Text

08/2003 Draft Written Exam
	ML033430138
Person / Time
Site:	South Texas
Issue date:	09/09/2003
From:	Gody A; Operations Branch IV
To:	Sheppard J; South Texas
References
	50-498/03-301, 50-499/03-301, ES-301, ES-401-5 50-498/03-301, 50-499/03-301
	Download: ML033430138 (117)
	v • d • e

RO WRITTEN EXAM QUESTIONS ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 008.AA2.01 Importance Rating 3.9 Proposed Question:

1. Given the following:

Unit 1 was operating at steady-state 100% power

Reactor Trip and Safety Injection actuated from low pressurizer pressure

RCS pressure decreased rapidly to 1150 psig and is now increasing very slowly

Pressurizer level decreased to 8% initially and then increased rapidly to stabilize at 100%

Reactor Containment Building process radiation monitors are alarming Which ONE of the following Loss of Primary Coolant events is the cause for these indications?

A. Pressurizer surge line rupture B. Pressurizer spray line rupture C. Reactor head vent line rupture D. Incore lower guide tube rupture Proposed Answer: B Explanation:

Technical

Reference:

LOT501.13 Proposed references to be provided to applicants during examination:

Learning Objective: 92023 Question Source: Bank # STP-419 Modified New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 009.EK1.01 Importance Rating 4.2 Proposed Question:

2. A small break LOCA has occurred and SI injection is not adequate to remove all core decay heat. At what approximate value would the RCS cold leg temperatures be expected to stabilize, assuming a loss of offsite power occurs simultaneous to the LOCA?

A. 571oF B. 651oF C. 668oF D. 682oF Proposed Answer: A Explanation:

Natural circulation and steam release from the SG PORVs will be required to remove excess decay heat. SG PORV setpoint is 1225 psig (1240 psia). Tsat for 1240 psia is about 571 degrees-F.

Technical

Reference:

LOT202.01, Rev 9, (Pg 13); 0POP05-EO-EO00 Rx Trip or Safety Injection (step 7 note); Steam Tables Proposed references to be provided to applicants during examination:

Steam Tables Learning Objective: 84041 Question Source: Bank # STP-519 Modified New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 011.EA1.13 Importance Rating 4.1 Proposed Question:

3. Unit 1 is operating at 100% power when a Large Break LOCA occurs. Five minutes later, the Primary Operator notices the following:

ECW Pump 1B is running

ECW Train 1B Blowdown Isolation Valve is closed

ECW Train 1B Screen Wash Booster Pump is running

ECW Pump 1B Discharge Valve indicates intermediate position (red AND green lights lit)

ECW Trains A and C are operating normally

The yard watch reports the ECW Pump 1B Discharge Valve is 50% open Which ONE of the following is true concerning ECW Train 1B?

A. Safety Injection actuation has blocked the trip of the pump to allow the train to operate. The pump will continue to run even if the discharge valve is partially closed.

B. Safety Injection Train B was reset prior to the discharge valve reaching full open. The discharge valve will open fully when the control switch is taken to OPEN.

C. Safety Injection Train B did not actuate. Manually actuating Safety Injection will open the discharge valve fully.

D. ECW Pump 1B did not receive a start signal from the sequencer. The pump was running prior to the Large Break LOCA.

Proposed Answer: A Explanation:

Technical

Reference:

9E-EW01-01 Rev 8, 9E-EW04-02 Rev 5 Proposed references to be provided to applicants during examination:

Learning Objective: 91193 Question Source: Bank # STP-19 Modified New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5, 10 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 015/017.AA1.21 Importance Rating 4.4 Proposed Question:

4. Unit 2 is recovering from a Loss of Offsite Power with the following conditions:

Reactor is tripped

All Reactor Coolant Pumps (RCP) are off and cannot be started

The Primary Reactor Operator is directed to verify natural circulation cooling exists In which ONE of the following sets of conditions can natural circulation cooling be verified to exist?

Time Core Exit RCS TH (oF) TC (oF) S/G Press.

T/Cs (oF) Subcool- (psig) ing (oF)

A. 0400 560 36 557 536 916 0430 555 32 552 532 886 B. 0400 560 40 558 540 940 0430 560 36 557 528 830 C. 0400 560 42 557 536 916 0430 555 41 552 532 886 D. 0400 560 40 558 540 948 0430 564 43 560 544 980 Proposed Answer: C subcooling >35 deg; PSG , TH , and core exit T/Cs are decreasing; and Tc is at the saturation temperature for SG pressure Technical

Reference:

0POP05-EO-ES01 Rev 15 step 14 RNO, steam tables Proposed references to be provided to applicants during examination:

Steam Tables Learning Objective: 92169 Question Source: Bank # STP-12 Modified New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5 55.43

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 026.AK3.04 Importance Rating 3.5 Proposed Question:

5. Given the following conditions:

Unit 1 is in Mode 5

CCW Trains A and C are in service

CCW Train B is selected to STANDBY

ALL ECW Trains are in service CCW Pump A trips causing common header pressure to decrease to 70 psig. What is the effect on CCW Pump B? CCW Pump B will:

A. start ONLY if the mode selector switch is placed in run.

B. NOT start because ECW Trains A and C are still in service.

C. start because the common header pressure is less than the low-pressure setpoint.

D. NOT start because the common header pressure did not decrease to the low-pressure setpoint.

Proposed Answer: C Explanation:

A. INCORRECT - The pump will start if the mode select switch is placed in run, but will also start on low pressure.

B. INCORRECT - The CCW pump will start on either a low CCW header pressure or low pressure in two ECW trains.

C. CORRECT - Common header pressure is less than 76 psig and the train is selected to standby.

D. INCORRECT - The auto start setpoint is 76 psig.

Technical

Reference:

LOT 201.12.LP Rev 7 section 4.3.3.C Proposed references to be provided to applicants during examination:

Learning Objective: 57126 Question Source: Bank # STP-124 Modified New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7, 8 55.43

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 027.AK2.03 Importance Rating 2.6 Proposed Question:

6. The pressurizer master pressure controller has failed to zero output in AUTO.

With no operator action RCS pressure will:

A. Decrease to the Reactor Trip setpoint.

B. Increase to the Reactor Trip setpoint.

C. Stabilize at Program setpoint D. Cycle at the PORV setpoint.

Proposed Answer: D Explanation:

The master controller will close both spray valves and turn on all heaters, causing pressure to increase. PORV PCV-456 is controlled by a bistable not the master controller so that when pressure reaches 2235 psig it will open and control pressure.

Technical

Reference:

Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # STP-674 Modified New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5, 7 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 038.EA1.36 Importance Rating 4.3 Proposed Question:

7. A SGTR has occurred. The ruptured S/G has been isolated and the plant stabilized. The following conditions exist:

-Containment pressure is 6 psig.

-Containment radiation levels are 5 R/hr.

-Containment integrated radiation dose is 6 RADS.

STEAM GENERATOR PRESSURE STEAM LINE RADIATION A 970 PSIG 4.56E-02 B 820 PSIG 3.45E-02 C 910 PSIG 3.78E+02 D 770 PSIG 2.97E-02 Based on the above plant conditions, how far should the RCS be cooled down?

A. 471oF B. 477oF C. 486oF D. 492oF Proposed Answer: A Explanation:

Adverse Containment (>5psig) requires the number in brackets on step 7.a. of EOP based on the pressure in the ruptured SG (C=910 psig requires using the 900 psig row).

Technical

Reference:

0POP05-EO-EO30 Steam Generator Tube Rupture Proposed references to be provided to applicants during examination:

0POP05-EO-EO30 Steam Generator Tube Rupture: chart for step 7.a. (pg 12 of 40, rev.15)

Question Source: Bank # Modified New X Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 040.AK3.04 Importance Rating 4.5 Proposed Question:

8. 0POP05-EO-EO20, Faulted Steam Generator Isolation, step 4 ensures isolation of Main and Auxiliary Feedwater to the affected SG(s).

Which ONE of the following is the reason for the actions of this step?

A. Maintains at least two loops available for cooldown.

B. Maximizes cooldown capability of the non-faulted SG(s).

C. Allows identification of the faulted SG(s).

D. Minimizes the loss of feedwater inventory through the affected SG(s).

Proposed Answer: B Explanation:

Technical

Reference:

0POP05-EO-EO20 Rev 3; 148--00039, WOG ERG E-2 Faulted SG Isolation Rev 1A, page 30 Proposed references to be provided to applicants during examination:

Learning Objective: 81264 Question Source: Bank # STP-2 Modified New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 054.AK1.02 Importance Rating 3.6 Proposed Question:

9. The operators are responding to a loss of secondary heat sink event. All four SG wide range levels are below 9%. Feed and bleed is in effect and containment conditions are as follows:

-Containment pressure is 0.6 psig.

-Containment radiation levels are 0.5 R/hr.

-Containment integrated radiation dose is 0.6 RADS.

Which of the following conditions must be met to allow terminating the feed and bleed following restoration of Auxiliary Feedwater?

A. Core exit thermocouples must be less than 700oF B. All intact SG narrow range levels must be greater than 26%

C. At least one SG narrow range level must be greater than 5%

D. Total AFW flow must be greater than 576 gpm Proposed Answer: C Explanation:

Technical

Reference:

0POP05-EO-FRH1, Rev 8; WOG Background Document, FRH-0.1 Proposed references to be provided to applicants during examination:

Learning Objective: 83013 Question Source: Bank # STP-503 Modified New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 055.EK1.01 Importance Rating 3.3 Proposed Question:

10. During a loss of all AC while performing 0POP05-EO-EC00, Loss of All AC, E1C11 battery is carrying its design loads and emergency lighting.

Which ONE of the following is the MINIMUM time that E1C11 could be predicted to operate by design assuming the battery was fully charged initially?

A. 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months B. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months C. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months D. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Proposed Answer: A Explanation:

Technical

Reference:

Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # STP-915 Modified New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 8 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 056.AA1.09 Importance Rating 3.3 Proposed Question:

11. A LOOP has occurred while the plant had been operating at 75% power. Prior to the LOOP, the CCW pump configuration had been as follows:

-CCW Pump 1A: RUNNING; mode switch: RUN; Local/Remote Switch: Remote

-CCW Pump 1B: NOT running; mode switch: STANDBY; Local/Remote Switch: Local

-CCW Pump 1C: NOT running; mode switch: OFF; Local/Remote Switch: Remote Subsequent to proper response of the diesels and sequencers, the expected CCW Pump configuration should be:

A. CCW Pump 1A: RUNNING CCW Pump 1B: NOT Running CCW Pump 1C: NOT Running B. CCW Pump 1A: RUNNING CCW Pump 1B: RUNNING CCW Pump 1C: NOT Running C. CCW Pump 1A: RUNNING CCW Pump 1B: RUNNING CCW Pump 1C: RUNNING D. CCW Pump 1A: RUNNING CCW Pump 1B: NOT Running CCW Pump 1C: RUNNING Proposed Answer: D Explanation:

Local/Remote switch in Local bypasses ALL automatic start signals, including LOOP.

Technical

Reference:

LOT 201.12 Question Source: Bank # Modified New X Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 057.AA1.02 Importance Rating 3.8 Proposed Question:

12. In response to a loss of Distribution Panel DP001, 0POP04-VA-001 Loss of 120 VAC Class Vital Distribution directs the operator to maintain Pressurizer Level by:

A. maintaining Pressurizer Level control in automatic.

B. adjusting Excess Letdown flow and Seal Injection flow.

C. adjusting Excess Letdown flow only.

D. adjusting Seal Injection flow only.

Proposed Answer: B Explanation:

Technical

Reference:

0POP04-VA-001 Loss of 120 VAC Class Vital Distribution Addendum 2, Step 8 and Addendum 10 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # Modified New X Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 058.AA2.03 Importance Rating 3.5 Proposed Question:

13. Unit 1 is in Mode 5.

RCS Temperature: 170 oF

RCS Pressure: 380 psig

RHR Trains A and B in service A problem occurs causing the RCS temperature to decrease. The Primary RO observes:

¨ Train A RHR Heat Exchanger Bypass Valve (FCV-0851) is full closed

¨ Train A RHR Heat Exchanger Flow Control Valve (HCV-0864) is full open

¨ RHR Train B operating normally Which ONE of the following failures accounts for these indications?

