.

-Extended Range Light is lit on Channel B.

WHICH ONE (1) of the following Channel B Nuclear Instruments has failed?

A. Log startup.

B. Linear Power Range Safety.

C. Wide Range Log Safety.

D. Linear Power Range Control.

Answer: C Question Source: Bank # __X___

Modified Bank # __ ___

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge _X__

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # CE/A11;W/E08 EA2.14 CE/A11;W/E08 EA2.14 Importance Rating Tier #

Group #

Q-16 (Q-51)

Which of the following best describes the configuration of the Containment Fan Coolers following an SIAS signal?

A. All fans start or shift to slow speed. The CCW outlet flow control valves will go full open for maximum flow $2115 gpm B. Three fans start or shift to fast speed. The CCW outlet flow control valves will go to the two fan flow setpoint $1400 gpm C. Three fans start or shift to slow speed. The CCW outlet flow control valves will go to the two fan flow setpoint $1400 gpm D. All fans start or shift to fast speed. The CCW outlet flow control valves will go full open for maximum flow $2115 gpm)

Answer: A Ref.: SO23-1-4.1; SO23-3-2.22 KA: 022 A3.01 Source: INPO Bank (Modified)

Replacement Question Need to make SONGS specific The following containment cooling lineup exists:

- Containment normal ACU A and B in-service

- Containment normal ACU C and D in standby

- CEDM ACU A in-service

- CEDM ACU B in standby

- Reactor cavity cooling fans A and C running

- Reactor cavity cooling fans B and D in standby

- Pressurizer cooling fan A running

- Pressurizer cooling fan Bin standby Computer point HCTS71A, HCTS71B Reactor cavity air temp Hi are in alarm Temperature indicates 115 degrees F.

Which of the following describes how cavity temp will be reduced?

A. Standby reactor cavity cooling fans will automatically start on high temperature.

B. Manually start standby cavity cooling fans or manually align the standby containment normal ACU.

C. Manually start standby cavity cooling fans or manually align the standby CEDM ACU.

D. Standby containment normal ACU automatically starts on high temperature.

Manually start standby cavity cooling fans.

Answer: B

Question Source: Bank # __X___

Modified Bank # __ ___

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge _X__

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # CE/A11;W/E08 EA2.14 CE/A11;W/E08 EA2.14 Importance Rating Tier #

Group #

Q-17 (Q-53)

The plant is operating at 85% power with both Heater Drain Pumps out of service when all operating condensate pumps trip. As a result, the MFW pumps trip. WHICH ONE of the following caused the MFW pumps to trip?

A. Reduction in MFW pump suction pressure B. Interlock with condensate pump breakers C. Overspeed of MFW pump turbines D. Excessive vibration of MFW pumps Answer: A Ref.: SO23-2-2 KA: 056 A2.04 Source: INPO Bank (Modified)

Q-82 from RO test, IDed as SRO Only The Containment cooling system and Containment Spray Systems provide redundant capabilities for all of the following purposes EXCEPT:

A. Remove heat energy form containment B. Reduce pressure in containment C. Iodine Removal D. Assist in maintaining containment integrity during a LOCA Answer: C Question Source: Bank # ______

Modified Bank # ___X__

New ___ _

Question Cognitive Level: Memory or Fundamental Knowledge __X__

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # 027K1.01 027K1.01 Importance Rating 3.4 3.7 Tier # 2 2 Group # 3 3

Q-18 (Q-55)

An EFAS 1 signal will be present for which of the following? (consider each answer separately)

A. S/G 1@ 5% NR, S/G 2@ 1O% NR, S/G 1@ 500 psia, S/G 2 @370 psia B. S/G 1@ 20% NR, S/G 2@ 26.5% NR, S/G I& 2 @ 600 psia C. S/G 1@ 30% NR, S/G 2@ 25% NR, S/G 1@ 700 psia, S/G 2@ 680 psia D. S/G 1@ 15% NR, S/G 2@ 20% NR, S/G 1@200 psia, S/G 2 @ 400 psia Answer: A Ref.: SO23-14-6 KA: 061 K4.02 Source: INPO Bank 89 from RO test IDed as SRO Only Given the following conditions:

- Current date and Time are December 10 at 1300 hours0.015 days 0.361 hours 0.00215 weeks 4.9465e-4 months .

- Electrical maintenance notifies the control room that SR3.8.4.2, 92 Day Class Battery Surveillance Test, was not performed on Channel C within the required 1.25 interval.

- The Shift Technical Advisor determines the interval expired at 0700 today.

- Electricians inform the Shift Supervisor the test will take an additional 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months to complete.

- All other surveillance tests are current.

WHICH ONE of the following identifies the technical specification required time to declare Channel C INOPERABLE and the action(s) for this condition?

A. 10 Dec 1300 and complete SR3.8.4.2 within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or commence plant shutdown at that time.

B. 10 Dec 0700 and commence plant shutdown C. 10 Dec 1300 and commence plant shutdown.

D. Complete SR3.8.4.2 within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or declare inoperability at that time and commence plant shutdown.

Answer: A

Reference:

Tech Spec 3.8.4 Question Source: Bank # ___ ___

Modified Bank # __X___

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge _____

Comprehension or Analysis __X__

Examination Outline Cross-reference:

Level RO SRO K/A # 2.1.12 2.1.12 Importance Rating 2.9 4.0 Tier # 3 3 Group # 1 1

Q-19 (Q-59)

A High Fuel Handling Building (FHB) airborne radiation alarm has been received. An Operator, dispatched to the FHB to check the status reports that the Spent Fuel Pool cooling line siphon breaker is uncovered and water is not coming out of the anti siphon hole. What action should you direct him to take?

A. Start a second Spent Fuel Pool pump B. Lower the Spent Fuel Pool level C. Stop all Spent Fuel Pool pumps D. Evacuate the FHB until the radiation alarm clears Answer: A Ref.: SO23-15-60.a1 KA: 072 K1.01 Source: NEW Question Source: Bank # __X___

Modified Bank # __ ___

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge _X__

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # CE/A11;W/E08 EA2.14 CE/A11;W/E08 EA2.14 Importance Rating Tier #

Group #

Q-20 (Q-61)

Given the following conditions: Reactor has tripped from 100% power. Reactor coolant system pressure is 1650 psia and dropping. Pressurizer level is 10% and dropping. Steam generator levels have turned at 36% wide range and are recovering with auxiliary feedwater. Steam generator pressures are 730 psia and rising. Tc is 555EF and steady. Containment pressure is 7.4 psig and rising. Safety Injection and Containment Isolation actuations have occurred.

WHICH ONE of the following states the additional Engineered Safety Features actuation(s) present assuming all systems functioned as designed?

A. Main Steam Isolation B. Auxiliary Feedwater Actuation C. Auxiliary Feedwater Actuation and Containment Spray Actuation D. Containment Spray Actuation and Main Steam Isolation Answer: A Ref.: SO23-12-1 KA: 013 K1.01 Source: INPO Bank (Modified)

Question Source: Bank # __X___

Modified Bank # __ ___

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge _X__

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # CE/A11;W/E08 EA2.14 CE/A11;W/E08 EA2.14 Importance Rating Tier #

Group #

Q-21 (Q-63)

Given the following conditions: Unit 2 is operating at 100% full power. Control room is notified that lift setpoint for one of the pressurizer code safety valves, is out of tolerance high due to an error in test calculation.

-The other pressurizer code safety valve is OPERABLE.

WHICH ONE of the following states the required Technical Specification action for this condition?

A. Restore within 15 minutes or be in MODE 3 in the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months B. Restore within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in MODE 3 in the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months C. Restore within 15 minutes or be in MODE 2 in the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months D. Restore within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in MODE 2 in the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Answer: A Ref: Tech. Specs. KA: 002 K6.12 Source: INPO Bank (Modified)

Question Source: Bank # __X___

Modified Bank # __ ___

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge _X__

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # CE/A11;W/E08 EA2.14 CE/A11;W/E08 EA2.14 Importance Rating Tier #

Group #

Q-22 (Q-65)

Given the following conditions: Unit operating at 100% full power; Pressurizer Pressure Control System, in AUTO with the setpoint at 2250 psia; Pressurizer pressure is 2270 psia and rising.

WHICH ONE of the following describes the next automatic action as pressurizer pressure continues to rise?

A. Pressurizer spray valves modulate open B. Pressurizer heaters deenergize C. Reactor trip on High -Pressurizer Pressure D. Reactor trip on Core Protection Calculators auxiliary trip Answer: A Ref.: SD-SO23-360 KA: 010 K4.03 Source: INPO Bank Q-22 (Q-94 for RO test IDed as SRO Only)

Which one of the following plant conditions is a Technical Specification requirement before a NEW fuel assembly can be moved into an empty (defueled) Reactor Vessel?

A. Both trains of shutdown cooling operating.

B. One source range neutron flux monitor operable and operating.

C. Source Range Neutron Flux Audible Indication in containment is operable.

D. Refueling cavity level of 23' 2".

Answer: C

Reference:

Tech. Spec, Question Source: Bank # ___X___

Modified Bank # _______

New ___ _

Question Cognitive Level: Memory or Fundamental Knowledge __X_

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # 2.2.27 2.2.27 Importance Rating 2.6 3.5 Tier # 3 3 Group # 2 2

Q-23 (Q-71)

Consider the following conditions:

-Refueling operations are in progress.

-The fuel transfer canal gate valve is open.

Which one of the following lists the expected indications for a Spent Fuel Pool leak?

A. Low level alarms in the refueling and fuel handling Spent Fuel Pools, Fuel Building sump level increase B. Low level alarms in the refueling and fuel handling Spent Fuel Pools, containment and Fuel Building sump level increase C. Low level alarm in the refueling pool only, Fuel Building sump level increase D. Low level alarm in the fuel handling pool only, Fuel Building sump level increase Answer: A Ref.: SD-SO23-430 KA: 033 A1.01 Source: INPO Bank (Modified)

Question Source: Bank # __X___

Modified Bank # __ ___

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge _X__

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # CE/A11;W/E08 EA2.14 CE/A11;W/E08 EA2.14 Importance Rating Tier #

Group #

Q-24 (Q-72)

Given the following conditions: Unit operating at 100% power and a power reduction is commenced. Both feedwater control systems are in "AUTO".

WHICH ONE of the following describe the action(s) on feedwater control system as power is lowered to 50% full power?

A. Feedwater flow is controlled by Feed Pump speed and Feedwater Regulating valves B. Feedwater flow is controlled by Feedwater Regulating Bypass valves C. The operator controls each Feedwater Control system in Preferred Manual Mode D. The operator controls each Feedwater Control system in Alternate Manual Mode Answer: A Ref.: SD-SO23-250 KA: 035 K4.01 Source: INPO Bank (Modified)

Replacement Question Given the following:

-A loss of offsite power and a reactor trip has occurred.

-SO23-12-7, "Loss of Forced Circulation/Loss of Offsite Power," has been implemented.

-The RCO states that he is not sure if natural circulation exits.

-RCS Pressure is 995psia WHICH ONE (1) of the following conditions would indicate a problem with natural circulation flow?

A. T-hot is 527 degrees F. and T-cold is 489F.

B. T-hot is 527 and stable, T-cold is 489 and stable.

C. REP CET is 530F.

D. T-hot is 527F and pressurizer temperature indicates 551F.

Answer: C Question Source: Bank # __X___

Modified Bank # __ ___

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge _X__

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # CE/A11;W/E08 EA2.14 CE/A11;W/E08 EA2.14 Importance Rating Tier #

Group #

Q-25 (Q-75)

Given the following conditions: An emergency diesel generator surveillance is in progress; 2G003 is fully loaded on bus 2A06.

Subsequently: A low voltage alarm is received; switchyard voltage is 218 kV and steady.

Operator response per SO23-13-4 Operation During Major System Disturbances requires unloading the emergency diesel generator and opening the output breaker.

Which of the following describes the reason for the actions required in SO23-14-4, Operation During Major System Disturbances?

A. To enable the Degraded Voltage protection circuit B. To restore Unit 2 to within the Limiting Condition for Operation (LCO)

C. To raise bus voltage which prevents damaging permanently connected bu loads D. To prevent EDG trip on generator differential voltage Answer: A Ref.: SO23-750, SO23-13-4 KA: 064 A1.03 Source: Songs Requal. bank b (modified)

Question Source: Bank # __X___

Modified Bank # __ ___

New __ __

Question Cognitive Level: Memory or Fundamental Knowledge _X__

Comprehension or Analysis __ __

Examination Outline Cross-reference:

Level RO SRO K/A # CE/A11;W/E08 EA2.14 CE/A11;W/E08 EA2.14 Importance Rating Tier #

Group #

JPM INFORMATION SHEET JPM NUMBER NRC RO Ala INITIAL PLANT CONDITIONS Diesel Generator 2G-003 is being run for a Post Maintenance Test per SO23-2-13, Attachment 2.

Maintenance requests the following:

Procedure change to allow monitoring of Air Receiver pressure drop for the DG start, requiring Air Compressor C013B control switch to be placed in OFF as an added substep to step 2.2.10.

Procedure change to return Air Compressor C013B control switch to AUTO as an added substep to step 2.5.4 TASK TO BE PERFORMED The CRS has directed you to prepare a Procedure Modification Permit to document the required changes to SO23-2-13.

Rev. 0 7/19/03 Page 1 of 13

JOB PERFORMANCE MEASURE NRC RO Ala SUGGESTED TESTING ENVIRONMENT: PLANT X SIMULATOR ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATOR'S NAME:

(Print)

The operator's performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

Rev. 0 7/19/03 Page 2 of 13

DOCUMENTATION NRC RO A1a JPM LEVEL: RO ESTIMATED TIME TO COMPLETE: 15 min.

TIME CRITICAL JPM: NO CRITICAL TIME:

POSITION: ACO TASK SYS ID:

TASK DESCRIPTION:

Prepare a Procedure Modification Permit KA NUMBER: G2.1.21 KA VALUES: RO 3.1 SRO 3.2 10CFR55.45 APPLICABILITY: 12, 13

REFERENCES:

SO123-0-20, Revision 14 AUTHOR: Joseph G. Arsenault DATE: 10/6/2003 OPERATIONS REVIEW: DATE:

APPROVED BY: DATE:

Rev. 0 7/19/03 Page 3 of 13

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 0 New JPM JGA 8/7/03 Rev. 0 7/19/03 Page 4 of 13

SET-UP Rev. 0 7/19/03 Page 5 of 13

JPM: NRC RO Ala TITLE: Prepare a Procedure Change Request using a Procedure Modification Permit.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat)

When candidate locates copy of SO123-0-20, provide with a clean copy.

1 Document Permit number, Documents Permit #1 Start Time:

Unit, Procedure number, Revision, and TCN, Checks box for Unit 2 Attachment, Pages of PMP, and Procedure title Procedure Number is SO23 13 REV/TCN is 23-2 Attachment is 2 PMP Page is 1 of 2 Procedure Title is 2G003 Diesel Generator Operation CUE: Permit Number is 1 Rev. 0 7/19/03 Page 6 of 13

JPM: NRC RO Ala TITLE: Prepare a Procedure Change Request using a Procedure Modification Permit.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat) 2 Determine if the activity Determine that the activity conflicts with the plant does NOT conflict with the operating license, plant operating license, Technical Specifications, Technical Specifications, and or LCS (Licensee and or LCS (Licensee Controlled Specifications) Controlled Specifications) and checks NO in the box for item 1 Rev. 0 7/19/03 Page 7 of 13

JPM: NRC RO Ala TITLE: Prepare a Procedure Change Request using a Procedure Modification Permit.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat) 3 Determine if Determines that implementation of activity implementation of activity could: does NOT:

Pose adverse

Pose adverse ENVIRONMENTAL EFFECTS ENVIRONMENTAL EFFECTS of any type directly of any type directly or or indirectly indirectly

Potentially impact

Potentially impact the the TOPIC REPORT, TOPIC REPORT, SECURITY SECURITY PLANS, PLANS, EMERGENCY PLAN, EMERGENCY PLAN, FIRE FIRE PROTECTION PROTECTION PROGRAM, PROGRAM, ODCM, IST, ODCM, IST, and/or ISI and/or ISI programs programs

Potentially impact

Potentially impact TECHNICAL REQUIREMENTS, TECHNICAL e.g.,, non-conservative REQUIREMENTS, e.g.,, changes to setpoints non-conservative and/or acceptance changes to setpoints criteria and/or acceptance criteria

Applicant checks NO for each impact in the box for item 2 Rev. 0 7/19/03 Page 8 of 13

JPM: NRC RO Ala TITLE: Prepare a Procedure Change Request using a Procedure Modification Permit.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat) 4* Check all items that apply Applicant determines that to the proposed PMP the change involves activity MAINTENANCE ACTIVITIES, and Checks the appropriate box

Implements already approved changes (per approval process) in Procedures, DSAR/UFSAR, UFHA, design documents, Tech Spec amendments, LCS, ODCM, EMERGENCY PLAN, TOPICAL REPORT, IST Plan, ISI Plan, OAs, or NCR dispositions. Enter identifiers and associated numbers

Involves Maintenance activities

Implements editorial corrections (ECs) or minor procedure modifications

Involves a procedure which is 10CFR50.59 Rev. 0 7/19/03 Page 9 of 13

JPM: NRC RO Ala TITLE: Prepare a Procedure Change Request using a Procedure Modification Permit.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat) 5 Determine if there are Applicant determines that parts of the modification the modification is entirely which are not entirely addressed by MAINTENANCE addressed by the items ACTIVITIES and checks NO in checked on previous step. the box for item 3.b 6 Determine if the PMP Determine that the PMP does changes the INTENT of the NOT change the INTENT of the operating instruction by: operating instruction by:

Allowing performance

Allowing performance of of a new, unrelated a new, unrelated function, not function, not originally authorized originally authorized

Requiring a new or

Requiring a new or additional 50.59 additional 50.59 evaluation evaluation

Applicant checks NO in boxes for items 4.a and 4.b 7* Document procedure step Applicant documents steps numbers that are affected 2.2.10 (will be substep 7) and step 2.5.4 (will be substep 4)

Rev. 0 7/19/03 Page 10 of 13

JPM: NRC RO Ala TITLE: Prepare a Procedure Change Request using a Procedure Modification Permit.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat) 8* Provide description of Step 2.2.10 - Place Air modification Compressor C013B control switch to OFF Step 2.5.4 - Place Air Compressor control switch C013B control switch to AUTO 9 Provide reason for Step 2.2.10 - Monitor Air modification Receiver pressure drop after DG start Step 2.5.4 - Restore system to normal alignment 10 Line out any blank spaces Places line across spaces on PMP not used 11 Determine if PMP should be Determines that the PMP is evaluated for one-time use and checks NO incorporation into existing procedures Rev. 0 7/19/03 Page 11 of 13

JPM: NRC RO Ala TITLE: Prepare a Procedure Change Request using a Procedure Modification Permit.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat) 12 Sign and date PMP as Signs and dates PMP Stop Time:

Preparer TERMINATING CUE: The CRS will attach the PMP to the procedure and make any required procedure modifications Rev. 0 7/19/03 Page 12 of 13

JPM CHECKLIST

1. The JPM is:

a. X Supported by facility's job task analysis.

b. X Operationally important (meets threshold criterion of K/A 3.0 or greater).

c. X Designed as either SRO only, or RO/SRO.

2. Each JPM includes:

a. X Initial conditions.

b. X Initiating cues.

c. X References, including associated procedures.

d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.

e. X System response cues that are complete and correct so that the examiner can properly cue the examinee, if asked.

f. X Statements describing important actions or observations that should be made by the examinee.

g. X Criteria for successful completion.

h. X Identification of the critical steps and their associated performance standards.

i. X Validated time limits (average time allowed for completion).

j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.

COMPLETED BY: J, Arsenault DATE: 10/7/2003 Page 13 of 13

JPM INFORMATION SHEET JPM NUMBER NRC RO A1b INITIAL PLANT CONDITIONS Unit 2 is in Mode 3 in preparation for a reactor startup after a reactor trip 109 hours0.00126 days 0.0303 hours 1.802249e-4 weeks 4.14745e-5 months ago.

Conditions are as follows:

MOC, 125 EFPD per Reactor Engineering.

RCS Boron Concentration is 1900 ppm.

Tave is 545°F.

All CEAs are inserted.

TASK TO BE PERFORMED Perform a Shutdown Margin calculation using MOC Core Physics Data.

REV 0, 08/19/03 Page 1 of 9

JOB PERFORMANCE MEASURE NRC RO A1b SUGGESTED TESTING ENVIRONMENT: PLANT X SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATOR'S NAME:

(Print)

The operator's performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

REV 0, 08/19/03 Page 2 of 9

DOCUMENTATION NRC RO A1b JPM LEVEL: RO/SRO ESTIMATED TIME TO COMPLETE: 20 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: UACO TASK SYS ID: 23717 TASK DESCRIPTION:

Technical Specification requirements for Shutdown Margin in Modes 1-4.

KA NUMBER: 001-A4.11 KA VALUES: RO 3.5 SRO 4.1 10CFR55.45 APPLICABILITY: 4, 12

REFERENCES:

SO23-3-3.29, Determination of Reactor Shutdown Margin, Rev. 16.

AUTHOR: J. Arsenault DATE: 08/19/03 OPERATIONS REVIEW: DATE:

APPROVED BY: DATE:

REV 0, 08/19/03 Page 3 of 9

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOL BY MODIFIED APPROVAL 0 Derived from Sim JPM 078S. New JGA 08/19/03 conditions, new JPM developed for 2003 NRC exam REV 0, 08/19/03 Page 4 of 9

SET-UP Provide examinee with a copy of SO23-3-3.29, Determination of Reactor Shutdown Margin, Attachment 2 after the examinee has identified the appropriate procedure and Attachment to use.

REV 0, 08/19/03 Page 5 of 9

JPM: NRC RO A1b TITLE: Perform a Shutdown Margin Calculation

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat) 1 Identify procedure Identifies procedure Start Time: ________

S023-3-3.29, Attachment 2. S023-3-3.29, Attachment 2.

NOTE: Provide the examinee with a copy of SO23-3-3.29, Attachment 2, with prerequisites signed.

2 Record present RCS boron Determines from initial concentration. conditions that boron concentration is 1900 ppm 3 Record present RCS Tavg. Determines from initial conditions that Tave is 545EF 4 Record present cycle Records present cycle burnup. burnup, 125 EFPD, per initial conditions.

NOTE: No correction factors have been provided by Reactor Engineering for B-10 depletion.

5 Calculate the adjusted Calculates the adjusted critical boron critical boron concentration concentration for from OPS Fig. 2.2-1 and adds potential reactivity bias. 150 ppm for B-10 depletion.

(1975-2025 ppm)

REV 0, 08/19/03 Page 6 of 9

JPM: NRC RO A1b TITLE: Perform a Shutdown Margin Calculation

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat) 6 Calculate the critical Calculates the critical boron margin. boron margin. (-75 to -125 ppm) 7 Determine the inverse Determines the inverse boron boron worth for the worth from OPS Fig. 3.3.

present RCS Tavg and boron (133 to 135 ppm/% ?K/K) concentration.

8 Calculate the boron Calculates the boron reactivity defect. reactivity defect.

(-0.56 to -0.92 %?K/K) 9 Determine the total CEA Determines the total CEA worth for present Tavg and worth from OPS Figure 4.3 RCS boron concentration. 4.4.

(8.8%?K/K) 10 Determine the withdrawn Determines the withdrawn CEA CEA worth. worth to be 0.

11 Determine the Xenon worth Determines the Xenon worth based on present cycle to be 0.

burnup and Xenon decay time.

REV 0, 08/19/03 Page 7 of 9

JPM: NRC RO A1b TITLE: Perform a Shutdown Margin Calculation

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat) 12 Calculate actual Shutdown Calculates actual Shutdown

Margin. Margin.

(7.88 to 8.24 %?K/K) 13 Calculate percent shutdown Calculates percent shutdown of the Reactor. of the Reactor.

(7.88 to 8.24 %?K/K) 14 Determine the actual Determines the actual Stop Time: ________

Shutdown Margin is greater Shutdown Margin is greater than or equal to than 5.15% ?K/K in Mode 3.

5.15% K/K in Mode 3.

TERMINATING CUE:

This JPM is complete.

REV 0, 08/19/03 Page 8 of 9

REV 0, 08/19/03 Page 9 of 9 JPM CHECKLIST

1. The JPM is:

a. X Supported by facility's job task analysis.

b. X Operationally important (meets threshold criterion of K/A 3.0 or greater).

c. X Designed as either SRO only, or RO/SRO.

2. Each JPM includes:

a. X Initial conditions.

b. X Initiating cues.

c. X References, including associated procedures.

d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.

e. X System response cues that are complete and correct so that the examiner can properly cue the examinee, if asked.

f. X Statements describing important actions or observations that should be made by the examinee.

g. X Criteria for successful completion.

h. X Identification of the critical steps and their associated performance standards.

i. X Validated time limits (average time allowed for completion).

j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.

COMPLETED BY: J. Arsenault DATE: 08/19/03 REV 0, 08/19/03 Page 10 of 9

JPM INFORMATION SHEET JPM NUMBER NRC RO A2 INITIAL PLANT CONDITIONS The Unit 2 Containment Spray Pump P-012 Casing Vent Valve (S21206MU040) is leaking. The pump will be isolated to stop the leak. A Work Authorization Request must be prepared to allow repairs to the pump.

TASK TO BE PERFORMED The Shift Manager directs you to identify the clearance boundaries required to allow repair of the Unit 2 Containment Spray Pump P-012 Casing Vent Valve. Inform the Shift Manager when complete.

REV 1, 08/19/03 Page 1 of 8

JOB PERFORMANCE MEASURE NRC RO A2 SUGGESTED TESTING ENVIRONMENT: PLANT X SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATOR'S NAME:

(Print)

The operator's performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

REV 1, 08/19/03 Page 2 of 8

DOCUMENTATION NRC RO A2 JPM LEVEL: RO/SRO ESTIMATED TIME TO COMPLETE: 20 minutes TIME CRITICAL JPM: N/A CRITICAL TIME: N/A POSITION: UACO TASK SYS ID: 1002 TASK DESCRIPTION:

Prepare a Work Authorization Record tagout.

KA NUMBER: 2.2.13 KA VALUES: RO 3.6 SRO 3.8 10CFR55.45 APPLICABILITY: 12, 13

REFERENCES:

SO123-XX-5, Work Authorizations, Rev. 12-2.

Containment Spray P&ID #40114A Safety injection P&ID #40112A 4160 V Switchgear Bus 2A04 One Line Diagram #30107 AUTHOR: L. Zilli DATE: 07/07/00 OPERATIONS REVIEW: M. Jones DATE: 08/02/00 APPROVED BY: W. Lyke DATE: 08/04/00 REV 1, 08/19/03 Page 3 of 8

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOL BY MODIFIED APPROVAL 1 Reviewed SO123-XX-5, Rev. 8 and LRZ 07/07/00 modified as required REV 1, 08/19/03 Page 4 of 8

SET-UP Obtain P&IDs for:

C Containment Spray Pumps #40114A C Safety Injection Pumps #40112A Obtain One-Line Diagram for:

C 4160 V Switchgear Bus 2A04 #30107 Provide the examinee with a blank WAR Tag Installation sheet and a highlighter to outline the flowpath.

REV 1, 08/19/03 Page 5 of 8

JPM: NRC RO A2 TITLE: Identify Clearance Boundary for Work Authorization Request

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat)

NOTE: Provide the applicant with copies of the prints and a blank WAR Removal from Service sheet.

1 Obtain P&IDs: Obtains P&IDs: Start Time: ________

C Containment Spray C Containment Spray #40114A

40114A C Safety Injection #40112A C Safety Injection #40112A Obtains One-Line Diagram:

Obtain One-Line Diagram: C 4160 V Bus 2A04 #30107 C 4160 V Bus 2A04 #30107 2 Locate the component to be Locates Containment Spray isolated. Pump P-012 Casing Vent Valve (S21206MU040).

REV 1, 08/19/03 Page 6 of 8

JPM: NRC RO A2 TITLE: Identify Clearance Boundary for Work Authorization Request

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat) 3* Determine the clearance Determines the clearance boundaries to be used to boundaries to be:

isolate the repair area. C P-012 Breaker 2A0403 RACKED OUT C P-012 Discharge Valve S21206MU012 CLOSED C P-012 Suction Isolation Valve S21204MU062 CLOSED C P-012 SFP Suction Isolation Valve S21201MU992 CLOSED C MU992 Integral Bypass S21201MU235 CLOSED C Recirculation Valve S21206MU010 CLOSED C Suction Drain Valve S21206MR439 OPEN.

4 Identify additional Identifies additional components requiring components requiring alignment. alignment.

C P-012 Control Switch to OFF C Casing Vent Valve S21206MU040 OPEN (no tag)

REV 1, 08/19/03 Page 7 of 8

JPM: NRC RO A2 TITLE: Identify Clearance Boundary for Work Authorization Request

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat) 5 Inform the Shift Manager Informs the Shift Manager Stop Time: ________

of task completion. that the clearance boundaries have been identified.

TERMINATING CUE:

This JPM is complete.

REV 1, 08/19/03 Page 8 of 8

REV 1, 08/19/03 Page 9 of 8 JPM CHECKLIST

1. The JPM is:

a. X Supported by facility's job task analysis.

b. X Operationally important (meets threshold criterion of K/A 3.0 or greater).

c. X Designed as either SRO only, or RO/SRO.

