ML103350273

2010 Clinton Power Station Initial License Examination as Administered Written Examination

ML103350273
Person / Time
Site:	Clinton
Issue date:	11/01/2010
From:	Moore C Operations Branch III
To:	AmerGen Energy Co
References
Download: ML103350273 (171)

Text

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 1 of 171 15 October 2010 1

ID: CL-ILT-9931 Points: 1.00 Which one of the following is a consequence of allowing suppression pool water level to drop to 13.0 feet?

Suppression pool water level at this value...

A.

results in uncovering of the SRV spargers.

B.

results in uncovering the upper horizontal vent.

C.

reduces the available net positive suction head for the Reactor Core Isolation Cooling pump below minimum required.

D.

reduces the available net positive suction head for the High Pressure Core Spray pump below minimum required.

Answer:

B Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 2

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 295030 Low Suppression Pool Water Level EK1.01 - Knowledge of the operational implications of the following concepts as they apply to LOW SUPPRESSION POOL WATER LEVEL: Steam condensation 3.8 Level RO Tier 1

Group 1

General References EOP-6 bases Explanation A. A is incorrect, the SRV spargers are five feet from the bottom of the suppression pool.

B. B is correct, the top horizontal vent will not be covered.

C. C is wrong, 11 feet is the minimum required level for RCIC and HPCS operation.

D. D is wrong, 11 feet is the minimum required level for RCIC and HPCS operation.

References to be provided during exam:

None

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 2 of 171 15 October 2010 Learning Objective 223001.03 DESCRIBE the function, operation, interlocks, trips, and power supplies of the following PRIMARY CONTAINMENT System components.

.1 Containment Structure

.2 Basemat

.3 Reactor Vessel Pedestal

.4 Biological Shield Wall

.5 Drywell

.6 Reactor Cavity Bellows

.7 Weir Wall

.8 Horizontal Vents

.9 Suppression Pool

.10 ECCS Suction Strainer

.11 Vacuum Breakers

.12 Containment Sprays

.13 Penetrations

.14 Guard Pipe

.15 Airlocks

.16 Containment Pools Question Source (New, Modified, Bank)

New Cognitive Level Low cognitive level recall levels in the suppression pool.

10CFR55 Content 55.41 14 55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 3 of 171 15 October 2010 2

ID: CL-ILT-6502 Points: 1.00 An accident occurred that required the initiation of containment sprays due to elevated containment temperatures and pressures. After containment spray has been initiated the following containment/drywell conditions exist:

- Containment pressure 0.1 psig and lowering at rate of.05 psig/min

- Containment temperature 185°F

- Drywell temperature 250°F Which of the following actions is required and why?

A.

Stop containment spray to avoid exceeding negative containment design pressure.

B.

Continue containment sprays to prevent exceeding containment design temperature.

C.

Stop containment sprays due to entry into the unsafe region of the Containment spray initiation limit (Fig. O).

D.

Continue containment sprays to maintain containment pressure below pressure suppression pressure (Fig. N).

Answer:

A Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 1

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 295024 High Drywell Pressure EK1.02 - Knowledge of the operational implications of the following concepts as they apply to HIGH DRYWELL PRESSURE : Containment building integrity:

Mark-III 3.9 Level RO Tier 1

Group 1

General References EOP-6 Bases Explanation Explanation: Containment sprays must be terminated by the time containment pressure decreases to 0 psig to ensure that pressure is not reduced below the negative design value.

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 4 of 171 15 October 2010 Distracters:

B is incorrect as containment sprays are not allowed for containment pressure below 0 psig.

C is incorrect because even though sprays should be stopped the reason is incorrect. Entry into the shaded region is allowed following initiation of sprays.

D is incorrect as containment sprays are not allowed for containment pressure below 0 psig.

High drywell condition is required as a permissive for containment spray initiation.

References to be provided during exam:

EOP's with entry conditions removed.

Block out stop containment sprays Learning Objective LP87558.01.11 Given a decreasing trend in containment pressure, state the pressure before which Containment Spray operation must be stopped.

Question Source (New, Modified, Bank)

Bank Cognitive Level High analysis of plant conditions 10CFR55 Content 55.41 7

55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 5 of 171 15 October 2010 3

ID: CL-ILT-6439 Points: 1.00 On the AR/PR Display, the Common Station HVAC Exhaust Stack Monitor, 0RIX-PR001 indicating tile is RED due to CHANNEL 5, LO NBL GAS, and has NOT reached the EAL threshold.

When it is verified that this indication is valid and steady, it is immediately required to enter

___(1)___.

The Accident Range HVAC Monitor, 0RIX-PR012 should be in ___(2)___.

A.

(1) EOP-9, Radioactivity Release Control (2) Standby B.

(1) CPS 4979.01, ABNORMAL RELEASE OF AIRBORNE RADIOACTIVITY (2) Standby C.