A. Loss of 125 VDC Bus E1A11.

B. Loss of 125 VDC Bus E1D11.

C. Loss of 480 MCC E1B1.

D. Loss of Instrument Air to Containment.

Proposed Answer: A Explanation:

Technical

Reference:

0POP04-DJ-0001, R. 10 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # STP-358 Modified New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 062.AA2.04 Importance Rating 2.5 Proposed Question:

14. Emergency Diesel Generator 11(21) is operating in Test Mode when Jacket Water temperature reaches 175oF as a result of poor ECW flow to the Jacket Water Cooler. At this temperature, the system response will be:

A. the EDG will trip on high Jacket Water Temperature if engine speed is >280 rpm.

B. the EDG will trip on high Jacket Water Temperature if engine speed is <280 rpm.

C. the Jacket Water Three-Way Thermostatic Control Valve will bypass all flow to the Jacket Water Cooler.

D. the Jacket Water Three-Way Thermostatic Control Valve will direct all flow to the Jacket Water Cooler.

Proposed Answer: D Explanation:

Jacket Water Three-Way Thermostatic Control Valve modulates to control JW Temp.

between 165oF and 175oF ; the high JW Temp. trip is 205oF.

Technical

Reference:

LOT201.39 slide 120; 0POP02-DG-0001 page 22 of 127.

Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # Modified New X Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7, 8 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 065.AK3.08 Importance Rating 3.7 Proposed Question:

15. If an operator notices the Instrument Air (IA) system pressure is at 60 psig and lowering, he should:

A. Trip the Reactor in order to avoid a loss of pressure control as the Letdown Orifice Header Isolation Valve (FV-0011)

B. Trip the Reactor in order to prevent a loss of Heat Sink as the Feed Regulating Valves drift shut on loss of IA pressure.

C. Trip the Reactor in order to prevent a power excursion resulting from the change in feedwater temperature caused by loss of IA to the feedwater heater level control valves.

D. Trip the Reactor in order to prevent challenging the Main Steam Safety Valves as a result of MSIVs drifting closed on loss of IA pressure.

Proposed Answer: D Explanation:

Technical

Reference:

0POP04-IA-0001 Loss of IA, Addendum 7 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # Modified New X Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # E04.EK2.1 Importance Rating 3.5 Proposed Question:

16. Unit 1 is operating at 100% power with all systems in their normal lineup. A small RCS leak develops in the Chemical and Volume Control System (CVCS) with the following Control Room indications:

Pressurizer level indicates 50% and is decreasing

RCS pressure indicates 2220 psig and is stable

Containment pressure is normal

LETDN HX OUTLET PRESSURE PI-0135 indicates 0 psig

PRT PRESS HI alarm is illuminated

LETDN HX OUTL FLOW HI/LO alarm is illuminated

ERFDADS Points (2) CVCS LTDN AREA TEMP TRN HI are in alarm Considering these indications, which ONE of the following AUTOMATIC actions has taken place?

A. TCV-0143, Letdown Temperature Divert Valve, positioned to the VCT.

B. MOV-0023/0024, Letdown Line Containment Isolation Valves closed.

C. FV-0011, Letdown Header Orifice Isolation Valve closed.

D. PCV-0135, Letdown Pressure Control Valve opened.

Proposed Answer: B Explanation:

MOV-0023/24 are designed to automatically close on high room temperature for high energy line break accident (HELBA) protection. The question stem indicates there is a small RCS leak present in the CVCS, however, there are no direct indications of leak location. The student must determine leak location and corresponding automatic actions by evaluating the given indications relative to the answers.

Technical

Reference:

0POP04-CV-0004, Rev 2, Step 1 RNO d.; Logic 9-Z-42410, Rev 8 Learning Objective: 70174 Question Source: Bank # STP-22 Modified New Question History: Last NRC Exam 6/30/98 Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # E11.EA1.02 Importance Rating 3.5 Proposed Question:

17. The following have occurred:

LOCA outside containment

Transfer to Cold Leg Recirculation

Transition to 0POP05-EO-EC11, Loss of Emergency Coolant Recirculation 0POP05-EO-EC11 provides instructions to stop backflow from the RWST to the containment sump to conserve RWST inventory.

Per 0POP05-EO-EC11 which ONE of the following is the correct sequence to stop the backflow?

A. 1. Stop the LHSI, HHSI and CS Pumps

2. Close the Containment Sump Suction Valves

3. Open the RWST to SI Suction Header Valves

4. Open the SI Pump Mini Flow Valves

5. Start the LHSI, HHSI and CS Pumps as necessary B. 1. Stop the LHSI, HHSI and CS Pumps

2. Open the RWST to SI Suction Header Valves

3. Open the SI Pump Mini Flow Valves

4. Close the Containment Sump Suction Valves

5. Start the LHSI, HHSI and CS Pumps as necessary C. 1. Stop the LHSI, HHSI and CS Pumps

2. Open the RWST to SI Suction Header Valves

3. Close the Containment Sump Suction Valves

4. Open the SI Pump Mini Flow Valves

5. Start the LHSI, HHSI and CS Pumps as necessary D. 1. Stop the LHSI, HHSI and CS Pumps

2. Open the SI Pump Mini Flow Valves

3. Close the Containment Sump Suction Valves

4. Open the RWST to SI Suction Header Valves

5. Start the LHSI, HHSI and CS Pumps as necessary Proposed Answer: A Technical

Reference:

0POP05-EO-EC11 Rev 7, LOT 201.10, Rev 8 Learning Objective: 82598 Question Source: Bank # STP-18 Modified New Question History: Last NRC Exam 6/30/98 Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # E05.EA1.1 Importance Rating 4.1 Proposed Question:

18. A complete loss of all feedwater has occurred on Unit 1 in conjunction with a feedline break inside containment on SG A. The following plant conditions currently exist:

RCS Pressure 1900 psig and INCREASING

Core Exit TCs 578 °F and STABLE

RCS THOT 575 °F and STABLE

RCS Tavg 547 °F and STABLE

RCS TCOLD 520 °F and STABLE

Pzr Level 45% and SLOWLY INCREASING

Containment Pressure 12 psig and DECREASING

Containment Temperature 170 °F and STABLE

SG NR Levels A=0%, B=0%, C=0%, D=0%

SG WR Levels A=0%, B=30%, C=20%, D=25%

0POP05-EO-FRH1, Response to Loss of Secondary Heat Sink, has been entered and RCS Bleed and Feed has just been established. A report is received in the Control Room that the Turbine Driven Auxiliary Feedwater Pump is recovered and ready for use.

Which ONE of the following actions should be taken under these circumstances?

A. Ensure total feed flow to the intact SGs is > 576 pgm.

B. Feed SG A, B, C, AND D at a rate not to exceed 100 gpm until THOT is less than 550 °F.

C. Feed SG A, B, C, OR D at a rate not to exceed 100 gpm until WR level reaches 73%.

D. Maintain bleed and feed until THOT is less than 550 °F, then feed SGs as desired.

Proposed Answer: A Technical

Reference:

0POP05-EO-FRH1, R11 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # STP-225 Modified New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 K/A # 024.AK2.03 Importance Rating 2.6 Proposed Question:

19. Unit 1 was operating at 100% power with Boric Acid Pump 1A OOS for motor replacement. A feedwater control failure results in the crew manually tripping the unit. The crew has transitioned to 0POP05-EO-ES01, Reactor Trip Response. The following conditions exist:

2 Control Rods indicate 12 steps

1 Control Rod indicates 18 steps The Reactor Operator attempts to Emergency Borate, but Boric Acid Pump 1B fails to start.

The following indications are observed:

¨ Both pump status lights (Green & Red) are extinguished

¨ Bypass/Inop 4M05/C2 BA XFER PUMP 1B is illuminated Which ONE of the following PAIRS of Emergency Boration flowpaths are available to be used?

A. 1-CV-0221 Manual Alternate Immediate Borate & Emergency Boration Via Gravity Feed.

B. Emergency Boration from RWST & Emergency Boration Via Gravity Feed.

C. Emergency Boration Through Normal Boration Flowpath & Emergency Boration from RWST D. Emergency Boration Through Normal Boration Flowpath & 1-CV-0221 Manual Alternate Immediate Borate Proposed Answer: B Explanation:

Technical

Reference:

0POP04-CV-0003 Rev 5 Addenda 1-4 Proposed references to be provided to applicants during examination:

Learning Objective: 92108 Question Source: Bank # STP-86 Modified New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7, 10 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 K/A # 033.AK3.02 Importance Rating 3.6 Proposed Question:

20. Intermediate Range channel B instrument has failed high. The failed IR channel has been bypassed as directed by 0POP04-NI-0001 Nuclear Instrument Malfunction. A reactor shutdown was commenced and reactor power has just dropped below the P-6 setpoint on the operable IR channel. At this point, 0POP04-NI-0001 directs the operator to reset Source Range channels because:

A. Source Range channels automatically energize when an Intermediate Range Channel is bypassed during a Reactor Shutdown.

B. Source Range channels automatically energize when an Intermediate Range Channel drops below 10-10 amps during a Reactor Shutdown.

C. Source Range channels need to be manually energized if an Intermediate Range Channel stays above 10-10 amps during a Reactor Shutdown.

D. Source Range channels need to be manually energized if an Intermediate Range Channel is bypassed during a Reactor Shutdown.

Proposed Answer: C Explanation:

Technical

Reference:

0POP04-NI-0001 Nuclear Instrument Malfunction, Rev.10, pg 41 of 68 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # Modified New X Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 6, 10 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 K/A # 037.AA1.08 Importance Rating 3.3 Proposed Question:

21. In response to Charging flow unexpectedly GREATER THAN letdown flow coincident with increasing secondary system radiation, 0POP04-RC-0004, Steam Generator Tube Leakage, was implemented. 0POP04-RC-0004 directs that if VCT level cannot be maintained >15% by ...

A. adjusting CCP flow with CCP suction aligned to RWST, then trip the reactor and initiate SI.

B. adjusting CCP flow with CCP suction aligned to RWST, then increase letdown.

C. adjusting CCP flow with CCP suction aligned to VCT, then trip the reactor and initiate SI.

D. adjusting CCP flow with CCP suction aligned to VCT, then shift CCP suction to RWST.

Proposed Answer: C Explanation:

The reactor should be tripped if VCT level cannot be maintained via normal makeup.

Technical

Reference:

0POP04-RC-0004, Steam Generator Tube Leakage, step 6 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # Modified New X Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 K/A # 061.G2.3.4 Importance Rating 2.5 Proposed Question:

22. Area Radiation Monitor RE-8052 in the In-Core Instrumentation Room is alarming HIGH at 1200 mrem/hr. Local surveys have confirmed that this radiation level is accurate. Due to his expertise, Jim Neutron, who was a contractor until he was hired by STP a few months ago, will need to enter the area to conduct repairs. Jim is 52 years old, has a lifetime TEDE of 40 rem to date, and has already accumulated 3.6 rem TEDE this year, 360 mrem of which at STP. In accordance with 0PGP03-ZR-0050, Radiation Protection Program, Joes stay time for the job should be limited to_________ unless a Form 2 extension is approved.

A. 0 minutes B. 20 minutes C. 57 minutes D. 70 minutes Proposed Answer: B Explanation:

A Form 2 extension is required if a person is expected to exceed 4 rem TEDE for the year or 1.5 rem TEDE for the year at STP. Since Jim only has 400 mrem left until he exceeds 4 rem total for the year, he is contrained to that limit even though he has 1140 mrem left before exceeding the 1.5 rem at STP limit.

Technical

Reference:

0PGP03-ZR-0050, Radiation Protection Program Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # Modified New X Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10, 11, 12 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 K/A # 074.EK2.03 Importance Rating 4.0 Proposed Question:

23. 0POP05-EO-FRC1, "Response to Inadequate Core Cooling", has been entered due to a red path on Critical Safety Function status tree. Some conditions are:

-Containment Pressure = 9 psig

-Containment Radiation Levels = 5x103 rad/hr

-Containment Integrated Radiation Dose = 3.7x104 rad

-NR SG Levels all <2%

Step 9 directs recovery of SG levels by controlling AFW flow...

A. >576 gpm until NR SG levels >14% in at least one SG.

B. >576 gpm until NR SG levels >14% in all intact SGs.

C. >576 gpm until NR SG levels >34% in at least one SG.

D. >576 gpm until NR SG levels >34% in all intact SGs.

Proposed Answer: C Explanation:

34% is the target under adverse containment conditions (>5psig).

Technical

Reference:

0POP05-EO-FRC1, "Response to Inadequate Core Cooling" Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # Modified New X Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 K/A # 076.G2.4.10 Importance Rating 3.0 Proposed Question:

24. Plant conditions:

Operating in Mode 1 at 100% power.

CVCS Letdown Failed Fuel Monitor is in High Alarm.

Chemistry has determined that the inservice demineralizer is working properly.

Which ONE of the following operator actions is required per 0POP04-RC-0001, High Reactor Coolant System Activity?