2. Each JPM includes:

a. X Initial conditions.

b. X Initiating cues.

c. X References, including associated procedures.

d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.

e. X System response cues that are complete and correct so that the examiner can properly cue the examinee, if asked.

f. X Statements describing important actions or observations that should be made by the examinee.

g. X Criteria for successful completion.

h. X Identification of the critical steps and their associated performance standards.

i. X Validated time limits (average time allowed for completion).

j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.

COMPLETED BY: J. Arsenault DATE: 08/19/03 REV 1, 08/19/03 Page 10 of 8

JPM INFORMATION SHEET JPM NUMBER NRC RO A3 INITIAL PLANT CONDITIONS You have been directed to perform a valve alignment in Containment Spray Pump P-012 room. The task involves uncapping and opening a drain valve, and attaching a drain hose directed to the floor drain.

TASK TO BE PERFORMED Select the appropriate REP for the work to be performed and determine allowable stay time in the work area.

Rev. 0 8/19/03 Page 1 of 8

JOB PERFORMANCE MEASURE NRC RO A3 SUGGESTED TESTING ENVIRONMENT: PLANT X SIMULATOR ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATOR'S NAME:

(Print)

The operator's performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

Rev. 0 8/19/03 Page 2 of 8

DOCUMENTATION NRC RO A3 JPM LEVEL: RO ESTIMATED TIME TO COMPLETE: 10 Min TIME CRITICAL JPM: NO CRITICAL TIME:

POSITION: ACO TASK SYS ID:

TASK DESCRIPTION:

Determine Stay Time KA NUMBER: G2.3.2 KA VALUES: RO 2.5 SRO 2.9 10CFR55.45 APPLICABILITY: 8, 9

REFERENCES:

AUTHOR: Joseph G. Arsenault DATE: 8/19/03 OPERATIONS REVIEW: DATE:

APPROVED BY: DATE:

Rev. 0 8/19/03 Page 3 of 8

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 0 New JPM JGA 8/19/03 Rev. 0 8/19/03 Page 4 of 8

SET-UP Provide applicant with survey maps and REPs to choose from. Also supply Unit 3 Safety Equipment Building Floor Plan. (Mosaic will NOT be available)

Rev. 0 8/19/03 Page 5 of 8

JPM: NRC RO A3 TITLE: Determine Stay Time for Work to be Performed

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat)

Cue: Provide applicant with Survey Maps and REPs to choose from. Direct candidate to assume all radiation exposure received is in the general area. Also supply Unit 3 Safety Equipment Building Floor Plan. (Mosaic will NOT be available) 1* Determine applicable Locates survey map #030905- Start Time:

survey map 006, Page 2 of 3 for the task to be performed.

(Safety Equipment Building)

CUE:

2* Determine REP that Locates and reviews REP provides coverage of the #200198.

task performed CUE:

Rev. 0 8/19/03 Page 6 of 8

JPM: NRC RO A3 TITLE: Determine Stay Time for Work to be Performed

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat) 3* Determine Stay Time in Based upon general area Stop Time:

work area radiation levels in area and required setpoint of alarming dosimeter, determine that stay time will be 30 minutes based on 200 Mr/hr general area radiation and 100 mr dose alarm TERMINATING CUE:

This JPM is complete.

Rev. 0 8/19/03 Page 7 of 8

JPM CHECKLIST

1. The JPM is:

a. X Supported by facility's job task analysis.

b. X Operationally important (meets threshold criterion of K/A 3.0 or greater).

c. X Designed as either SRO only, or RO/SRO.

2. Each JPM includes:

a. X Initial conditions.

b. X Initiating cues.

c. X References, including associated procedures.

d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.

e. X System response cues that are complete and correct so that the examiner can properly cue the examinee, if asked.

f. X Statements describing important actions or observations that should be made by the examinee.

g. X Criteria for successful completion.

h. X Identification of the critical steps and their associated performance standards.

i. X Validated time limits (average time allowed for completion).

j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.

COMPLETED BY: J. Arsenault DATE: 8/19/03 Rev. 0 7/19/03 Page 8 of 8

JPM INFORMATION SHEET JPM NUMBER NRC RO A4 INITIAL PLANT CONDITIONS The time is 0300, Sunday night. A Site Area Emergency has been declared. The Shift Manager has activated the Emergency Plan and you have been directed to initiate Operations Leader actions in accordance with SO23-VIII-30 TASK TO BE PERFORMED Initiate initial Site Accountability in accordance with SO23-VIII-30 Rev. 0 8/19/03 Page 1 of 9

JOB PERFORMANCE MEASURE NRC RO A4 SUGGESTED TESTING ENVIRONMENT: PLANT X SIMULATOR ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATOR'S NAME:

(Print)

The operator's performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

Rev. 0 8/19/03 Page 2 of 9

DOCUMENTATION NRC RO A4 JPM LEVEL: RO ESTIMATED TIME TO COMPLETE: 10 Min TIME CRITICAL JPM: NO CRITICAL TIME:

POSITION: ACO TASK SYS ID:

TASK DESCRIPTION:

Initiate initial Site Accountability KA NUMBER: G2.4.39 KA VALUES: RO 3.3 SRO 3.1 10CFR55.45 APPLICABILITY: 11, 12

REFERENCES:

SO23-VIII-30 Revision 6 AUTHOR: Joseph G. Arsenault DATE: 8/19/03 OPERATIONS REVIEW: DATE:

APPROVED BY: DATE:

Rev. 0 8/19/03 Page 3 of 9

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 0 New JPM JGA 8/19/03 Rev. 0 8/19/03 Page 4 of 9

SET-UP Have appropriate log or manning sheet available for use once the applicant describes which documents and logs would be used Rev. 0 8/19/03 Page 5 of 9

JPM: NRC RO A4 TITLE: Initiate Initial Site Accountability

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat)

Cue: When SO23-VIII-30 has been located, provide a copy to applicant.

1 Obtain current copy of Obtains SO23-VIII-30, Start Time:

SO23-VIII-30, Units 2/3 Revision 6 Operations Leader Duties 2 Edit the operator watch Locates night shift portion bill to ensure an accurate of Operations manning sheet.

list of on-shift operators. Include all Units 2 and 3 operators CUE: The shift manning sheet accurately reflects the shift complement at the start of the shift 3* Identify which operators Requests names of personnel are in the control room present in control room and area and check their names checks each name off on the on the watch bill or log manning sheet their presence CUE: When applicant requests operators present in control room, hand them attachment 1 of this JPM Rev. 0 7/19/03 Page 6 of 9

JPM: NRC RO A4 TITLE: Initiate Initial Site Accountability

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat) 4* Contact all operators who Contacts each person not are outside the control listed in control room room area and do the either by phone or radio.

following: Enters red badge information and location of each.

Determine their location Continues attempting to

Ensure their red contact the 43 watch badge number is (Studley). May report written on the watch missing employee to Shift bill or in the log Manager

Enter their location on the watch bill or log CUE: each employee is called, report that you are in the lunch room. DO NOT respond to calls for Studley. Indicate there is no response.

Gilliam, badge #31 Rohan, Badge #44 Smiley, Badge #72 Klink, Badge #12 Schultz, Badge #20 Hogan, Badge #3 Wake, Badge #18 Rev. 0 7/19/03 Page 7 of 9

JPM: NRC RO A4 TITLE: Initiate Initial Site Accountability

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat)

CUE: The OSC Ops Coordinator position is staffed 5* Turn over operator Provides name, location, and Stop Time:

accountability and badge number of each person tracking to the OSC OPS outside of control room.

Coordinator and provide Reports status of employee the following information that cannot be located.

for all operators outside of the control room area:

Name and current TERMINATING CUE:

location

Red Badge Number This JPM is complete.

Rev. 0 7/19/03 Page 8 of 9

JPM CHECKLIST

1. The JPM is:

a. X Supported by facility's job task analysis.

b. X Operationally important (meets threshold criterion of K/A 3.0 or greater).

c. X Designed as either SRO only, or RO/SRO.

2. Each JPM includes:

a. X Initial conditions.

b. X Initiating cues.

c. X References, including associated procedures.

d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.

e. X System response cues that are complete and correct so that the examiner can properly cue the examinee, if asked.

f. X Statements describing important actions or observations that should be made by the examinee.

g. X Criteria for successful completion.

h. X Identification of the critical steps and their associated performance standards.

i. X Validated time limits (average time allowed for completion).

j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.

COMPLETED BY: J. Arsenault DATE: 8/19/03 Rev. 0 8/19/03 Page 9 of 9

JPM INFORMATION SHEET JPM NUMBER NRC SRO A1a INITIAL PLANT CONDITIONS Unit 2 is in Mode 5 in preparation for a Refueling Outage after a 400 day run. Work is currently being performed on the RCS with SG E089 Hot Leg Manway OPEN. RCS level is currently 27 inches.

RCS Temperature is currently 148BF. The reactor has been shut down for 9 days.

Outage specific Time to Boil Data Transmittal has NOT been provided by Reactor Engineering TASK TO BE PERFORMED Determine Time to Boil Margin for Shutdown Nuclear Safety in accordance with SO23-5-1.8.1 Rev. 0 8/19/03 Page 1 of 8

JOB PERFORMANCE MEASURE NRC SRO A1a SUGGESTED TESTING ENVIRONMENT: PLANT X SIMULATOR ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATOR'S NAME:

(Print)

The operator's performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

Rev. 0 8/19/03 Page 2 of 8

DOCUMENTATION NRC SRO A1a JPM LEVEL: SRO ESTIMATED TIME TO COMPLETE: 15 Min TIME CRITICAL JPM: NO CRITICAL TIME:

POSITION: CRS TASK SYS ID:

TASK DESCRIPTION:

Determine Time to Boil Margin KA NUMBER: G2.1.4 KA VALUES: RO 2.3 SRO 3.4 10CFR55.45 APPLICABILITY: 4, 12

REFERENCES:

SO23-5-1.8.1 Revision 12 AUTHOR: Joseph G. Arsenault DATE: 8/19/03 OPERATIONS REVIEW: DATE:

APPROVED BY: DATE:

Rev. 0 8/19/03 Page 3 of 8

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 0 New JPM JGA 8/19/03 Rev. 0 8/19/03 Page 4 of 8

SET-UP Provide the candidate a copy of SO23-5-1.8.1 Rev. 0 8/19/03 Page 5 of 8

JPM: NRC SRO A1a TITLE: Determine Time to Boil Margin for Shutdown Nuclear Safety

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat)

Cue: Provide the candidate a copy of SO23-5-1.8.1 1 Obtain SO23-5-1.8.1 Obtains provided copy of Start Time:

SO23-5-1.8.1 2* Determine TTB based upon Determines that after 9 days time shutdown shut down, TTB is 23.75 minutes 3* Determine Level Correction Determines Level Correction Factor for RCS Level of 27 Factor is 1.008 inches Rev. 0 8/19/03 Page 6 of 8

JPM: NRC SRO A1a TITLE: Determine Time to Boil Margin for Shutdown Nuclear Safety

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat) 4* Calculate Time to Boil

Determines Temperature Stop Time:

correction factor is (212-148) / 92 = 0.70

Determines new fuel correction factor is 1.0 (No new fuel assemblies)

Calculation is:

23.75 X 1.008 X 0.70 = 16.65 minutes TERMINATING CUE:

This JPM is complete.

Rev. 0 8/19/03 Page 7 of 8

JPM CHECKLIST

1. The JPM is:

a. X Supported by facility's job task analysis.

b. X Operationally important (meets threshold criterion of K/A 3.0 or greater).

c. X Designed as either SRO only, or RO/SRO.

2. Each JPM includes:

a. X Initial conditions.

b. X Initiating cues.

c. X References, including associated procedures.

d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.

e. X System response cues that are complete and correct so that the examiner can properly cue the examinee, if asked.

f. X Statements describing important actions or observations that should be made by the examinee.

g. X Criteria for successful completion.

h. X Identification of the critical steps and their associated performance standards.

i. X Validated time limits (average time allowed for completion).

j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.

COMPLETED BY: J. Arsenault DATE: 8/19/03 Rev. 0 8/19/03 Page 8 of 8

JPM INFORMATION SHEET JPM NUMBER NRC SRO A1b INITIAL PLANT CONDITIONS Unit 2 is in Mode 3 in preparation for a reactor startup after a reactor trip 109 hours0.00126 days 0.0303 hours 1.802249e-4 weeks 4.14745e-5 months ago.

Conditions are as follows:

MOC, 125 EFPD per Reactor Engineering.

RCS Boron Concentration is 1900 ppm.

Tave is 545°F.

All CEAs are inserted.

A Shutdown Margin calculation has been performed TASK TO BE PERFORMED Review the Shutdown Margin calculation for approval REV 0, 08/19/03 Page 1 of 9

JOB PERFORMANCE MEASURE NRC SRO A1b SUGGESTED TESTING ENVIRONMENT: PLANT X SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATOR'S NAME:

(Print)

The operator's performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

REV 0, 08/19/03 Page 2 of 9

DOCUMENTATION NRC SRO A1b JPM LEVEL: RO/SRO ESTIMATED TIME TO COMPLETE: 20 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: UACO TASK SYS ID: 23717 TASK DESCRIPTION:

Technical Specification requirements for Shutdown Margin in Modes 1-4.

KA NUMBER: 001-A4.11 KA VALUES: RO 3.5 SRO 4.1 10CFR55.45 APPLICABILITY: 4, 12

REFERENCES:

SO23-3-3.29, Determination of Reactor Shutdown Margin, Rev. 16.

AUTHOR: J. Arsenault DATE: 08/19/03 OPERATIONS REVIEW: DATE:

APPROVED BY: DATE:

REV 0, 08/19/03 Page 3 of 9

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOL BY MODIFIED APPROVAL 0 Derived from Sim JPM 078S. New JGA 08/19/03 conditions, new JPM developed for 2003 NRC exam REV 0, 08/19/03 Page 4 of 9

SET-UP Provide examinee with a completed copy of SO23-3-3.29, Determination of Reactor Shutdown Margin, Attachment 2.

REV 0, 08/19/03 Page 5 of 9

JPM: NRC SRO A1b TITLE: Review a Shutdown Margin Calculation

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat) 1 Identify procedure Identifies procedure Start Time: ________

S023-3-3.29, Attachment 2. S023-3-3.29, Attachment 2.

NOTE: Provide the examinee with a copy of SO23-3-3.29 when identified.

2 Record present RCS boron Determines from initial concentration. conditions that boron concentration is 1900 ppm 3 Record present RCS Tavg. Determines from initial conditions that Tave is 545EF 4 Record present cycle Records present cycle burnup. burnup, 125 EFPD, per initial conditions.

NOTE: No correction factors have been provided by Reactor Engineering for B-10 depletion.

REV 0, 08/19/03 Page 6 of 9

JPM: NRC SRO A1b TITLE: Review a Shutdown Margin Calculation

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat) 5* Calculate the adjusted Determines the adjusted critical boron critical boron concentration concentration for from OPS Fig. 2.2-1 and adds potential reactivity bias. 150 ppm for B-10 depletion.

(1975-2025 ppm)

Determines that the 150 ppm for Boron Depletion was NOT added 6 Calculate the critical Calculates the critical boron margin. boron margin. (-75 to -125 ppm)Determines an error was made and carried to this step 7 Determine the inverse Determines the inverse boron boron worth for the worth from OPS Fig. 3.3.

present RCS Tavg and boron (133 to 135 ppm/% ?K/K) concentration.

8 Calculate the boron Calculates the boron reactivity defect. reactivity defect.

(-0.56 to -0.92

%?K/K)Determines an error was made and carried to this step REV 0, 08/19/03 Page 7 of 9

JPM: NRC SRO A1b TITLE: Review a Shutdown Margin Calculation

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat) 9* Determine the total CEA Determines the total CEA worth for present Tavg and worth from OPS Figure 4.3 RCS boron concentration. 4.4.

(8.8%?K/K)

Determines that incorrect value was used (Net worth value of 8.2) 10 Determine the withdrawn Determines the withdrawn CEA CEA worth. worth to be 0.

11 Determine the Xenon worth Determines the Xenon worth based on present cycle to be 0.

burnup and Xenon decay time.

12 Calculate actual Shutdown Calculates actual Shutdown Margin. Margin.

(7.88 to 8.24 %?K/K) 13 Calculate percent shutdown Calculates percent shutdown of the Reactor. of the Reactor.

(7.88 to 8.24 %?K/K)

REV 0, 08/19/03 Page 8 of 9

JPM: NRC SRO A1b TITLE: Review a Shutdown Margin Calculation

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat) 14 Determine the actual Determines the actual Stop Time: ________

Shutdown Margin is greater Shutdown Margin is greater than or equal to than 5.15% ?K/K in Mode 3.

5.15% K/K in Mode 3.

TERMINATING CUE:

This JPM is complete.

REV 0, 08/19/03 Page 9 of 9

REV 0, 08/19/03 Page 10 of 9 JPM CHECKLIST

1. The JPM is:

a. X Supported by facility's job task analysis.

b. X Operationally important (meets threshold criterion of K/A 3.0 or greater).

c. X Designed as either SRO only, or RO/SRO.

2. Each JPM includes:

a. X Initial conditions.

b. X Initiating cues.

c. X References, including associated procedures.

d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.

e. X System response cues that are complete and correct so that the examiner can properly cue the examinee, if asked.

f. X Statements describing important actions or observations that should be made by the examinee.

g. X Criteria for successful completion.

h. X Identification of the critical steps and their associated performance standards.

i. X Validated time limits (average time allowed for completion).

j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.

COMPLETED BY: J. Arsenault DATE: 08/19/03 REV 0, 08/19/03 Page 11 of 9

JPM INFORMATION SHEET JPM NUMBER NRC SRO A2 INITIAL PLANT CONDITIONS The Containment Spray Pump P012 has been removed from service and requires a Work Authorization to permit repair of several pump and valve boric acid leaks.

TASK TO BE PERFORMED A Work Authorization for the Containment Spray Pump P012 has just been prepared and requires review for immediate application. The Shift Manager directs you to review the Tagging List and report your findings when complete.

REV 1-1, 08/19/03 Page 1 of 8

JOB PERFORMANCE MEASURE NRC SRO A2 SUGGESTED TESTING ENVIRONMENT: PLANT X SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATOR'S NAME:

(Print)

The operator's performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

REV 1-1, 08/19/03 Page 2 of 8

DOCUMENTATION NRC SRO A2 JPM LEVEL: SRO ESTIMATED TIME TO COMPLETE: 30 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: CRS TASK SYS ID: 141 TASK DESCRIPTION:

Manage the control of equipment status.

KA NUMBER: 2.2.13 KA VALUES: RO 3.6 SRO 3.8 10CFR55.45 APPLICABILITY: 13

REFERENCES:

SO123-XX-5, Work Authorizations, Rev. 12-2.

Containment Spray P&ID #40114A Safety injection P&ID #40112A 4160 V Switchgear Bus 2A04 One Line Diagram #30107 AUTHOR: L. Zilli DATE: 07/07/00 OPERATIONS REVIEW: M. Jones DATE: 08/03/00 APPROVED BY: W. Lyke DATE: 08/04/00 REV 1-1, 08/19/03 Page 3 of 8

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOL BY MODIFIED APPROVAL 1 Reviewed SO123-XX-5, Rev.8 and LRZ 07/07/00 WLL modified as required.

1-1 Reviewed against procedure JGA 08/19/03 revision 12-2 REV 1-1, 08/19/03 Page 4 of 8

SET-UP Prepare a Work Authorization Request that is complete up to the SRO review of the Tagging List. Include errors associated with the clearance.

Obtain P&IDs for:

C Containment Spray Pumps #40114A C Safety Injection Pumps #40112A Obtain One-Line Diagram for:

C 4160 V Switchgear Bus 2A04 #30107 The P&IDs should be prepared as follows:

Highlight in BLUE the problem area(s)

Highlight in YELLOW the Cleared line(s)

Highlight in RED the isolation area(s)

The completed Tagging List should be prepared as follows:

Obtain a CLOSED Work Authorization Record (WAR)

Modify the WAR to includes errors and omissions

Reflect those errors and omissions in the body of the JPM Provide the examinee with a copy of SO123-XX-5, Work Authorizations, the applicable P&IDs and drawings, and the completed Work Authorization Record for the Containment Spray Pump.

REV 1-1, 08/19/03 Page 5 of 8

JPM: NRC SRO A2 TITLE: Review the Tagging List of a completed Work Authorization.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat)

NOTE: The following steps may be performed in a sequence other than indicated below.

NOTE: Provide the examinee with a copy of SO123-XX-5, the completed Tagging List (with errors and omissions) and copies of highlighted P&IDs and Electrical Print when located.

1 Check the Equipment ID, Checks the Equipment ID, Start Time: ________

Equipment Description and Equipment Description and Work Description. Work Description on the WAR to compare with the information on the Tagging List and the applicable drawings.

2 Check the Work Checks the Work Authorization Numbers Authorization Numbers match match for each page of the on each page of the Request.

Request.

3* Examine the clearance to Examines the adequacy and determine if it is correct accuracy of the clearance and adequate for the work and identifies:

to be performed. C Discharge valve closed after the suction valve REV 1-1, 08/19/03 Page 6 of 8

JPM: NRC SRO A2 TITLE: Review the Tagging List of a completed Work Authorization.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat) 4 Examine the clearance to Examines the adequacy and determine if it is correct accuracy of the clearance and adequate for the work and identifies:

to be performed. C No vent & drain sequence NOTE: If the examinee starts to review the Return to Service column of the clearance inform them that this is not required.

5 Report to the Shift Reports to the Shift Manager Stop Time: ________

Manager the incorrect the incorrect clearance and clearance and return the returns the Tagging List Tagging List without without signature.

signature.

TERMINATING CUE:

This JPM is complete.

REV 1-1, 08/19/03 Page 7 of 8

REV 1-1, 08/19/03 Page 8 of 8 JPM CHECKLIST

1. The JPM is:

a. X Supported by facility's job task analysis.

b. X Operationally important (meets threshold criterion of K/A 3.0 or greater).

c. X Designed as either SRO only, or RO/SRO.

2. Each JPM includes:

a. X Initial conditions.

b. X Initiating cues.

c. X References, including associated procedures.

d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.

e. X System response cues that are complete and correct so that the examiner can properly cue the examinee, if asked.

f. X Statements describing important actions or observations that should be made by the examinee.

g. X Criteria for successful completion.

h. X Identification of the critical steps and their associated performance standards.

i. X Validated time limits (average time allowed for completion).

j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.

COMPLETED BY: L. Zilli DATE: 08/08/00 REV 1-1, 08/19/03 Page 9 of 8

JPM INFORMATION SHEET JPM NUMBER NRC SRO A3 INITIAL PLANT CONDITIONS You have been directed to perform a valve alignment in the Unit 3 Containment Spray Pump P-012 room.

The task involves uncapping and opening a drain valve, and attaching a drain hose directed to the floor drain.

TASK TO BE PERFORMED Select the appropriate REP for the work to be performed and determine allowable stay time in the work area Rev. 0 8/19/03 Page 1 of 8

JOB PERFORMANCE MEASURE NRC SRO A3 SUGGESTED TESTING ENVIRONMENT: PLANT X SIMULATOR ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATOR'S NAME:

(Print)

The operator's performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

Rev. 0 8/19/03 Page 2 of 8

DOCUMENTATION NRC SRO A3 JPM LEVEL: RO ESTIMATED TIME TO COMPLETE: 10 Min TIME CRITICAL JPM: NO CRITICAL TIME:

POSITION: ACO TASK SYS ID:

TASK DESCRIPTION:

Determine Stay Time KA NUMBER: G2.3.2 KA VALUES: RO 2.5 SRO 2.9 10CFR55.45 APPLICABILITY: 8, 9

REFERENCES:

AUTHOR: Joseph G. Arsenault DATE: 8/19/03 OPERATIONS REVIEW: DATE:

APPROVED BY: DATE:

Rev. 0 8/19/03 Page 3 of 8

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 0 New JPM JGA 8/19/03 Rev. 0 8/19/03 Page 4 of 8

SET-UP Provide applicant with survey maps and REPs to choose from. Also supply Unit 3 Safety Equipment Building Floor Plan. (Mosaic will NOT be available)

Rev. 0 8/19/03 Page 5 of 8

JPM: NRC SRO A3 TITLE: Determine Stay Time for Work to be Performed

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat)

Cue: Provide applicant with Survey Maps and REPs to choose from. Direct candidate to assume all radiation exposure received is in the general area. Also supply Unit 3 Safety Equipment Building Floor Plan. (Mosaic will NOT be available) 1* Determine applicable Located survey map #030905- Start Time:

survey map 006, page 2 of 3 for the task to be performed.

(Safety Equipment Building)

CUE:

2* Determine REP that Locates and reviews REP provides coverage of the #200198 task performed CUE:

3* Determine Stay Time in Based upon 200 mr/hr general work area radiation levels in area and required setpoint of alarming dosimeter of 100 mr, determine that stay time will be 30 minutes Rev. 0 8/19/03 Page 6 of 8

JPM: NRC SRO A3 TITLE: Determine Stay Time for Work to be Performed

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat)

CUE: Inform applicant that the task is underway and approximately 1/2 way through completion, their alarming dosimeter is beeping. If they check the dose, indicate that it is 115 mr. The dose rate indicates 800 mr/hr. The dosimeter is chirping approximately once every 5 seconds.

4 Acknowledge alarming Checks dosimeter, determines dosimeter alarm. that the total dose has been exceeded and that the rate is quadruple the original estimated dose from the survey sheet 5* Determines action based Leave area immediately. Stop Time:

upon alarming dosimeter Inform Health Physics of the readings change in radiological conditions TERMINATING CUE:

This JPM is complete.

Rev. 0 8/19/03 Page 7 of 8

JPM CHECKLIST

1. The JPM is:

a. X Supported by facility's job task analysis.

b. X Operationally important (meets threshold criterion of K/A 3.0 or greater).

c. X Designed as either SRO only, or RO/SRO.

2. Each JPM includes:

a. X Initial conditions.

b. X Initiating cues.

c. X References, including associated procedures.

d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.

e. X System response cues that are complete and correct so that the examiner can properly cue the examinee, if asked.

f. X Statements describing important actions or observations that should be made by the examinee.

g. X Criteria for successful completion.

h. X Identification of the critical steps and their associated performance standards.

i. X Validated time limits (average time allowed for completion).

j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.

COMPLETED BY: J. Arsenault DATE: 8/19/03 Rev. 0 7/19/03 Page 8 of 8

JPM INFORMATION SHEET JPM NUMBER NRC SRO A4 INITIAL PLANT CONDITIONS Unit 2 was operating at 100% power when the following events occurred:

0233 All Diesel Generators are declared inoperable due to a faulty part installed during a recent outage.

0253 A plant shutdown is commenced to comply with Technical Specifications.

0313 A Loss of Offsite Power occurs and the G002 Diesel Generator fails to start.

A ground fault occurs on the 2A04 bus.

0316 The G003 Diesel Generator is started and energizes the 2A06 Bus.

0319 The G003 Diesel Generator trips.

0327 S023-12-8, Station Blackout is initiated.

0331 Reports indicate the G003 Diesel Generator has suffered major mechanical damage.

0335 Present time.

TASK TO BE PERFORMED Classify the event for the plant conditions in accordance with SO123-VIII-1, Recognition and Classification of Emergencies.

REV 1-3, 08/19/03 Page 1 of 7

JOB PERFORMANCE MEASURE NRC SRO A4 SUGGESTED TESTING ENVIRONMENT: PLANT X SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATOR'S NAME:

(Print)

The operator's performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

REV 1-3, 08/19/03 Page 2 of 7

DOCUMENTATION NRC SRO A4 JPM LEVEL: SRO ESTIMATED TIME TO COMPLETE: 6 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: SM TASK SYS ID: 142 TASK DESCRIPTION:

Classify emergency events requiring Emergency Plan implementation.

KA NUMBER: 2.4.41 KA VALUES: RO N/A SRO 4.1 10CFR55.45 APPLICABILITY: 11

REFERENCES:

SO123-VIII-1, Recognition and Classification of Emergencies, Rev. 20.

AUTHOR: J. Arsenault DATE: 08/19/03 OPERATIONS REVIEW: DATE:

APPROVED BY: DATE:

REV 1-3, 08/19/03 Page 3 of 7

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 1 Compared against SO123-VIII-1, LRZ 07/10/00 WLL Rev.12 and modified as required.

1-1 Compared against SO123-VIII-1, LRZ 05/11/01 N/A Rev.14 with no changes required.

1-2 Compared against SO123-VIII-1, LRZ 08/22/01 N/A Rev.15 with no changes required.

1-3 Compared against Rev. 20 with JGA 08/19/03 N/A no changes required REV 1-3, 08/19/03 Page 4 of 7

SET-UP No simulator setup is required for this JPM.

Provide the Examinee with a copy of SO123-VIII-1, Recognition and Classification of Emergencies, when identified.

REV 1-3, 08/19/03 Page 5 of 7

JPM: NRC SRO A4 TITLE: Classify an Emergency Plan event

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat)

NOTE: Provide the Examinee with a copy of SO123-VIII-1, Recognition and Classification of Emergencies, when identified.

NOTE: The following steps can be performed in any order.

1 Determine the Event Determines the event to be a Time Start: ________

Category. Loss of Safety Equipment.