(1) EOP-9, Radioactivity Release Control (2) Operation D.

(1) CPS 4979.01, ABNORMAL RELEASE OF AIRBORNE RADIOACTIVITY (2) Operation Answer:

D Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 4

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 295038 High Off-site Release Rate EA2.03 - Ability to determine and/or interpret the following as they apply to HIGH OFF-SITE RELEASE RATE : Radiation levels 3.5 Level RO Tier 1

Group 1

General References Off normal 4979 5140.41 Explanation RED Tile implies HIGH Alarm. 0RIX-PR001in High Alarm starts 0RIX-PR012. This gives the operator the ability to determine off site release rates.

D is correct, 0RIX-PR012 is in operation; enter Abnormal Release of Airborne Radioactivity.

A is incorrect, 0RIX-PR012 is in operation, enter Abnormal Release

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 6 of 171 15 October 2010 of Airborne Radioactivity.

B is incorrect, 0RIX-PR012 is in operation.

C is incorrect, enter Abnormal Release of Airborne Radioactivity.

References to be provided during exam:

None Learning Objective DB497901.01.01 Given specific plant conditions, determine if CPS No.

4979.01, ABNORMAL RELEASE OF AIRBORNE RADIOACTIVITY, should be used.

Question Source (New, Modified, Bank)

Bank 08 NRC Cognitive Level High analysis of plant response and operator actions due to indications received.

10CFR55 Content 55.41 11 55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 7 of 171 15 October 2010 4

ID: CL-ILT-6921 Points: 1.00 The unit is operating at rated power.

Annunciator 5040-1B, AUTO TRIP PUMP/MOTOR, actuates when CC pump 1C trips.

A few seconds later annunciator 5003-3D, RECIRC MTR A WDG CLG WTR FLOW LO actuates.

Three minutes later annunciator 5003-1K, RECIRC PMP MTR A OR B TEMP HI actuates.

How can the control room operator determine which Reactor Recirculation (RR) Pump component temperature is causing the alarm?

A.

Direct the Equipment Operator to check RR temperatures at local panel B33-P001A(B).

B.

Direct the Equipment Operator to check RR temperatures at local HPU panel.

C.

Check RR temperatures on Control Room panel 1H13-P614.

D.

Check RR temperatures on Control Room panel 1H13-P678 standby information panel.

Answer:

C Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 3

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 295018 Partial or Total Loss of CCW AA2.01 - Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER : Component temperatures 3.3 Level RO Tier 1

Group 1

General References 5003.01K Explanation The RR pumps' motor winding, bearing, seal, and cooling water outlet temperatures are recorded on recorder 1B33-R601 at panel 1H13-P614. H13-P678 has recirc. pump speed and secondary containment temperatures.

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 8 of 171 15 October 2010 References to be provided during exam:

None Learning Objective 4000001.06 Given a Component Cooling Water System Annunciator, DESCRIBE:

a.

The condition causing the annunciator

b.

Any automatic actions

c.

Any operational implications

.1 CCW HX Outlet Header Pressure

.2 CCW Pump Amps Question Source (New, Modified, Bank)

Bank 06 NRC Cognitive Level Low monitoring indications based on plant conditions.

10CFR55 Content 55.41 4

55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 9 of 171 15 October 2010 5

ID: CL-ILT-6567 Points: 1.00 Plant conditions are as follows:

- The unit is shutdown with a coolant temperature of 320 degrees F.

- Reactor pressure is 75 psig.

- Both loops of RHR Shutdown Cooling are operable but neither has been in operation for the last hour.

- Recirc loop 'A' is shutdown and isolated due to a failed pump seal.

- Recirc loop 'B' has just tripped for unknown reasons.

What action(s) if any is/are required?

A.

No actions are required. Shutdown cooling and reactor recirc may be removed for up to eight hours.

B.

Immediately start both loops of RHR Shutdown Cooling.

C.

Verify an alternate method of decay heat removal is available within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ONLY.

D.

Immediately initiate action to restore one RHR Shutdown Cooling Subsystem to service and verify alternate coolant circulation method within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and monitor coolant temperature and pressure once per hour.

Answer:

D Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 4

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 295021 Loss of Shutdown Cooling 2.2.39-Equipment Control: Knowledge of less than or equal to one hour Technical Specification action statements for systems.

3.9 Level RO Tier 1

Group 1

General References Tech Spec. 3.4.9 Explanation Per CPS technical specifications 3.4.9

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 10 of 171 15 October 2010 References to be provided during exam:

None Learning Objective 203000.13 Given RESIDUAL HEAT REMOVAL System key parameter indications and plant conditions, DETERMINE if the Tech Spec LCOs have been met for one hour or less LCOs.

Question Source (New, Modified, Bank)

Bank Cognitive Level High cognitive analysis and application of plant conditions and one hour or less technical specifications.