A. Reduce power B. Isolate letdown C. Increase letdown to 220 gpm D. Initiate hourly sampling of the RCS Proposed Answer: C Explanation:

Technical

Reference:

0POP04-RC-0001 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # STP-958 Modified New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 K/A # E02.EK1.2 Importance Rating 3.4 Proposed Question:

25. A Small Break LOCA has occurred, primary plant conditions have been stabilized and SI has been terminated in accordance with 0POP05-EO-ES11, SI Termination. Operators have just restored MINIMUM charging flow and continue performing ES11 when the following conditions are identified:

RCS subcooling = 45°F and stable

Pressurizer level = 5% and stable

Containment Pressure = 1.5 psig

Containment Radiation Levels = 2x102 rad/hr

Containment Integrated Radiation Dose = 6.7x102 rad Which ONE of the following actions will the operators perform?

A. Increase charging flow to restore pressurizer level and continue with 0POP05-EO-ES11, SI Termination.

B. Operate SI pumps and continue with 0POP05-EO-ES11, SI Termination.

C. Operate SI pumps and transition to 0POP05-EO-EO10, Loss of Reactor or Secondary Coolant.

D. Manually initiate SI and transition to 0POP05-EO-EO00, Reactor Trip or Safety Injection.

Proposed Answer: A Explanation:

Technical

Reference:

0POP05-EO-ES11, Step 9 Proposed references to be provided to applicants during examination:

Learning Objective: 92226 Question Source: Bank # STP-416 Modified New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 K/A # E15.EK1.3 Importance Rating 2.8 Proposed Question:

26. Under what condition is entry into OPOP05-EO-FRZ2, Response to Containment Flooding, warranted?

A. Containment water level is less than 69 inches.

B. Containment Radiation is greater than 2.0 + 03E R/HR.

C. Containment Critical Safety function tree is in an Orange Condition.

D. Containment Pressure is greater than 9.5 psig.

Proposed Answer: C Explanation:

Technical

Reference:

POP05-EO-FRZ2 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # STP-1068 Modified New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 K/A # E08.EK3.3 Importance Rating 3.7 Proposed Question:

27. Procedure 0POP05-EO-FRP1, "Response to Imminent Pressurized Thermal Shock Condition," has a step to terminate safety injection flow. However, if the safety injection termination criteria are not satisfied, a reactor coolant pump should be started. What is the reason for starting an RCP in this condition?

A. Establishes forced flow to control the cooldown rate.

B. Allows RCS depressurization via the pressurizer spray nozzle.

C. Equalizes steam generator pressures to allow cooldown of all 4 loops.

D. Mixes the incoming SI water and the RCS water to raise the temperature of the water entering the downcomer.

Proposed Answer: D Explanation:

Technical

Reference:

POP05-EO-FRP1 background document Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # STP-1046 Modified New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5, 10 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 003.K4.07 Importance Rating 3.2 Proposed Question:

28. Which ONE of the following describes the RCP No. 2 Seal during normal at power operation?

A. A film riding seal with a leakoff flow rate of 3 gph to the RCDT.

B. A face rubbing seal with a leakoff flow rate of 3 gpm to the CCP suction.

C. A film riding seal with a leakoff flow rate of 400 cc/hr to the Containment Sump and 400 cc/hr to the RCDT.

D. A face rubbing seal with a leakoff flow rate of 3 gph to the RCDT.

Proposed Answer: D Explanation:

Technical

Reference:

LOT201.05, section 2.7.2 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # STP-146 Modified New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 3, 7 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 004.A4.18 Importance Rating 4.3 Proposed Question:

29. Which ONE of the following Emergency Boration Flowpaths and Flowrates meet the requirements of 0POP04-CV-0003, Emergency Boration?

A. Emergency Boration through MOV-0218 at 60 gpm B. Emergency Boration through Normal Boration (blender) Flowpath at 30 gpm C. Emergency Boration From RWST at 100 gpm D. Emergency Boration Via Gravity Feed at 35 gpm Proposed Answer: A Explanation:

Technical

Reference:

0POP04-CV-0003, R6 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # STP-273 Modified New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 3, 6, 10 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 005.K6.03 Importance Rating 2.5 Proposed Question:

30. Loss of one train of RHR would limit the capability of the RHR system to reduce the reactor coolant temperature under design conditions from...

A. 350oF to 212oF within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

B. 350oF to 212oF within 11 hours1.273148e-4 days 0.00306 hours 1.818783e-5 weeks 4.1855e-6 months .

C. 350oF to 150oF within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

D. 350oF to 200oF within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

Proposed Answer: B Explanation:

Technical

Reference:

STPEGS UFSAR 5.4.7.1, LOT201.09 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # Modified New X Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5, 8 55.43 Comments:

- NOTE** The numbers differ between the UFSAR and the LOT201.09 Training guide; UFSAR numbers were used in developing this question

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 005.A1.01 Importance Rating 3.5 Proposed Question:

31. Which ONE of the following describes the parameter(s) that are varied to control RCS cooldown rate when using RHR?

A. Both CCW flowrate and RHR flowrate passing through the RHR heat exchanger are varied.

B. CCW flowrate through the RHR heat exchanger is varied, while maintaining RHR flowrate constant.

C. RHR flowrate passing through the RHR heat exchanger is varied, while maintaining total RHR system flowrate constant.

D. Total RHR system flowrate is varied, while maintaining RHR flowrate through the RHR heat exchanger constant.

Proposed Answer: C Explanation:

Technical

Reference:

0POP02-RH-0001; 0POP03-ZG-0007 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # STP-171 Modified New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7, 10 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 006.K5.09 Importance Rating 3.3 Proposed Question:

32. During a small-break Loss of Coolant Accident, the operators are directed to calculate the RCS subcooled margin because the subcooled margin indication on QDPS is known to be inaccurate. The following Reactor Coolant System indications are available:

Average of the ten highest exit core thermocouples = 565oF.

All Hot Leg Temperatures = 559oF.

All Cold Leg Temperatures = 528oF.

The RCS Wide Range Pressure Channels = 1435 psig.

Based on the above indications, the Reactor Coolant System is subcooled by A. 25oF to 30oF B. 30oF to 35oF C. 45oF to 50oF D. 50oF to 55oF Proposed Answer: A Explanation:

Technical

Reference:

0POP05-EO-EO10, Loss of Reactor or Secondary Coolant Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # STP-B10253- Modified 99781-01 New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10, 14 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 006.A2.03 Importance Rating 3.3 Proposed Question:

33. The plant is at 100% power. At 1300 an annunciator alarms due to a low water level condition in A SI Accumulator. The operators restore accumulator level to its normal operating band by 1330. A leak rate test is then conducted on A SI Accumulator Cold Leg Injection Check Valve, XSI0046A which reveals the leakage to be 1.2 gpm.

What actions should the operators take?

A. Monitor accumulator level and verify accumulator boron concentration within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months of each solution volume increase of greater than or equal to 1% of tank volume.

B. Reduce the leak rate to within limits within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

C. Isolate the check valve within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least two closed manual or deactivated automatic valves, or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

D. Commence an orderly shutdown and be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

Proposed Answer: A Explanation:

Technical

Reference:

Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # STP-B20102- Modified 33522-10 New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 007.K1.03 Importance Rating 3.0 Proposed Question:

34. The following Unit 2 conditions exist:

A faulted steam generator (outside containment) resulted in a reactor trip and safety injection

Operators have isolated the faulted steam generator

RCS pressure is currently 1800 psig and INCREASING

PRT PRESS HI alarm illuminates

PRT level and pressure are INCREASING slowly Which ONE of the following is the cause of the PRT level and pressure increase?

A. Reactor Coolant Pump seal leakoff flow is returning to the PRT.

B. A Pressurizer Power Operated Relief Valve is open.

C. Normal letdown flow is diverted to the PRT.

D. Loss of instrument air to containment fails open the Reactor Make Up Water valve to the PRT, SPRAY ISOL FV-3650.

Proposed Answer: A Explanation:

Technical

Reference:

Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # STP-160 Modified New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5, 7, 8 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 008.K3.03 Importance Rating 4.1 Proposed Question:

35. Which ONE of the following describes the effect on RCP operation if ONLY thermal barrier cooling is lost?

A. RCP operation may continue indefinitely providing seal injection flow is increased to 15 gpm/pump.

B. The RCP must be tripped within 1 minute to prevent damage to the thermal barrier.

C. The RCP must be tripped within 3-5 minutes to prevent damage to #1 seal.

D. RCP operation may continue indefinitely providing seal inlet temperature remains below 135°F.

Proposed Answer: D Explanation:

Technical

Reference:

POP04-RC-0002 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # STP-1072 Modified New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 3, 7 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 010.A4.01 Importance Rating 3.7 Proposed Question:

36. At 2335 psig and increasing, the response of the Pressurizer Pressure Master Controller SHOULD be:

A. Spray Valves CLOSED, and PORV CLOSED.

B. Spray Valves PARTIALLY OPEN, and PORV CLOSED.

C. Spray Valves PARTIALLY OPEN, and PORV OPEN.

D. Spray Valves FULLY OPEN, and PORV OPEN.

Proposed Answer: D Explanation:

Technical

Reference:

LOT201.14 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # Modified New X Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 012.K6.06 Importance Rating 2.7 Proposed Question:

37. Given the following:

Unit 1 is steady-state at 100% power, with all controls in automatic

Pressurizer level control channel selector switch is in the L465/466 position.

LT-0467 failed low.

All required actions of 0POP04-RP-0002, Loss of Automatic Pressurizer Level Control are complete.

The reference leg for LT-0466 ruptures.

Which ONE of the following describes the plant response? (Assume NO operator actions)

A. Backup Heaters energize.

B. Charging flow reduces to minimum.

C. Letdown isolation valve LCV-0465 closes.

D. Reactor trip signal is actuated.

Proposed Answer: D Explanation:

PZR Hi level B/S for RC-LT-0467 tripped as an action of 0POP04-RP-0002. Reference leg failure on RC-LT-0466 results in indicated level going to 100% making up Hi level B/S for this channel. 2/3 Hi Level B/S picked up results in a Rx trip if the unit is > 10% power.

Technical

Reference:

Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # STP-861 Modified New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 6, 7 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 012.A4.05 Importance Rating 3.6 Proposed Question:

38. The following conditions exist:

Containment pressure transmitter PT-937 has been declared inoperable.

Required Technical Specification actions have been taken for Channel 937.

Which ONE of the following statements describes the coincidence for a Containment Spray Actuation to occur and the actions that will result in this coincidence?

A. 2/3 coincidence after the channel is placed in the TRIP condition, by placing bistable (PB-937A) in the TEST position.

B. 2/3 coincidence after the channel is placed in the BYPASS condition, by placing bistable (PB-937A) in the TEST position.

C. 1/2 coincidence after the channel is placed in the TRIP condition, by placing bistable (PB-937A) in the TEST position.

D. 1/2 coincidence after the channel is placed in the BYPASS condition, by placing bistable (PB-937A) in the TEST position.

Proposed Answer: B Explanation:

Technical

Reference:

LOT 201.11 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # STP-895 Modified New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 6, 7 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 013.K6.01 Importance Rating 2.7 Proposed Question:

39. While Unit 2 is operating at 75% power, a Steam Pressure detector on the steam line from the A SG has failed low. With no action on the part of operators in response, the condition of the ESF logic is that ESF actuation would occur if...

A. a second steam pressure detector on the A steam line generates a low steam pressure signal.

B. a second steam pressure detector on the A steam line detects steam pressure dropping at greater than 100 psig/sec.

C. a steam pressure detector from any other steam line detects steam pressure dropping at greater than 100 psig/sec.

D. a steam pressure detector from any other steam line generates a low steam pressure signal.

Proposed Answer: D Explanation:

Technical

Reference:

LOT201.22 page 21 of Lesson Plan Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # Modified New X Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 013.A3.01 Importance Rating 3.7 Proposed Question:

40. All ESF load sequencers are responding in Mode II to a Loss of Offsite Power. The two-second load shed signals have been generated and the EDG output breakers have closed to re-energize the ESF 4.16KV buses. As the AFW pumps are sequenced on, an SI signal is received. The ESF system response is:

A. ESF load sequencers complete sequencing the loads onto the bus in Mode II operation and then the additional loads required by Mode III are sequenced onto the bus.

B. ESF load sequencers shift to Mode III operation and another two-second load shed is generated before loads are sequenced back onto the bus.

C. ESF load sequencers complete sequencing the loads onto the bus in Mode II operation and then the additional loads required by Mode III must be manually started.

D. ESF load sequencers shift to Mode III operation, loads already started during the Mode II sequence remain on the bus, and the remaining Mode.