2 Match plant conditions Reviews EAL descriptions to with the EALs listed in determine the EAL that most the selected Event closely matches the plant Category tabs. conditions.

3 Review the notes Reviews notes preceding/following the preceding/following the EAL selected EAL to find the selected.

highest level applicable EAL.

4* Classify the emergency Classifies as a Site Area Time Stop: ________

using the highest Emergency per Tab D3-1.

applicable Event Code.

TERMINATING CUE:

This JPM is complete.

REV 1-3, 08/19/03 Page 6 of 7

REV 1-3, 08/19/03 Page 7 of 7 JPM CHECKLIST

1. The JPM is:

a. X Supported by facility's job task analysis.

b. X Operationally important (meets threshold criterion of K/A 3.0 or greater).

c. X Designed as either SRO only, or RO/SRO.

2. Each JPM includes:

a. X Initial conditions.

b. X Initiating cues.

c. X References, including associated procedures.

d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.

e. X System response cues that are complete and correct so that the examiner can properly cue the Examinee, if asked.

f. X Statements describing important actions or observations that should be made by the Examinee.

g. X Criteria for successful completion.

h. X Identification of the critical steps and their associated performance standards.

i. X Validated time limits (average time allowed for completion).

j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.

COMPLETED BY: L. Zilli DATE: 08/22/01 REV 1-3, 08/19/03 Page 8 of 7

JPM INFORMATION SHEET JPM NUMBER NRC P1 INITIAL PLANT CONDITIONS The Unit 2 (Unit 3) Reactor has just tripped.

Several full length CEA's have not fully inserted.

The Control Operator has directed you to locally open the Reactor Trip Circuit Breakers and all Motor Generator Set Input and Output Breakers as indicated in SO23-12-1, Standard Post Trip Actions.

TASK TO BE PERFORMED Locally open the Unit 2 (Unit 3) Reactor Trip Circuit Breakers and Motor Generator Set Input and Output Breakers as directed in the Standard Post Trip Actions.

THIS IS A TIME CRITICAL JPM REV 2-3, 08/04/03 Page 1 of 12

JOB PERFORMANCE MEASURE NRC P1 SUGGESTED TESTING ENVIRONMENT: PLANT X SIMULATOR ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATOR'S NAME:

(Print)

The operator's performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

REV 2-3, 08/04/03 Page 2 of 12

DOCUMENTATION NRC P1 JPM LEVEL: RO/SRO ESTIMATED TIME TO COMPLETE: 5 minutes TIME CRITICAL JPM: YES CRITICAL TIME: 8 minutes POSITION: RWOP TASK SYS ID: 399 TASK DESCRIPTION:

Manually operate the reactor trip breakers.

KA NUMBER: EA1.1 KA VALUES: RO 3.7 SRO 3.7 10CFR55.45 APPLICABILITY: 6, 8, 12

REFERENCES:

SO23-12-1, Rev. 18, Standard Post Trip Actions.

SO23-3-2.19.1 TCN 17-2, Att. 5, Remove MG set from service.

AUTHOR: L. Zilli DATE: 06/13/00 OPERATIONS REVIEW: M. Jones DATE: 06/27/00 APPROVED BY: W. Lyke DATE: 06/29/00 REV 2-3, 08/04/03 Page 3 of 12

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 2 Compared against SO23-12-1, LRZ 06/13/00 REV Rev. 16, made minor editorial corrections and converted to a Unit 3 task to meet opposite Unit testing requirements.

2-1 Compared to SO23-12-1, Rev. 16. KM 07/26/01 KR No changes required.

Updated KA number.

Made non-Unit specific.

Re-ordered steps for opening CEDM MG set breakers to conform to SO23-3-2.19.1.

2-2 Added wording to cues to say KM 01/15/02 KR the breaker indicator flags say open.

2-3 Changed SO23-3-2.19 and SO23- JGA 08/04/03 12-1 Revision numbers and compared JPM to Revisions REV 2-3, 08/04/03 Page 4 of 12

SET-UP No procedure allowed for this JPM. Examiner should use the CEDM Bus mimic below to determine when power is deenergized to the CEAs.

Inform the Examinee which Unit this JPM will be performed on.

REV 2-3, 08/04/03 Page 5 of 12

JPM: NRC P1 TITLE: Locally Open Reactor Trip Breakers and MG Set Breakers.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat)

NOTE: Proceed to the Rad Waste Control Room before providing the examinee with a copy of the JPM information sheet.

NOTE: The examinee is not allowed to refer to a procedure.

NOTE: Any combination of open breakers (either 1 or 2 and 7 or 8 for Bus 1 AND 3 or 4 and 5 or 6 for Bus 2) that results in an open circuit to CEDM Buses 1 and 2 satisfies Critical Steps 1 through 8 inclusive for this JPM.

NOTE: The Emergency Trip push button trips 2 associated breakers simultaneously.

NOTE: The following steps may be performed in any sequence.

1* Open Reactor Trip Circuit Simulates pressing the local Start Time:

Breakers TCB-1. trip push button on breaker (From the Rad Waste cubicle (behind the Control Room) stainless steel guard plate), or simulates pressing the Emergency Trip push button TCB-5 & TCB-1 on TCB-5 cubicle.

CUE: The green light(s) is (are) on and indicator flags indicate open.

REV 2-3, 08/04/03 Page 6 of 12

JPM: NRC P1 TITLE: Locally Open Reactor Trip Breakers and MG Set Breakers.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat) 2* Open Reactor Trip Circuit Simulates pressing the local Breaker TCB-2. trip push button on breaker cubicle (behind the stainless steel guard plate), or simulates pressing the Emergency Trip push button TCB-6 & TCB-2 on TCB-6 cubicle.

CUE: The green light(s) is (are) on and indicator flags indicate open.

3* Open Reactor Trip Circuit Simulates pressing the local Breaker TCB-3. trip push button on breaker cubicle (behind the stainless steel guard plate), or simulates pressing the Emergency Trip push button TCB-3 & TCB-7 on TCB-3 cubicle.

CUE: The green light(s) is (are) on and indicator flags indicate open.

REV 2-3, 08/04/03 Page 7 of 12

JPM: NRC P1 TITLE: Locally Open Reactor Trip Breakers and MG Set Breakers.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat) 4* Open Reactor Trip Circuit Simulates pressing the local Breaker TCB-4. trip push button on breaker cubicle (behind the stainless steel guard plate), or simulates pressing the Emergency Trip push button TCB-4 & TCB-8 on TCB-4 cubicle.

CUE: The green light(s) is (are) on and indicator flags indicate open.

5* Open Reactor Trip Circuit Simulates pressing the local Breaker TCB-5. trip push button on breaker cubicle (behind the stainless steel guard plate), or simulates pressing the Emergency Trip push button TCB-5 & TCB-1 on TCB-5 cubicle.

CUE: The green light(s) is (are) on and indicator flags indicate open.

REV 2-3, 08/04/03 Page 8 of 12

JPM: NRC P1 TITLE: Locally Open Reactor Trip Breakers and MG Set Breakers.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat) 6* Open Reactor Trip Circuit Simulates pressing the local Breaker TCB-6. trip push button on breaker cubicle (behind the stainless steel guard plate), or simulates pressing the Emergency Trip push button TCB-6 & TCB-2 on TCB-6 cubicle.

CUE: The green light(s) is (are) on and indicator flags indicate open.

7* Open Reactor Trip Circuit Simulates pressing the local Breaker TCB-7. trip push button on breaker cubicle (behind the stainless steel guard plate), or simulates pressing the Emergency Trip push button TCB-3 & TCB-7 on TCB-3 cubicle.

CUE: The green light(s) is (are) on and indicator flags indicate open.

REV 2-3, 08/04/03 Page 9 of 12

JPM: NRC P1 TITLE: Locally Open Reactor Trip Breakers and MG Set Breakers.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat) 8* Open Reactor Trip Circuit Simulates pressing the local Breaker TCB-8. trip push button on breaker cubicle (behind the stainless steel guard plate), or simulates pressing the Emergency Trip push button TCB-4 & TCB-8 on TCB-4 cubicle.

CUE: The green light(s) is (are) on and indicator flags indicate open.

9* Open MG set 1 output On 2(3)L-045 simulates breaker. placing the GENERATOR OUTPUT breaker in OFF.

CUE: The breaker is in OFF.

10 Open MG set 1 input On 2(3)L-045 simulates

breaker. placing the MOTOR INPUT breaker in OFF.

CUE: The breaker is in OFF.

REV 2-3, 08/04/03 Page 10 of 12

JPM: NRC P1 TITLE: Locally Open Reactor Trip Breakers and MG Set Breakers.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat) 11 Open MG set 2 output On 2(3)L-046 simulates

breaker. placing the GENERATOR OUTPUT breaker in OFF.

CUE: The breaker is in OFF.

12 Open MG set 2 input On 2(3)L-046 simulates Stop Time:

breaker. placing the MOTOR INPUT breaker in OFF.

TERMINATING CUE:

When the applicant has completed opening Reactor Trip and MG set breakers, the evaluation for this JPM is complete.

REV 2-3, 08/04/03 Page 11 of 12

REV 2-3, 08/04/03 Page 12 of 12 JPM CHECKLIST

1. The JPM is:

a. X Supported by facility's job task analysis.

b. X Operationally important (meets threshold criterion of K/A 3.0 or greater).

c. X Designed as either SRO only, or RO/SRO.

2. Each JPM includes:

a. X Initial conditions.

b. X Initiating cues.

c. X References, including associated procedures.

d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.

e. X System response cues that are complete and correct so that the examiner can properly cue the examinee, if asked.

f. X Statements describing important actions or observations that should be made by the examinee.

g. X Criteria for successful completion.

h. X Identification of the critical steps and their associated performance standards.

i. X Validated time limits (average time allowed for completion).

j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.

COMPLETED BY: K. Meagher DATE: 07/21/01 REV 2-3, 08/04/03 Page 13 of 12

JPM INFORMATION SHEET JPM NUMBER NRC P2 INITIAL PLANT CONDITIONS You are the Auxiliary Operator.

Unit 2(3) is in Mode 3, HOT STANDBY.

The Unit 2(3) Atmospheric Dump Valve, 2(3)HV-8419, needs to be tested to prove operability following maintenance TASK TO BE PERFORMED Manually open the Atmospheric Dump Valve 2(3)HV-8419 per procedure SO23-3-2.18.1, Attachment 4, Local Manual Operation of the Atmospheric Dump Valves.

REV 1-7, 08/04/03 Page 1 of 14

JOB PERFORMANCE MEASURE NRC P2 SUGGESTED TESTING ENVIRONMENT: Plant X Simulator ACTUAL TESTING ENVIRONMENT: Plant Simulator ACTUAL TESTING Performed Simulated METHOD:

OPERATOR'S NAME:

(Print)

The operator's performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

REV 1-7, 08/04/03 Page 2 of 14

DOCUMENTATION NRC P2 JPM LEVEL: RO ESTIMATED TIME TO COMPLETE: 16 minutes TIME CRITICAL JPM: NO CRITICAL TIME: n/a minutes POSITION: PPEO TASK SYS ID: 684 TASK DESCRIPTION:

Operate the Atmospheric Dump Valve in Local Manual.

KA NUMBER: 039-A2.04 KA VALUES: RO 3.4 SRO 3.7 BR-0122 CATEGORY: II 10CFR55.45 APPLICABILITY: 3, 5, 13

REFERENCES:

SO23-3-2.18.1, Atmospheric Dump Valve Operation , TCN 12-1 AUTHOR: S Popowski DATE: 11/05/91 OPERATIONS REVIEW: D.J. Turner DATE: 10/02/93 APPROVED BY: M Kirby DATE: 10/14/93 REV 1-7, 08/04/03 Page 3 of 14

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOL BY MODIFIED APPROVAL 1 Updated the JPM to the new format; separated GLM 09/13/93 MJK combined steps; isolated cues from the performance steps.

1-1 Changed setup page; minor editorial HJW 03/17/94 n/a corrections for clarity; changed estimated time from 15 to 16 minutes based on history.

1-2 Corrected KA number. HJW 08/04/95 n/a 1-3 Compared against SO23-3-2.18.1, Rev. 8 HJW 06/04/97 n/a with minor editorial corrections. Updated Documentation page for NUREG-1122, Rev.

1.

1-4 Compared against SO23-3-2.18.1, Rev. 9 JJM 10/27/99 WLL with no changes required. Changed equipment designations so that JPM can be performed on either unit. Updated KA designation and changed old task number to VISION SYS ID.

1-5 Compared against SO23-3-2.18.1, TCN 9-1 JJM 09/14/00 WLL with no changes required. Changed cue near end of JPM that directs the operator to realign the isolation valve in the locked open position.

Changed note to provide the examinee with the entire procedure rather than attachment 6 only.

1-6 Compared against SO23-3-2.18.1, Rev 12 JJM 10/21/02 N/A with no changes required. Corrected typos.

1-7 Updated SO23-2.18.1 Revision in JPM and JGA 08/04/03 compared JPM to new revision REV 1-7, 08/04/03 Page 4 of 14

SET-UP Provide copy of SO23-3-2.18.1.

REV 1-7, 08/04/03 Page 5 of 14

JPM: NRC P2 TITLE: Manually open the Atmospheric Dump Valve 2(3)HV-8419 per procedure SO23-3-2.18.1, Attachment 4, Local Manual Operation of the Atmospheric Dump Valves.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat)

NOTE: Provide examinee with a copy of SO23-3-2.18.1 CUE: Atmospheric Dump Valve 2(3)HV-8419 has been selected.

1 Establish communications between the Indicate the form of communication to be Start Time:

control room and the operator at the used between the Control Room Operator atmospheric dump valve. and the Operator at the valve.

NOTE: Communications may be established via radio, telephone (Hear-Here booth) or sound powered phone. If sound powered phone is selected, examinee should point out location of jack on west fence.

CUE: Communications have been established.

2* Close the Atmospheric Dump Valve Simulate closing Atmospheric Dump Valve 2(3)HV-8419 Positioner Instrument Air 2(3)HV-8419 Positioner Instrument Air Isolation Valve S2(3)1301MU1304. Isolation Valve S2(3)1301MU1304.

CUE: The Valve is closed.

REV 1-7, 08/04/03 Page 6 of 14

JPM: NRC P2 TITLE: Manually open the Atmospheric Dump Valve 2(3)HV-8419 per procedure SO23-3-2.18.1, Attachment 4, Local Manual Operation of the Atmospheric Dump Valves.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat) 3* Close the Atmospheric Dump Valve Simulate closing the Atmospheric Dump 2(3)HV-8419 Positioner Nitrogen Valve 2(3)HV-8419 Positioner Nitrogen Isolation Valve S2(3)1301MU1328. Isolation Valve S2(3)1301MU1328.

CUE: The valve is closed.

4* Open the Atmospheric Dump Valve Simulate opening the Atmospheric Dump 2(3)HV-8419 Positioner Equalizing Valve 2(3)HV-8419 Positioner Equalizing Valve S2(3)1301MU1264. Valve S2(3)1301MU1264.

CUE: The valve is open.

5* Unscrew the Clevis from the Manual Simulate unscrewing the Clevis from the Override Shaft. Manual Override Shaft.

CUE: The Clevis is unscrewed from the shaft.

REV 1-7, 08/04/03 Page 7 of 14

JPM: NRC P2 TITLE: Manually open the Atmospheric Dump Valve 2(3)HV-8419 per procedure SO23-3-2.18.1, Attachment 4, Local Manual Operation of the Atmospheric Dump Valves.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat) 6* Turn 2(3)HV-8419 handwheel in the Simulate turning 2(3)HV-8419 handwheel in close (clockwise) direction, until the the close (clockwise) direction.

clevis detent on the actuator shaft is exposed.

CUE: The detent is exposed.

7* Slide the Clevis into the detent. Simulate sliding the clevis into the detent.

CUE: The clevis is in the detent.

CUE: No leverage device is needed.

CUE: The Control Room requests you to open the Atmospheric Dump Valve 2(3)HV-8419 approximately 5%.

8 Attempt to open Atmospheric Dump Simulate turning 2(3)HV-8419 handwheel in Valve 2(3)HV-8419. the counterclockwise direction.

REV 1-7, 08/04/03 Page 8 of 14

JPM: NRC P2 TITLE: Manually open the Atmospheric Dump Valve 2(3)HV-8419 per procedure SO23-3-2.18.1, Attachment 4, Local Manual Operation of the Atmospheric Dump Valves.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat)

CUE: The handwheel will not turn. The valve stem did not move.

9 Inform the Control Room that Simulate contacting the control room to Atmospheric Dump Valve 2(3)HV-8419 inform them that Atmospheric Dump Valve will not open. 2(3)HV-8419 will not open.

CUE: The Control Room directs you to restore the ADV per section 2.2 of this attachment.

10* Close the Atmospheric Dump Valve Simulate turning 2(3)HV-8419 handwheel in 2(3)HV-8419. the clockwise direction.

CUE: The valve is closed.

11* Rotate the handwheel back and forth Simulate rotating 2(3)HV-8419 handwheel until pressure is relieved from the clevis. back and forth.

REV 1-7, 08/04/03 Page 9 of 14

JPM: NRC P2 TITLE: Manually open the Atmospheric Dump Valve 2(3)HV-8419 per procedure SO23-3-2.18.1, Attachment 4, Local Manual Operation of the Atmospheric Dump Valves.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat)

CUE: The pressure is relieved from the clevis.

12* Remove the clevis from the detent on the Simulate removing the clevis from the detent actuator shaft. on the shaft.

CUE: The clevis is removed.

13* Fully extend the Manual override shaft Simulate fully extending the Manual by turning the handle counterclockwise Override Shaft by turning the handle until resistance is encountered. counterclockwise.

CUE: You feel resistance.

14* Screw the clevis fully into the manual Simulate screwing the clevis into the manual override shaft override shaft.

REV 1-7, 08/04/03 Page 10 of 14

JPM: NRC P2 TITLE: Manually open the Atmospheric Dump Valve 2(3)HV-8419 per procedure SO23-3-2.18.1, Attachment 4, Local Manual Operation of the Atmospheric Dump Valves.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat)

CUE: The Clevis is in the manual override shaft.

15 Contact the control room to verify that Simulate contacting the control room to the Atmospheric Dump Valve Position verify that the Atmospheric Dump Valve Controller is adjusted to Zero, and the Position Controller is adjusted to zero, and Atmospheric Dump Valve Control the Atmospheric Dump Valve control Switches are selected to close at CR-52, switches are selected to close at CR-52, and and L-042. L-042.

CUE: The positioners are at zero. The hand switches are selected to close.

16* Close the Atmospheric Dump Valve Simulate closing the Atmospheric Dump 2(3)HV-8419 Equalizing Valve Valve 2(3)HV-8419 Equalizing Valve S2(3)1301MU1264. S2(3)1301MU1264.

CUE: The equalizing valve is closed.

17* Open the Instrument Air Isolation Valve Simulate opening the Instrument Air S2(3)1301MU1304, for the positioner on Isolation Valve S2(3)1301MU1304, for Atmospheric Dump Valve 2(3)HV-8419. Atmospheric Dump Valve 2(3)HV-8419.

REV 1-7, 08/04/03 Page 11 of 14

JPM: NRC P2 TITLE: Manually open the Atmospheric Dump Valve 2(3)HV-8419 per procedure SO23-3-2.18.1, Attachment 4, Local Manual Operation of the Atmospheric Dump Valves.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat)

CUE: The valve is open.

18* Open the Atmospheric Dump Valve Simulate opening the Atmospheric Dump 2(3)HV-8419 positioner Nitrogen Valve 2(3)HV-8419 positioner Nitrogen Isolation Valve S2(3)1301MU1328. Isolation Valve S2(3)1301MU1328.

CUE: The Valve is open.

19 Contact the control room and inform Simulate contacting the control room to relay them that Atmospheric Dump Valve the information that the Atmospheric Dump 2(3)HV-8419 is aligned for remote Valve is aligned for remote operation.

operation.

CUE: The Control Room directs you to throttle close ADV Isolation Valve 2(3)1301MU231 per step 6.4.4.3. Steps 6.4.4.1 and 6.4.4.2 have been completed.

CUE: You have the appropriate Train Key.

REV 1-7, 08/04/03 Page 12 of 14

JPM: NRC P2 TITLE: Manually open the Atmospheric Dump Valve 2(3)HV-8419 per procedure SO23-3-2.18.1, Attachment 4, Local Manual Operation of the Atmospheric Dump Valves.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat) 20* Unlock Atmospheric Dump Valve Simulate unlocking Atmospheric Dump 2(3)HV-8419 Manual Isolation Valve Valve 2(3)HV-8419 Manual Isolation Valve S2(3)1301MU231. S2(3)1301MU231.

CUE: The valve is unlocked.

21* Throttle S2(3)1301MU231, Atmospheric Simulate throttling S2(3)1301MU231, Dump Valve 2(3)HV-8419 Manual Atmospheric Dump Valve 2(3)HV-8419 Isolation Valve in the closed direction Manual Isolation Valve, in the closed until the Atmospheric Dump Valve direction.

Opens.

CUE: The Atmospheric Dump Valve 2HV-8419 is open. You are directed to realign ADV Isolation Valve MU231 in the locked open position.

22* Open S2(3)1301MU231, Atmospheric Simulate opening S2(3)1301MU231, Dump Valve 2(3)HV-8419 Manual Atmospheric Dump Valve 2(3)HV-8419 Isolation Valve. Manual Isolation Valve.

CUE: The Valve is open.

REV 1-7, 08/04/03 Page 13 of 14

JPM: NRC P2 TITLE: Manually open the Atmospheric Dump Valve 2(3)HV-8419 per procedure SO23-3-2.18.1, Attachment 4, Local Manual Operation of the Atmospheric Dump Valves.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat) 23 Lock open S2(3)1301MU231, Simulate locking open S2(3)1301MU231, Stop Time:

Atmospheric Dump Valve 2(3)HV-8419 Atmospheric Dump Valve 2(3)HV-8419 Manual Isolation Valve. Manual Isolation Valve.

TERMINATING CUE: Attachment 7 will be completed by an auxiliary Operator.

This JPM is complete.

REV 1-7, 08/04/03 Page 14 of 14

REV 1-7, 08/04/03 Page 15 of 14 JPM CHECKLIST

1. The JPM is:

a. X Supported by facility's job task analysis.

b. X Operationally important (meets threshold criterion of K/A 3.0 or greater.

c. X Designed as either SRO only, or RO/SRO.

2. Each JPM includes:

a. X Initial conditions.

b. X Initiating cues.

c. X References, including associated procedures.

d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.

e. X System response cues that are complete and correct so that the examiner can properly cue the examinee, if asked.

f. X Statements describing important actions or observations that should be made by the examinee.

g. X Criteria for successful completion.

h. X Identification of the critical steps and their associated performance standards.

i. X Validated time limits (average time allowed for completion).

j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.

COMPLETED BY: J.J. Marron DATE: 09/14/00 REV 1-7, 08/04/03 Page 16 of 14

JPM INFORMATION SHEET JPM NUMBER NRC P3 INITIAL PLANT CONDITIONS You are the Unit 2 (Unit 3) Primary ACO.

The Control Room has been evacuated due to dense smoke.

The fire has resulted in a loss of offsite power.

Offsite power is now available and the Control Room is habitable.

The process of returning the Control Room command function to the Control Room is in progress using SO23-13-2, Shutdown from Outside the Control Room, Attachment 18.

TASK TO BE PERFORMED Transfer 1E 4 kV Bus 2(3)A04 from 2(3)G002 Diesel Generator to the Reserve Auxiliary Transformer using Step 3.4 of SO23-13-2, Shutdown From Outside The Control Room, Attachment 18.

Then shutdown the Diesel Generator locally and transfer control back to the Control Room using Step 2.8 of SO23-3-3.23, Diesel Generator Monthly Test, Attachment 1.

REV 2-1, 08/04/03 Page 1 of 12

JOB PERFORMANCE MEASURE NRC P3 SUGGESTED TESTING ENVIRONMENT: PLANT X SIMULATOR ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATOR'S NAME:

(Print)

The operator's performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

REV 2-1, 08/04/03 Page 2 of 12

DOCUMENTATION NRC P3 JPM LEVEL: RO/SRO ESTIMATED TIME TO COMPLETE: 11 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: PPEO TASK SYS ID: 705, 2802 TASK DESCRIPTION:

Perform Primary ACO assigned actions during shutdown of the unit from outside the Control Room.

Restore offsite power during response to an emergency event.

KA NUMBER: 068-AA1.31 KA VALUES: RO 3.9 SRO 4.0 10CFR55.45 APPLICABILITY: 6, 8

REFERENCES:

SO23-13-2, Shutdown From Outside The Control Room, Rev. 7, TCN 7-1.

SO23-3-3.23, Diesel Generator Monthly Test, Rev. 22, TCN 22-1.

AUTHOR: L. Zilli DATE: 08/15/01 OPERATIONS REVIEW: W. Reeves DATE: 09/28/01 APPROVED BY: A. Hagemeyer DATE: 10/08/01 REV 2-1, 08/04/03 Page 3 of 12

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 2 Updated to current rev of procedure LRZ 08/10/01 REV and corrected Attachment numbers.

Incorporated new procedure SO23-3-3.23 used to shutdown the EDG and added critical steps as necessary to comply with procedure steps. Modified JPM so that it can be performed on either unit.

2-1 Updated SO23-3-3.23 and SO23-13-2 JGA 08/04/03 Revision numbers and compared steps in JPM to updated references REV 2-1, 08/04/03 Page 4 of 12

SET-UP NOTE: Circle the unit on the JPM Information Sheet on which this JPM will be performed and inform the Examinee.

Provide the Examinee with a copy of SO23-13-2, Attachment 18, Returning the Control Room Command Function to the Control Room.

Provide the Examinee with a copy of SO23-3-3.23, Diesel Generator Monthly Test, Attachment 1, Diesel Generator Operation.

REV 2-1, 08/04/03 Page 5 of 12

JPM: NRC P3 TITLE: Transfer 4 kV Bus from Diesel Generator to the Reserve Auxiliary Transformer then transfer Diesel Generator control to the Control Room.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat)

NOTE: Circle the unit on the JPM Information Sheet on which this JPM will be performed and inform the Examinee.

NOTE: Proceed to 2(3)G002 and provide the Examinee with a copy of SO23-13-2, Shutdown from Outside the Control Room, Attachment 18, Step 3.4.

CUE: You have Safe Shutdown Kit 23 (33).

1* ENSURE G002 D/G Control Simulates placing 2(3)HS- Time Start: ________

Fire Isolation switch on L- 1670A1, FIRE ISO. SWITCH DG 160 is aligned to REMOTE & CONTROL on 2(3)L-160, in REMOTE LOCAL. & LOCAL position.

CUE: The switch is in the REMOTE & LOCAL position.

2* ENSURE G002 Governor and Simulates placing 2(3)HS-Excitation Control Fire 1669A1, FIRE ISO. SWITCH GOV. &

Isolation switch on L-160 EXCT. CONT on 2(3)L-160, in is aligned to REMOTE & REMOTE & LOCAL position.

LOCAL.

CUE: The switch is in the REMOTE & LOCAL position.

REV 2-1, 08/04/03 Page 6 of 12

JPM: NRC P3 TITLE: Transfer 4 kV Bus from Diesel Generator to the Reserve Auxiliary Transformer then transfer Diesel Generator control to the Control Room.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat) 3* ENSURE G002 D/G Building Simulates placing 2(3)HS-Fans Fire Isolation switch 9537E1, FIRE ISO. SWITCH DG on L-160 is aligned to BLDG FANS on 2(3)L-160, in REMOTE & LOCAL. REMOTE & LOCAL position.

CUE: The switch is in the REMOTE & LOCAL position.

4* ENSURE Fuel Oil Transfer Simulates placing Fuel Oil Pumps on L-160A selected to Transfer Pump switches C.R.

2(3)HS-5901B1 for Pump P093

2(3)HS-5902B1 for Pump P096 on 2(3)L-160A in the CONTROL ROOM position.

CUE: The switches are in the Control Room position.

5 ENSURE D/G G-002 Output Contacts Operator at ESF Breaker A04-13 on L-412 switchgear room to obtain selected to REMOTE. status of A04-13 breaker control at L-412.

CUE: G-002 Output Breaker A04-13 on L-412 is selected to remote REV 2-1, 08/04/03 Page 7 of 12

JPM: NRC P3 TITLE: Transfer 4 kV Bus from Diesel Generator to the Reserve Auxiliary Transformer then transfer Diesel Generator control to the Control Room.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat) 6 ENSURE LOCAL Mode Select Contacts Control Room to verify HS-1665-1 (HS-1664-2) on LOCAL CONTROL Mode Selector CR-63 backlight 2(3)HS-1665-1 on CR-63 extinguished. backlight is extinguished.

CUE: Control Room reports 2(3)HS-1665-1 on CR-63 LOCAL CONTROL backlight extinguished.

7 ENSURE CLOSED DC control Contacts Control Room or local power breaker for A04-18, Operator to Verify DC control Reserve Auxiliary power breaker for 2(3)A0418, Transformer. Reserve Auxiliary Transformer is closed.

CUE: Unit ACO reports 2(3)A0418 DC control power breaker closed.

8 Unload and Shutdown the D/G Refers to SO23-3-3.23, per SO23-3-3.23, Attachment Attachment 1, Diesel Generator for Diesel Generator Operation to unload and Operation. shutdown the D/G.