Proposed Answer: B Explanation:

Technical

Reference:

LOT201.22 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # Modified New X Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 8 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 022.K4.05 Importance Rating 2.6 Proposed Question:

41. The minimum containment cooling components required to prevent exceeding design containment pressure during DBA is:

A. 2 CS pumps in conjunction with 2 RCFCs.

B. 2 CS pumps in conjunction with 3 RCFCs.

C. 3 CS pumps in conjunction with 4 RCFCs.

D. 3 CS pumps in conjunction with 6 RCFCs.

Proposed Answer: B Explanation:

Technical

Reference:

LOT201.11 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # Modified New X Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 8 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 026.K2.01 Importance Rating 3.4 Proposed Question:

42. WHICH ONE (1) of the following bus losses will result in the loss of Containment Spray Pump 1C?

A. Class 1E 4.16 KV Bus E1C B. Non-Class 1E 4.16 KV Bus 1D1 C. Class 1E 480 V Bus E1C1 D. Non-Class 1E 480 V Bus LC 1L2 Proposed Answer: A Explanation:

Technical

Reference:

201.11 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # STP-1029 Modified New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 8 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 026.A3.01 Importance Rating 4.3 Proposed Question:

43. The following sequence of events has occured:

-LOCA inside containment

-35 seconds after the Mode I sequencer started, the Mode III sequencer starts as a result of a LOOP.

-59 seconds after the Mode I sequencer started, containment pressure reaches the Hi-3 setpoint.

When should the CS pumps have started?

A. 15 seconds after the Mode III sequencer started.

B. 40 seconds after the Mode III sequencer started.

C. 15 seconds after the Mode I sequencer started.

D. 59 seconds after the Mode I sequencer started.

Proposed Answer: B Explanation:

Technical

Reference:

LOT201.22 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # Modified New X Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 8 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 039.A2.01 Importance Rating 3.1 Proposed Question:

44. The Reactor, which was operating at 92%, has tripped on low PZR Pressure due to a large break LOCA. All systems are responding to the LOCA as designed. Five seconds after the LOCA initiated, the following parameters are indicated:

Tave = 575oF SG Pressure = 1125 psig PZR Pressure = 1003 psig Containment Pressure = 2.9 psig Under these conditions, the state of the main steam system is:

A. MSIVs are closed on High Containment Pressure and SG PORVs are relieving SG pressure.

B. MSIVs are closed on Low SG Pressure but SG PORVs and SG Safeties remain closed.

C. MISVs are open and Steam Dump Valves are passing steam to the condenser.

D. MSIVs are open but Steam Dumps are shut since they have not yet armed.

Proposed Answer: C Explanation:

MSIVs have not received a closure signal yet, SDs armed when the Turbine tripped on interlock with the RX trip, and Tave is currently above Tref, which places a demand on the SDs to pass steam.

Technical

Reference:

LOT202.02 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # Modified New X Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 056.K1.03 Importance Rating 2.6 Proposed Question:

45. Unit 2 is operating at 7% power with the following conditions:

Dumping steam to the Condenser

Turbine rolling up to 1800 rpm

Condensate Pump 11 operating

SUFP is operating Which ONE of the following describes the plant response to Condensate Pump 11 tripping?

(ASSUME no operator action is taken.)

SUFP AFWPs Reactor Trip A. Trips Start on Lo-Lo SG Level On Lo-Lo SG Level B. Does Not Trip Start on Lo-Lo SG Level On Turbine Trip C. Trips Start on SUFP Trip On Lo-Lo SG Level D. Does Not Trip Start on Reactor Trip On Turbine Trip Proposed Answer: A Explanation:

Technical

Reference:

Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # STP-140 Modified New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 4 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 056.G2.2.2 Importance Rating 4.0 Proposed Question:

46. 0POP02-CD-0001, Condensate System, requires that the Condensate pump discharge common vent line isolation valve and the Condensate pump 13 vent at the mini-flow check valve be open prior to starting Condensate pump 13.

Which ONE of the following statements is the reason for opening these two valves prior to starting the pump?

A. To flush out corrosion particles that collect in the low flow areas of recirculation line check valve CD-0740.

B. To extend the life of recirculation valve CD-FV-7016 by eliminating air pockets that promote erosion.

C. To minimize the occurrence of hydraulic transients in the Condensate pump #13 recirculation line.

D. To ensure that no steam binding will occur in the Condensate pump (low pressure, low temperature impeller boiling).

Proposed Answer: C Explanation:

Technical

Reference:

0POP02-CD-0001 Proposed references to be provided to applicants during examination:

Learning Objective: 40611 Question Source: Bank # STP-454 Modified New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 4 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 059.A4.01 Importance Rating 3.1 Proposed Question:

47. The following conditions have resulted in a Feedwater Isolation Signal:

Rx Trip Breakers = Open SG Level = 85.7%

Tavg = 571oF Containment Pressure = 15 psia PZR Pressure = 2237 psig Steam Pressure = 1180 psig The following actions are required to reset/block the FWI:

A. Press the Train A & Train B LOW Tavg Reset/Block PBs.

B. Clear P-4 and Press the Train A & Train B LOW Tavg Reset/Block PBs.

C. Clear P-4, Press the Train A & Train B SI/SG HI-HI LEVEL Reset PBs, and press the SI Reset/Block PBs on CP-001.

D. Clear P-4, Press the Train A & Train B SI/SG HI-HI LEVEL Reset PBs, and reduce LSG below the HI-HI alarm setpoint.

Proposed Answer: A Explanation:

FWI occured on Rx Trip with Low Tavg; P-4 must be cleared on all FWI signals except this one.

Technical

Reference:

LOT202.13 page 60 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # Modified New X Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7, 10 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 061.K4.01 Importance Rating 4.1 Proposed Question:

48. Which of the following describes the makeup sources to the Auxiliary Feedwater Storage Tank (AFWST)?

A. Normal - Condenser Hotwell Backup - Demineralized Water Emergency - Fire Water B. Normal - Condenser Hotwell Backup - Demineralized Water Emergency - Service Water C. Normal - Demineralized Water Backup - Condenser Hotwell Emergency - Fire Water D. Normal - Demineralized Water Backup - Condenser Hotwell Emergency - Service Water Proposed Answer: C Explanation:

Technical

Reference:

0POP02-AF-0001, Rev 8, (Pg 41); LOT202.28, Rev 4, (Pg 43)

Proposed references to be provided to applicants during examination:

Learning Objective: 43808 Question Source: Bank # STP-511 Modified New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 4, 7 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 062.G2.4.6 Importance Rating 3.1 Proposed Question:

49. The following conditions exist on Unit 1:

Unit 1 is operating at full power

ECW Trains A and B are in service

A manual SI is initiated

All equipment function as designed

The crew is currently performing the actions of Addendum 5 of 0POP05-EO-EO00, Reactor Trip or Safety Injection 10 minutes later power is lost to 4160v ESF Bus E1A.

Which of the following describes the expected equipment response AND appropriate procedural guidance?

A. ESF Train A Sequencer will strip ECW Pump A and restart it per the programmed sequencing once ESF Diesel Generator 11 re-energizes the 4160v Bus. Operators should GO TO 0POP04-AE-0001, Loss of Any 13.8 or 4.16 KV Bus, to restart ECW Pump A B. ESF Train A Sequencer will strip ECW Pump A but will NOT automatically restart (reload) the pump after ESF Diesel Generator 11 re-energizes the 4160v Bus. Operators should GO TO 0POP04-AE-0001, Loss of Any 13.8 or 4.16 KV Bus, to restart ECW Pump A.

C. ESF Train A Sequencer will strip ECW Pump A but will NOT automatically restart (reload) the pump after ESF Diesel Generator 11 re-energizes the 4160v Bus. Operators should ensure ECW Pump A is in operation per Addendum 5 of 0POP05-EO-EO00.

D. ESF Train A Sequencer will strip ECW Pump A and restart it per the programmed sequencing once ESF Diesel Generator 11 re-energizes the 4160v Bus. Operators should ensure ECW Pump A is in operation per Addendum 5 of 0POP05-EO-EO00.

Proposed Answer: D Technical

Reference:

POP01-ZA-0018, Elem drawings 9E-EW01-01, 9E-EW04-02 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # STP-1090 Modified New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7, 10 55.43

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 063.K3.02 Importance Rating 3.5 Proposed Question:

50. Which ONE of the following statements describes the effect of a loss of DC control power to the 4160 VAC breaker supplying 4160 VAC bus E1A?

The breaker will:

A. remain in its current position and can be tripped, but not closed from the MCB.

B. remain in its current position and cannot be tripped or closed from the MCB.

C. trip open and can be closed, but not tripped from the MCB.

D. trip open and cannot be tripped or closed from the MCB.

Proposed Answer: B Explanation:

Technical

Reference:

0POP02-DJ-0001 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # STP-960 Modified New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7, 8 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 064.A1.03 Importance Rating 3.2 Proposed Question:

51. What are the Emergency Diesel Generator voltage and 2-hour loading limits?

A. Generator voltage limits are 3744 volts to 4576 volts; Emergency Diesel Generator load limits are 6050 KW for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months B. Generator voltage limits are 3952 volts to 4368 volts; Emergency Diesel Generator load limits are 5400 KW for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months C. Generator voltage limits are 3744 volts to 4576 volts; Emergency Diesel Generator load limits are 5400 KW for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months D. Generator voltage limits are 3952 volts to 4368 volts; Emergency Diesel Generator load limits are 6050 KW for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Proposed Answer: A Explanation:

Technical

Reference:

0POP02-DG-0001, Rev 14, (Pg 21); 0POP02-DG-0002, Rev 17, (Pg 20); 0POP02-DG-0003, Rev 17, (Pg 20)

Proposed references to be provided to applicants during examination:

Learning Objective: 45060 Question Source: Bank # STP-500 Modified New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 8 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 073.K5.03 Importance Rating 2.9 Proposed Question:

52. Local radiation surveys in response to a Reactor Containment Building Atmosphere PRM alarm indicate a general area dose rate of 80 mrem/hr. Which ONE of the following would exceed his/her 10CFR20 Dose Limits in only one hour of work in this environment?

A. Plant worker with a year-to-date exposure of 1430 mrem (TEDE)

B. Working Visitor with a year-to-date exposure of 10 mrem (TEDE)

C. Contract employee with a year-to-date exposure at all sites of 3975 mrem (TEDE)

D. Declared pregnant worker with a to date exposure of 430 mrem (DDE) during the pregnancy Proposed Answer: D Explanation:

A. INCORRECT - Limited to 5 rem total B. INCORRECT - Limited to 100 mrem total with 100 mrem left C. INCORRECT - Limited to 5 rem total D. CORRECT - Limited to 500 mrem total with 75 mrem left Technical

Reference:

10 CFR 20 (1-1-98 edition)

Proposed references to be provided to applicants during examination:

Learning Objective: N0045 Question Source: Bank # STP-90 Modified X New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 12 55.43 Comments:

Adjusted the stem to better address the KA, and modified the values in the choices.

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 076.A3.02 Importance Rating 3.7 Proposed Question:

53. Given the following:

Unit 1 Control Room was abandoned due to a fire in the Relay Room.

0POP04-ZO-0001, Control Room Evacuation is in progress.

All transfer switch checklists have been completed.

A total loss of offsite power occurs.

Which ONE of the following describes the response of the ECW system?

A. ECW pumps will automatically start after the DGs energize the 4.16 KV ESF Buses.

B. ECW pumps must be manually started from the ASP after the DGs energize the 4.16 KV ESF Buses.

C. ECW pumps in service prior to the blackout will automatically restart, all others must be manually started after the DGs energize the 4.16 KV ESF Buses.

D. ECW pumps must be manually started from the ESF Train Switchgear Rooms after the DGs energize the 4.16 KV ESF Buses.

Proposed Answer: D Explanation:

Technical

Reference:

0POP04-ZO-0001, Addendum 7 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # STP-857 Modified New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7, 8 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 078.K2.02 Importance Rating 3.3 Proposed Question:

54. Which ONE of the following describes the EMERGENCY power supply to Instrument Air Compressor #12?

A. TSC diesel generator which energizes LC 1U B. TSC diesel generator which energizes MCC 1G5 C. BOP diesel generator which energizes LC 1U D. BOP diesel generator which energizes MCC 1G5 Proposed Answer: D Explanation:

Technical

Reference:

Single Line Drawing 9-E-PFAR-01 Rev 13 Proposed references to be provided to applicants during examination:

Learning Objective: 25610 Question Source: Bank # STP-96 Modified New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7, 8 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 103.A1.01 Importance Rating 3.7 Proposed Question:

55. Given the following:

A Reactor Trip occurs due to a Loss of Offsite Power

The ESF Diesel Generators have all started and restored power to their ESF buses

The Control Room crew has just completed the Immediate Actions of 0POP05-EO-EO00, Reactor Trip or Safety Injection Which ONE of the following correctly predicts the RCB Temperature trend and the reason for the trend?

A. Temperature is slowly decreasing because the RCFCs are running with CCW flowing through the cooling coils.

B. Temperature is slowly increasing because the RCFCs are running with NO cooling flow through the cooling coils.

C. Temperature is slowly decreasing because the RCFCs are running with Chilled Water flowing through the cooling coils.

D. Temperature is slowly increasing because the RCFCs are NOT running.

Proposed Answer: B Explanation:

Technical

Reference:

logics 42041, 42042, 41630 Proposed references to be provided to applicants during examination:

Learning Objective: 4967 Question Source: Bank # STP-1080 Modified New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 9 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross- Level RO SRO Tier # 2 Group # 2 K/A # 001.K3.01 Importance 2.9 Proposed Question:

56. The following conditions exits on Unit 1:

Reactor power is 20%

Control Bank D position is 118 steps

Rod Control is in automatic

Control rod Full Out Position (FOP) is 257 steps and Bank Overlap (BO) is 120 steps

SUFP is out of service for seal replacement

-At 0300 hours0.00347 days 0.0833 hours 4.960317e-4 weeks 1.1415e-4 months a rapid load reduction to 3% reactor power occurs due to a trip of the only available main feedpump. Control Bank D demand position is now 93 steps.-At 0320 hours0.0037 days 0.0889 hours 5.291005e-4 weeks 1.2176e-4 months , the primary Reactor operator notices control rod D4 in Control Bank D did not move during the power reduction.

In accordance with 0POP04-RS-0001"Control Rod Malfunction, how should Tavg be controlled while I&C evaluate whether the stationary and moveable grippers and the lift coils are properly energized with the correct currents and in proper sequence?

A. Tavg should be maintained within 1.5oF of Tref with rods in Auto.

B. Tavg should be maintained within 1.5oF of Tref by moving rods in Manual.

C. Tavg should be maintained within 1.5oF of Tref by adjusting Turbine Load and/or adjusting RCS boron concentration.

D. Tavg should be maintained within 1.5oF of Tref by adjusting Turbine Load in combination with manual rod motion.

Proposed Answer: C Technical

Reference:

0POP04-RS-0001 Rev 12 step 5 and Caution Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # Modified New X Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 K/A # 002.A3.01 Importance Rating 3.7 Proposed Question:

57. Which ONE of the following indications is used to detect "identified RCS leakage?"

A. Pressurizer relief tank pressure B. Reactor coolant drain tank temperature C. Containment noble gas activity D. Reactor coolant drain tank level Proposed Answer: D Explanation:

Technical

Reference:

UFSAR 5.2.5.2 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # STP-1084 Modified New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 K/A # 016.K1.09 Importance Rating 3.7 Proposed Question:

58. Unit 2 is in the process of a normal shutdown and cooldown for refuelling. Currently:

- PZR Pressure = 1850 psig

- Steam Line Pressure = 725 psig

- Containment Pressure = 15.0 psia Some minutes later, a pipe rupture in containment results in a Steam Line Isolation. At the moment of Steam Line Isolation actuation, the above parameters had reached the following values:

- PZR Pressure = 1213 psig

- Steam Line Pressure = 325 psig

- Containment Pressure = 17.0 psia Steam Line Isolation actuation was due to:

A. Low PZR Pressure B. Low Steam Line Pressure C. High Containment Pressure D. High Rate of Change of Steam Line Pressure Proposed Answer: D Explanation:

Low PPZR and Low PSTM signals are blocked due to the cooldown below 1985#, and Pcont did not exceed 3psig; Low PSTM block also sets the Stm Line Isolation signal to high rate instead of low pressure, therefore it is the only reasonable cause.

Technical

Reference:

LOT201.22 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # Modified New X Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 K/A # 035.K5.13 Importance Rating 3.4 Proposed Question:

59. With Unit 2 operating at 80%, a 10% load increase on the Turbine will cause:

Steam Pressure Control Rods Tavg A. DECREASE STEP OUT DECREASE B. DECREASE STEP IN INCREASE D. INCREASE STEP OUT INCREASE C. INCREASE STEP IN DECREASE Proposed Answer: B Explanation:

Due to Tavg programming, Rods will step out with a power increase in order to raise Tavg and mitigate somewhat the pressure drop in the SG.

Technical

Reference:

Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # Modified New X Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 K/A # 041.A2.03 Importance Rating 2.8 Proposed Question:

60. While Unit 2 is operating at 85%, a leak in the Instrument Air System causes IAS pressure to drop, IAS HDR PRESS LO annunciator alarms, but the compressors are able to maintain IAS header pressure at 10 psig below the annunciator alarm setpoint.

In this condition, the status of the Steam Dumps is:

A. They are available for controlled actuation and are currently shut.

B. They are available for controlled actuation and have actuated full open.

C. They are unavailable for controlled actuation and have failed shut on low IAS pressure.

D. They are unavailable for controlled actuation and have failed open on low IAS pressure.

Proposed Answer: C Explanation:

Steam Dumps require 55 psig from the IAS, and the alarm comes in at 90 psig, so there is still sufficient IAS pressure for Steam Dump actuation if necessary.

Technical

Reference:

LOT202.09, 0POP09-AN-08M3 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # Modified New X Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7, 8 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 K/A # 055.K1.06 Importance Rating 2.6 Proposed Question:

61. RT-8027, Condenser Air Removal System PRM monitors levels of _______ (controlling isotope) and provides ________ automatically when the High Alarm setpoint is reached?

A. Kr-85; audible alarm in the control room and closure of Vacuum Pump suction valves.

B. Kr-85; audible alarm in the control room but no control function.

C. I-131; audible alarm in the control room and closure of Vacuum Pump suction valves.

D. I-131; audible alarm in the control room but no control function.

Proposed Answer: B Explanation:

Technical

Reference:

LOT202.41 Table 1 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # Modified New X Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 11, 13 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 K/A # 068.A3.02 Importance Rating 3.6 Proposed Question:

62. A release of a Waste Monitor Tank is in progress through the Liquid Radwaste System.

Which ONE of the following conditions will result in WL-FV-4077, Liquid Radwaste Discharge Valve, shifting to the RECIRC position?

A. ALERT alarm on RT-8038, LWPS Monitor.

B. HIGH alarm on RT-8045, LWPS Monitor #2.

C. Loss of sample flow to RT-8038, LWPS Monitor.

D. Loss of sample flow to RT-8045, LWPS Monitor #2.

Proposed Answer: C Explanation:

Technical

Reference:

LOT202.41 Table 1 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # STP-694 Modified New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 11, 13 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 K/A # 072.A1.01 Importance Rating 3.4 Proposed Question:

63. Unit 1 is operating at 100% power when a valid High Alarm is received on RT-8013, RCB Purge Exhaust Monitor.

Which ONE of the following radiation monitors is now inoperable?

A. RCB High Range Radiation Monitor (RT-8051)

B. RCB Atmosphere Radiation Monitor (RT-8011)

C. Unit Vent Stack Monitor (RT-8010A)

D. GWPS Outlet Radiation Monitor (RT-8032)

Proposed Answer: B Explanation:

A. INCORRECT: RT-8051 is an area monitor inside containment, a CVI does not affect its operation.

B. CORRECT: RT-8011 sample lines isolate on a CVI rendering the monitor inoperable.

C. INCORRECT: RT-8010A is a process monitor associated with the Unit Vent Stack Exhaust, a CVI does not affect its operation.

D. INCORRECT: RT-8032 is a process monitor associated with the GWPS, a CVI does not affect its operation.

Technical

Reference:

0POP04-RA-0001, RT-8012/8013 Alarm Response Section Proposed references to be provided to applicants during examination:

Learning Objective: 92102 Question Source: Bank # STP-390 Modified New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 11 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 K/A # 075.K1.02 Importance Rating 2.9 Proposed Question:

64. Which ONE of the following describes the release pathway of a Waste Monitor Tank (WMT) to the reservoir?

Waste Monitor Tank (WMT) to the:

A. Circulating Water (CW) discharge piping into the outfall structure.

B. Open Loop Cooling (OC) discharge piping to Circulating Water (CW) discharge piping into the outfall structure.

C. Floor Drain Tank (FDT) into the outfall structure.

D. Open Loop Cooling (OC) discharge piping into the outfall structure.

Proposed Answer: B Explanation:

Technical

Reference:

drawings 9F90001, 9F00033, 2F00032 Proposed references to be provided to applicants during examination:

Learning Objective: 92082 Question Source: Bank # STP-1078 Modified New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 13 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 K/A # 086.K504 Importance Rating 2.9 Proposed Question:

65. For a Class C fire in the TSC, the primary extinguishing agent for that fire would be A. Halon because it is effective and safer since it remains breathable in the 7 to 7.5%

concentration for which the system is designed.

B. Halon because it is effective and safer since it gives a pre-discharge evacuation alarm in the affected area to warn personnel since Halon is not breathable.

C. Carbon Dioxide because it is effective and safer since it remains breathable in the 7 to 7.5% concentration for which the system is designed.

D. Carbon Dioxide because it is effective and safer since it gives a pre-discharge evacuation alarm in the affected area to warn personnel since CO2 is not breathable.

Proposed Answer: A Explanation:

Technical

Reference:

LOT201.29 page 11 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # Modified New X Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 8 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Group # 1 K/A # G2.1.27 Importance Rating 3.2 Proposed Question:

66. While Unit 2 is operating steady at 60% power, THOT of Loop 1 fails high. How does the PZR Level Control System respond to this event?

A. PZR Level Control System is not affected by only one THOT channel failing high.

B. PZR Level Control System decreases LPZR to 25%.

C. PZR Level Control System increases LPZR to 92% and causes a Reactor Trip.

D. PZR Level Control System increases LPZR to 57%.

Proposed Answer: D Explanation:

Technical

Reference:

LOT201.15 and LOT201.14 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # Modified New X Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Group # 1 K/A # G2.1.32 Importance Rating 3.4 Proposed Question:

67. A plant heatup was in progress in accordance with 0POP03-ZG-0001, Plant Heatup. The following RCS temperatures were observed at the given times:

TIME TEMP 1000 362°F 1030 383°F 1050 400°F 1115 423°F It is now 1130. Which ONE of the following is the MAXIMUM RCS temperature allowed per the administrative limit of 0POP03-ZG-0001?

A. 423°F B. 433°F C. 463°F D. 483°F Proposed Answer: B Explanation:

Technical

Reference:

Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # STP-736 Modified New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5, 10 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Group # 2 K/A # G2.2.12 Importance Rating 3.0 Proposed Question:

68. It has been discovered that the surveillance to demonstrate primary CONTAINMENT INTEGRITY was not performed within the allotted time frame, including the 25% extension. It is, in fact, now months past due. The LCO ACTION states, Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . Which of the following is correct concerning this condition?

A. If Containment Integrity cannot be verified within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , the unit must be in HOT STANDBY within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

B. Containment Integrity is assumed to have been lost since the last surveillance, so the unit must be placed in COLD SHUTDOWN within the following 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

C. Containment Integrity is assumed to have been lost since discovery of the missed surveillance, so the unit must be placed in HOT STANDBY within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

D. If Containment Integrity cannot be verified within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , the unit must be placed in HOT STANDBY within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Proposed Answer: D Explanation:

Technical

Reference:

Technical Specification 4.0.3 Proposed references to be provided to applicants during examination:

Learning Objective: 10300 Question Source: Bank # STP-562 Modified New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Group # 2 K/A # G2.2.13 Importance Rating 3.6 Proposed Question:

69. A work package has been written to re-pack SI-MOV-0031A, LHSI Pump A Cold Leg Injection Valve, on its backseat. The Equipment Clearance Order written for the job calls for one of the boundaries to be the valve on its backseat.

Which ONE of the following identifies the HIGHEST level of authorization necessary to work the job as planned?

A. Plant Manager B. Maintenance Department Manager C. Maintenance Supervisor D. Shift Supervisor Proposed Answer: A Explanation:

Technical

Reference:

0PGP03-ZO-EC01, Rev 10, Addendum 3 step 1 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # STP-367 Modified New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Group # 3 K/A # G2.3.1 Importance Rating 2.6 Proposed Question:

70. An operator is required to complete a valve lineup in an area where the radiation level is 50 mrem/hour. The operators current Total Effective Dose Equivalent (TEDE) is 1850 mrem.

Which ONE of the following indicates the MAXIMUM amount of time the operator can work in this area and NOT exceed STPs Administrative Action Level (AAL)?

A. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months B. 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months C. 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months D. 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months Proposed Answer: B Explanation:

Technical

Reference:

Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # STP-347 Modified New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10, 12 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Group # 3 K/A # G2.3.2 Importance Rating 2.5 Proposed Question:

71. Work must be performed in the MAB near a point source that is producing a radiation level of 300 mrem/hr at a distance of 4 feet.

Which ONE of the following methods of work performance will result in the lowest TOTAL personnel radiation exposure?

Number of Time to Distance from Operators Complete Point Source A. 1 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 8 feet B. 1 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months 12 feet C. 2 1 hour/each 10 feet D. 2 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months s/each 14 feet Proposed Answer: C Explanation:

Technical

Reference:

Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # STP-600 Modified New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 12 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Group # 4 K/A # G2.4.49 Importance Rating 4.0 Proposed Question:

72. Given the following conditions on Unit 1:

Reactor power is being maintained at 30%

SGFPs 11 and 12 are in service

All controls are in automatic SGFP 12 trips due to a loss of lube oil and 0POP04-FW-0002, Steam Generator Feed Pump Trip is entered.

Which ONE of the following describes the immediate operator actions that should be taken?

A. 1) Check SGFPs - Required number running.

5) Check SGFP Master Controller - OPERABLE.

B. 1) Start a standby FW Booster Pump.

2) Check SG Feedwater Regulating Valves responding in AUTOMATIC.

C. 1) Check SGFP Master Controller - OPERABLE.

2) Check SG Feedwater Regulating Valves responding in AUTOMATIC.

D. 1) Place Low Power Feedwater Regulating Valves in MANUAL.

2) Check SGFPs - Required number running.

Proposed Answer: A Explanation:

Technical

Reference:

0POP04-FW-0002 Rev 6, Steps 1-2 Proposed references to be provided to applicants during examination:

Learning Objective: 92108 Question Source: Bank # STP-110 Modified New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Group # 4 K/A # G2.4.1 Importance Rating 4.3 Proposed Question:

73. Current plant conditions are:

Control rods are moving outward.

Reactor power was initially 50% and stable, but is now increasing slowly.

Tave 578°F initially stable but is now increasing slowly.

Turbine load 655 MWe and stable.

Average loop DT is 50% and stable.

Control rods are in AUTO.

Under these conditions, the operators actions are to:

A. Select Rod Control to MANUAL to stop the rod motion.

B. Select Steam Dumps to Steam Pressure Control mode.

C. Monitor Control Rod motion to ensure proper system response.

D. Monitor Steam Dumps to ensure proper system response.

Proposed Answer: A Explanation:

Technical

Reference:

0POP04-RS-0001 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # STP-610 Modified New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Group # 4 K/A # G2.4.7 Importance Rating 3.1 Proposed Question:

74. 0POP05-EO-EO30, Steam Generator Tube Rupture, is being performed in response to a tube rupture on SG 1A.

The cooldown has just been completed but the target temperature value selected by the crew was 50°F higher than that stipulated in the procedure.

This error could result in which ONE of the following conditions?

A. Filling the Pressurizer solid during the subsequent depressurization.

B. Decrease the time for termination of the primary to secondary leakage.

C. Decrease in pressure of the ruptured SG with increased leakage from the RCS.

D. Loss of RCS subcooling before RCS and ruptured SG pressures are equalized.

Proposed Answer: D Explanation:

A. Incorrect - The pressurizer being overfilled is a symptom of overcooling the RCS instead of undercooling.

B. Incorrect - The time will not decrease, the undercooling would cause a situation where the leakage cannot be stopped due to loss of subcooling before the pressures are equal.

C. Incorrect - The situation given will result in the leakage not stopping causing steam generator overfill and pressure increase to RCS pressure.

D. Correct - To stop primary to secondary leakage the RCS pressure must be decreased to a value equal to the ruptures S/G pressure. If cooldown is stopped too soon the required subcooling will be lost before RCS & S/G pressures are equalized.

Technical

Reference:

Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # STP-654 Modified New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 5, 10 55.43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Group # 4 K/A # G2.4.2 Importance Rating 3.9 Proposed Question:

75. In accordance with 0POP01-ZA-0018, Emergency Operating Procedures Users Guide, during the performance of the EOPs, which of the following actions is permissible?

A. Cross-connecting AFW to supply all four SGs, at 200 gpm per SG, with one AFW pump during the performance of 0POP05-EO-FRS1, Response to Nuclear Power Generation -

ATWS, with all SG narrow range levels below 5%

B. Restoring AFW to a faulted SG after it has been isolated to establish the maximum cooldown rate available while performing 0POP05-EO-EO30, Steam Generator Tube Rupture C. Resetting Phase A Isolation and restoring Instrument Air to Containment during the performance of 0POP05-EO-EO00, Reactor Trip or Safety Injection D. Isolating AFW to a ruptured SG and closing the Main Steam Isolation Valve from the ruptured SG during the performance of 0POP05-EO-EO00, Reactor Trip or Safety Injection Proposed Answer: C Explanation:

A. INCORRECT - FRS1 requires 1080 gpm total AFW flow if all SGs are <5% and a single AFW pump is limited to 675 gpm.

B. INCORRECT - A faulted SG is not to be used for cooldown unless required.

C. CORRECT - IA to containment allows pressure control using spray valves to avoid pressurizer PORV operation.

D. INCORRECT - Only the AFW supplies can be closed to a ruptured SG prior to direction of EO30 to isolate the SG.

Technical

Reference:

0POP01-ZA-0018, Rev 9; 0POP05-EO-EO20, Rev 3 Proposed references to be provided to applicants during examination:

Learning Objective: 50354 Question Source: Bank # STP-582 Modified New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 10 55.43 Comments:

SRO EXAM QUESTIONS ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # E05.EA2.1 Importance Rating 4.4 Proposed Question 1:

Unit 2 is in a Train B Outage when a reactor trip occurs followed by a loss of offsite power (LOOP). The operators have just completed 0POP05-EO-EO00, Reactor Trip and Safety Injection," including Addendum 5.

Current conditions are:

Containment Pressure: 5.5 psig

Containment Radiation: 10.1 R/hr

Core Exit Thermocouples: 584 °F

RCS Pressure: 1352 psig

SG A WR Level: 31%

SGs B-D WR Levels: 5 % 8%

AFW Pump 21 failed to start

Total AFW flow is approximately 500 gpm and cannot be increased What actions are required?

A. Immediately transition to Procedure 0POP-EO-FRH1, "Response to Loss of Secondary Heat Sink," and establish feed and bleed.

B. Immediately transition to Procedure 0POP-EO-EO10, "Loss of Reactor or Secondary Coolant," and depressurize the intact SGs to 1000 psig.

C. Immediately transition to Procedure 0POP-EO-FRH1, "Response to Loss of Secondary Heat Sink," dump steam to the condenser to reduce SG pressures.

D. Perform Procedure 0POP-EO-FRH1, "Response to Loss of Secondary Heat Sink,"

concurrently with Procedure 0POP05-EO-EO10, Loss of Reactor or Secondary Coolant."

Proposed A Answer:

Explanation:

Technical POP01-ZA-0018, POP05-EO-FRH1

Reference:

Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Ba STP-1092 Modi nk fied New Question History: Last NRC Class 13 Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.

41

55. 5 43 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross- Level RO SRO Tier # 1 Group # 1 K/A # APE 062.AK3.02 Importance 3.9 Proposed Question 2:

Unit 1 is operating at full power

ECW Trains A and B are in service

An inadvertent SI occurs

All equipment functioned as designed

The crew is currently performing the actions of Addendum 5 of 0POP05-EO-EO00, Reactor Trip or Safety Injection 10 minutes later power is lost to 4160v ESF Bus E1A.

Which of the following describes the expected equipment response AND appropriate procedural guidance?

A. ESF Train A Sequencer will strip ECW Pump A and restart it per the programmed sequencing once ESF Diesel Generator 11 re-energizes the 4160v Bus. Operators should GO TO 0POP04-AE-0001, Loss of Any 13.8 or 4.16 KV Bus, to restart ECW Pump A B. ESF Train A Sequencer will strip ECW Pump A but will NOT automatically restart (reload) the pump after ESF Diesel Generator 11 re-energizes the 4160v Bus. Operators should GO TO 0POP04-AE-0001, Loss of Any 13.8 or 4.16 KV Bus, to restart ECW Pump A.

C. ESF Train A Sequencer will strip ECW Pump A and restart it per the programmed sequencing once ESF Diesel Generator 11 re-energizes the 4160v Bus. Operators should ensure ECW Pump A is in operation per Addendum 5 of 0POP05-EO-EO00.

D. ESF Train A Sequencer will strip ECW Pump A but will NOT automatically restart (reload) the pump after ESF Diesel Generator 11 re-energizes the 4160v Bus. Operators should ensure ECW Pump A is in operation per Addendum 5 of 0POP05-EO-EO00.

Proposed Answer: C Explanation:

ESF Train A Sequencer will strip ECW Pump A and restart it per the programmed sequencing once ESF Diesel Generator 11 re-energizes the 4160v Bus. Operators should ensure ECW Pump A is in operation per Addendum 5 of 0POP05-EO-EO00.

Technical

Reference:

POP01-ZA-0018, Elem drawings 9E-EW01-01, 9E-EW04-02 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # STP-1090 Modified New

Question History: Last NRC Exam NRC Class 13 Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 5 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 K/A # APE 037.AA2.12 Importance Rating 4.1 Proposed Question 3:

Unit 1 plant parameters:

Letdown flow is 125 gpm.

Tave is STABLE.

Pressurizer level is STABLE.

Seal injection flow to each RCP is 8 gpm.

Seal leakoff flow from each RCP is 3 gpm.

Charging flow is 115 gpm as indicated on FI-0205A.

MOV-001A, PZR PORV Block Valve has a 0.5 gpm packing leak.

Leakage from known sources other than S/G leakage is 8.5 gpm.

Unidentified leakage is 0.6 gpm.

SG 1A has a primary-to-secondary leak Based on the above conditions, what actions are required to be taken and why?

A. Continue plant operations, unidentified leakage is less than 1 gpm.

B. Continue plant operations, identified leakage is less than 10 gpm.

C. Commence a plant shutdown, primary-to-secondary leakage through 1 steam generator greater than or equal to 150 gallons per day.

D. Commence a plant shutdown, leakage exceeds pressure boundary leakage.

Proposed Answer: C Explanation:

SG 1A has a primary-to-secondary leak rate of 0.4 gpm (576 gpd) and this exceeds the TS limit of 150 gpd.

Technical

Reference:

TS 3.4.6.2 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # STP- Modified New X Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis

10 CFR Part 55 Content: 55.41 55.43 2 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 K/A # APE068.G2.4.11 Importance Rating 4.6 Proposed Question 4:

Unit 2 has experienced a reactor trip and Safety Injection. While performing 0POP05-EO-EO00, Reactor Trip or Safety Injection, a fire breaks out in CP-004. The Control Room must be evacuated.

Which ONE of the following must be performed when the Control Room personnel arrive at the Aux Shutdown Panel?

A. 0POP05-EO-EO00 should be continued where left off, and 0POP04-ZO-0001, Control Room Evacuation, initiated when 0POP05-EO-EO00 is completed.

B. 0POP05-EO-EO00 and 0POP04-ZO-0001, Control Room Evacuation, are to be performed concurrently, to the degree possible.

C. 0POP04-ZO-0001, Control Room Evacuation, must be performed exclusively.

D. 0POP04-ZO-0001, Control Room Evacuation, is to be performed, unless a CSF Orange or Red condition exists. At which time implementation of the associated FRG is required.

Proposed Answer: C Explanation:

0POP04-ZO-0001, Control Room Evacuation, must be performed exclusively.

Technical

Reference:

0POP04-ZO-0001, Control Room Evacuation and 0POP01-ZA-0018, EOP usage Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # STP-1012 Modified New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 5 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 063A2.01 Importance Rating 3.2 Proposed Question 5:

Unit 2 is in Mode 2. Electrical Maintenance personnel identify the cause of a DC ground alarm as a problem in Switchboard E2A11, Cubicle 4A, Train A RX Trip SWGR Control Power. The system engineer determines that the ground on the load cubicle disables Reactor Trip Breakers 1B and 2B shunt trip circuits. What action(s) is the SRO required to complete for Unit 2?

A. No impact due to redundant trip circuits. No action required.

B. Declare the effected trip breakers inoperable. Enter T.S. 3.0.3 and commence a reactor shutdown within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

C. Restore the effected trip breakers to an operable status with 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

D. Declare the effected trip breakers inoperable and restore the inoperable channel to operable within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or open the reactor trip breakers within the next hour.