REV 2-1, 08/04/03 Page 8 of 12

JPM: NRC P3 TITLE: Transfer 4 kV Bus from Diesel Generator to the Reserve Auxiliary Transformer then transfer Diesel Generator control to the Control Room.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat)

CUE: The Diesel Generator is unloaded. The Control Room Supervisor directs you to stop the Diesel Generator using SO23-3-3.23, Step 2.8 NOTE: Provide the Examinee with a copy of SO23-3-3.23, Diesel Generator Operations, Attachment 1, Step 2.8, Stop the Diesel Generator.

9* TRANSFER Diesel Control to Notifies Control Room to LOCAL. transfer Diesel Control to Local.

CUE: The Control Room has transferred the 2(3)G002 Diesel to LOCAL.

10 Verify LOCAL CONTROL light Observes LOCAL CONTROL light ILLUMINATED. 2(3)ZL-E918 on Panel 2(3)L-160 illuminated.

CUE: The LOCAL CONTROL light is on.

11 DEPRESS IDLE SPEED ON. Simulates depressing

2(3)HS-1701A, IDLE SPEED ON red pushbutton.

CUE: Diesel generator sound changes to indicate a reduction in speed.

REV 2-1, 08/04/03 Page 9 of 12

JPM: NRC P3 TITLE: Transfer 4 kV Bus from Diesel Generator to the Reserve Auxiliary Transformer then transfer Diesel Generator control to the Control Room.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat) 12 Verify IDLE SPEED light Observes 2(3)ZL-1700A IDLE ILLUMINATED. SPEED indicator light illuminated.

CUE: The IDLE SPEED light is on.

13 Verify the Diesel at idle Observes 2(3)G002 Diesel fuel speed. rack movement and/or indicates the sound of the diesel speed lowering would be heard.

CUE: The Diesel is at idle speed.

14 Allow diesel to run at idle Verifies diesel runs at idle for at least 15 minutes. speed for at least 15 minutes.

CUE: 15 minutes have passed.

15 Ensure both AC Lube Oil Observes indicating lights on:

Circulating Pumps and both

2(3)ZL-E925B ENGINE 1 AC Turbocharger Pumps are LUBE OIL CIRC operating. PUMP/TURBOCHARGER PUMP

2(3)ZL-E925A ENGINE 2 AC LUBE OIL CIRC PUMP/TURBOCHARGER PUMP REV 2-1, 08/04/03 Page 10 of 12

JPM: NRC P3 TITLE: Transfer 4 kV Bus from Diesel Generator to the Reserve Auxiliary Transformer then transfer Diesel Generator control to the Control Room.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat)

CUE: The red lights for both sets of pumps are on.

16 Verify the Air Start Observes pressure indicators Manifolds > 185 psig as for the Air Start Manifolds indicated on PI-5958A(C) & greater than 185 psig on PI-5958B(D).

2(3)PI-5958A

2(3)PI-5958B.

CUE: Both Air Start Manifolds indicate 200 psig.

17 ROTATE HS-5995-1(2), Local Simulates rotating the LOCAL

Engine Control, to STOP and ENGINE CONTROL Switch, record time. 2(3)HS-5995-1, to the STOP position and records the time.

CUE: The Diesel is stopped.

18 DEPRESS IDLE SPEED OFF. Simulates depressing

2(3)HS-1702A, IDLE SPEED OFF green pushbutton.

19 Verify IDLE SPEED light Verifies 2(3)ZL-1700A IDLE EXTINGUISHED. SPEED indicator light is extinguished.

REV 2-1, 08/04/03 Page 11 of 12

JPM: NRC P3 TITLE: Transfer 4 kV Bus from Diesel Generator to the Reserve Auxiliary Transformer then transfer Diesel Generator control to the Control Room.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat)

CUE: The IDLE SPEED light is off.

20 TRANSFER Diesel Control to Notifies the Control Room that the Control Room. Diesel Control is ready to be transferred to the Control Room.

CUE: The Control Room has transferred the 2(3)G002 Diesel to REMOTE.

21 Verify the LOCAL CONTROL Observes LOCAL CONTROL light Time Stop: ________

light EXTINGUISHED. 2(3)ZL-E918 on Panel 2(3)L-160 is off.

TERMINATING CUE:

The LOCAL CONTROL light is off.

This JPM is complete.

REV 2-1, 08/04/03 Page 12 of 12

REV 2, 08/10/01 Page 13 of 12 JPM CHECKLIST

1. The JPM is:

a. X Supported by facility's job task analysis.

b. X Operationally important (meets threshold criterion of K/A 3.0 or greater).

c. X Designed as either SRO only, or RO/SRO.

2. Each JPM includes:

a. X Initial conditions.

b. X Initiating cues.

c. X References, including associated procedures.

d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.

e. X System response cues that are complete and correct so that the examiner can properly cue the Examinee, if asked.

f. X Statements describing important actions or observations that should be made by the Examinee.

g. X Criteria for successful completion.

h. X Identification of the critical steps and their associated performance standards.

i. X Validated time limits (average time allowed for completion).

j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.

COMPLETED BY: L. Zilli DATE: 08/10/01 REV 2, 08/10/01 Page 14 of 12

JPM INFORMATION SHEET JPM NUMBER NRC S1 INITIAL PLANT CONDITIONS You are operating at a steady state power level of 100%.

Core analysis engineering has completed observation and data collection for generation of a new ESI value.

The new ESI was determined to be 0.00. The actual ASI at this time is -

0.015 and trending toward -0.2.

The CEAs are fully withdrawn.

The CRS directs you to dampen the oscillation using CEAs.

TASK TO BE PERFORMED Dampen ASI oscillation and hold ASI to ESI using SO23-5-1.7, Attachment 6.

REV 0, 08/04/03 Page 1 of 9

JOB PERFORMANCE MEASURE NRC S1 SUGGESTED TESTING ENVIRONMENT: PLANT SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING PERFORMED SIMULATED METHOD:

OPERATOR'S NAME:

(Print)

The operator's performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

REV 0, 08/04/03 Page 2 of 9

DOCUMENTATION NRC S1 JPM LEVEL: RO ESTIMATED TIME TO COMPLETE: 10 minutes TIME CRITICAL JPM: NO CRITICAL TIME: n/a minutes POSITION: UACO TASK NUMBER: 006499 TASK DESCRIPTION:

Monitor and control ASI during steady state operations.

KA NUMBER: 001-A2-01 KA VALUES: RO 3.4 SRO 3.7 BR-0122 CATEGORY: I 10CFR55.45 APPLICABILITY: 2, 4, 5, 6

REFERENCES:

SO23-5-1.7, Power Operations, TCN 22-3 SO23-3-2.19, CEDMCS SO23-13-13, Misaligned Control Element Assembly AUTHOR: J. Arsenault DATE: 08/04/03 OPERATIONS REVIEW: DATE:

APPROVED BY: DATE:

REV 0, 08/04/03 Page 3 of 9

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOL BY MODIFIED APPROVAL 0 Developed from JPM 045S JGA 08/04/03 REV 0, 08/04/03 Page 4 of 9

SET-UP Use IC-85 from 2003 NRC Examination.

REV 0, 08/04/03 Page 5 of 9

JPM: NRC S1 TITLE: Dampen ASI oscillation.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat)

CUE: The CRS directs you to use PLCEAs.

Note: The applicant may also refer to SO23-3-2.19, CEDMCS Operation 1 Select the PLCEAs with the Group Place the Group Selector Switch to P. Time start: ________

Selector Switch.

2* Insert the PLCEAs. Insert the PLCEAs in small, smooth, frequent movements of less than 3 inches per minute. Insertion should not exceed 112.5" (TS 3.1.8 and LCS 3.1.103) 3 Monitor ASI and ESI. Observe PMS screen and/or chart for ASI trend. Determine that a second CEA insertion is required 4* Insert the PLCEAs. Insert the PLCEAs in small, smooth, frequent movements of less than 3 inches per minute. Insertion should not exceed 112.5" (TS 3.1.8 and LCS 3.1.103)

REV 0, 08/04/03 Page 6 of 9

JPM: NRC S1 TITLE: Dampen ASI oscillation.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat) 5 Determine that two PLCEAs have Verify Rod Bottom indication dropped Note:

Applicant may refer to SO23-13-13, Misaligned Control Element Assembly, to determine appropriate action 6* Trip the reactor Initiate Reactor Trip by depressing red Stop Time:

pushbuttons Terminating cue: When the applicant has tripped the reactor, the evaluation for this JPM is complete REV 0, 08/04/03 Page 7 of 9

REV 0, 08/04/03 Page 8 of 9 JPM CHECKLIST

1. The JPM is:

a. X Supported by facility's job task analysis.

b. X Operationally important (meets threshold criterion of K/A 3.0 or greater.

c. X Designed as either SRO only, or RO/SRO.

2. Each JPM includes:

a. X Initial conditions.

b. X Initiating cues.

c. X References, including associated procedures.

d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.

e. X System response cues that are complete and correct so that the examiner can properly cue the examinee, if asked.

f. X Statements describing important actions or observations that should be made by the examinee.

g. X Criteria for successful completion.

h. X Identification of the critical steps and their associated performance standards.

i. X Validated time limits (average time allowed for completion).

j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.

COMPLETED BY: J. Arsenault DATE: 08/04/03 REV 0, 08/04/03 Page 9 of 9

JPM INFORMATION SHEET JPM NUMBER NRC S2 INITIAL PLANT CONDITIONS Safety Injection Tank (SIT) T-007 level and pressure have increased due to backleakage through MU029. Backleakage has stopped.

All prerequisites to drain SIT T007 are established.

TASK TO BE PERFORMED Drain SIT T-007 to the RCDT to approximately 81% level to clear annunciator 57A39, SIT T-007 Pressure HI/LO, using Attachment 5 of SO23-3-2.7.1, Safety Injection Tank Operation.

REV 1-9, 08/04/03 Page 1 of 8

JOB PERFORMANCE MEASURE NRC S2 SUGGESTED TESTING ENVIRONMENT: Plant SIMULATOR X ACTUAL TESTING ENVIRONMENT: Plant SIMULATOR ACTUAL TESTING PERFORMED SIMULATED METHOD:

OPERATOR'S NAME:

(Print)

The operator's performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

REV 1-9, 08/04/03 Page 2 of 8

DOCUMENTATION NRC S2 JPM LEVEL: RO ESTIMATED TIME TO COMPLETE: 8 minutes TIME CRITICAL JPM: NO CRITICAL TIME: n/a minutes POSITION: UACO TASK SYS ID: 554 TASK DESCRIPTION:

Drain a safety injection tank to RCDT.

KA NUMBER: 006-A1.13 KA VALUES: RO 3.5 SRO 3.7 10CFR55.45 APPLICABILITY: 5

REFERENCES:

SO23-3-2.7.1, Safety Injection Tank Operation, Rev 10.

AUTHOR: S Hollinger DATE: 09/16/92 OPERATIONS REVIEW: D. Davison DATE: 10/08/93 APPROVED BY: M Kirby DATE: 10/20/93 REV 1-9, 08/04/03 Page 3 of 8

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOL BY MODIFIED APPROVAL 1 New Format. Modified cues to reflect SW 07/03/93 MJK simulator setup change.

1-1 Changed setup page; changed estimated time HJW 03/22/94 n/a from 10 to 8 minutes based on history; minor editorial changes to standards for clarity.

1-2 Compared against SO23-3-2.7.1, TCN 2-15 HJW 09/12/94 n/a with no changes required.

1-3 Compared against SO23-3-2.7.1, TCN 2-17 HJW 04/17/95 n/a with no changes required.

1-4 Compared against SO23-3-2.7.1, TCN 2-18 HJW 10/19/95 n/a with no changes required.

1-5 Compared against SO23-3-2.7.1, Rev. 5 with HJW 06/04/97 n/a minor editorial corrections. Added step 10 (non-critical) to allow natural completion of JPM. Updated KA number for NUREG-1122, Rev. 1.

1-6 Compared against SO23-3-2.7.1, TCN 6-1 RCW 09/22/98 n/a with no changes required.

1-7 Compared against SO23-3-2.7.1, TCN 9-2. JJM 07/25/02 AH Added step to record pre-start press and level for all SITs, added steps to log the inoperability and operability of the SIT, and added appropriate cues. Changed old task number to VISION SYS ID and updated the KA designation. Added LS from procedure to be provided to student. Added more inventory to the SIT such that the JPM is starting out of the green band. Changed tolerance for the final level 1-8 Added the requirement that the HI/LO Pressure JJM 09/26/02 alarm for the SIT is clear.

1-9 Verified against Revision SO23-3-2.7.1, JGA 08/04/03 Revision 10 REV 1-9, 08/04/03 Page 4 of 8

REV 1-9, 08/04/03 Page 5 of 8 SET-UP IC 84 for 2003 NRC Examination.

Provide copy of SO23-3-2.7.1 REV 1-9, 08/04/03 Page 6 of 8

JPM: NRC S2 TITLE: Drain SIT T-007 to the RCDT to 80.5% level, using Attachment 5 of SO23-3-2.7.1, Safety Injection Tank Operation.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat)

NOTE: Provide copy of SO23-3-2.7.1 1 Verify closed HV-9334, SIT drain to Observes green CLOSE indicating light for Start Time:

RWST Isolation Valve. HV-9334, SIT Drain to RWST Iso Valve.

2 Verify closed HV-9341, Cold Leg Observes green CLOSE indicating light for Injection Loop 1A Drain Valve. HV-9341, Cold Leg Injection Loop 1A Drain Valve..

3 Verify closed HV-9351, Cold Leg Observes green CLOSE indicating light for Injection Loop 1B Drain Valve. HV-9351, Cold Leg Injection Loop 1B Drain Valve.

4 Verify closed HV-9361, Cold Leg Observes green CLOSE indicating light for Injection Loop 2A Drain Valve. HV-9361, Cold Leg Injection Loop 2A Drain Valve.

REV 1-9, 08/04/03 Page 7 of 8

JPM: NRC S2 TITLE: Drain SIT T-007 to the RCDT to 80.5% level, using Attachment 5 of SO23-3-2.7.1, Safety Injection Tank Operation.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat) 5 Verify closed HV-9371, Cold Leg Observes green CLOSE indicating light for Injection Loop 2B Drain Valve. HV-9371, Cold Leg Injection Loop 2B Drain Valve.

6 Verify closed HV-9335, SIT to RCDT Observes green CLOSE indicating light for T-012 Drain Valve. HV-9335, SIT to RCDT T-012 Drain Valve.

7 Record the pre-start pressure and level Records the pre-start pressure and level for for all SITs. all SITs on Attachment 5.

CUE: Pumping Down the RCDT will not be necessary.

8 Log SIT T-007 as Inoperable. Informs CO to log SIT T-007 as Inoperable.

CUE: The CO will log SIT T-007 as Inoperable.

9* Open HV-9352, SIT T-007 Fill and Depresses OPEN pushbutton for HS-9352, Drain Valve. SIT 2T007 (Loop 1B) Fill & Drain Valve.

10* Open HV-9335, SIT to RCDT T-012 Depresses OPEN pushbutton for HV-9335, Drain Valve. SIT to RCDT 2T012 Drain Valve.

REV 1-9, 08/04/03 Page 8 of 8

JPM: NRC S2 TITLE: Drain SIT T-007 to the RCDT to 80.5% level, using Attachment 5 of SO23-3-2.7.1, Safety Injection Tank Operation.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat) 11* Close HV-9335, SIT to RCDT T-012 Depresseses CLOSE pushbutton for HV-Drain Valve after level lowers to 9335, SIT to RCDT 2T012 Drain Valve approximately 81%. when SIT T-007 Pressure HI/LO alarm clears and SIT level lowers to 81% plus or minus 2% (in green band).

12 Close HV-9352 SIT T-007 Fill and Depress CLOSE on HV-9352, SIT 2T007 Drain Valve. (Loop 1B) Fill & Drain Valve.

13 Log SIT T-007 as Operable. Informs CO to log SIT T-007 as Operable.

CUE: The CO will log SIT T-007 as Operable.

11 Record the post-drain pressures and Record the pressure and level for all SITs on Stop Time:

levels of all SITs. the procedure.

CUE: The CO will check SO23-3-3.25 for SIT Change Log - Six Hour Monitoring to determine SIT level plotting requirements.

TERMINATING CUE: This JPM is complete.

REV 1-9, 08/04/03 Page 9 of 8

REV 1-9, 08/04/03 Page 10 of 8 JPM CHECKLIST

1. The JPM is:

a. X Supported by facility's job task analysis.

b. X Operationally important (meets threshold criterion of K/A 3.0 or greater.

c. X Designed as either SRO only, or RO/SRO.

2. Each JPM includes:

a. X Initial conditions.

b. X Initiating cues.

c. X References, including associated procedures.

d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.

e. X System response cues that are complete and correct so that the examiner can properly cue the examinee, if asked.

f. X Statements describing important actions or observations that should be made by the examinee.

g. X Criteria for successful completion.

h. X Identification of the critical steps and their associated performance standards.

i. X Validated time limits (average time allowed for completion).

j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.

COMPLETED BY: J. Marron DATE: 07/25/02 REV 1-9, 08/04/03 Page 11 of 8

JPM INFORMATION SHEET JPM NUMBER NRC S3 INITIAL PLANT CONDITIONS A SGTR has occurred on Unit 2.

SPTAs are complete, and transition has been made to SO23-12-4, SGTR.

TASK TO BE PERFORMED The CRS has directed you to initiate RCS cooldown to Th <530BF using SBCS in MANUAL mode per SO23 4, Steam Generator Tube Rupture, Step 4 REV 0, 08/04/03 Page 1 of 11

JOB PERFORMANCE MEASURE NRC S3 SUGGESTED TESTING ENVIRONMENT: PLANT SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATOR'S NAME:

(Print)

The operator's performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

REV 0, 08/04/03 Page 2 of 11

DOCUMENTATION NRC S3 JPM LEVEL: RO/SRO ESTIMATED TIME TO COMPLETE: 15 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: UACO TASK SYS ID: 527 TASK DESCRIPTION:

Cooldown the RCS to less than 530 deg F KA NUMBER: 038 EA1.36 KA VALUES: RO 3.5 SRO 3.4 10CFR55.45 APPLICABILITY: 3,4,5,6,7,8,13

REFERENCES:

SO23-12-4, Steam Generator Tube Rupture, Revision 18 SO23-3-2.18, Steam Bypass System Operation, Revision 15 AUTHOR: J. Arsenault DATE: 08/04/03 OPERATIONS REVIEW: DATE:

APPROVED BY: DATE:

REV 0, 08/04/03 Page 3 of 11

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL REV 0, 08/04/03 Page 4 of 11

SET-UP SIMULATOR Simulator IC 82 for 2003 NRC Examination REV 0, 08/04/03 Page 5 of 11

JPM: NRC S3 TITLE: Cooldown RCS to less than 530 deg F using SBCS in Manual.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat)

NOTE: Provide the Examinee with a copy of SO23-12-4, Steam Generator Tube Rupture.

1 Verify BOTH SGs available Determines both Sgs are Time Start:

for cooldown available for cooldown based on SG pressures in normal post trip band 2 Ensure one RCP in each loop Verifies that one RCP is stopped stopped in each loop Note: The following steps describe the method for cooling the RCS down using SBCS in Manual. It is NOT necessary to perform these steps in the order written.

3* Depress OFF on 2HS-8424 and Locates 2HS-8424 and 2HS-8426 2HS-8426, HV-8424 and HV- and places in OFF 8426 Permissive Handswitches 4 Adjust the manual control Matches the manual signal signal on HIC-8423 and HIC- (black pen) to the automatic 8425 to match the automatic signal (green pen) on HIC-8423 setpoint signal and HIC-8425 controllers 5* Transfer HIC-8423 and HIC- Places HIC-8423 and HIC-8425 8425 to MANUAL switches in MANUAL position REV 0, 08/04/03 Page 6 of 11

JPM: NRC S3 TITLE: Cooldown RCS to less than 530 deg F using SBCS in Manual.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat) 6* Depress MANUAL PERMISSIVE Locates 2HS-8423 and 2HS-8425 on HS-8423 and HS-8425, HV- Manual Permissives and 8423 and HV-8425 Permissive depresses.

Handswitches, to place the permissives in MANUAL 7* Adjust HV-8423 and HV-8425 Slowly adjusts HV-8423 and HV-using the manual setpoint 8425 manual control knobs and control on HIC-8423 and observes valve position (red HIC-8425 to balance flow pen) tracking demand (black pen) 8 Check CFMS page 223 for Observes CFMS or other Time Stop:

highest Th below 530 deg F indication fot Th below 530 deg F.

Stabilize cooldown when criteria met.

Cue:

When the cooldown is stabilized at Th <530 deg F, the evaluation for this JPM is complete 20 REV 0, 08/04/03 Page 7 of 11

REV 0, 08/04/03 Page 8 of 9 JPM CHECKLIST

1. The JPM is:

a. X Supported by facility's job task analysis.

b. X Operationally important

c. X Designed as either SRO only, or RO/SRO.

2. Each JPM includes:

a. X Initial conditions.

b. X Initiating cues.

c. X References, including associated procedures.

d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.

e. X System response cues that are complete and correct so that the examiner can properly cue the Examinee, if asked.

f. X Statements describing important actions or observations that should be made by the Examinee.

g. X Criteria for successful completion.

h. X Identification of the critical steps and their associated performance standards.

i. X Validated time limits (average time allowed for completion).

j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.

COMPLETED BY: J. Arsenault DATE: 08/04/03 REV 0, 08/04/03 Page 9 of 9

JPM INFORMATION SHEET JPM NUMBER NRC S4 INITIAL PLANT CONDITIONS Unit 2 is in Mode 3.

A Plant heat up is in progress to the point of starting the fourth Reactor Coolant Pump, P004.

All actions of SO23-3-1.7, Reactor Coolant Pump Operation, through Step 6.1.16 are complete.

An Operator is stationed at the Reactor Coolant Pump (RCP).

TASK TO BE PERFORMED Start RCP P004 using SO23-3-1.7, Reactor Coolant Pump Operation, beginning with step 6.1.17.

REV 0, 08/04/03 Page 1 of 11

JOB PERFORMANCE MEASURE NRC S4 SUGGESTED TESTING ENVIRONMENT: PLANT SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATOR'S NAME:

(Print)

The operator's performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

REV 0, 08/04/03 Page 2 of 11

DOCUMENTATION NRC S4 JPM LEVEL: RO/SRO ESTIMATED TIME TO COMPLETE: 15 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: UACO TASK SYS ID: 527 TASK DESCRIPTION:

Startup a Reactor Coolant Pump.

KA NUMBER: 003-A4.06 KA VALUES: RO 2.9 SRO 2.9 10CFR55.45 APPLICABILITY: 5, 6, 7, 8

REFERENCES:

SO23-3-1.7, Reactor Coolant Pump Operation, Rev. 25 AUTHOR: J. Arsenault DATE: 08/04/03 OPERATIONS REVIEW: DATE:

APPROVED BY: DATE:

REV 0, 08/04/03 Page 3 of 11

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOT BY MODIFIED APPROVAL 0 Developed from JPM J010S for 2003 NRC JGA 08/04/03 Examination REV 0, 08/04/03 Page 4 of 11

SET-UP SIMULATOR Simulator IC 83 for 2003 NRC Examination (Link the meter failure to the RCP Start PB)

(Link the alarm override on to 35 seconds after the meter failure)

INSTRUCTOR/MACHINE OPERATOR Provide the Examinee with a copy of SO23-3-1.7, Reactor Coolant Pump Operation.

REV 0, 08/04/03 Page 5 of 11

JPM: NRC S4 TITLE: Startup a Reactor Coolant Pump.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat)

NOTE: Provide the Examinee with a copy of SO23-3-1.7, Reactor Coolant Pump Operation.

1* START one Oil Lift Pump by Depresses the NORMAL pushbutton Time Start:

selecting the NORMAL mode. on either 2P004 Oil Lift Pump 2P266, or 2P004 Oil Lift Pump 2P267.

Note: Annunciators 56C27 and 56C37 will come in and go out (Expected) 2 ENSURE the second oil lift Depresses the STANDBY pump selected to STANDBY. pushbutton on either 2P004 Oil Lift Pump 2P266 or 2P004 Oil Lift Pump 2P267, whichever was not started in the previous step.

Cue: Two minutes has elapsed 3* After the Oil Lift System Depresses the NORMAL pushbutton has run approximately 2 on either 2P004 ARRD Pump 2P405 minutes, then START one or 2P004 ARRD Pump 2P406.

ARRD Lube Oil Pump by selecting the NORMAL mode.

REV 0, 08/04/03 Page 6 of 11

JPM: NRC S4 TITLE: Startup a Reactor Coolant Pump.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat) 4 ENSURE the second ARRD pump Depresses the STANDBY is available by selecting pushbutton on either 2P004 ARRD the STANDBY mode. Pump 2P405, or 2P004 ARRD Pump 2P406, whichever was not started in the previous step.

5 VERIFY the following alarms Observes the following alarms on Panel CR56 are clear on Panel CR56 are clear prior prior to starting the RCP: to starting the RCP:

- RCP P004 THRUST BEARINGS - RCP P004 THRUST BRG TEMP TEMP HI, 56C07 HI, 56C07

- RCP P004 LUBE OIL FLOW - RCP P004 LUBE OIL FLOW LO, LO, 56C17 56C17

- RCP P004 REVERSE - RCP P004 REVERSE ROTATION, 56C18 ROTATION, 56C18

- RCP P004 OIL LIFT FLOW - RCP P004 OIL LIFT FLOW LO, 56C27 LO, 56C27

- RCP P004 OIL LIFT PRESS - RCP P004 OIL LIFT PRESS LO, 56C37 LO, 56C37

- RCP P004 CCW FLOW LO, - RCP P004 CCW FLOW LO, 56C38 56C38

- RCP P004 ARRD LUBE OIL - RCP P004 ARRD LUBE OIL FLOW LO, 56C47 FLOW LO, 56C47 REV 0, 08/04/03 Page 7 of 11

JPM: NRC S4 TITLE: Startup a Reactor Coolant Pump.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat) 6 Verify PMS Points selected Observe the following alarms on in Step 6.1.6 not in alarm: PMS:

- Computer Trend Groups - Computer Trend Groups

- RCP Controlled Bleed-off - RCP Controlled Bleed-off Flow Flow

- CCW Seal Heat Exchanger - CCW Seal Heat Exchanger Temperature Hi Temperature Hi CUE: There are no PMS points in alarm for the RCPs.

7 Verify RCP CONTROLLED Verifies RCP CONTROLLED BLEED-BLEED-OFF FLOW (PMS) is OFF FLOW (PMS) is clear or clear or proper RCP CBO proper RCP CBO flow for the flow for the existing RCS existing RCS pressure. (1.3 pressure. GPM) 8 Verify CCW SEAL EXCHANGER Verifies CCW SEAL EXCHANGER TEMPERATURE HI(PMS) alarm TEMPERATURE HI(PMS) alarm is is clear. clear.

REV 0, 08/04/03 Page 8 of 11

JPM: NRC S4 TITLE: Startup a Reactor Coolant Pump.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat) 9 Final configuration check Checks:

is to VERIFY:

One Oil Lift Pump, 2P266

One Oil Lift Pump and/or 2P267 selected to selected to NORMAL NORMAL and one selected to

One Oil Lift Pump STANDBY selected to STANDBY

One ARRD Pump, 2P405

One ARRD Pump selected to and/or 2P406 selected to NORMAL NORMAL and one selected to

One ARRD Pump selected to STANDBY STANDBY

Vibration Alarm reset

Vibration Alarm reset 10 VERIFY RCP Zero Speed Lamp Observes RCP P-004 Zero Speed illuminated. indication is illuminated.

11 ANNOUNCE pump start using Announces pump start using local area page. local area page.

12 START the Reactor Coolant Depresses the START pushbutton

Pump P-004. on 2P004.

13 Verify motor amps stabilize Observe RCP P-004 Motor Ammeter between 470 and 800 amps. and verifies motor amps stabilize between 470 and 800 amps.

REV 0, 08/04/03 Page 9 of 11

JPM: NRC S4 TITLE: Startup a Reactor Coolant Pump.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat) 14 Closely MONITOR RCS Using any combination of pressure. Control Board, CFMS, QSPDS or PMS indicators, observes RCS pressure is satisfactory.

15 Verify the Oil Lift and Observes:

ARRD Pumps automatically

Oil Lift Pump indicators stop and Zero Speed lamp for 2P004 Oil Lift Pump extinguishes. 2P266 and 2P267, stop indicating lights illuminated.

ARRD Pump Indicators for 2P004 ARRD Pump 2P405 and 2P406, stop indicating lights illuminated.

Zero Speed light extinguished.

16 Check RCP Oil Reservoir Directs an Operator to observe levels SAT. RCP P004 Oil Reservoir levels.

Cue:

Operator at the pump reports oil levels are satisfactory.

REV 0, 08/04/03 Page 10 of 11

JPM: NRC S4 TITLE: Startup a Reactor Coolant Pump.

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat) 17 Acknowledge Annunciator Acknowledge annunciator and 56C07, RCP P004 THRUST BRG refer to ARP for alarm received TEMP HI 18 Determine that RCP P004 Verifies TI-0178, P004 Upward Upward Thrust Bearing Thrust Bearing temperature, is temperature is >225 deg F pegged HIGH 19 Trip the reactor Inserts reactor trip signal by

depressing MANUAL reactor trip pushbuttons. Verifies reactor trip by checking all CEAs inserted 20 Trip RCP P004 TERMINATING CUE: Time Stop:

When the applicant trips the RCP, or takes other action related to the malfunction, the evaluation for this JPM is complete.