Proposed Answer: C Explanation:

Technical

Reference:

T.S. 3.3.1 Action 12 & Procedure 0POP04-DJ-0001, Loss of Class 1E 125 VDC Power Proposed references to be provided to applicants during examination:

T.S. 3.3.1 Learning Objective:

Question Source: Bank # STP- Modified New X Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 2 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 064.G.2.1.11 Importance Rating 3.8 Proposed Question 6:

Unit 1 is in Mode 1 and DG 12 and DG 13 are tagged out for emergency maintenance. The remaining DG 13 is operable and applicable action statements for T.S 3.8.1.1 are complete. Sometime later, an auxiliary operator reports the air pressure for DG 11 Starting Air Receivers 11 and 12 as 165 psig and 155 psig, respectively.

What actions are required?

A. Declare 50.54x and immediately request an exigent technical specification waiver.

B. Demonstrate the operability of two offsite power sources within one hour and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter. In addition, restore one diesel generator to an operable status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

C. Demonstrate the operability of two offsite power sources within one hour and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter. In addition, restore two diesel generators to an operable status within 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

D. Enter T.S. 3.0.3 and commence a reactor shutdown within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

Proposed Answer: B Explanation:

T.S. 3.8.1.1, Action e. requires B above.

Technical

Reference:

T.S. 3.8.1.1 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # STP- Modified New X Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 2 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Group # 1 K/A # 2.1.7 Importance Rating 4.4 Proposed Question 7:

Unit 1 is in Mode 6 with core alterations in progress.

Train C Control Room HVAC has been tagged out for maintenance for the last eight days.

Train A and B Control Room HVAC are in the recirculation and makeup air filtration mode of operation.

Essential Chiller 12 B has been tagged out for maintenance for an oil change.

Essential Chiller 11B (150 ton chiller) trips and cannot be restarted.

Based on this information, which ONE of the following describes acceptable actions to comply with Tech Specs?

A. Suspend core alterations. Core alterations may resume after Essential Chiller 11B or 12B is placed in service and Train "B" Essential Chill Water is aligned for operability.

B. Suspend core alterations. Core alterations may resume after Control Room Envelope HVAC train B is be secured and control room temperatures remains less than or equal to 78oF.

C. Core alterations may continue. Re-verify that both Train "A" and "B" Control Room HVAC are in recirculation and makeup air filtration mode of operation.

D. Core alterations may continue. Re-verify that Train "A" Control Room HVAC is in recirculation and makeup air filtration mode of operation and capable of being powered from DG 11.

Proposed Answer: A Explanation:

Technical

Reference:

T.S. 3.7.7, Modes 5 and 6, Section b. and basis.

Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # STP-Requal Modified X B20237-33269-01 New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis

10 CFR Part 55 Content: 55.41 55.43 7 and 2 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 K/A # 034 A2.01 Importance Rating 4.4 Proposed Question 8:

Unit 2 is in Mode 6 with the following conditions:

A fuel assembly was dropped in the reactor cavity.

0POP04-FH-0001, Fuel Handling Accident, was entered.

The containment building has been evacuated.

Health Physics has verified that dose rates and airborne radioactivity levels on the refueling deck are acceptable.

The refueling crew has requested entry into the containment building to begin recovery actions.

Per 0POP04-FH-0001, which ONE of the following individuals must give permission to allow the refueling crew to enter containment?

A. Shift Supervisor B. Operations Manager C. Technical Services Department Manager D. Plant Manager Proposed Answer: A Explanation:

Technical

Reference:

Proposed references to be provided to applicants during examination:

Learning Objective: LOT 505.01 Objective 92109 Question Source: Bank # STP-118 Modified New Question History: Last NRC Exam Class 12 Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41

55.43 7 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 2 K/A # 086.A1.02 Importance Rating 3.2 Proposed Question 9:

Unit 1 is operating at 100% power when it is discovered that the total available volume in the Fire Water Storage Tanks is 250,000 gallons.

In accordance with 0PGP03-ZF-0018, "Fire Protection System Operability," which ONE of the following compensatory actions must be taken?

A. Restore at least one Fire Water Storage Tank to > 300,000 gallons within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

B. Restore at least one Fire Water Storage Tank to > 300,000 gallons within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

C. Restore both Fire Water Storage Tanks to > 300,000 gallons each within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

D. Restore both Fire Water Storage Tanks to > 300,000 gallons each within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Proposed Answer: B Explanation:

0PGP0S-ZF-0018, Section 4.3.1 Technical

Reference:

0PGP0S-ZF-0018, Section 4.3.1 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # STP-601 Modified New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 1 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 003.A2.01 Importance Rating 3.9 Proposed Question 10:

Unit 2 is in Mode 2 at approximately 4% power. In preparation for entering Mode 1 (7:05 a.m.),

the SRO is walking down the control board and observes the following parameters for the RCPs:

RCP 2 A No 1 Seal Leakoff - 3.2 gpm RCP 2C No 1 Seal Leakoff - > 6.0 gpm RCP 2 B No 1 Seal Leakoff - 3.5 gpm RCP 2D No 1 Seal Leakoff - 3.4 gpm Other RCP 2C parameters are:

Motor Bearing Temp - 167oF Motor Winding Temp - 293oF No 1 Seal D/P - 275 psid No 1 Seal Injection Flow - 8.3 gpm Case Vibration - 2.9 mils Shaft Vibration - 11.2 mils Based on the above indications, the SRO should:

A. Enter Procedure 0POP04-RC-0002, Reactor Coolant Pump Off Normal, and:

immediately begin a reactor shutdown; isolate RCP 2C seal leakoff by 7:20 a.m.; then, stop RCP 2C.

B. Enter Procedure 0POP04-RC-0003, Excessive RCS Leakage, and: immediately begin and reactor shutdown; stop RCP 2C; and, isolate RCP 2C seal leakoff by 7:20 a.m.

C. Enter Procedure 0POP04-RC-002, Reactor Coolant Pump Off Normal, and:

immediately trip the reactor; stop RCP 2C; and isolate RCP 2C seal leakoff by 7:10 a.m.

D. Enter Procedure 0POP04-RC-0003, Excessive RCS Leakage, and: immediately trip the reactor; isolate RCP 2C seal leakoff by 7:10 a.m.; then stop RCP 2C.

Proposed Answer: C Explanation:

Procedure 0POP04-RC-002, Reactor Coolant Pump Off Normal, Technical

Reference:

Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # STP B20105- Modified X T50551-1 New

Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 5 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Group # 1 K/A # 2.1.4 Importance Rating 3.4 Proposed Question 11:

Given the following:

Assume that today is January 15 of the current year.

A Staff SRO, maintaining an "active" license, has performed the functions of an SRO during one 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shift since January 1.

Which ONE of the following actions will maintain the SROs license in an "active" status in accordance with 0POP01-ZA-0014, Licensed Operator Maintenance?

A. Two more 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shifts performing SRO functions during January.

One more 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shift performing SRO functions during February.

B. Two more 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shifts performing SRO functions during February.

Two more 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shifts performing SRO functions during March.

C. Two more 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shifts performing SRO functions during March.

Four more 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shifts performing SRO functions during April.

D. Two more 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shifts performing SRO functions during January.

One more 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shift performing SRO functions during March.

Four more 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shifts performing SRO functions during April.

Proposed Answer: B Explanation:

Two more 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shifts performing SRO functions during February, Two more 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shifts performing SRO functions during March.

Technical

Reference:

0POP01-ZA-0014, Licensed Operator Maintenance, Step 4.3 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # STP-854 Modified New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis

10 CFR Part 55 Content: 55.41 55.43 2 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Group # 3 K/A # 2.3.9 Importance Rating 3.4 Proposed Question 12:

Unit 2 containment pressure is 0.4 psig and requires a containment vent. The following conditions exist:

Mode 4

Containment Radiation Monitor RT-8011 is out-of-service, compensatory Tech Spec actions are being performed.

Reactor Containment Purge Permit has expired.

What is/are the action(s) for the above plant conditions?

A. Per Procedure 0POP02-HC-0003, "Supplementary Containment Purge," with Chemistry approval, a containment purge is allowed.

B. Per Procedure 0POP02-HC-0003, "Supplementary Containment Purge," conduct a containment purge, then notify Chemistry to update the Reactor Containment Purge Permit.

C. Per Technical Specification 3.3.3.1, obtain a new purge permit and then perform the containment purge.

D. Per Technical Specification 3.3.3.1, a containment grab sample must be obtained and analyzed prior to performing the containment purge.

Proposed Answer: A Explanation:

Per Procedure 0POP02-HC-0003, "Supplementary Containment Purge," with Chemistry approval, a containment purge is allowed.

Technical

Reference:

Procedure 0POP02-HC-0003, "Supplementary Containment Purge,"

Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # STP-1098 Modified New Question History: Last NRC Exam Class 13 Cognitive Level: X Memory or Fundamental Knowledge

Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 5 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Group # 4 K/A # 2.4.16 Importance Rating 4.0 Proposed Question 13:

The following conditions exist on Unit 1:

The crew is responding to an ORANGE path condition for CONTAINMENT by performing the actions of 0POP05-EO-FRZ1, Response to High Containment Pressure.

They have just performed the first substep for verifying Containment Ventilation Isolation when a RED path condition is noted for HEAT SINK.

No other RED or ORANGE paths exist.

Which ONE of the following indicates the correct procedure usage for this condition?

A. Complete all steps of 0POP05-EO-FRZ1, Response to High Containment Pressure, then transition to 0POP05-EO-FRH1, Response to Loss of Secondary Heat Sink.

B. Complete all steps of 0POP05-EO-FRZ1, Response to High Containment Pressure, then transition to 0POP05-EO-FRH1, Response to Loss of Secondary Heat Sink, only if the CFST for CONTAINMENT is satisfied.

C. Immediately transition to 0POP05-EO-FRH1, Response to Loss of Secondary Heat Sink without completing the step in progress in 0POP05-EO-FRZ1, Response to High Containment Pressure.

D. Complete the step in progress in 0POP05-EO-FRZ1, Response to High Containment Pressure, then transition to 0POP05-EO-FRH1, Response to Loss of Secondary Heat Sink.

Proposed Answer: B Explanation:

Complete the step in progress in 0POP05-EO-FRS1, Response to Nuclear Power Generation - ATWS, then transition to 0POP05-EO-FRH1, Response to Loss of Secondary Heat Sink Technical

Reference:

0POP01-ZA-0018, Rev 9; LOT504.04, Rev 6 Proposed references to be provided to applicants during examination:

Learning Objective: LOT 504.04 Obj 92245 Question Source: Bank # STP-352 Modified New Question History: Last NRC Exam Class 10

Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 5 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Group # 4 K/A # 2.4.27 Importance Rating 3.5 Proposed Question 14:

The following events have occurred on Unit 1with reactor power at 35%:

10:00 a.m. A fire in CP 004 required a control room evacuation due to heavy smoke.

10:02 a.m. All control room actions specified in Procedure 0POP04-ZO-0001, Control Room Evacuation were completed.

10:08 a.m. All remote shutdown stations were manned and ready.

10:10 a.m. Communications have been established between ASP and all remote shutdown operators.

10:11 a.m. All switches, required by Step 12 of Procedure 0POP04-ZO-0001, on auxiliary shutdown panel in the ASP position.

10:16 a.m. Step 11 of Procedure 0POP04-ZO-0001 is still in progress. Safe Shutdown Watch estimated that ESF Train B switchgear room alignment would be completed in 2 minutes. All other alignments completed.

Based on the above events, what actions are required:

A. The Unit 1 Shift Supervisor shall coordinate the fire response and declare an ALERT.

B. The Unit 2 Shift Supervisor shall coordinate the fire response and declare an ALERT.

C. The Unit 1 Shift Supervisor shall coordinate the fire response and declare a Site Area Emergency.

D. The Unit 2 Shift Supervisor shall coordinate the fire response and declare a Site Area Emergency.

Proposed Answer: D Explanation:

The unaffected Unit personnel shall coordinate the response to fires in the affected unit and common areas (0POP04-ZO-0008, Note before Step 2.0). Site Area emergency based on not completing Procedure 0POP04-ZO-0001 through Step 12 within 15 minutes.

Technical

Reference:

0POP04-ZO-0008, 0POP04-ZO-0001, and 0ERP01-ZV-IN01 Proposed references to be provided to applicants during examination:

Provide Emergency Classification Tables for Fire/Explosion, Control Room Evacuation, and Misc Events.

Learning Objective: LOT 504.50 Obj A92210

Question Source: Bank # STP Requal Modified X B50450-92210-05 New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 See explanation below Comments:

SRO only since SRO is responsible for emergency classification (if the emergency director) and is responsible for direction of fire brigade response.