REV 0, 08/04/03 Page 11 of 11

REV 2-2, 08/29/01 Page 12 of 13 JPM CHECKLIST

1. The JPM is:

a. X Supported by facility's job task analysis.

b. X** Operationally important (** K/A is < 3.0, however, task is infrequently performed).

c. X Designed as either SRO only, or RO/SRO.

2. Each JPM includes:

a. X Initial conditions.

b. X Initiating cues.

c. X References, including associated procedures.

d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.

e. X System response cues that are complete and correct so that the examiner can properly cue the Examinee, if asked.

f. X Statements describing important actions or observations that should be made by the Examinee.

g. X Criteria for successful completion.

h. X Identification of the critical steps and their associated performance standards.

i. X Validated time limits (average time allowed for completion).

j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.

COMPLETED BY: J. Arsenault DATE: 08/04/03 REV 2-2, 08/29/01 Page 13 of 13

JPM INFORMATION SHEET JPM NUMBER NRC S5 INITIAL PLANT CONDITIONS Unit 2 has undergone a major LOCA. The operating crew has transitioned to SO23-12-3, Loss of Coolant Accident.

RWST level has lowered below 19%. The CRS has directed you to implement SO23-12-11, Attachment 14, RAS Actuation.

TASK TO BE PERFORMED Perform Attachment 14, RAS Actuation, of SO23-12-11, EOI Supporting Attachments REV 2, 08/04/03 Page 1 of 10

JOB PERFORMANCE MEASURE NRC S5 SUGGESTED TESTING ENVIRONMENT: PLANT SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATOR'S NAME:

(Print)

The operator's performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

REV 2, 08/04/03 Page 2 of 10

DOCUMENTATION NRC S5 JPM LEVEL: RO/SRO ESTIMATED TIME TO COMPLETE: 15 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: UACO TASK SYS ID: 2007 TASK DESCRIPTION:

Verify proper actuation of the recirculation actuation system.

KA NUMBER: 011-EA1.11 KA VALUES: RO 4.2 SRO 4.2 10CFR55.45 APPLICABILITY: 4, 5, 7

REFERENCES:

SO23-12-11, EOI Supporting Attachments, Revision 1, Attachment 14.

AUTHOR: L. Zilli DATE: 06/14/00 OPERATIONS REVIEW: M. Jones DATE: 06/26/00 APPROVED BY: W. Lyke DATE: 06/29/00 REV 2, 08/04/03 Page 3 of 10

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOL BY MODIFIED APPROVAL 0-1 Compared against SO23-12-3, SGA 06/24/97 N/A Rev. 14, no changes required.

Minor editorial changes. Update KA to agree with NUREG-1122, Rev. 1.

0-2 Changed standard for step 18 to HJW 09/09/97 N/A remove guage observation for hot/cold leg simultaneous flow at direction of SOT.

0-3 Compared against SO23-12-3, Rev JJM 10/21/99 WLL 16, changed attachment number to 6, changed verb check to verify, deleted step to notify HP on rad levels, added each operating train for containment spray, added verify that RWST not reqd for borated water source (and its associated cue). Updated the KA designation and values and changed old task number to VISION SYS ID.

1 Compared against SO23-12-3, Rev LRZ 06/14/00 WLL 16, and incorporated changes.

2 Changed reference to SO23-12-11 JGA 08/04/03 for 2003 NRC Examination REV 2, 08/04/03 Page 4 of 10

SET-UP Reset to IC-89 for 2003 NRC Examination NOTE: Place key switches back to open prior to restoring for next JPM.

Provide the examinee with a copy of SO23-12-3, Loss of Coolant Accident, .

Provide keys #8, #9, #10, #23, #24, & #25 to examiner.

Note: Verify that the CCW to Letdown Heat Exchanger valve is reopened when repeating this JPM.

REV 2, 08/04/03 Page 5 of 10

JPM: NRC S5 TITLE: Verification of RAS Actuation

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat)

NOTE: Provide the examinee with a copy of SO23-12-11, EOI Supporting Attachments, Attachment 14.

1 Verify RAS conditions Observes at least two (2) of Time Start: ________

established by checking the following; RWT 2T006 RWST level <19%. LEVEL LI-0305-1, 2, 3, and/or 4 RWST levels <19%.

2 Verify Containment Observes CNTMT EMER SUMP Emergency Sump level >18' LEVEL 2LI-9386-1 or 4". 2LI-9389-2 >18' 4".

NOTE: The following four (4) valves can be opened in any order.

3* Ensure Containment Depresses OPEN pushbutton Emergency Sump Outlet for CNTMT EMER SUMP OUTLET Valve, HV-9303, open. ISO VALVE, 2HV-9303.

4* Ensure Containment Depresses OPEN pushbutton Emergency Sump Outlet for CNTMT EMER SUMP OUTLET Valve, HV-9305, open. ISO VALVE, 2HV-9305.

5* Ensure Containment Depresses OPEN pushbutton Emergency Sump Outlet for CNTMT EMER SUMP OUTLET Valve, HV-9302, open. ISO VALVE, 2HV-9302.

REV 2, 08/04/03 Page 6 of 10

JPM: NRC S5 TITLE: Verification of RAS Actuation

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat) 6* Ensure Containment Depresses OPEN pushbutton Emergency Sump Outlet for CNTMT EMER SUMP OUTLET Valve, HV-9304, open. ISO VALVE, 2HV-9304.

7* Ensure LPSI Pump P015 Depresses SIAS OVERRIDE stopped. pushbutton and then STOP pushbutton for LPSI PUMP P015, 2HS-9390-1.

8* Ensure LPSI Pump P016 Depresses SIAS OVERRIDE stopped. pushbutton and then STOP pushbutton for LPSI PUMP P016, 2HS-9391-2.

NOTE: The following four (4) valves can be closed in any order.

9* Ensure SI Pump & CNTMT Closes SI Pump & CNTMT Spray Spray Pump mini-flow HV- Pump mini-flow Iso valve, 9306 closed. 2HV-9306. (Key #9) 10 Ensure SI Pump & CNTMT Closes SI Pump & CNTMT Spray

Spray Pump mini-flow HV- Pump mini-flow Iso valve, 9307 closed. 2HV-9307. (Key #10) 11 Ensure SI Pump & CNTMT Closes SI Pump & CNTMT Spray

Spray Pump mini-flow HV- Pump mini-flow Iso valve, 9347 closed. 2HV-9347. (Key #24)

REV 2, 08/04/03 Page 7 of 10

JPM: NRC S5 TITLE: Verification of RAS Actuation

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat) 12 Ensure SI Pump & CNTMT Closes SI Pump & CNTMT Spray

Spray Pump mini-flow HV- Pump mini-flow Iso valve, 9348 closed. 2HV-9348. (Key #25) 13 Verify Containment Spray Observes Containment Spray flow on each operating Hdr No. 1 & No. 2 flow train >1625 gpm. indicators 2FI-0338-1 and 2FI-0348-2 >1625 gpm.

14 Verify Containment Observes CNTMT EMER SUMP Emergency Sump level >18' LEVEL 2LI-9386-1 OR 4" and RWST not required 2LI-9389-2 >18' 4".

for borated water source.

CUE: The RWST is not required for a borated water source.

NOTE: The RWST valves may be aligned in any order.

15 Close RWST outlet Inserts key and closes RWT

Isolation valve HV-9300. 2T005 Outlet Iso Valve, 2HV-9300. (Key #8) 16 Close RWST outlet Inserts key and closes RWT

Isolation valve HV-9301. 2T005 Outlet Iso Valve, 2HV-9301. (Key #23)

REV 2, 08/04/03 Page 8 of 10

JPM: NRC S5 TITLE: Verification of RAS Actuation

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat) 17 Verify HPSI Flow criteria: Observes HPSI FLOW TO COLD With Cold Leg Injection LEGS (any one (1) only: Total HPSI flow >160 instrument) 2FI-0321-1, 2FI-gpm in any one loop per 0331-1, operating pump. 2FI-0311-2, & 2FI-0341-2 to verify total HPSI flow >160 gpm in any one loop per operating pump.

18 Close CCW to Letdown Heat Depresses the CLOSE Time Stop: ________

Exchanger valve Train A pushbutton for the in-2HV-6293B/A and service CCW CLA/B LTDN HX 2HV-6522B/A. 2E062 Supply/Return valves, 2HV-6293B/A or 2HV-6522B/A.

TERMINATING CUE:

When RAS actuation has been completed manually, the evaluation for this JPM is complete.

REV 2, 08/04/03 Page 9 of 10

REV 2, 08/04/03 Page 10 of 10 JPM CHECKLIST

1. The JPM is:

a. X Supported by facility's job task analysis.

b. X Operationally important (meets threshold criterion of K/A 3.0 or greater).

c. X Designed as either SRO only, or RO/SRO.

2. Each JPM includes:

a. X Initial conditions.

b. X Initiating cues.

c. X References, including associated procedures.

d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.

e. X System response cues that are complete and correct so that the examiner can properly cue the examinee, if asked.

f. X Statements describing important actions or observations that should be made by the examinee.

g. X Criteria for successful completion.

h. X Identification of the critical steps and their associated performance standards.

i. X Validated time limits (average time allowed for completion).

j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.

COMPLETED BY: J. Arsenault DATE: 08/04/03 REV 2, 08/04/03 Page 11 of 10

JPM INFORMATION SHEET JPM NUMBER NRC C1 INITIAL PLANT CONDITIONS The Control Room Supervisor directs a transfer of 2A06 from the Bus Tie to the Reserve Auxiliary Transformer.

2A06 is on the bus tie due to a recent electrical transient resulting in an inadvertent transfer to the bus tie.

TASK TO BE PERFORMED REV 2, 08/04/03 Page 1 of 10

JOB PERFORMANCE MEASURE NRC C1 SUGGESTED TESTING ENVIRONMENT: PLANT SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATOR'S NAME:

(Print)

The operator's performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

REV 2, 08/04/03 Page 2 of 10

DOCUMENTATION NRC C1 JPM LEVEL: RO/SRO ESTIMATED TIME TO COMPLETE: 20 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: CACO TASK SYS ID: 271 TASK DESCRIPTION:

Manually transfer 1E 4KV bus power source.

KA NUMBER: 062-A4.07 KA VALUES: RO 3.1 SRO 3.1 10CFR55.45 APPLICABILITY: 6

REFERENCES:

SO23-6-2, Transferring of 4 kV Buses, TCN 8-1 AUTHOR: L. Zilli DATE: 06/09/00 OPERATIONS REVIEW: M. Jones DATE: 06/26/00 APPROVED BY: W. Lyke DATE: 06/29/00 REV 2, 08/04/03 Page 3 of 10

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOL BY MODIFIED APPROVAL 0-1 Corrected "Position" on HJW 02/09/95 N/A Documentation page.

0-2 Compared against SO23-6-2 with HJW 07/02/96 N/A minor editorial corrections.

0-3 Compared against SO23-6-2 with RCW 09/02/98 N/A no modifications required.

0-4 Compared against SO23-6-2 with JJM 10/26/99 WLL no changes reqd. Changed Common CO to SRO Ops Supv.

for initial plant conditions.

Added two cues to the beginning of the JPM to preclude confusion for the student.

Updated KA designation and changed old task number to VISION SYS ID.

1 Compared against SO23-6-2, Rev. LRZ 06/15/00 WLL 7 with minor changes required.

Updated format.

2 Updated SO23-6-2 Revision and JGA 08/04/03 changed JPM to reflect different bus.

REV 2, 08/04/03 Page 4 of 10

SET-UP IC 84 if simulator is used.

Ensure Cross tie to bus 2A06 from Unit 3 3A06, using SO23-6-2, Section 6.2 Provide the examinee with a copy of SO23-6-2, Transferring of 4 kV Buses, when located.

REV 2, 08/04/03 Page 5 of 10

JPM: NRC C1 TITLE: Restore Bus 2A06 from 1E Cross-Tie operations to the RAT

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat)

NOTE: Provide the examinee with a copy of SO23-6-2, Transferring of 4 kV Buses, when located.

CUE: The CRS has reviewed Technical Specification 3.8.1 and actions are being met.

CUE: The Tailboard session between all participants is complete.

1 Ensure the affected Makes announcement or sends Start Time: ________

Switchgear Room is clear PEO to clear personnel of all unnecessary personnel and maintain it Cue: Switchgear Room is clear until after 4kV bus clear transfer is complete 2 Verify the incoming 4160V Checks electrical mimic and source has normal voltage metering and is available for load.

CUE: The incoming 4 kV source has normal voltage and is available for load.

3* Place the synchroscope in Places the synchroscope, service by placing the 2/3SI-1627A, in service by respective key operated placing key operated TRAIN B Master Control switch to SYNC CKT CONTROL, 2HS-1627-2 ON. ESF B SYNC MASTER Control switch to ON.

REV 2, 08/04/03 Page 6 of 10

JPM: NRC C1 TITLE: Restore Bus 2A06 from 1E Cross-Tie operations to the RAT

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat) 4* Place synchronizing Presses SYNC pushbutton for circuit in service by Incoming Breaker (identified depressing SYNC pushbutton from Attachment 1) RES AUX for the Incoming Breaker. XFMR 2XR1 FDR BREAKER 2A0618, 2HS-1637-2.

5 Verify breaker SYNC light Verifies breaker SYNC light illuminated. illuminated on RES AUX XFMR 2XR1 FDR BREAKER 2A0618, 2HS-1637-2.

CUE: 2XR2 Feeder 2A016 SYNCH light is illuminated 6 Verify SYNC IN MODE light Verifies SYNC IN MODE light illuminated. illuminated on TRAIN B SYNC CKT CONTROL, 2HS-1627-2 ESF B SYNC MASTER Control switch.

CUE: Train B SYNCH IN MODE light is illuminated 7 Verify SYNC RELAY TROUBLE Verifies SYNC RELAY TROUBLE light off. light off on TRAIN B SYNC CKT CONTROL, 2HS-1627-2 ESF B SYNC MASTER Control switch.

REV 2, 08/04/03 Page 7 of 10

JPM: NRC C1 TITLE: Restore Bus 2A06 from 1E Cross-Tie operations to the RAT

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat)

CUE: Train B Synch. Ckt. Ctrl SYNCH RELAY TROUBLE light is extinguished 8 Verify Incoming and Verifies Incoming and Running voltages and Running voltages matched on frequencies matched. 2/3EI-1627A & 2/3EI-1627B and frequencies matched on 2/3SI-1627C & 2/3SI-1627D.

CUE: Incoming and running voltages and frequencies are matched 9 Verify synchroscope moves Verifies synchroscope to straight up (12 2/3SI-1627A moves to o'clock) position. straight up (12 o'clock) position.

CUE: Synchroscope pointer is straight up at 12 oclock position 10 Close the Incoming Depresses the CLOSE

breaker. pushbutton on RES AUX XFMR 2XR2 FDR BREAKER 2A0618 2HS-1637-2.

11 Verify the BUSES Observes 63C55 2A06/3A06 PARALLELED alarm. BUSES PARALLELED alarm.

CUE: Annunciator 63C55 is illuminated. 2A016 breaker CLOSE light is illuminated REV 2, 08/04/03 Page 8 of 10

JPM: NRC C1 TITLE: Restore Bus 2A06 from 1E Cross-Tie operations to the RAT

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat) 12 Perform SO23-3-3.23, Refers to SO23-3-3.23.

Attachment for AC Sources for both Units, due to the Cue: SO23-3-3.23 is being bus tie breakers being performed by another placed in MANUAL operator 13 Select the affected unit Places 2HS-1639B-2 to MANUAL bus tie FDR BKR selector and acknowledges alarm 63C35 for affected train to (2A06 - 3A06)

MANUAL CUE: 2HS-1639B2 MANUAL light is illuminated. Annunciator 63C35 is illuminated.

14 Select the opposite unit Places 3HS-1639B-2 to MANUAL bus tie FDR BKR selector (3A06 - 2A06) for affected train to MANUAL CUE: 3HS-1639B2 MANUAL light is illuminated 15 Open the receiving bus tie Depresses the TRIP

breaker manually. pushbutton on BUS TIE 2A06 TO 3A06 FDR BKR 2A0619 2HS-1639A2 Acknowledges parallel alarm cleared REV 2, 08/04/03 Page 9 of 10

JPM: NRC C1 TITLE: Restore Bus 2A06 from 1E Cross-Tie operations to the RAT

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat)

CUE: Breaker 2A0619 TRIP light is illuminated. Annunciator 63C55 is clear 16 Open the opposite unit Opens the Unit 3 supply bus supply bus tie breaker. tie breaker 3A0603 3HS-1639A2.

CUE: Breaker 3A0603 TRIP light is illuminated 17 Select the Bus Transfer Selects BUS TIE 2A06 TO 3A06

Controls AUTO/MANUAL FDR BKR 2A0619 SELECTOR switch to AUTO for both 2HS-1639B2 to AUTO and place units. the Unit 3bus tie breaker Auto/Manual switch in AUTO.

CUE: FDR BKR 2A0619 and 3A0603 AUTO lights are illuminated 18 Remove the synchronizing Presses SYNC pushbutton for circuit from service by Incoming Breaker RES AUX depressing SYNC pushbutton XFMR 2XR2 FDR BREAKER for the Incoming breaker. 2A0618, 2HS-1637-2.

CUE: 2A0618 SYNCH light is extinguished REV 2, 08/04/03 Page 10 of 10

JPM: NRC C1 TITLE: Restore Bus 2A06 from 1E Cross-Tie operations to the RAT

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat) 16 Remove the synchroscope Removes the synchroscope, Stop Time: ________

from service by placing 2/3SI-1627A, from service by the respective placing key operated TRAIN B key-operated Master SYNC CKT CONTROL, 2HS-1627-2 Controls switch to OFF. ESF B SYNC MASTER Control switch to OFF.

TERMINATING CUE:

This JPM is complete.

REV 2, 08/04/03 Page 11 of 10

REV 2, 08/04/03 Page 12 of 10 JPM CHECKLIST

1. The JPM is:

a. X Supported by facility's job task analysis.

b. X Operationally important (meets threshold criterion of K/A 3.0 or greater).

c. X Designed as either SRO only, or RO/SRO.

2. Each JPM includes:

a. X Initial conditions.

b. X Initiating cues.

c. X References, including associated procedures.

d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.

e. X System response cues that are complete and correct so that the examiner can properly cue the examinee, if asked.

f. X Statements describing important actions or observations that should be made by the examinee.

g. X Criteria for successful completion.

h. X Identification of the critical steps and their associated performance standards.

i. X Validated time limits (average time allowed for completion).

j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.

COMPLETED BY: L. Zilli DATE: 09/05/00 REV 2, 08/04/03 Page 13 of 10

JPM INFORMATION SHEET JPM NUMBER NRC S7 INITIAL PLANT CONDITIONS A computer technician is preparing to do investigative work on CPC channel D due to erratic CEAC #1.

CEAC No. 1 INOP flags are to be set in all 4 CPCs per direction of the Plant Superintendent.

Shift Manager approval has been given.

TASK TO BE PERFORMED Set CEAC No. 1 INOP flag in CPC Channel D per SO23-3-2.13, Core Protection/Control Element Assembly Calculator Operation.

REV 2-2, 08/04/03 Page 1 of 11

JOB PERFORMANCE MEASURE NRC S7 SUGGESTED TESTING ENVIRONMENT: PLANT SIMULATOR X ACTUAL TESTING ENVIRONMENT: PLANT SIMULATOR ACTUAL TESTING METHOD: PERFORMED SIMULATED OPERATOR'S NAME:

(Print)

The operator's performance was evaluated against the standards contained in this JPM and is determined to be:

SATISFACTORY:

UNSATISFACTORY:

REV 2-2, 08/04/03 Page 2 of 11

DOCUMENTATION NRC S7 JPM LEVEL: RO/SRO ESTIMATED TIME TO COMPLETE: 6 minutes TIME CRITICAL JPM: NO CRITICAL TIME: N/A POSITION: ACO TASK SYS ID: 651 TASK DESCRIPTION:

Change the value of a CPC addressable constant.

KA NUMBER: 012-A4.05 KA VALUES: RO 3.6 SRO 3.6 10CFR55.45 APPLICABILITY: 2, 4

REFERENCES:

SO23-3-2.13, Core Protection/Control Element Assembly Calculator Operation, Revision 13.

AUTHOR: C. Baker DATE: 09/04/00 OPERATIONS REVIEW: R Clement DATE: 09/05/00 APPROVED BY: W. Lyke DATE: 09/06/00 REV 2-2, 08/04/03 Page 3 of 11

MODIFICATION HISTORY REV DESCRIPTION OF CHANGE MODIFIED DATE SOL BY MODIFIED APPROVAL 1 Incorporated changes in the procedure RR 9/26/93 MJK and comments from testing. Added critical steps 6, 7, 9, 10, and 11.

1-1 Changed setup page; changed estimated HJW 03/23/94 N/A time from 10 to 6 minutes based on history; minor changes to standards for clarity; deleted step 1 and identified procedure in task statement.

1-2 Compared against SO23-3-2.13, TCN 5-14 HJW 09/26/94 N/A with no changes required.

1-3 Compared against SO23-3-2.13, TCN 5-15 HJW 05/05/95 N/A with no changes required.

1-4 Compared against SO23-3-2.13, TCN 5-17 HJW 10/02/95 N/A with changes made to record values for PID 179 & 406. Also changed setup page and notes to enhance simulator operation.

1-5 Comparted against SO23-3-2.13, TCN HJW 11/21/95 N/A 5-18, with no changes required.

1-6 Compared against SO23-3-2.13, Rev. 7. HJW 08/30/96 N/A Changed sequence of steps per procedure.

1-7 Compared against SO23-3-2.13, TCN 10-1.RCS 10/26/99 WLL Modified the notes concerning bypassing trips. Added JPM COMPLETE to terminating cue. Upgraded KA desig. and changed old task mumber to VISION SYS ID.

2 Compared against SO23-3-2.13, Rev. 11 JJM 09/02/00 WLL and added cue stating that the Type I constant Change Notification has bee made. Simplified the notes for the machine operator actions on bypassing the bistables.

REV 2-2, 08/04/03 Page 4 of 11

2-1 Compared against SO23-3-2.13, TCN 12-3.JJM 08/05/02 Added more info on the setup page for the Log. Added note that DNBR and LPD bistables may not need to be bypassed.

Reworded step 9 to match the procedure.

2-2 Revised procedure revision and comparedJGA 08/04/03 against SO23-3-2.13, Revision 13 REV 2-2, 08/04/03 Page 5 of 11

SET-UP Restore to IC 84 for 2003 NRC Examination.

When directed by the examiner, place LPD and DNBR Trips in BYPASS on Channel D. (Contingency)

When directed by the examiner, remove the LPD and DNB Trip Bypasses on Channel D.

Provide key #40 for the CPC D FUNCTION keylock.

Provide examinee with a copy of SO23-3-2.13, Core Protection/Control Element Assembly Calculator Operation and a copy of CEANOP Log page (from procedure SO23-XXXVII-4.7), with the following items filled in:

on top of the page:

Unit CPC Channel CPC Point ID Program Label 2 D 062 CEANOP on the first line:

Before and After PID 179: 10.81 Before and After PID 406: 2.13 Value Entered: 0 CPC Readout Value: 0.000 CPC Readout n: 0 4 Hr CEA Verif: N/A REV 2-2, 08/04/03 Page 6 of 11

JPM: NRC S7 TITLE: Set CEAC No. 1 Inoperable flag in CPC Channel D

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat)

NOTE: Provide examinee with a copy of SO23-3-2.13, Core Protection/Control Element Assembly Calculator Operation as well as the CEANOP Log Page with appropriate information filled out.

CUE: All Addressable Constant changes will be documented using the Addressable Constant Change Log provided by the instructor.

NOTE: Since PID 334 and PID 406 are both greater than 1.70, then the CEA INOP flag, PID 062 may be changed without installing the DNBR and LPD trip bypasses. If the examinee chooses not to have these bistables bypassed, then mark JPM step 1 as N/A.

CUE: CRS should concur with whatever applicant chooses to do CUE: CEA position verification has been completed If the Examinee chooses to have the DNBR and LPD trip bistables placed in bypass, then have the machine operator bypass PPS Channel D DNBR and LPD.

1 Direct an operator to Directs an operator to Start Time:

bypass PPS channel D DNBR bypass PPS Channel A DNBR and LPD trips. and LPD trips.

CUE: The DNBR and LPD trips are bypassed (if examinee directs bistables placed in bypass)

REV 2-2, 08/04/03 Page 7 of 11

JPM: NRC S7 TITLE: Set CEAC No. 1 Inoperable flag in CPC Channel D

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat) 2 Select CPC mode on the Places the Calculator Select Operator Module. switch to the CPC position.

3 Obtain key for CPC D Obtains key # 52 for CPC D FUNCTION keylock. FUNCTION keylock and insert.

4* TURN the FUNCTION keylock Turns the FUNCTION keylock to ON. to ON.

5 Enter the initial value Depresses the DISPLAY for Point ID 179 in the pushbutton and then 1, 7, 9 CPC Addressable Constants on the keypad. Records the Change Log. resulting value in the appropriate column of the CPC Addressable Constants Change Log.

6 Enter the initial value Depresses the DISPLAY for Point ID 406 in the pushbutton and then 4, 0, 6 CPC Addressable Constants on the keypad. Records the Change Log. resulting value in the appropriate column of the CPC Addressable Constants Change Log.

7* DEPRESS CHANGE VALUE Depresses the CHANGE VALUE pushbutton. pushbutton.

REV 2-2, 08/04/03 Page 8 of 11

JPM: NRC S7 TITLE: Set CEAC No. 1 Inoperable flag in CPC Channel D

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat) 8* Use the key pad and enter Depresses the 0, 6, and 2 062. pushbuttons.

9 VERIFY the value for PID Refers to CPC Addressable 062 matches the value in Change Constants Log and the CPC Addressable Change verifies current PID 062 Constants Log. display matches the last entry in the log (0).

10 Depress the ENTER key. Depresses the ENTER key.

11 Use the key pad and ENTER Depresses 1 on key pad.

1.

12 DEPRESS EXECUTE key to Depresses the EXECUTE key.

complete the value change.

13 Verify the VALUE display Observes the VALUE display indicates 1. and verifies that it is 1.

REV 2-2, 08/04/03 Page 9 of 11

JPM: NRC S7 TITLE: Set CEAC No. 1 Inoperable flag in CPC Channel D

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat) 14 Enter the final value for Depresses the DISPLAY Point ID 179 in the CPC pushbutton and then 1, 7, 9 Addressable Constants on the keypad. Records the Change Log. resulting value in the appropriate column of the CPC Addressable Constants Change Log.

15 Enter the final value for Depresses the DISPLAY Point ID 406 in the CPC pushbutton and then 4, 0, 6 Addressable Constants on the keypad. Records the Change Log. resulting value in the appropriate column of the CPC Addressable Constants Change Log.

16 Verify the CEAC INOP light Observes the CEAC INOP light illuminates on the CPC illuminated on the CPC Operators Module. Operators Module.

17 TURN the FUNCTION keylock Turns the FUNCTION keylock to OFF. to the OFF position.

REV 2-2, 08/04/03 Page 10 of 11

JPM: NRC S7 TITLE: Set CEAC No. 1 Inoperable flag in CPC Channel D

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat) 18 ENSURE that the CPC Records the value 1" in the addressable Constant Value Entered Column of Change Log has been CPC addressable Change Log updated for the Point ID and records the CPC Readout that was changed, and that on the CPC Addressable the value recorded was Change Log.

actually entered into the CPC.

19 Ensure Addressable Depresses the display Constant Point ID 419 is pushbutton and then 419 on reset to zero the keypad and observes the value for Point ID 419 is zero.

CUE: The Type I Constant Change Notification has been completed by the CRS.

NOTE: If directed by the examinee, have the machine operator remove the bypasses for PPS Channel A DNB and LPD trips.

REV 2-2, 08/04/03 Page 11 of 11

JPM: NRC S7 TITLE: Set CEAC No. 1 Inoperable flag in CPC Channel D

Denotes a CRITICAL STEP NO PERFORMANCE STEP STANDARD S/U Comments (Required for Unsat) 20 If directed by an operator Directs an operator to Stop Time:

remove the bypasses on PPS remove the bypasses on PPS channel D DNB and LPD channel D DNB and LPD trips.

trips.

TERMINATING CUE:

When the bypasses are removed, the evaluation for this JPM is complete.

REV 2-2, 08/04/03 Page 12 of 11

REV 2-2, 08/04/03 Page 13 of 10 JPM CHECKLIST

1. The JPM is:

a. X Supported by facility's job task analysis.

b. X Operationally important (meets threshold criterion of K/A 3.0 or greater).

c. X Designed as either SRO only, or RO/SRO.

2. Each JPM includes:

a. X Initial conditions.

b. X Initiating cues.

c. X References, including associated procedures.

d. X Performance standards which are specific in that control and indication nomenclature and criteria (switch position, meter reading) are specified, even if these criteria are not specified in the procedural step.

e. X System response cues that are complete and correct so that the examiner can properly cue the Examinee, if asked.

f. X Statements describing important actions or observations that should be made by the Examinee.

g. X Criteria for successful completion.

h. X Identification of the critical steps and their associated performance standards.

I. X Validated time limits (average time allowed for completion).

j. X JPMs identified as time critical or not time critical by the Operations Division based on NRC commitments.

COMPLETED BY: James Marron DATE: 08/05/00 REV 2-2, 08/04/03 Page 14 of 10

Appendix D Scenario Outline Form ES-D-1 Facility: SONGS Scenario No.: 1 Op Test No.: 1 Examiners: Candidates: CRS RO PO Initial Conditions: 53% Power, BOC. Dilution and power increase in progress Train A CCW in service HPSI P-017 OOS MDAFW P-141 OOS RM-7818 OOS Turnover: Continue to raise power at 10% per hour Critical Tasks: Establish minimum design safety injection flow rate Re-establish RCS Subcooling by establishing a primary to secondary heat sink Event Malf. Event No. No. Type* Event Description 1 (R) CO Raise Power (N) ACO (N) CRS 2 TU10A (C) ALL Main Turbine HP Governor Valve B fails closed 3 CC03A (C) ACO Train A CCW Header Rupture 4 CV02A (C) CO RCP P-001 Lower and Middle Seal Failures CV03A 5 RC05A (C) ALL RCP P-001 Shaft Shear 6 RC03 (M) ALL SBLOCA upon Reactor Trip, 1300 GPM 7 RP01C (C) CO HPSI Pump P-019 Auto Start Failure EC08D HPSI Pump P-018 Overcurrent Trip (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Scenario Event Description NRC Scenario 1 The crew will assume the shift at 53% power, Beginning of Cycle. A power increase is in progress in accordance with SO23-5-1.7, Power Operations.

After the crew has demonstrated control of the plant power change, Main Turbine HP Governor Control valve B will fail closed, requiring the crew to stabilize the plant and respond to the failure in accordance with Annunciator Response Procedures and SO23-10-3, Operation of the Turbine Control and Protection System.

When the plant is stable and action for the failed governor control valve is complete, a rupture of the operating CCW loop will occur. The crew will diagnose the failure using Annunciator Response Procedures and SO23-13-7, Loss of Component Cooling Water/Salt Water Cooling.

The crew will be required to start the idle CCW and SWC pumps and transfer cooling loads to the operable header. The ruptured header will be removed from service. The CRS will be required to evaluate Technical Specifications.

The following event is an RCP P-001 seal failure. The crew will respond in accordance with Annunciator Response Procedures and SO23-13-6, RCP Seal Failure. The crew will diagnose a failure of the lower and middle seals on RCP P-001, and the CRS will determine the need for a plant shutdown in accordance with SO23-5-1.7, Power Operations.

As the crew prepares to initiate a plant shutdown, RCP P-001 shaft shears, and the reactor will trip on low RCS loop flow.

A Small Break LOCA develops, and the remaining RCPs must be tripped due to CIAS actuation or loss of RCS subcooling. Additionally, the crew must manually start the available HPSI pump due to an automatic start failure.

The crew diagnoses a LOCA and enters SO23-12-3, LOCA. The crew will determine that RCS Subcooling is less than 20ºF and will take action to restore subcooling.

The scenario is terminated upon initiation of action to reestablish RCS Subcooling.

Risk Significance:

Risk important components out of service: HPSI P-017, MDAFW P-141

Failure of risk important system prior to trip: CCW Rupture

Risk significant core damage sequence: SBLOCA with HPSI failure

Risk significant operator actions: Manual HPSI initiation SONGS 2003 NRC Initial License Examination Simulator Scenario Setup Scenario 1 MACHINE OPERATOR'S INSTRUCTIONS SETUP IC: IC-80: 53% Power, BOC, Train A CCW 10.4 gpm dilution and 10%/hr power increase in progress OOS Equipment: AFW P-141, HPSI P-017, RM-7818 USER: OPTEST RLPs/ TYPE MALF # DESCRIPTION DEMAND INITIATING STEPS VALUE PARAMETER 10(1) RF FW70 AFW Pump P-141 Breaker Racked Out True 10(2) RF EC80 HPSI Pump P-017 OOS: DC Control Power Off False 10(3) RF EC86 HPSI Pump P-017 OOS: Breaker Racked Out 3 10(4) MF RC03 LOCA, 1300 gpm 20% RX Trip 10(5) MF EC08D HPSI Pump P-018 OC Trip True 10(6) MF RP01C HPSI Pump P-019 Auto Start Failure True MO Action Place mag tag on AFW P-141 handswitch MO Action Push EMER FW SYS INOPERABLE pushbutton on ESF Bypass Status Train A 2HS-0065 MO Action Place mag tag on HPSI P-017 handswitch MO Action Set up ASI/ESI recorder for operation MO Action Leave Simulator in Freeze after setup is complete (due to dilution and power increase)

SONGS 2003 NRC Initial License Examination Simulator Scenario Setup Scenario 1 MACHINE OPERATOR'S INSTRUCTIONS SCENARIO RLPs/ TYPE MALF # DESCRIPTION DEMAND RAMP DELAY STEPS VALUE 11(1) MF TU10A Turbine Governor Valve B Fails Closed 0 11(2) MF CC03A CCW Line Rupture in SDC Room on HX E004 50%

Inlet 11(3) OVER 57C46 Override ON SEB Train A Flooding alarm and 1 2 min SDC HX area light on 2ZL-9480-1 flooding indication panel [Linked to 11(2)]

11(4) RF CC67 Close CCW Surge Tank T-003 Outlet Valve 0%

HV-6225 11(5) RF CC57 CCW Pump P-024 DC Off (Contingency) False 11(6) RF CC58 CCW Pump P-025 Train A DC Off False (Contingency) 11(7) RF EC81 HPSI Pump P-018 Train A DC Off False (Contingency) 11(8) RF EC78 LPSI Pump P-015 DC Off (Contingency) False 11(9) RF CS57 CS Pump P-012 DC Off (Contingency) False 11(10) MF CV02A RCP P-001 Lower Seal Failure 1.0 MF CV03A RCP P-001 Middle Seal Failure 1.0 2 sec 11(11) MF RC05A RCP P-001 Sheared Shaft True 11(12) RF ED85 Non-Qualified Loads Restoration True (N) INDICATES STEP N OF THE INDICATED RLP.

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 1 Event # 1 Page 5 of 24 Event

Description:

Raise Power Time Position Applicants Actions or Behavior Note:

Crew turnover will be performed with simulator in FREEZE due to dilution and power increase in progress at turnover.

Review requirements of SO23-5-1.7, Power Operations, and CREW SO23-3-2.2, Makeup Operations Verifies Batch Counter and Makeup Integrator settings CO Verifies dilution valve alignment

FV-9253 open CO

FIC-0210X in AUTO

HS-0210 selected to DILUTE Verifies Tcold changing as dilution progresses CO Maintains Tcold within required band by raising Main Generator ACO load using VV OPEN LMT RAISE pushbutton Acknowledges LOSS OF LOAD TRIP DISABLED annunciators clear as reactor power is raised. (Expected)

CO 56A30, 40, 50, 60 clear At Lead Evaluators discretion, proceed to Event 2

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 1 Event # 2 Page 6 of 24 Event

Description:

Main Turbine HP Governor Valve failure Time Position Applicants Actions or Behavior Machine Operator: When directed, execute RLP 11 (1), Turbine Governor Valve B Fails Closed Indications available:

99A13, TURBINE GOVERNOR TROUBLE 99A15, TURBINE GOVERNOR FAULT HP Turbine Governor Valve UV-2200B indicates closed SBCS valves HV-8423 and HV-8425 modulate open 50A07, SBCS DEMAND PRESENT 50A14, PZR PRESS HI/LO RCS pressure, Tcold, and Letdown flow are rising Main Spray valves modulate open Main Generator output drops by approximately 100 Mwe Respond to alarms as applicable by referring to Annunciator CO/ACO Response Procedures Stop dilution in progress by placing Makeup Mode Selector CO Switch to AUTO Immediately check turbine load, turbine speed, and valve ACO positions Identify cause of failure CREW

Dispatch PEO to valve actuators and/or alarm modules M.O. Cue:

If dispatched to identify alarms on the governor cubicle, wait 3 minutes and report that there is a MOD F alarm

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 1 Event # 2 Page 7 of 24 Event

Description:

Main Turbine HP Governor Valve failure Time Position Applicants Actions or Behavior Refer to SO23-10-3, Attachment 6, HPSV or HPGV Failure CRS Record the HPSV/HPGV pair CRS/ACO

Affected valve is UV-2200B

Associated valve is UV-2200A Initiate Attachment 3 in conjunction with this attachment CRS/ACO Initiate action to return Tc and power back to the pre-transient values using the turbine and/or SBCS (Raise Turbine Load until SBCS valves close)

CO/ACO (This action may be completed to stabilize the plant prior to referring to SO23-10-3)

Notify the GOC of load reduction and that additional generator CRS load swings may occur Notify Chemistry that HPSV/HPGV failure may cause spiking of CRS Chemistry parameters IF RCS Pressure exceeded 2275 psia, refer to Technical CRS Specification 3.4.1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 1 Event # 2 Page 8 of 24 Event

Description:

Main Turbine HP Governor Valve failure Time Position Applicants Actions or Behavior Note: The following actions are directed by Attachment 3 ACO Verify a turbine stop or governor valve has closed Dispatch operator to affected valve (May have already ACO/CRS done so)

Record control room, (UA-99A), Turbine Governor CTRL Cubicle Module, (L-017), and Turbine Governor CTRL panel ACO alarms and oil temp (L-014)

M.O. Cue:

When requested to report local information, report the following:

At the Unitized Actuator, one of the two solenoids is deenergized. All other indications appear normal

At L-14, Turbine Governor Control Panel, no alarms are present and UV-2200B oil temperature is 112ºF

At L-17, Turbine Governor Control Cubicle, MOD F light is energized for HP GOV 2 Refer to LCS 3.3.109, restore UV-2200B to operable status CRS within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months When the crew has restored turbine load with SBCS valves closed or at discretion of Lead Evaluator, proceed to Event 3

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 1 Event # 3 Page 9 of 24 Event

Description:

Component Cooling Water Header leak Time Position Applicants Actions or Behavior Machine Operator: When directed, execute RLP 11 (2), CCW Line Rupture in SDC HX Room on HX E004 Inlet Indications available:

64A7, CCW PUMP TRAIN A DISCH PRESS LO 64A45, CCW HX TRAIN A OUTLET PRESS LO 64A26, CCW SURGE TANK TRAIN A LEVEL HI/LO 57C46, SAFETY EQPT BLDG TRAIN A FLOODING after a time delay Refer to applicable Annunciator Response Procedures ACO Refer to SO23-13-7, Loss of Component Cooling Water/Salt CRS Water Cooling, section for CCW System leak Isolate Radwaste by closing 2HV-6465 and 3HV-6465 ACO Verify the leak is isolated (NO)

ACO

Report CCW Surge Tank level still lowering M.O. Cue:

If called to report status of Unit 3 CCW Surge Tank Level, report that Train A CCW Surge Tank level is stable and unchanged Ensure CCW/SWC on the unaffected loop is in service CRS

Direct ACO to place Train B CCW/SWC in service Start CCW Pump P-026 and verify that SWC P-114 ACO automatically starts

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 1 Event # 3 Page 10 of 24 Event

Description:

Component Cooling Water Header leak Time Position Applicants Actions or Behavior Verify Letdown HX is aligned to the operating loop CRS

Direct transfer of Letdown HX to Train B Transfer Letdown HX to Train B

Close HV-6293B/A ACO

Open HV-6522B/A Verify NCL is aligned to the operating loop CRS

Direct transfer of NCL to Train B Transfer NCL to Train B CCW

Open HV-6213/6219 ACO

Verify HV-6212/6218 close automatically If necessary, respond to annunciator 56C58, SAFETY EQUIPMENT BLDG TRAIN A FLOODING AND 2ZL-9480-1, CO Flooding Indication Panel Shutdown Clg HX area light

Dispatch PEO to investigate If necessary, respond to annunciator 57C46, 1A, SD HX E004 AREA FLOODING CO

Dispatch PEO to investigate Ensure STOPPED the CCW Pump on the affected loop CRS

Direct stopping CCW Pump P-025

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 1 Event # 3 Page 11 of 24 Event

Description:

Component Cooling Water Header leak Time Position Applicants Actions or Behavior Stop CCW Pump P-025 and SWC pump P-112 ACO M.O. Cue:

If directed to rack out breaker for CCW Pump P-024, wait 3 minutes and execute RLP 11 (5). If directed to rack out breaker for CCW Pump P-025, wait 3 minutes and execute RLP 11 (6)

Ensure ECCS is not required

HPSI, LPSI, CS pumps are stopped CRS Note: Crew may rack out breakers for HPSI, LPSI, and CS pumps on affected train to avoid damage due to lack of cooling water M.O. Cue:

If directed to rack out breakers for Train A ESF Pumps, execute the following RLPs as applicable:

HPSI P-018; RLP 11 (7)

LPSI P-015; RLP 11 (8)

CS P-012; RLP 11 (9)

Dispatch PEO to close Loop A CCW Surge Tank Outlet, HV-ACO 6225 M.O. Cue:

When directed to close Surge Tank T-003 outlet valve HV-6225, wait 2 minutes and then execute RLP 11 (4)

When complete, report that HV-6225 is closed.

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 1 Event # 3 Page 12 of 24 Event

Description:

Component Cooling Water Header leak Time Position Applicants Actions or Behavior M.O. Cue:

If directed to investigate leak location, wait 2 minutes and report flooding in E-004 SDC HX area due to a CCW pipe burst. The break is located between inlet isolation valve 2HCV-6548 and HX 2E-004 Verify CCW Surge Tank Level is stable ACO Close the affected CCW Surge Tank Makeup, HV-6273 ACO

Verifies valve is closed Refer to T.S. 3.7.7, 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to restore Train A CCW to CRS OPERABLE M.O. Cue:

If directed to swap CCW Pump P-025 or HPSI Pump P-018 to Train B, acknowledge the order but do not perform.

If directed to swap Emergency Chiller ME-336 from Unit 2 to Unit 3, acknowledge the order but do not perform. (Scenario Time Restriction)

When Loop A CCW is isolated and CCW Surge Tank level is verified stable, proceed to Event 4

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 1 Event # 4 Page 13 of 24 Event

Description:

RCP Seal Failure Time Position Applicants Actions or Behavior Machine Operator: When directed, execute RLP 11(10), RCP P-001 Lower and Middle Seal Failures Indications available:

56C24, RCP P001 SEAL PRESS HI/LO 56B57, RCP BLEEDOFF FLOW HI/LO Respond to applicable annunciators CO Refer to SO23-13-6, Reactor Coolant Pump Seal Failure CRS Determine if RCP Seal failure has occurred per Attachment 1

Verifies indication of Lower and Middle seal failures CO based on seal cavity pressure readings in accordance with Attachment 1 Determine if any RCP operating parameters are out of normal range per Attachment 2 CO

Have already identified seal pressures

No others out of range Inform Maintenance Engineering of the situation CRS Note: May perform after all actions have been determined Trend abnormal parameters on Plant Monitoring System per Attachment 3 CREW

Set up PMS point trends for RCP P-001

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 1 Event # 4 Page 14 of 24 Event

Description:

RCP Seal Failure Time Position Applicants Actions or Behavior Based upon determination that 2 seal stages have failed, CRS initiate a plant shutdown per SO23-5-1.7.

Upon determination that a plant shutdown is required, or at Lead Evaluators discretion, proceed to Event 5

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # All Event # 5, 6, 7 Page 15 of 24 Event

Description:

RCP Shaft Shear, SBLOCA, HPSI Actuation Failure Time Position Applicants Actions or Behavior Machine Operator: When directed, execute RLP 11 (11), RCP P-001 Sheared Shaft Determine that the reactor has tripped CREW Note:

Crew may take all action required during SPTAs prior to reporting status Direct crew to perform SO23-12-1, Standard Post Trip Actions CRS Perform the following:

Record time of reactor trip CRS

Announce reactor trip via PA system

Initiate attachment 4, WORKSHEET

Initiate attachment 5, ADMINISTRATIVE ACTIONS Verify Reactivity Control criteria satisfied:

Verify reactor trip circuit breakers (8) open CO

Verify all full length CEAs fully inserted

Verify reactor power lowering and startup rate negative Determine that RCP P-001 has a sheared shaft CO

Trip RCP P-001

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # All Event # 5, 6, 7 Page 16 of 24 Event

Description:

RCP Shaft Shear, SBLOCA, HPSI Actuation Failure Time Position Applicants Actions or Behavior Verify Vital Auxiliaries functioning properly:

Verify Main Turbine tripped o HP and LP stop and governor valves closed o Mwe output lowering

Verify both Unit Output Breakers open

Verify Main Turbine speed less than 2000 rpm or lowering ACO

Verify CCW pump aligned to Non-Critical Loop and Letdown - Operating (NO; CIAS Actuated)

Verify both 1E 4KV buses energized

Verify both 1E 480V buses B04 and B06 energized

Verify all 6.9KV and Non-1E 4KV buses energized

Verify all Class 1E DC buses energized Verify RCS Inventory Control criteria satisfied:

Verify PZR level o between 10% and 70%

o Trending to between 30% and 60% (NO)

Verify Core Exit Saturation Margin greater than or equal CO to 20°F (NO) o QSPDS page 611 o CFMS page 311

ENSURE PZR Level Control System operating in AUTO or MANUAL to restore PZR level (LOCA in progress)

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # All Event # 5, 6, 7 Page 17 of 24 Event

Description:

RCP Shaft Shear, SBLOCA, HPSI Actuation Failure Time Position Applicants Actions or Behavior Verify RCS Pressure Control criteria satisfied:

VERIFY PZR pressure (WR and NR) o Between 1740 and 2380 psia (NO) o Controlled CO

Trending to between 2025 psia and 2275 psia (NO)

IF PZR pressure less than PZR pressure control system setpoint and lowering, THEN ENSURE Normal and Auxiliary Spray Valves closed Verify Core Heat Removal criteria satisfied:

Verify at least ONE RCP operating (When conditions are met due to CIAS or loss of NPSH, all RCPs will be stopped)

CO

Verify core loop Delta T (Th-Tc) less than 10°F

Verify Core Exit Saturation Margin greater than or equal to 20°F (NO) o QSPDS page 611 o CFMS page 311

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # All Event # 5, 6, 7 Page 18 of 24 Event

Description:

RCP Shaft Shear, SBLOCA, HPSI Actuation Failure Time Position Applicants Actions or Behavior Verify RCS Heat removal criteria satisfied:

Both SG levels between 21% and 80% NR AND

AFW available to restore both SG levels between 40%

NR and 80% NR at greater than or equal to 200 GPM OR

Main Feedwater available to restore both SG levels between 40% and 80% NR with flow to each SG:

o At least one MFW pump operating o RTO o MFW pump discharge to SG DP greater than 25 PSID ACO

Prevent SG High level o Close MFW Block Valves HV-4047 and HV-4051

Verify heat removal adequate o Tc less than 555°F o SG Pressures approximately 1000 psia

Restore RCS Heat Removal on ADVs

Verify Tc greater than 545°F or controlled

Verify SG pressures greater than 740 psia

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # All Event # 5, 6, 7 Page 19 of 24 Event

Description:

RCP Shaft Shear, SBLOCA, HPSI Actuation Failure Time Position Applicants Actions or Behavior Verify Containment Isolation criteria satisfied:

Verify Containment pressure less than 1.5 psig (NO) o When containment pressure exceeds 3.4 psig, ensure the following actuated:

§ SIAS, CIAS, CCAS, CRIS o Stop RCPs CO

Verify Containment Radiation monitors energized AND

Not alarming or trending to alarm (NO) o Record status of radiation monitors

Verify secondary plant radiation monitors energized AND

Not alarming or trending to alarm Note:

CO MAY override and stop Train A LPSI and Containment Spray pumps due to lack of CCW cooling Record time of SIAS, CIAS, CCAS, CRIS CRS Verify Containment temperature, Pressure and Combustible Gas Control criteria satisfied:

Verify Containment average temperature less than 120°F (NO)

Verify Containment pressure less than 1.5 psig (NO)

CO o Verify proper functioning of containment cooling o Ensure at least one Containment Dome Air Circulator operating o When containment pressure exceeds 3.4 psig, ensure the following actuated:

§ SIAS, CIAS, CCAS, CRIS o Ensure all available Containment Emergency Cooling Units operating

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # All Event # 5, 6, 7 Page 20 of 24 Event

Description:

RCP Shaft Shear, SBLOCA, HPSI Actuation Failure Time Position Applicants Actions or Behavior Record time of SIAS, CIAS, CCAS, CRIS CRS Diagnose event in progress:

Verify all safety function criteria per attachment 4, WORKSHEET, recovered (NO) o Complete attachment 1, RECOVERY DIAGNOSTIC o Diagnose LOCA Inside Containment CRS

Notify personnel of event in progress

Designate SRO in Charge

Initiate steps 11-14

Determine Reactor Trip Recovery is NOT diagnosed Based on Attachment 1, RECOVERY DIAGNOSTIC, the CRS CRS should direct entry to SO23-12-3, LOCA Ensure SO23-12-1, STANDARD POST TRIP ACTIONS, steps 1-10 are complete CRS

Record time of EOI entry

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # All Event # 5, 6, 7 Page 21 of 24 Event

Description:

RCP Shaft Shear, SBLOCA, HPSI Actuation Failure Time Position Applicants Actions or Behavior Verify LOCA diagnosis:

Initiate SO23-12-10, LOCA Safety Function Status Checks (May request STA assistance)

Initiate Foldout Page o FS-7, HPSI Throttle/Stop CRS o FS-3, Monitor Natural Circulation o Attachment 22, Non-Qualified Loads Restoration

Verify LOCA diagnosis, using Figure 1, BREAK IDENTIFICATION CHART

Initiate sampling of both steam generators for radioactivity and boron M.O. Cue:

If directed to sample SGs, wait 10 minutes and then report that E088 and E089 both have activity near background, and normal boron levels.

If the SG sample valves are closed, report that you are unable to establish sample flow Initiate Administrative actions:

Notify Shift Manager/Operations Leader of SO23-12-3, Loss of Coolant Accident, initiation CRS

Ensure Emergency Plan is initiated

IMPLEMENT PLACEKEEPER

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # All Event # 5, 6, 7 Page 22 of 24 Event

Description:

RCP Shaft Shear, SBLOCA, HPSI Actuation Failure Time Position Applicants Actions or Behavior Verify ESF actuation:

Verify SIAS actuation required o PZR Pressure less than SIAS setpoint CO OR o Containment pressure greater than 3.4 psig

Ensure SIAS, CCAS, CRIS are actuated Record time of SIAS CRS Stop unloaded Diesel Generators ACO Initiate SO23-12-11, Attachment 22, NON-QUALIFIED LOAD ACO RESTORATION (Also Foldout Page item)

M.O. Cue:

When directed to restore non-qualified loads, wait 3 minutes, then call the control room and state that you are ready to restore. When directed, execute RLP 11 (12),

Non-Qualified Load Restoration When complete, inform the control room that you have restored non-qualified loads.

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # All Event # 5, 6, 7 Page 23 of 24 Event

Description:

RCP Shaft Shear, SBLOCA, HPSI Actuation Failure Time Position Applicants Actions or Behavior Critical Establish Optimum SI Alignment Task

Establish two train operation o All Charging Pumps operating o One HPSI and One LPSI per train operating (NO)

MANUALLY START HPSI PUMP P-019 o All Cold leg flow paths aligned CO o Verify SI flow required

SI flow indicated

RCS pressure greater than 1250 psia OR

Verify FS-7, Verify HPSI Throttle/Stop criteria satisfied (NO)

Verify PZR pressure

Verify RCP NPSH requirements of SO23-12-11, CO attachment 29, POST ACCIDENT PRESSURE/TEMPERATURE LIMITS - satisfied (NO) o Stop RCPs (Already stopped) and initiate FS-3, MONITOR Natural Circulation established

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # All Event # 5, 6, 7 Page 24 of 24 Event

Description:

RCP Shaft Shear, SBLOCA, HPSI Actuation Failure Time Position Applicants Actions or Behavior Implement Floating Steps:

CRS

Initiate applicable sections of SO23-12-11, Attachment 2, Floating Steps Inform CRS that RNO action is required for FS-3 due to RCS CO/ACO subcooling less than minimum Critical Override and open AFW flow control valves to increase AFW Task ACO flow to raise SG levels to <80% NR or as directed by CRS Raise SG steaming rate, using ADVs in manual. (If MSIS ACO actuates, ADVs must be placed in OVERRIDE to operate)

Terminate scenario when RCS subcooling restoration has been initiated

Appendix D Scenario Outline Form ES-D-1 Facility: SONGS Scenario No.: 2 Op Test No.: 1 Examiners: Candidates: CRS RO PO Initial Conditions: 100% Power, MOC Train A CCW in service HPSI P-017 OOS MDAFW P-141 OOS RM-7818 OOS Turnover: CREACUS surveillance is completed and restoration is in progress. Perform SO23-3-3.20, Attachment 1, steps 2.11.6 and 2.11.7 Critical Tasks: Depressurize RCS Perform HPSI Throttle Stop Event No. Malf. No. Event Type* Event Description 1 (N) ACO CREACUS monthly surveillance restoration 2 RC15B (I) CO Pressurizer Pressure Transmitter PT-0100Y Fails High 3 SG04C (I) ACO SG E089 level transmitter LT-1105 fails high 4 FW09A (C) ALL Main Feed Pump P-062 Trip - Load Reduction required (R) CO 5 SG01B (C) ALL SG E089 Tube Leak 10 GPM, increases to 800 GPM SGTR on reactor trip SG02B 6 FW09B (M) ALL Main Feed Pump P-063 Trip - Reactor Trip required 7 TU07 (C) ACO Turbine fails to trip. Manual trip required 8 MS05B (M) ALL ESDE outside containment SG E089 upon reactor trip (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Scenario Event Description NRC Scenario 2 The crew will assume the shift at 100% power, Middle of Cycle. Initial conditions will require the crew to partially restore CREACUS from a surveillance run when they assume the shift.

The controlling Pressurizer Pressure Channel, PT-0100-Y, will fail high. The crew will take action in accordance with Annunciator Response Procedures and SO23-3-1.10, Pressurizer Pressure and Level Control. Channel X will be selected for control and the CRS will evaluate Technical Specifications.

When Pressurizer Pressure Control is restored, SG E089 level transmitter LT-1105 will fail high.

The crew must take action to restore feed flow in accordance with Annunciator Response Procedures and SO23-13-24, Feedwater Control System Malfunction. SG E089 level will ultimately be restored to automatic control by contacting I&C.

When SG level control is restored to automatic, Main Feedwater Pump P-062 will trip on high vibration, requiring a rapid power reduction to approximately 75-80% power in accordance with SO23-13-24 and SO23-5-1.7, Power Operations.

When the plant is stabilized, a steam generator tube leak will develop on SG E089. The crew will respond in accordance with Annunciator Response Procedures, SO23-13-14, Reactor Coolant Leak, and Technical Specifications. The CRS will determine that a reactor shutdown is required due to excessive primary to secondary leakage.

When preparations for plant shutdown are being made, Main Feedwater Pump P-063 will trip, requiring a reactor trip.

The Main Turbine fails to automatically trip and must be manually tripped. The steam generator tube leak will increase in severity, and after the Main Turbine is manually tripped an ESDE outside containment will occur on SG E089.

The crew will diagnose a SGTR and ESDE on SG E089, and enters SO23-12-9, Functional Recovery.

The scenario is terminated when RCS pressure reduction is in progress and HPSI is throttled.

Risk Significance:

Risk important components out of service: HPSI P-017, MDAFW P-141

Risk significant initiating event: Loss of Main Feedwater

Risk significant operator actions: Manual Turbine Trip, RCS depressurization SONGS 2003 NRC Initial License Examination Simulator Scenario Setup Scenario 2 MACHINE OPERATOR'S INSTRUCTIONS SETUP IC: IC-94: 100% Power, MOC, Train A CCW. Train A CREACUS Monthly test restoration in progress OOS Equipment: AFW P-141, HPSI P-017, RM-7818 USER: OPTEST RLPs/ TYPE MALF # DESCRIPTION DEMAND INITIATING STEPS VALUE PARAMETER 13(1) RF FW70 AFW Pump P-141 Breaker Racked Out True 13(2) RF EC80 HPSI Pump P-017 OOS: DC Control Power Off False 13(3) RF EC86 HPSI Pump P-017 OOS: Breaker Racked Out 3 13(4) MF SG02B SGTR on E089, 800 gpm 40% RX Trip 13(5) MF MS05B ESDE on E089 Outside Containment 7% RX Trip 13(6) MF TU07 Turbine Auto Trip Failure (on RX Trip) True MO Action Place mag tag on AFW P-141 handswitch MO Action Push EMER FW SYS INOPERABLE pushbutton on ESF Bypass Status Train A 2HS-0065 MO Action Place mag tag on HPSI P-017 handswitch SONGS 2003 NRC Initial License Examination Simulator Scenario Setup Scenario 2 MACHINE OPERATOR'S INSTRUCTIONS SCENARIO RLPs/ TYPE MALF # DESCRIPTION DEMAND RAMP DELAY STEPS VALUE 14(1) MF RC15B PZR Pressure Controlling Ch. PT-0100Y Fails 75%

As-Is MF RC15B PZR Pressure Controlling Ch. PT-0100Y Fails 100% 1 min 2 sec High 14(2) MF SG04C SG E089 LT-1105 to FWCS Fails As -Is 66%

MF SG04C SG E089 LT-1105 to FWCS Fails High 100% 2 min 2 sec 14(3) RF RX53 Align E089 FWCS level input to Position 2, LT- 2 1111 only 14(4) MF FW09A MFW Pump P-062/K006 High Vibration Trip 60% 2 min 14(5) RF FW73A CST T-121 Makeup Valve in Auto True (Contingency for tank low level alarm) 14(6) MF SG01B SG E089 Tube Leak, 10 gpm 1.7%

14(7) MF FW09B MFW Pump P-063/K005 High Vibration Trip 75% 1 min 14(8) RF ED85 Non-Qualified Loads Restoration True (N) INDICATES STEP N OF THE INDICATED RLP.