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 029.EA2.01 Importance Rating 4.7 Proposed Question 15:

Unit 2 has experienced the following casualty:

A Steam Line Break inside containment has occurred.

0POP05-EO-EO00, Reactor Trip or Safety Injection was entered at Step 1 but the reactor failed to trip.

The crew then implemented 0POP05-EO-FRS1, Response to Nuclear Power Generation/ATWS.

At Step 16, "Verify Reactor Subcritical", the following conditions exist:

Extended Range NIs indicate 0%

Extended Range NIs SUR is + 0.2 dpm Which ONE of the following actions is required based on the given conditions?

A. Continue Emergency Boration and perform FRS1 and EO00 concurrently and implement actions of other Optimal Recovery Guidelines (ORPs) which do not cooldown or add positive reactivity.

B. Continue Emergency Boration and continue with FRS1 and implement actions of other Optimal Recovery Guidelines (ORPs) which do not cooldown or add positive reactivity.

C. Continue Emergency Boration and return to procedure and step in effect (EO00, Step 1).

D. Continue Emergency Boration and suspend actions of FRS1 until SUR is zero or negative.

Proposed Answer: B Explanation:

Technical

Reference:

POP05-EO-FRS1 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # STP-735 Modified New Question History: Last NRC Exam

Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 5 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 055.EA1.05 Importance Rating 3.6 Proposed Question 16:

Given the following conditions on Unit 2:

A loss of all AC power has occurred.

The operators are performing Procedure 0POP05-EO-EC00, "Loss of All AC Power."

Annunciator "125 V DC SYSTEM E2A11 TRBL" is in alarm.

Control Board Meter "BUS A11 TRN A CH 1" is reading 107 V dc.

What actions are required to be taken?

A. Transition to Procedure 0POP05-EO-ES05, "Natural Circulation Cooldown without Letdown," and open all reactor vessel head vent isolation valves and throttle open one head vent valve.

B. Transition to Procedure 0POP05-EO-ES02, "Natural Circulation Cooldown," and locally open SG PORVs to commence a cooldown.

C. Remain in Procedure 0POP05-EO-EC00 and per Attachment 4, de-energize 120 V AC non 1E loads.

D. Remain in Procedure 0POP05-EO-EC00 and per Attachment 4, open Breaker E2A11 1B, "BTRY E2A11 Main BKR."

Proposed Answer: D Explanation:

Technical

Reference:

Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # STP-340 Modified X New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41

55.43 5 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # 056.G.2.4.30 Importance Rating 3.6 Proposed Question 17:

Unit 1 is in Mode 5 and a loss of offsite power occurs. All three ESF DGs are supplying their respective buses. You as the shift manager have declared an Unusual Event. Describe the notifications required to be made by Procedure 0ERP01-ZV-IN02, Notifications to Offsite Agencies?

A. NRC Operations Center immediately and the State of Texas and Matagorda County no later than one hour after emergency declared.

B. State of Texas and Matagorda County within 15 minutes and the NRC Operations Center no later than one hour after emergency declared.

C. State of Texas and Matagorda County with 15 minutes and the NRC Region IV no later than one hour after emergency declared.

D. State of Texas, Matagorda County, and NRC Region IV no later than one hour after emergency declared.

Proposed Answer: B Explanation:

Technical

Reference:

Proc 0ERP01-ZV-IN02 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # STP- Modified New X Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 Comments:

SROs can and do have the responsibility of the emergency director and per the procedure are required to approve all notifications and make sure the notifications are made within the required time frame.

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # E04.EA1.3 Importance Rating 4 Proposed Question 18:

Unit 2 was operating at 100% power when a LOCA occurred in the FHB. The following conditions exist:

The crew is performing 0POP05-EO-EC12, "LOCA Outside Containment"

Train A ECCS and Containment Spray have been isolated based on high SI/CS sump level.

RCS temperature is slowly increasing

RCS Pressure continues to decrease Based on these conditions, what is the next action to be taken in accordance with 0POP05-EO-EC12, LOCA Outside Containment?

A. Transition to 0POP05-EO-ES12, "Post-LOCA Cooldown and Depressurization," to cool down and depressurize to Cold Shutdown conditions.

B. Remain in 0POP05-EO-EC12, "LOCA Outside Containment," and sequentially isolate the remaining ECCS and CS trains in an attempt to stop the leakage.

C. Transition to 0POP05-EO-EC11, "Loss of Emergency Coolant Recirculation," to cool down and depressurize to Cold Shutdown conditions.

D. Concurrently perform 0POP05-EO-EC11, "Loss of Emergency Coolant Recirculation," and 0POP05-EO-EC12, "LOCA Outside Containment."

Proposed Answer: B Explanation:

Assumptions - SBLOCA approximately 1.5" diameter in the FHB.

Technical

Reference:

0POP05-EO-EC12, LOCA Outside Containment, Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # STP- Modified New X Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis

10 CFR Part 55 Content: 55.41 55.43 5 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 K/A # 005.AA2.03 Importance Rating 4.4 Proposed Question 19:

The following conditions exits on Unit 1:

Reactor power is 20%

Control Bank D position is 118 steps

Rod Control is in automatic

Control rod Full Out Position (FOP) is 257 steps and Bank Overlap (BO) is 120 steps

SUFP is out of service for seal replacement At 0300 hours0.00347 days 0.0833 hours 4.960317e-4 weeks 1.1415e-4 months a rapid load reduction to 3% reactor power occurs due to a trip of the only available main feedpump. Control Bank D demand position is now 93 steps. The following subsequently occur:

At 0320 hours0.0037 days 0.0889 hours 5.291005e-4 weeks 1.2176e-4 months , the primary Reactor operator notices control rod C8 in Control Bank C and control rod D4 in Control Bank D did not move during the power reduction.

At 0430 hours0.00498 days 0.119 hours 7.109788e-4 weeks 1.63615e-4 months , I&C verified the stationary and moveable grippers and the lift coils are properly energized with the correct currents and in proper sequence.

Which ONE of the following indicates the correct action to be taken by the Control Room Staff?

A. Per Procedure 0POP04-RS-0001, "Control Rod Malfunction," declare control rod C8 and D4 inoperable; commence a rapid shutdown; and, be in Hot Standby by 0530 hours0.00613 days 0.147 hours 8.763227e-4 weeks 2.01665e-4 months .

B. Per Technical Specification 3.1.3.1, within one hour declare the rods inoperable and re-align the remaining rods in Control Bank C and D to within "12 steps of C8 and D4, respectively.

C. Per Procedure 0POP04-RS-0001, "Control Rod Malfunction," trip the reactor and go to Procedure 0POP05-EO-EO00, "Reactor Trip or Safety Injection."

D. Per Technical Specification 3.1.3.1, within one hour determine the shutdown margin requirement of Technical Specification 3.1.1.1 is satisfied and be in Hot Standby by 1030 hours0.0119 days 0.286 hours 0.0017 weeks 3.91915e-4 months .

Proposed Answer: C Explanation:

Technical

Reference:

Technical Specification 3.1.3.1 and Procedure 0POP04-RS-0001, "Control Rod Malfunction,"

Proposed references to be provided to applicants during examination:

Learning Objective: LOT 505.01 Obj 92108 Question Source: Bank # STP-3 Modified New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 2 and 5 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 K/A # 033.G2..4.11 Importance Rating 3.6 Proposed Question 20:

A plant startup is in progress.

At 7% power, the compensating voltage power supply in Intermediate Range Channel N35 failed. Reactor power is being maintained at 9% power until N35 is repaired.

What action(s) is required to be taken?

A. Initiate action within one hour to place the unit in Hot Standby within the next six hours.

B. Place the N35 LEVEL TRIP switch in the TRIP position and continue with the startup.

C. Place the N35 LEVEL TRIP switch in the BYPASS position and reduce reactor power to just below the P-6 setpoint within one hour D. Maintain reactor power less than 10% of rated thermal power until Channel N35 is repaired.

Proposed Answer: D Explanation:

Technical

Reference:

T.S. 3.3.1, Action 3 and Procedure 0POP04-NI-0001, Nuclear Instrument Malfunction Proposed references to be provided to applicants during examination:

Learning Objective: LOT503.01 Task # A92103 Question Source: Bank # STP- Modified X B50301-92103-19 New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 2 and 5 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 2 K/A # E16.G2.3.10 Importance Rating 3.3 Proposed Question 21:

Plant conditions are as follows:

A large break LOCA has occurred

Containment pressure = 9.2 psig

Containment water level = 62 inches

Containment radiation level = 2500 R/hr

RWST Level is 175,000 gallons Which procedure is appropriate for the above conditions:

A. Procedure 0POP05-EO-FRZ1, "Response to High Containment Pressure" B. Procedure 0POP05-EO-FRZ2, "Response to Containment Flooding" C. Procedure 0POP05-EO-FRZ3, "Response to High Containment Radiation Level" D. Procedure 0POP05-EO-ES13, "Transfer to Cold Leg Recirculation" Proposed Answer: C Explanation:

Technical

Reference:

0POP05-EO-FRZ3, "Response to High Containment Radiation Level" Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # STP-1099 Modified New Question History: Last NRC Exam Class 13 Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 5 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 K/A # 012.G2.1.32 Importance Rating 3.8 Proposed Question 22:

Which ONE of the following Reactor Trip System instrumentation setpoints is designed to protect the reactor core against Departure from Nucleate Boiling?

A. Power Range Positive Rate B. Overpower - Delta T C. Pressurizer High Pressure D. RCP Underfrequency Proposed Answer: D Explanation:

Technical

Reference:

T.S. Basis 2.2.1 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # STP-812 Modified New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 2 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Group # 3 K/A # 2.3.4 Importance Rating 3.1 Proposed Question 23:

A LOCA has occurred on Unit 1 and a SAE has just been declared. The TSC and EOF have been activated.

To prevent core damage it is recommended that entry be made into Safety Injection Pump Room 1A.

Projected dose rate in the Pump Room is 1.16E+5 mR/hr.

Duration of the exposure is expected to be 3 minutes.

Who must authorize this exposure?

A. Radiological Director B. Emergency Director C. Plant Manager D. Vice President of Nuclear Group Proposed Answer: B Explanation:

Technical

Reference:

0ERP01-ZV-IN06; 0PGP03-ZR-0050 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # 661 Modified New Question History: Last NRC Exam Cognitive Level: X Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 4 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 3 Group # 3 K/A # 2.2.5 Importance Rating 2.7 Proposed Question 24:

You are the Unit Supervisor for Unit 1. Currently Unit 1 is in Mode 1 with 79 days remaining until the refueling outage. Accumulator Tank 1C is experiencing problems with increased RCS backleage and requires draining twice per shift and the leak rate is increasing. In order to continue operation, a work package has been developed to shut Accumulator Tank 1C Discharge Isolation Valve, 1MOV-0039C.

The valve will be modified to receive an open signal on low RCS pressure and/or safety injection actuation signal.

What are the requirements for this modification to be implemented?

A. Since this modification will inservice for less than 90 days, process this work package through the temporary modification process.

B. Since this modification may affect the safety injection function, process this work package through the 10 CFR 50.59 evaluation process.

C. Since this modification is a change to the safety injection system as described in the FSAR, a technical specification amendment is required.

D. Since this modification meets the same functional requirements as the original design, the work package can be approved for implementation.

Proposed Answer: B Explanation:

Technical

Reference:

Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # STP- Modified New X Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 3 Comments:

ES-401 Written Examination Question Worksheet Form ES-401-5 Examination Outline Cross-reference: Level RO SRO Tier # 1 Group # 1 K/A # APE 057.G.2.4.45 Importance Rating Proposed Question 25:

Unit 1 is operating at 100% power and the following annunciator alarms, AC Bus DP 1202 U/V. The plant remains at 100% power. What actions are required?

A. Since the plant should have tripped due to loss of power to DP 1202, immediately trip the reactor and enter Procedure 0POP05-EO-EO00, Reactor Trip or Safety Injection.

B. Since this would cause Steam Generator Feed Pump 12 to trip, immediately begin reducing reactor power per Procedure 0POP04-TM-0005, Fast Load Reduction.

C. Enter Procedure 0POP04-VA-0001, Loss of 120 VAC Class Vital Distribution, and re-energize Bus DP 1202 within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

D. Enter Procedure 0POP04-VA-0001, Loss of 120 VAC Class Vital Distribution, and re-energize Bus DP 1202 within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Proposed Answer: D Explanation:

Technical

Reference:

Procedure 0POP04-VA-0001 and TS 3.8.3.1 Proposed references to be provided to applicants during examination:

Learning Objective:

Question Source: Bank # STP- Modified X B50301-92104-10 New Question History: Last NRC Exam Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 5 Comments:

ML033430138

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