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 1 Page 5 of 33 Event

Description:

Complete CREACUS Surveillance Time Position Applicants Actions or Behavior Shutdown the Train A Emergency Air Conditioning and Ventilation Units, and align Train A Isolation Dampers, as ACO follows:

Stop 2MA-207, CR Emergency Vent Supply Unit Train A (2HS-ACO 9760-1) and record Stop time Verify 2FV-9761, CR Emergency Vent Unit Train A Damper, ACO indicates CLOSE Verify 2ME-297, CR Emergency Vent Unit Train A Heater, ACO indicates OFF (2ZL-9759A1)

Stop 2ME-418, CR Emergency A/C Unit Train A, at 2CR-60 ACO and record stop time (Check unit to which 2ME-418 is aligned)

(2HS-9749-1)

Select 2HV-9702, Control Room Air A/C Unit 2ME-295 ACO Discharge Damper, to OPEN Select 2HV-9712, Control Room Recirc 2ME-295 Suction ACO Damper, to OPEN Select 2HV-9717, Control Room Outside Air Isolation Damper, ACO to OPEN

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 1 Page 6 of 33 Event

Description:

Complete CREACUS Surveillance Time Position Applicants Actions or Behavior Select 2HV-9769, Control Room Outside Air Isolation Damper, ACO to OPEN Select 2HV-9756, Control Room Outside Air Isolation Damper, ACO to OPEN At Lead Evaluators discretion, proceed to Event 2

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 2 Page 7 of 33 Event

Description:

PZR PT-100Y Fails High Time Position Applicants Actions or Behavior Machine Operator: When directed, execute RLP 14 (1), Pressurizer PT-0100Y fails high Indications available:

50A04, PZR PRESSURE DEVIATION HI/LO 50A14, PZR PRESSURE HI/LO PZR Heaters Trip OFF PZR Spray valves modulate OPEN if control channel drifts high enough prior to action Refer to Annunciator Response Procedures CO Determine which channel initiated the alarm using 2PR-100 CO

PIC-0100B has failed high If a control channel failure has occurred, then select 2PIC-100 to MANUAL, and return pressure to the normal band CO

Selects MANUAL and ensures spray valves closed, PZR pressure trending to normal Refer to SO23-3-1.10, to direct placing PZR Pressure control to CRS the unaffected channel.

Verify PI-0100X is operable CO Transfer PIC-0100 to MANUAL by depressing the A/M pushbutton (Should have already been performed when CO channel failure diagnosed)

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 2 Page 8 of 33 Event

Description:

PZR PT-100Y Fails High Time Position Applicants Actions or Behavior Position HS-0100A, Pressurizer Pressure Channel Select CO switch, to the desired channel (CH. X)

Transfer PIC-0100, PZR Pressure Controller, to AUTO by depressing the A/M pushbutton and verify proper system CO response Restore PZR heaters to normal configuration

Place heater control switches to OFF, then AUTO (May CO wait until PZR pressure has been returned to the normal band)

Recognize and report SBCS permissives are active ACO (Not recoverable or controllable)

Refer to Technical Specifications CRS

3.4.1 ONLY if PZR pressure dropped below 2025 psia When Technical Specifications have been addressed or at the Lead Evaluators discretion, proceed to Event 3

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 3 Page 9 of 33 Event

Description:

SG-E089 LT-1105 Fails High Time Position Applicants Actions or Behavior Machine Operator: When directed, execute RLP 14 (2), SG E089 LT-1105 fails high:

Indications available:

52A07, FWCS SG1 E089 LEVEL CHANNEL DEVIATION 52A06, SG1 E089 LEVEL HI/LO (POSSIBLE) 50A02, COLSS ALARM (POSSIBLE)

Condensate Pump P-053 Auto Start (POSSIBLE)

Feedwater Regulating Valve position modulates closed Actual SG E089 level trending down Refer to SO23-13-24, Feedwater Control System malfunction CRS Refer to Attachment 1 for initial action ACO Determine SG E089 actual level is low ACO Determine Master Controller Output is NOT Rising ACO Place SG E-089 Master Controller in MANUAL and raise output ACO to stabilize SG level Refer to remainder of flowchart to determine if other failures ACO present Direct I&C to remove LT-1105 from service in accordance with CRS SO23-9-6, section 6.7.1

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 3 Page 10 of 33 Event

Description:

SG-E089 LT-1105 Fails High Time Position Applicants Actions or Behavior Machine Operator Cue:

When directed to remove LT-1105 from service, wait 1 minute, then execute RLP 14 (3), align E-089 FWCS level input to position 2 When complete, report that LT-1105 has been removed from service Restore SG E089 Level control to AUTO ACO Note:

If Condensate Pump P-053 auto starts during this event, the crew MAY elect to place it back in STANDBY When SG E089 is restored to automatic level control, proceed to Event 4

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 4 Page 11 of 33 Event

Description:

MFW Pump P-062/K006 High Vibration Trip Time Position Applicants Actions or Behavior Machine Operator: When directed, execute RLP 14 (4), MFW Pump P062/K006 High Vibration Trip Indications available:

53A15, MFWP TURBINE K006 VIBRATION HI PRETRIP 53A30, MFWP/TURBINE P062/K006 VIBRATION HI 53A03, MFWP TURBINE K006 TRIP MAY refer to Annunciator Response Procedures if time permits ACO Refer to SO23-13-24, Feedwater Control System Malfunctions CRS Determine reactor power is greater than 80%

CREW Initiate EFAS 1 and EFAS 2 by depressing all 8 EFAS CO/ACO pushbuttons 1 time Perform Rapid Power Reduction using boration and CEA insertion to reduce reactor power to 75% - 80% per SO23 CREW 1.7, Power Operations Note:

The CRS may direct the CO to initiate forcing sprays for boron equalization Determine amount of CEA movement and quantity of boric acid to be used for power reduction CO

Group 6 CEAs will be inserted approximately 40 - 50 inches for the power reduction

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 4 Page 12 of 33 Event

Description:

MFW Pump P-062/K006 High Vibration Trip Time Position Applicants Actions or Behavior LOWER Turbine load to raise Tc until SBCS permissives are in ACO (Permissives are already in)

Borate as required via Alternate or Direct Boration CO Insert Group 6 CEAs to target level CO Note: The CO will stop CEA insertion if PPDIL alarm is received. Insertion may continue when the alarm clears Note: The following steps resume actions of AOI SO23-13-24 M.O. Cue:

If directed to investigate MFW Pump P062/K006 locally, wait 3 minutes and report that there are no obvious signs of distress at the pump Ensure all available Condensate Pumps are running ACO Ensure Feedwater Control valves are <100% open and ACO controlling SG level Ensure SG levels are stable or rising ACO Ensure SG Low Level alarms are reset ACO Depress ALL EFAS Actuation pushbuttons a second time to CO/ACO reset the cycling relays

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 4 Page 13 of 33 Event

Description:

MFW Pump P-062/K006 High Vibration Trip Time Position Applicants Actions or Behavior Contact Chemistry and the GOC to inform them of the Rapid CRS Power Reduction Refer to SO23-5-1.7, Attachment 2 for recommended power plateau with one Main Feedwater Pump out of service CRS (75-80%)

Control ASI when steady state power is reached CO M.O. Cue:

If directed to reset EFEAS 1 and EFAS 2, acknowledge the order but do not perform (Scenario time restriction)

When plant is stable, or at Lead Evaluators discretion, proceed to Event 5

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 5 Page 14 of 33 Event

Description:

SG Tube Leak Time Position Applicants Actions or Behavior Machine Operator: When directed, execute RLP 14 (6), SG E089 Tube Leak, 10 GPM Indications available:

60A46, SECONDARY RADIATION HI 63B02, CRITICAL PARAMETERS Refer to Annunciator Response Procedure.

CO/ACO Determine radiation monitor status

Air Ejector High Range 7870 in alarm CO/ACO

Main Steam Line 7874B1 (E089) in alarm

SG Blowdown 6753 in alarm after a time delay Determine that high radiation is due to a SG Tube Leak on SG CRS E089 Initiate SO23-13-14, section for Primary to Secondary leakage

Request Chemistry to confirm and quantify the steam generator tube leak by sampling the condenser air CRS ejector discharge

When leak rate is quantified, determine reportability requirements Direct action of SO23-13-14, Step 4 for Primary to Secondary CRS leak rate

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 5 Page 15 of 33 Event

Description:

SG Tube Leak Time Position Applicants Actions or Behavior Verify PZR level NOT LOWERING CO Verify VCT level is being maintained within programmed band CO Verify PZR level NOT LOWERING with all available charging CO pumps in operation Verify PZR level stable or rising CO Inform Shift Manager and Chemistry of required actions per CRS AOI SO23-13-14 M.O. Cue:

When contacted as Chemistry, wait 5 minutes and report that a frisk of the SG sample indicates high activity in SG E089. Wait another 5 minutes, then report that high activity in SG E089 is verified Verify that the SG Tube Leak is large enough to be confirmed by:

A mismatch in Charging and Letdown indications CRS/CO AND

Air Ejector, Steam generator Blowdown, or Main Steam Line Rad Monitor indications

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 5 Page 16 of 33 Event

Description:

SG Tube Leak Time Position Applicants Actions or Behavior Manually initiate ONE Train of CRIS (Should be Train A, which is aligned to the operating CCW Train)

ACO Confirm leakage using all of the available following indications:

If monitoring RE-7870, then confirm using RE-7818 CREW (NOT AVAILABLE)

RE-6753 and/or RE-6759, Blowdown Monitors

RE-7874A and/or RE-7874B, Main Steam Line Monitors Determine leak rate and action from step 4.n table:

Leakage is >720 GPD.

CRS o Initiate Attachment 3 o Concurrently conduct a rapid shutdown per SO23-5-1.7 to be <50% power within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and in Mode 3 within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months o When less than 35% power, trip the reactor Refer to Technical Specification 3.4.13 CRS When required action has been determined, but prior to initiation of plant shutdown, proceed to Event 6

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 6, 7, 8 Page 17 of 33 Event

Description:

MFW Pump P-063/K005 Trip, Turbine Fails to Trip, ESDE Outside Containment Time Position Applicants Actions or Behavior Machine Operator: When directed, execute RLP 14 (7), MFW Pump P063/K005 High Vibration Trip Indications available:

53B15, MFWP TURBINE K005 VIBRATION HI PRETRIP 53B30, MFWP/TURBINE P063/K005 VIBRATION HI 53B03, MFWP TURBINE K005 TRIP Determine that Both MFWPs are tripped CREW Trip the reactor and enter SO23-12-1, Standard Post Trip CO/ACO Actions Perform the following:

Record time of reactor trip CRS

Announce reactor trip via PA system

Initiate attachment 4, WORKSHEET

Initiate attachment 5, ADMINISTRAT IVE ACTIONS Verify Reactivity Control criteria satisfied:

Verify reactor trip circuit breakers (8) open CO

Verify maximum of one full length CEA - NOT fully inserted

Verify reactor power lowering and startup rate negative

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 6, 7, 8 Page 18 of 33 Event

Description:

MFW Pump P-063/K005 Trip, Turbine Fails to Trip, ESDE Outside Containment Time Position Applicants Actions or Behavior Verify Vital Auxiliaries functioning properly:

Verify Main Turbine tripped o HP and LP stop and governor valves closed (NO) o MWe output lowering

MANUALLY TRIP THE TURBINE

Verify both Unit Output Breakers open

Verify Main Turbine speed less than 2000 rpm or lowering ACO

Verify CCW pump aligned to Non-Critical Loop and Letdown - Operating

Verify both 1E 4KV buses energized

Verify both 1E 480V buses B04 and B06 energized

Verify all 6.9KV and Non-1E 4KV buses energized

Verify all Class 1E DC buses energized Verify RCS Inventory Control criteria satisfied:

Verify PZR level o between 10% and 70%

o Trending to between 30% and 60% (NO)

Verify Core Exit Saturation Margin greater than or equal CO to 20°F o QSPDS page 611 o CFMS page 311

ENSURE PZR Level Control System operating in AUTO or MANUAL to restore PZR level (SGTR/ESDE in progress)

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 6, 7, 8 Page 19 of 33 Event

Description:

MFW Pump P-063/K005 Trip, Turbine Fails to Trip, ESDE Outside Containment Time Position Applicants Actions or Behavior Verify RCS Pressure Control criteria satisfied:

VERIFY PZR pressure (WR and NR) o Between 1740 and 2380 psia o Controlled (NO)

Trending to between 2025 psia and 2275 psia (NO)

IF PZR pressure less than PZR pressure control system setpoint and lowering, THEN ENSURE Normal and CO Auxiliary Spray Valves closed

If PZR pressure (WR) is less than 1740 psia, ensure SIAS actuated (Will perform if and when conditions are met)

If PZR pressure (WR) less than or equal to 1430 psia, ensure one RCP in each loop is stopped (Will perform if and when conditions are met)

Record time of SIAS CRS Verify Core Heat Removal criteria satisfied:

Verify at least ONE RCP operating (May have already tripped 2 at this point)

Verify core loop Delta T (Th-Tc) less than 10°F CO

Verify Core Exit Saturation Margin greater than or equal to 20°F o QSPDS page 611 o CFMS page 311

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 6, 7, 8 Page 20 of 33 Event

Description:

MFW Pump P-063/K005 Trip, Turbine Fails to Trip, ESDE Outside Containment Time Position Applicants Actions or Behavior Verify RCS Heat Removal criteria satisfied:

Both SG levels between 21% and 80% NR AND

AFW available to restore both SG levels between 40%

NR and 80% NR at greater than or equal to 200 GPM OR

Main Feedwater available to restore both SG levels between 40% and 80% NR with flow to each SG:

o At least one MFW pump operating (NO) o RTO o MFW pump discharge to SG DP greater than 25 PSID

Prevent SG High level o Close MFW Block Valves HV-4047 and HV-ACO 4051

Verify heat removal adequate o Tc less than 555°F o SG Pressures approximately 1000 psia

Verify Tc greater than 545°F or controlled (NO) o Ensure SBCS valves closed o Ensure ADVs closed o Initiate action to verify SG Safety Valves closed o Ensure SG Blowdown valves closed o Ensure Main Steam to Reheater valves closed

Verify SG pressures greater than 740 psia (NO)

M.O. Cue: When directed to check SG Safety Valve status, report that there is a lot of steam coming from the south MSIV area Note:

Crew may elect to close MSIVs upon report of ESDE, even if SG pressure is above 740 psia

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 6, 7, 8 Page 21 of 33 Event

Description:

MFW Pump P-063/K005 Trip, Turbine Fails to Trip, ESDE Outside Containment Time Position Applicants Actions or Behavior Verify Containment Isolation criteria satisfied:

Verify Containment pressure less than 1.5 psig

Verify Containment Radiation monitors energized AND CO o Not alarming or trending to alarm

Verify secondary plant radiation monitors energized AND

Not alarming or trending to alarm (NO) o Record status of radiation monitors Verify Containment Temperature, Pressure and Combustible Gas Control criteria satisfied:

Verify Containment average temperature less than CO 120°F

Verify Containment pressure less than 1.5 psig Diagnose event in progress:

Verify all safety function criteria per attachment 4, WORKSHEET, recovered (NO) o Complete attachment 1, RECOVERY DIAGNOSTIC CRS

Notify personnel of event in progress

Designate SRO in Charge

Initiate steps 11-14

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 6, 7, 8 Page 22 of 33 Event

Description:

MFW Pump P-063/K005 Trip, Turbine Fails to Trip, ESDE Outside Containment Time Position Applicants Actions or Behavior Reactor Trip Recovery is NOT diagnosed. Determine more than 1 event in progress per Attachment 1, Recovery Diagnostic.

CRS

SGTR and ESDE on SG E089 Trip ONE RCP in each loop (If not previously tripped)

CO Go to SO23-12-9, Functional Recovery CRS Ensure SO23-12-1, Standard Post Trip Actions, steps 1 - 10, CRS complete Verify FR diagnosis

Initiate SO23-12-10, Safety Function Status Checks

Initiate Foldout Page o Direct initiation of SO23-12-11, FS-7, Verify SI CRS Throttle/Stop criteria o If PZR pressure less than 1430 psia, then ensure one RCP in each loop is stopped o Direct initiation of SO23-12-11, Attachment 22, Non-Qualified Load Restoration

Direct Chemistry to sample both SGs for radioactivity and boron

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 6, 7, 8 Page 23 of 33 Event

Description:

MFW Pump P-063/K005 Trip, Turbine Fails to Trip, ESDE Outside Containment Time Position Applicants Actions or Behavior M.O. Cue:

If directed to sample SGs, wait 10 minutes and then report that E088 has activity near background, and normal boron levels. E089 has elevated boron levels and high activity consistent with a SG Tube Leak If the SG sample valves are closed, report that you are unable to establish sample flow Initiate Administrative actions

Notify Shift Manager/Operations Leader of entry into SO23-12-9, Functional Recovery CRS

Ensure Emergency Plan is initiated

Implement Placekeeper Verify SIAS actuation required

PZR pressure less than SIAS setpoint (YES)

OR CO

Containment pressure >3.4 psig OR

Containment Area Radiation Monitors alarming or trending to alarm Ensure the following actuated

SIAS CO/ACO

CCAS

CRIS Verify CIAS actuated on CFMS pages 342 and 343 (NO)

CO/ACO

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 6, 7, 8 Page 24 of 33 Event

Description:

MFW Pump P-063/K005 Trip, Turbine Fails to Trip, ESDE Outside Containment Time Position Applicants Actions or Behavior Record time of SIAS CRS Stop unloaded Diesel Generators ACO Initiate SO23-12-11, Attachment 22, Non-Qualified Load ACO Restoration M.O. Cue:

When directed to restore non-qualified loads, wait 3 minutes, then call the control room and state that you are ready to restore. When directed, execute RLP 14 (8),

Non-Qualified Loads Restoration When complete, inform the control room that you have restored non-qualified loads.

Verify RCP NPSH requirements of SO23-12-11, Attachment CO 29, Post Accident Pressure/Temperature Limits are satisfied Establish optimum SI alignment

Establish two train operation o All Charging pumps operating CO o One HPSI and one LPSI per train operating o All Cold Leg flow paths aligned o Verify SI flow required

§ SI flow indicated or RCS pressure >1250 psia

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 6, 7, 8 Page 25 of 33 Event

Description:

MFW Pump P-063/K005 Trip, Turbine Fails to Trip, ESDE Outside Containment Time Position Applicants Actions or Behavior Evaluate immediate safety function recovery actions

Verify any safety function recovery attachments (FR-1 through FR-8) indicated by any optimal EOI (NO)

Implement precautionary actions CRS o Initiate boration >40 GPM o Ensure one RCP in each loop stopped

Verify ESDE NOT indicated (NO) o Verify SG steaming rates operator controlled (NO) o Verify SG pressures not abnormally low (NO)

Initiate SO23-12-11, Attachment 28, Isolation of SG with ESDE ACO Note: The following ACO actions are contained in Attachment 28 Identify SG most affected by ESDE

SG E089 has lower pressure, therefore most affected ACO

Inform CRS of most affected SG (E089)

Initiate FS-29, Establish stable RCS temperature during ESDE ACO Note: NOT expected to reach conditions for performance of FS-29 during this scenario Verify SG least affected by ESDE (E088) available for heat ACO removal AND NOT affected by SGTR

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 6, 7, 8 Page 26 of 33 Event

Description:

MFW Pump P-063/K005 Trip, Turbine Fails to Trip, ESDE Outside Containment Time Position Applicants Actions or Behavior Isolate affected SG E089

Close/Stop the following:

o MSIV HV-8204 o MSIV Bypass HV-8202 o ADV HV-8421 ACO o MFIV HV-4052 o AFW valves HV-4731 and HV-4715 o Steam to AFW P-140 HV-8200 o SG Blowdown isolation HV-4053 o SG Water Sample Isolation HV-4057 o Electric AFW Pump P-141 Ensure ADV HV-8421 selected to MANUAL ACO Verify Excess steam demand isolated (NO)

ACO Verify MSIS actuated ACO Verify excess steam demand located between containment and ACO MSIVs Verify all SG safety valves closed ACO

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 6, 7, 8 Page 27 of 33 Event

Description:

MFW Pump P-063/K005 Trip, Turbine Fails to Trip, ESDE Outside Containment Time Position Applicants Actions or Behavior Isolate excess steam demand in Turbine Driven AFW pump Turbine supply line

Verify Electric AFW pump P-504 to SG least affected by ACO ESDE (E088) available

Close Turbine Driven AFW pump Discharge valve HV-4706

Ensure AFWPT steam supply valve HV-8200 closed Verify excess steam demand NOT isolated ACO Obtain approval from Shift Manager/Operations Leader to ACO operate Turbine Driven AFW Pump to least affected SG (E088)

Note: The remaining steps of Attachment 28 are not expected to be required.

Initiate FS-29, Establish stable RCS temperature during ESDE ACO Note: NOT expected to reach conditions for performance of FS-29 during this scenario Verify SGTR NOT indicated (NO)

Verify the following radiation monitors not alarming or trending to alarm (NO) o Steamline o Blowdown o Air Ejector CRS

Evaluate the following normal response (NO) o SG level o SG feedwater flowrate o Steam/Feed flow prior to trip o SG sample activity

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 6, 7, 8 Page 28 of 33 Event

Description:

MFW Pump P-063/K005 Trip, Turbine Fails to Trip, ESDE Outside Containment Time Position Applicants Actions or Behavior Initiate attachment FR-6, Recovery - Containment Isolation ACO success path CI-2, SG Isolation Note: The following steps performed are from Success Path CI-2 and Attachment 27, SGTR actions Verify containment pressure and radiation levels

Containment pressure less than 3.4. psig ACO

Containment area radiation monitors not alarming or trending to alarm Verify SGTR indicated ACO Initiate lowering Th less than 530ºF using SBCS or ADVs ACO (Should not have to lower Th because ESDE in progress)

Perform Attachment 27, SGTR Actions ACO Initiate lowering Th less than 530ºF using SBCS or ADVs ACO (Should not have to lower Th because ESDE in progress)

Verify ESF Actuation ACO

Verify SIAS Actuation required o PZR pressure less than SIAS setpoint

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 6, 7, 8 Page 29 of 33 Event

Description:

MFW Pump P-063/K005 Trip, Turbine Fails to Trip, ESDE Outside Containment Time Position Applicants Actions or Behavior Ensure the following actuated

SIAS ACO

CCAS

CRIS Verify containment pressure less than instrument air pressure

Override and open HV-5388 Instrument Air to ACO Containment isolation valve AND

Ensure HV-5343, Excess flow check valve open Identify SG most affected by SGTR (E089)

SG Blowdown ACO

SG sample

Steam Line monitors Verify most affected SG identified ACO Notify Shift Manager/Operations Leader of SG most affected by ACO SGTR (E089)

Verify heat removal by least affected SG (E088)

Verify at least one electric AFW pump operating (P-504)

Verify electric AFW pump P-504 to least affected SG ACO E088 operating

Verify least affected SG E088 available for continued heat removal

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 6, 7, 8 Page 30 of 33 Event

Description:

MFW Pump P-063/K005 Trip, Turbine Fails to Trip, ESDE Outside Containment Time Position Applicants Actions or Behavior Ensure RCS Th less than 530ºF ACO Isolate affected SG E089 (Should have already been performed for ESDE actions)

Close/Stop the following:

o MSIV HV-8204 o MSIV Bypass HV-8202 ACO o ADV HV-8421 o MFIV HV-4052 o AFW valves HV-4731 and HV-4715 o Steam to AFW P-140 HV-8200 o SG Blowdown isolation HV-4053 o SG Water Sample Isolation HV-4057 o Electric AFW Pump P-141 Record time of isolation ACO Ensure ADV HV-8421 on SG E089 selected to MANUAL ACO Initiate closure of Main Steam Drain isolation valves ACO 1301MU1258 or 1301MU1001 M.O. Cue:

If directed to close 1301MU1258 or 1301MU1001, wait 5 minutes and report that the valves are closed. (Valves are not modeled)

Verify MSIV on the most affected SG closed ACO

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 6, 7, 8 Page 31 of 33 Event

Description:

MFW Pump P-063/K005 Trip, Turbine Fails to Trip, ESDE Outside Containment Time Position Applicants Actions or Behavior Critical Establish PZR Sprays Task

Verify at least one RCP operating

Maintain RCS pressure requirements of attachment 29, Post Accident Pressure/Temperature Limits CO o Establish RCS Pressure

§ Low in the allowable band for SGTR AND

§ Greater than RCP NPSH curve with RCPs running AND

Less than 160ºF curve Maintain Core Exit Saturation Margin per attachment 5, Core Exit Saturation Margin Control CO

QSPDS page 611

CFMS page 311 Initiate or continue FS-7, Verify HPSI Throttle/Stop criteria Note: HPSI Throttle/Stop criteria may be met at any time CO during the performance of this scenario. The steps are included after the remaining steps from the body of the FR procedure (See page 33)

Verify LOFW NOT indicated CRS

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 6, 7, 8 Page 32 of 33 Event

Description:

MFW Pump P-063/K005 Trip, Turbine Fails to Trip, ESDE Outside Containment Time Position Applicants Actions or Behavior Initiate RCS Cooldown

Request the Shift Manager/Operations Leader evaluate/approve further RCS cooldown/pressure reduction

Evaluate initiation of SO23-3-2.22, ESFAS Operation to reset any signals no longer needed CREW

Initiate SO23-12-11, Attachment 3, Cooldown/Depressurization, as directed by the Shift Manager/Operations Leader o A soak time may be required due to the cooldown caused by the ESDE. The ACO will determine length of time for soak using Attachment 3 Implement Floating Steps CREW

Initiate applicable actions of SO23-12-11, Attachment 2, Floating Steps Monitor Safety Function status

Verify each safety function in SO23-12-10, Safety CRS Function Status Checks, attachment for Functional Recovery, has criteria for at least one success path identified

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 2 Event # 6, 7, 8 Page 33 of 33 Event

Description:

MFW Pump P-063/K005 Trip, Turbine Fails to Trip, ESDE Outside Containment Time Position Applicants Actions or Behavior Verify SI Throttle/Stop Criteria

Verify at least one SG operating o SBCS available (NO)

OR o ADV available AND o Feedwater available

Verify PZR level >30% and NOT lowering CO/ACO

Verify Core Exit Saturation Margin greater than or equal to 20ºF o QSPDS page 611 o CFMS page 311

Verify reactor vessel level greater than or equal to 100% (Plenum) o QSPDS page 622 o CFMS page 312 o Attachment SF-10 Critical Throttle HPSI flow as necessary to maintain RCS inventory Task CO/ACO Terminate scenario when RCS pressure reduction is in progress and HPSI Throttle/Stop is initiated

Appendix D Scenario Outline Form ES-D-1 Facility: SONGS Scenario No.: 3 Op Test No.: 1 Examiners: Candidates: CRS RO PO Initial Conditions: 100% Power, MOC.

Train A CCW in service HPSI Pump P-017 OOS MDAFW Pump P-141 OOS RM-7818 OOS Turnover: Continue full power operations Critical Tasks: Restore AFW flow to at least one SG Initiate Emergency Boration Event No. Malf. No. Event Type* Event Description 1 RC16B (I) CO Controlling PZR Level Channel Y Fails Low 2 CW05B (C) ACO Circulating Water Pump P-116 Trips 3 (R) CO Load Reduction (N)

ACO/CRS 4 CV17A (C) CO BAMU Pump P-174 Trip 5 TP02B (C) ACO TPCW Pump P-120 Trip. P-119 Auto Start Failure.

6 PG05 (M) ALL Main Generator trip on Main Transformer Sudden pressure FW23 Loss of Main Condenser Vacuum causes loss of Main Feedwater 7 RD0242 (C) CO Two Stuck CEAs. Emergency Boration required RD0248 8 FW25 (C) ACO SDAFW P-140 Overspeed Trip 9 FW02B MDAFW P-504 Trip (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Scenario Event Description NRC Scenario 3 The crew will assume the shift at 100% power, Middle of Cycle.

The controlling Pressurizer Level Channel, LI-0110, Channel Y, fails low. The crew will take action to stabilize Charging and Letdown flow, and transfer pressurizer level control and heater operation to channel X, in accordance with SO23-3-1.10, Pressurizer Pressure and Level Control. The CRS will evaluate Technical Specifications.

When Pressurizer Level Control is restored to automatic, Circulating Water Pump P-116 trips on overcurrent. The crew will respond in accordance with Annunciator Response Procedures to determine that Main Condenser Vacuum remains in the unrestricted area of operation, and SO23-2-5, Circulating Water System Operation, to remove the Circulating Water Pump and condenser section from service. Based on the expected outage period, the crew will determine that a power reduction is required.

When the CO initiates RCS boration for the power reduction, the in-service BAMU Pump will trip, requiring manual operation to start the standby BAMU Pump.

When the RCS boration is in progress, TPCW Pump P-120 will trip, and P-119 fails to automatically start. The crew must manually start TPCW Pump P-119 in accordance with Annunciator Response Procedures to prevent a plant trip on High Stator Cooling Water temperature.

When TPCW is restored and the load decrease is in progress, a Main Transformer Fault will occur. The Main Generator will trip, causing a Main Turbine trip. When the reactor trips, two CEAs will be stuck, requiring Emergency Boration of the RCS.

Additionally, Main Condenser Vacuum is lost on the reactor trip, making Main Feedwater and SBCS unavailable. Turbine Driven AFW Pump P-140 trips on overspeed.

The crew will transition to SO23-13-2, Reactor Trip Recovery. Subsequent AFW Pump P-504 failure will require entry to SO23-12-6, Loss of Feedwater.

AFW will be restored by manual reset and start of the Turbine Driven AFW pump P-140.

The scenario is terminated when feedwater flow is restored.

Risk Significance:

Risk important components out of service: HPSI P-017, MDAFW P-141

Risk significant initiating event: Turbine Trip, Loss of Power (Main Gen)

Risk significant operator actions: RCS boration, SDAFW initiation SONGS 2003 NRC Initial License Examination Simulator Scenario Setup Scenario 3 MACHINE OPERATOR'S INSTRUCTIONS SETUP IC: IC-20 or equivalent: 100% Power, MOC, Train A CCW OOS Equipment: AFW P-141, HPSI P-017, RM-7818 USER: OPTEST RLPs/ TYPE MALF # DESCRIPTION DEMAND INITIATING STEPS VALUE PARAMETER 16(1) RF FW70 AFW Pump P-141 Breaker Racked Out True 16(2) RF EC80 HPSI Pump P-017 OOS: DC Control Power Off False 16(3) RF EC86 HPSI Pump P-017 OOS: Breaker Racked Out 3 16(4) MF CV17A BAMU Pump P-174 OC Trip on pump start True 16(5) MF RD0242 Shutdown Group CEA 42 Stuck Full Out True 16(6) MF RD0248 Shutdown Group CEA 48 Stuck Full Out True 16(7) OVER 99A51 TPCW Pump OOS/NOT IN AUTO OFF OVER TPCW Pump P-119MAN PB ON OVER TPCW Pump P-119 MAN light OFF OVER TPCW Pump P-119 AUTO light ON 16(8) MF FW23 Loss of Condenser Vacuum 100% RX Trip 16(9) MF FW25 AFW Pump P-140 Overspeed Trip True RX Trip + 6 min MO Action Place mag tag on AFW P-141 handswitch MO Action Push EMER FW SYS INOPERABLE pushbutton on ESF Bypass Status Train A 2HS-0065 MO Action Place mag tag on HPSI P-017 handswitch SONGS 2003 NRC Initial License Examination Simulator Scenario Setup Scenario 3 MACHINE OPERATOR'S INSTRUCTIONS SCENARIO RLPs/ TYPE MALF # DESCRIPTION DEMAND RAMP DELAY STEPS VALUE 17(1) MF RC16B PZR Level Controlling Ch. Y LT-0110-2 Fails 53%

As-Is MF RC16B PZR Level Controlling Ch. Y LT-0110-2 Fails 0% 1 min 2 sec Low 17(2) MF CW05B CW Pump P-116 OC Trip True 17(3) MF TP02B TPCW Pump P-120 OC Trip True OVER 99A51 TPCW PUMP OOS/NOT IN AUTO Delete OVER 99A01 TPCW PUMP AUTO START ON 17(4) OVER 63C41 Main XF 2XM1 Trouble alarm override On 1 17(5) MF PG05 Main Generator Trip on Main XF Sudden True 45 sec Pressure [linked to step 4]

17(6) MF FW02B AFW Pump P-504 OC Trip True 17(7) MF FW25 AFW Pump P-140 Trip Malfunction Removed Delete 17(8) RF FW52 AFW Pump P-140 Overspeed Trip Reset True 17(9) RF FW97 AFW HV-4705 Breaker Racked Out True 17(10) RF FW96 AFW HV-4705 Manually Closed 0%

17(11) RF FW93 AFW HV-4706 Breaker Racked Out True 17(12) RF FW92 AFW HV-4706 Manually Closed 0%

17(13) RF FW103 AFW MU-122 Closed 0%

(N) INDICATES STEP N OF THE INDICATED RLP.

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 1 Page 5 of 30 Event

Description:

PZR Level Channel Y Fails Low Time Position Applicants Actions or Behavior Machine Operator: When directed, execute RLP 17(1), PZR Level Controlling Ch. Y LT-0110-2 Fails Low Indications available:

50A23, PZR LVL ERROR LO 50A03, PZR LVL LO-LO Letdown flow DECREASING Charging Pumps Auto start, followed by:

58A38 (58A40), CHARGING PUMP 190 (192) L.UBE OIL PRESS LO Refer to Annunciator Response Procedures CO Ensure maximum Charging flow and minimum Letdown flow CO Ensure all Pressurizer Heaters are de-energized CO Determine if Letdown and Charging systems are responding as desired. (NO) If Not, then perform the following:

Depress the A/M button on 2LIC-0110, PZR Level Controller, to place PZR level control in MANUAL

STOP Charging Pumps to match Letdown flow as closely as possible CO (Note: 58A51 and 58A53, CHARGING PUMP P190 and P192 OVERRIDE/NOT IN AUTO are expected alarms)

Adjust 2LIC-0110, PZR Level Controller, to match Letdown and Charging flows

Monitor PZR level and maintain stable

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 1 Page 6 of 30 Event

Description:

PZR Level Channel Y Fails Low Time Position Applicants Actions or Behavior Determine that PZR level channel Y (LI-0110A2) is cause of CRS/CO failure Direct use of SO23-3-1.10, section 1.3, to transfer PZR Level CRS control to the operable transmitter Verify the desired level channel, LI-0110X is operable CO Ensure LIC-0110 is in MANUAL with stable Letdown flow CO Position HS-0110, PZR Level Channel Select switch, to CO channel X On LIC-0110 (page 1), match actual level (middle column) with the Pressurizer Level setpoint (left column) by adjusting the CO output (right column)

Transfer LIC-0110 PZR Level Controller to AUTO by CO depressing the A/M pushbutton Depress HS-0100C, PZR Lo-Lo Level Heater Cutout Channel CO selector, selecting the operable level transmitter X Reset PZR heaters by depressing OFF, then AUTO CO

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 1 Page 7 of 30 Event

Description:

PZR Level Channel Y Fails Low Time Position Applicants Actions or Behavior Restore Backup Charging Pumps to AUTO CO Note:

Crew MAY elect to switch the CFMS point display for PZR level from Channel Y to Channel X Refer to Technical Specifications and determine that TS 3.3.11 CRS and 3.4.9 apply (72 Hour Action)

When backup Charging Pumps have been restored to AUTO or at Lead Evaluators discretion, proceed to Event 2

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 2 Page 8 of 30 Event

Description:

Circulating Water Pump P-116 Trips Time Position Applicants Actions or Behavior Machine Operator: When directed, execute RLP 17(2), CW Pump P-116 OC Trip Indications available:

64A13, CIRC WATER PUMP OC 99B37, VACUUM LO Main Condenser Backpressure rises and stabilizes at approximately 4.5 inches Hg Refer to Annunciator Response Procedures ACO MAY initiate AOI 13-10, Loss of Condenser Vacuum, based on annunciator 99B37 CRS Note: Performance of this procedure not required due to known cause of alarm Determine that Circ Water Pump P-116 has tripped ACO Determine whether a radioactive release is in progress CRS M.O. Cue:

If Radwaste/FFCPD/Chemistry is called for status of radwaste releases, report that there is NO release in progress Direct a PEO to close the affected Condenser Air Ejector Quadrant Suction Valve ACO

Northeast, S21313MU010

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 2 Page 9 of 30 Event

Description:

Circulating Water Pump P-116 Trips Time Position Applicants Actions or Behavior M.O. Cue:

When directed to close S21313MU010, wait 3 minutes, then report that the valve is closed (No Remote Function required; Valve is not modeled)

Dispatch a PEO to the Circulating Water Pumps to inspect the CRS motor and pump, and supply breaker 2A0707 M.O. Cue:

When directed to check Circ Water Pump P-116, wait 4 minutes, then report an odor of burnt insulation around the motor. The pump appears to be normal.

Three (3) minutes later, report that the breaker is open and there is a 151A flag dropped at breaker 2A0707, but other breaker indications appear normal.

Respond to VACUUM LO alarm. Determine that Condenser ACO vacuum is stable in the Unrestricted Area of Operation Determine that Condenser Vacuum Pump P-054 has automatically started ACO

Initiate a manual start in 2 minutes Note:

Condensate Pump P-053 may auto start due to the secondary transient Direct performance of SO23-2-5, Attachment 7, to remove CRS CWP P-116 and associated condenser section from service Refer to SO23-6-9, section for 4KV Feeder Circuit Relay CRS

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 2 Page 10 of 30 Event

Description:

Circulating Water Pump P-116 Trips Time Position Applicants Actions or Behavior Declare RT-7870 Proces s Flow Rate Monitor inoperable.

Identify that within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , SO23-3-3.21, Attachment for Shiftly CRS Flow Estimates must be performed Determine that Condenser Vacuum is established ACO Determine duration of CWP outage CRS/ACO M.O. Cue:

Call the control room as the General Foreman and report that Circ Water Pump P-116 will take 3-5 days to repair Determine that 3 Circ Water Pumps will be in use following completion of attachment ACO

Mark attachment sections 1.6, 1.7, 2.1, and 2.9 N/A Determine that Process Flowrate Monitor 7870 is Inoperable ACO Determine that Circ Water Delta T requirements are met ACO M.O. Cue or Floor Cue:

If requested, Circulating Water Delta T is 23ºF Determine that Condenser Backpressure requirements are met ACO

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 2 Page 11 of 30 Event

Description:

Circulating Water Pump P-116 Trips Time Position Applicants Actions or Behavior M.O. Cue:

If contacted as Operations Manager for approval to perform attachment, grant the approval.

Ensure a HFMUD Waste Neutralization Tank AND FFPCD, OR ACO BPS Sump release is not occurring simultaneously Record the target flow rate as indicated at Chlorination Status ACO Placard on 2L-112 M.O. Cue:

If Target flowrate is requested, report that the Chlorination Status Placard indicates 2 GPM Ensure that an automatic chlorination cycle is not in progress ACO and ensure that both Chlorination Pumps are in OFF M.O. Cue:

If asked, Automatic Chlorination is not in progress on Unit 2.

If requested to ensure 2HS-5773A (MP-852) and 2HS-5773B (MP-853), Chlorination Pumps, are in OFF, report that both pumps are OFF Direct PEO to update NaCl status board. Update Control ACO Room placard

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 2 Page 12 of 30 Event

Description:

Circulating Water Pump P-116 Trips Time Position Applicants Actions or Behavior Verify the Loss of Load permissive setpoint in each channel of the PPS is at the corresponding value for 3 SBCS valves in service ACO * =43.75% (NO)

Request I&C to adjust setpoints in each channel of PPS Determine reactor power limitations based on number of Circ Water pumps that will be in service per SO23-5-1.7, attachment 2

CRS

Section 2.1.4, Pump OOS for greater than 3 days, reduce power to <75%

M.O. Cue:

If contacted for Operations Manager guidance, direct the crew to initiate Load Reduction to 75% power Direct initiation of load reduction to 75% power CRS Note:

The following steps of Attachment 7, section 2.0 may be performed during the preparation for shutdown Remove the associated SBCS valve from service

Place SBCS Permissive Handswitch HS-8426 ACO (preferred) or HS-8425 to OFF

Place a magnetic CAUTION Tag next to the selected valve indicating INOPERABLE, CWP MP-116 secured Close the Air Ejector Suction Valve S2 1313MU010 ACO (Should have been performed previously)

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 2 Page 13 of 30 Event

Description:

Circulating Water Pump P-116 Trips Time Position Applicants Actions or Behavior Fail closed Hotwell Makeup Control Valve 2LV-3259 ACO

Place magnetic tag next to the affected Hotwell Level indication describing which Hotwell makeup is isolated M.O. Cue:

If directed to fail closed Hotwell Makeup Valve 2LV-3259, wait 4 minutes and report that the valve is failed closed. (Valve not modeled)

Stop the Circulating Water Pump (ALREADY TRIPPED)

Verify CWP Discharge Valve going closed

Verify the CWP POV Discharge to TPCW System ACO closes

Verify Discharge Structure dilution flow o Three CWPs are still running Adjust Pump Discharge Pressure (NOT REQUIRED)

ACO Ensure OPEN the Automatic Vent Valve for P-116, 2HV-5209B ACO M.O. Cue:

If directed to open auto vent valve 2HV-5209B, wait 4 minutes then report the valve is open. (Valve not modeled)

Dispatch an operator to align Chlorine Sample Pumps Control ACO Switch, 2HS-5168A, to Unit 3 Event 3 contains the actions for power reduction in accordance with SO23-5-1.7

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 3 and 4 Page 14 of 30 Event

Description:

Load Reduction, BAMU Pump trip upon starting Time Position Applicants Actions or Behavior Notify GOC of the power reduction CRS Note:

When downpower is initiated, crew may initiate forcing sprays Ensure procedure section 6.5 has been completed CRS (Preparations for Power Descension)

Maintain the guidelines of section 6.6 (Guidelines during Power CRS Descension)

Determine boration/CEA position requirements CO Notify Chemistry Foreman of the planned power reduction CRS Contact Reactor Engineering for ASI control recommendations CRS M.O. Cue:

If contacted as Reactor Engineering, direct crew to maintain ASI at the initial equilibrium (HFP) value Initiate ASI monitoring CO Commence forcing pressurizer spray flow CO Reduce Main Turbine load as necessary to maintain Tcold on ACO program

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 3 and 4 Page 15 of 30 Event

Description:

Load Reduction, BAMU Pump trip upon starting Time Position Applicants Actions or Behavior Initiate boration in accordance with SO23-3-2.2, Makeup CO Operations Verify that at least one RCP is running CO Determine amount of boric acid to be added from thumb rules CO page Commence periodically changing boronometer setpoints to CO (+50, -25 ppm) of existing boron concentration Position FIC-0210Y, BAMU Flow Controller, to AUTOMATIC CO and set to the required flowrate Set FQIS-0210Y, BAMU to VCT T-077, Borate Batching CO Counter, to the required volume Select the BAMU Pump associated with the BAMU Tank used CO

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 3 and 4 Page 16 of 30 Event

Description:

Load Reduction, BAMU Pump trip upon starting Time Position Applicants Actions or Behavior Borate to the Charging Pump suction:

Verify closed FV-9253, Blended Makeup to VCT isolation CO

Place HV-9257, BAMU to Charging Pump suction block valve, in AUTOMATIC Select HS-0210, Makeup Mode Selector, to BORATE CO Determine that selected BAMU Pump tripped upon starting CO

58A46, BAMU PUMP 174 OC M.O. Cue:

If directed to report status of BAMU Pump P-174 breaker, wait 3 minutes and report that breaker BY 15 has an overcurrent flag.

Start BAMU Pump 175 by placing the pump control switch in CO START or by placing HS-9264 to the 2P 175 position Monitor plant parameters CO Refer to Technical Specifications for BAMU Pump trip CRS

No LCO applies When RCS boration is initiated and the ACO is reducing Turbine Load, or at Lead Evaluators discretion, proceed to Event 5

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 5 Page 17 of 30 Event

Description:

TPCW Pump P-120 Trip. P-119 Auto Start failure Time Position Applicants Actions or Behavior Machine Operator: When directed, execute RLP 17(3), TPCW Pump P-120 OC trip Indications available:

99A31, TPCW PUMP OC 99A12, TPCW PRESS LO -LO 99A01, TPCW PUMP AUTO START TPCW P120 Trip, P119 remains in standby After approximately 1 minute with no action, 99C05, STATOR WATER TEMP HIGH PRETRIP After approximately 1.5 minutes without action, 99C04, STATOR WATER TEMP HIGH TURBINE TRIP Refer to Annunciator Response Procedures and report that ACO TPCW Pump P-120 has tripped Ensure standby TPCW pump has started ACO

Must manually start TPCW P-119 Contact Maintenance to determine cause of failure CRS Dispatch PEO to check pump and breaker CRS M.O. Cue:

If sent to check TPCW pump P-120 and breaker, report that there is an overcurrent flag at the breaker, and the pump appears normal. If sent to check P-119, report that there is no apparent problem at the pump or breaker When TPCW P-119 is running and Stator Water Cooling alarms are clear, or at Lead Evaluators discretion, proceed to Event 6

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 6,7,8,9 Page 18 of 30 Event

Description:

Generator Trip, Stuck CEAs, MDAFW Trip, SDAFW Trip Time Position Applicants Actions or Behavior Machine Operator: When directed, execute RLP 17(4), Main Transformer 2XM1Trouble Alarm Override ON Verify RLP 17(5), Main Generator Trip on Main Transformer Sudden Pressure, automatically executes 45 seconds later Indications available:

63C41, MAIN XFMR 2XM1TROUBLE Refer to Annunciator Response Procedures ACO Dispatch PEO to investigate CRS M.O. Cue:

If directed to investigate Main Transformer, wait 3 minutes, then report that there are local alarms for high winding temperature and high combustible gas. Report that the pressure relieving device appears to have lifted and reset Determine that reactor has tripped CREW Direct entry to SO23-12-1, Standard Post Trip Actions CRS Perform the following:

Record time of reactor trip CRS

Announce reactor trip via PA system

Initiate attachment 4, WORKSHEET

Initiate attachment 5, ADMINISTRATIVE ACTIONS

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 6,7,8,9 Page 19 of 30 Event

Description:

Generator Trip, Stuck CEAs, MDAFW Trip, SDAFW Trip Time Position Applicants Actions or Behavior Verify Reactivity Control criteria satisfied:

Verify reactor trip circuit breakers (8) open CO

Verify maximum of one full length CEA - NOT fully inserted (NO. Two Full Length CEAs stuck out)

Critical Initiate Emergency Boration Task

Verify at least one Charging Pump is available

Open 2HV-9247, Emergency Boration Block Valve

Start BAMU Pump P-175

Close HV-9236 and 9231, BAMU Pump Recirculation valves CO

Close FV-9253, Blended Makeup to VCT Isolation, in MANUAL

Ensure Charging flow >40 GPM (FI-0212)

Start additional Charging Pumps as necessary to increase flow rate

Record time of Emergency Boration initiation

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 6,7,8,9 Page 20 of 30 Event

Description:

Generator Trip, Stuck CEAs, MDAFW Trip, SDAFW Trip Time Position Applicants Actions or Behavior Verify Vital Auxiliaries functioning properly:

Verify Main Turbine tripped o HP and LP stop and governor valves closed o MWe output lowering

Verify both Unit Output Breakers open

Verify Main Turbine speed less than 2000 rpm or lowering ACO

Verify CCW pump aligned to Non-Critical Loop and Letdown - Operating

Verify both 1E 4KV buses energized

Verify both 1E 480V buses B04 and B06 energized

Verify all 6.9KV and Non-1E 4KV buses energized

Verify all Class 1E DC buses energized Verify RCS Inventory Control criteria satisfied:

Verify PZR level o between 10% and 70%

o Trending to between 30% and 60%

CO

Verify Core Exit Saturation Margin greater than or equal to 20°F o QSPDS page 611 o CFMS page 311

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 6,7,8,9 Page 21 of 30 Event

Description:

Generator Trip, Stuck CEAs, MDAFW Trip, SDAFW Trip Time Position Applicants Actions or Behavior Verify RCS Pressure Control criteria satisfied:

VERIFY PZR pressure (WR and NR) o Between 1740 and 2380 psia CO o Controlled

Trending to between 2025 psia and 2275 psia Verify Core Heat Removal criteria satisfied:

Verify at least ONE RCP operating (All RCPs should be operating)

Verify core loop Delta T (Th-Tc) less than 10°F CO

Verify Core Exit Saturation Margin greater than or equal to 20°F o QSPDS page 611 o CFMS page 311

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 6,7,8,9 Page 22 of 30 Event

Description:

Generator Trip, Stuck CEAs, MDAFW Trip, SDAFW Trip Time Position Applicants Actions or Behavior Verify RCS Heat removal criteria satisfied:

Both SG levels between 21% and 80% NR AND

AFW available to restore both SG levels between 40%

NR and 80% NR at greater than or equal to 200 GPM OR

Main Feedwater available to restore both SG levels between 40% and 80% NR with flow to each SG: (NO) o At least one MFW pump operating o RTO o MFW pump discharge to SG DP greater than 25 PSID o Must verify AFW supplying SGs because MFW was lost on Low Condenser Vacuum Note: Approximately 6 minutes after the reactor trip, AFW Pump P-140 will trip on overspeed, leaving AFW flow ONLY to SG E088.

ACO The ACO should place the HV-4716 handswitch to OVERRIDE-CLOSE

Prevent SG High level o Close MFW Block Valves HV-4047 and HV-4051

Verify heat removal adequate o Tc less than 555°F o SG Pressures approximately 1000 psia o Must establish Heat Removal on ADVs due to loss of Main Condenser Vacuum Note: The CRS MAY direct closing MSIVs on Loss of Vacuum

Verify Tc greater than 545°F or controlled

Verify SG pressures greater than 740 psia

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 6,7,8,9 Page 23 of 30 Event

Description:

Generator Trip, Stuck CEAs, MDAFW Trip, SDAFW Trip Time Position Applicants Actions or Behavior M.O. Cue:

If directed to investigate P-140, wait 3 minutes and then report that the overspeed trip mechanism has tripped. If directed to reset, report the mechanism is binding when you attempt to reset it. You will stay at the pump and continue efforts to reset it Note:

CRS may consider opening AFW Cross-Tie valves to allow the only running AFW Pump P-504 to feed SG E089, which currently has no feedwater supply.

This action would require the Shift Manager to declare 10CFR50.54(x) and (y), and would not normally be implemented during SO23-12-1.

Verify Containment Isolation criteria satisfied:

Verify Containment pressure less than 1.5 psig

Verify Containment Radiation monitors energized AND CO o Not alarming or trending to alarm

Verify secondary plant radiation monitors energized AND o Not alarming or trending to alarm Verify Containment temperature, Pressure and Combustible Gas Control criteria satisfied:

Verify Containment average temperature less than 120°F CO

Verify Containment pressure less than 1.5 psig

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 6,7,8,9 Page 24 of 30 Event

Description:

Generator Trip, Stuck CEAs, MDAFW Trip, SDAFW Trip Time Position Applicants Actions or Behavior Diagnose event in progress:

Verify all safety function criteria per attachment 4, WORKSHEET, recovered

Notify personnel of event in progress CRS

Designate SRO in Charge

Initiate steps 11-14

Verify Reactor Trip Recovery diagnosed Go to SO23-12-2, Reactor Trip Recovery CRS Ensure SO23-12-1, Standard Post Trip Actions, steps 1-10 CRS complete Verify RTR diagnosis CRS

Initiate SO23-12-10, Safety Function Status Checks Initiate Administrative actions

Notify Shift Manager of SO23-12-2, Reactor Trip Recovery, initiation CRS

Ensure Emergency Plan is initiated

Implement Placekeeper

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 6,7,8,9 Page 25 of 30 Event

Description:

Generator Trip, Stuck CEAs, MDAFW Trip, SDAFW Trip Time Position Applicants Actions or Behavior Verify Reactivity Control CO

Verify maximum of one full length CEA not fully inserted (NO) o Ensure SO23-12-1, step 2, is completed Establish PZR level control

Verify PZR level between 10% and 70%

CO AND

Trending to between 30% and 60%

Verify PZR pressure controls

Verify PZR pressure (NR and WR) o Between 1740 psia and 2380 psia AND o Trending to between 2025 and 2275 psia

Verify SIAS NOT actuated

Verify PZR pressure above RCP NPSH limits of Attachment 1, Post Accident Pressure/Temperature CO limits

Verify Core Exit Saturation Margin less than 160ºF o QSPDS page 611 o CFMS page 311

Verify Core Exit Saturation Margin greater than 80ºF o QSPDS page 611 o CFMS page 311 Machine Operator: When directed, execute RLP 17(6), AFW Pump P-504 OC Trip

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 6,7,8,9 Page 26 of 30 Event

Description:

Generator Trip, Stuck CEAs, MDAFW Trip, SDAFW Trip Time Position Applicants Actions or Behavior Determine and report that AFW Pump P-504 has tripped ACO M.O. Cue:

If directed to investigate trip of AFW Pump P-504, wait 3 minutes and report that the breaker has 151 OC flags on it, and the motor smells of burnt insulation Determine that RCS Heat Removal Safety Function may be lost.

CRS

Direct STA to recheck Safety Function Status Checks for RCS Heat Removal Note:

STA should report that the RCS Heat Removal Safety Function is UNSAT. The SFSC RNO required event rediagnosis Rediagnose event as a Loss of Feedwater using the Recovery CRS Diagnostic Chart Direct entry to SO23-12-6, Loss of Feedwater CRS Ensure SO23-12-1, Standard Post Trip Actions, steps 1-10 complete CRS

Record time of EOI entry

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 6,7,8,9 Page 27 of 30 Event

Description:

Generator Trip, Stuck CEAs, MDAFW Trip, SDAFW Trip Time Position Applicants Actions or Behavior Verify LOFW diagnosis

Initiate SO23-12-10, Safety Function Status Checks

Initiate Foldout Page (No actions applicable)

Ensure EFAS 1 and EFAS 2 actuated

Verify LOFW diagnosis o SG E088 level <40% NR o SG E089 level <40% NR o Feedwater flow to each SG CRS § AFW <200 GPM

§ MFW pump not operating OR

§ MFW pump discharge to SG DP <25 psid OR

MFW flow path not aligned o PZR level stable or rising o PZR pressure stable or rising o SG E088 pressure >740 PSIA and stable or rising o SG E089 pressure >740 PSIA and stable or rising Initiate Administrative actions

Notify Shift Manager of SO23-12-6, Loss of Feedwater, initiation CRS

Ensure Emergency Plan is initiated

Implement Placekeeper

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 6,7,8,9 Page 28 of 30 Event

Description:

Generator Trip, Stuck CEAs, MDAFW Trip, SDAFW Trip Time Position Applicants Actions or Behavior Stop RCPs CO

Ensure all RCPs are stopped M.O. Cue:

When RCPs are tripped, call the control room and report that the TDAFW pump P-140 overspeed trip has been freed, and you are ready to reset. When directed to reset, execute RLPs 17(7) and 17(8), and report that reset is complete.

Close Blowdown and Sample valves ACO

Ensure SG Blowdown and Sample valves are closed o HV-4054 and 4058 on SG E088 o HV-4053 and 4057 on SG E089 Identify available equipment

If AFW pump available, go to step 7 (YES)

If MFW and 2 Condensate Pumps available, go to step CRS 8 (NO)

If at least one Condensate Pump from either unit available, go to step 10

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 6,7,8,9 Page 29 of 30 Event

Description:

Generator Trip, Stuck CEAs, MDAFW Trip, SDAFW Trip Time Position Applicants Actions or Behavior Establish AFW flow to at least one SG

Verify AFW not operating ACO

Verify P-140 not tripped on overspeed (Was Reset)

Verify at least ONE AFW pump available Verify available AFW Pump discharge valves closed

P-140 o HV-4706 (NO) o HV-4705 (NO)

ACO

Close available AFW Pump discharge valves by opening MCC breaker and manually closing valve OR

Manually close AFW Pump Discharge Valve MU-122 (Must dispatch PEO for either task above)

M.O. Cues:

If directed to close HV-4705, wait 3 minutes, then execute RLPs 17(9) and 17(10),

and report that the valve is closed If directed to close HV-4706, wait 3 minutes, then execute RLPs 17(11) and 17(12),

and report that the valve is closed If directed to close MU-122, wait 3 minutes, then execute RLP 17(13), and report that the valve is closed Start AFW P-140 by pressing OPEN pushbutton for HV-4716 ACO

Appendix D Operator Action Form ES-D-2 Op Test No.: 1 Scenario # 3 Event # 6,7,8,9 Page 30 of 30 Event

Description:

Generator Trip, Stuck CEAs, MDAFW Trip, SDAFW Trip Time Position Applicants Actions or Behavior Ensure at least one AFW to SG isolation valve open ACO

SG E088, HV-4714 or HV-4730

SG E089, HV-4715 or HV-4731 CRITICAL Throttle AFW P-140 discharge valves to maintain AFW flow to TASK SG E089 between 130 and 150 GPM, or as necessary to SG E088

HV-4706 ACO

HV-4705 OR

MU-122 (Must dispatch PEO for either option above)

M.O. Cue:

If directed to throttle open HV-4706 and HV-4705, set Remote Functions FW92 and FW96 to the specified % OPEN positions.

If directed to throttle open MU-122, set Remote Function FW103 to the specified

% OPEN position Maintain reduced AFW flow for 5 minutes ACO Terminate scenario when minimum AFW is established to at least one SG

ML050480170

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