10CFR55 Content 55.41 10 55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 11 of 171 15 October 2010 6

ID: CL-ILT-0954 Points: 1.00 In accordance with CPS No. 4003.01, Remote Shutdown, which of the following Subsequent Operator Actions is to be performed ON the Remote Shutdown Panel after the Control Room has been abandoned?

A.

Ensure that all control rods receive a scram signal by placing the Group Solenoid breakers in OFF.

B.

Close the MSIVs by placing the breakers for the inboard and outboard solenoids in OFF.

C.

If the Unit Sub Feed Breaker 1AP09EB on 4160V Bus 1B1 trips, attempt to close the breaker.

D.

If RCIC is NOT running, start RCIC and establish level and pressure control as necessary.

Answer:

D Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 4

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 295016 Control Room Abandonment G2.4.11 Knowledge of abnormal condition procedures.

4.0 Level RO Tier 1

Group 1

General References IAW 4003.01 COO2 Explanation IAW 4003.01 COO2 RCIC is started to maintain inventory and pressure control. RCIC controls are located on the remote shutdown panel.

References to be provided during exam:

None Learning Objective DB400301.01.01 Given specific plant conditions, determine if CPS No. 4003.01 REMOTE SHUTDOWN (RS) should be used.

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 12 of 171 15 October 2010 Question Source (New, Modified, Bank)

Bank Cognitive Level Low recall of basis in evacuation procedure.

10CFR55 Content 55.41 10 55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 13 of 171 15 October 2010 7

ID: CL-ILT-0614 Points: 1.00 The plant is at 56% reactor power, steady state. The A CRD pump has failed. The B CRD pump has NOT been started.

Which ONE of the following describes the IMMEDIATE effect on the control rod drive system during the time when NEITHER CRD pumps are running.

A.

The control rods will begin to drift out.

B.

The control rods CANNOT be scrammed.

C.

The control rod drive mechanism temperatures will begin rising.

D.

The control rod scram times will exceed technical specification limits.

Answer:

C Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 3

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 295022 Loss of CRD Pumps AA1.01 - Ability to operate and/or monitor the following as they apply to LOSS OF CRD PUMPS:

CRD hydraulic system 3.1 Level RO Tier 1

Group 2

General References ARP 5068-3B M05-1078 5006-1G Explanation A. Incorrect-Scram times will remain the same as long as the accumulators are pressurized and the plant is at rated pressure.

B. Incorrect-Rods will remain at current location with the collet fingers.

C Correct-Temperatures will begin to overheat.

D. Incorrect-Scram times will not be exceeded.

References to be provided during exam:

None Learning Objective Discuss the effect of a loss of CRD has on the plant.

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 14 of 171 15 October 2010 Question Source (New, Modified, Bank)

Bank Cognitive Level Low recall of the effect of loss of CRD on an operating plant.

10CFR55 Content 55.41 6

55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 15 of 171 15 October 2010 8

ID: CL-ILT-6257 Points: 1.00 Which of the following describes INITIAL reactor water level response to a reactor scram initiated by a main turbine generator trip from rated conditions?

Other than the Turbine Trip all other systems function as expected.

A.

Reactor water level lowers due to the higher pressure in the core region.

B.

Reactor water level remains the same due to the collapsing voids in the core region and auto start of the motor driven reactor feed water pump.

C.

Reactor water level rises due to the higher pressure in the core region.

D.

Reactor water level lowers due to lower pressure in the core region.

Answer:

A Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 1

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 295006 SCRAM AK3.01 - Knowledge of the reasons for the following responses as they apply to SCRAM : Reactor water level response 3.8 Level RO Tier 1

Group 1

General References Fundamental Explanation The pressure spike from the turbine trip collapses the voids in the reactor. The reactor water level is measured outside the the shroud when the voids are collapsed indicated level lowers.

References to be provided during exam:

None Learning Objective DB410001.01 Given specific plant conditions, determine if CPS No.

4100.01, REACTOR SCRAM should be used.

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 16 of 171 15 October 2010 Question Source (New, Modified, Bank)

Modified Cognitive Level Low response to reactor scram.

10CFR55 Content 55.41 5

55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 17 of 171 15 October 2010 9

ID: CL-ILT-9932 Points: 1.00 Plant is operating at 97%

'B' Turbine driven reactor feed pump trips RR FCV runback occurs Reactor power is 65%

Using the attached figures determine the proper RPC MODE display which reflects current plant conditions.

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 18 of 171 15 October 2010

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 19 of 171 15 October 2010

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 20 of 171 15 October 2010

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 21 of 171 15 October 2010

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 22 of 171 15 October 2010 A.

A B.

B C.

C D.

D Answer:

C Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 3

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 295001 Partial or Complete Loss of Forced Core Flow Circulation AA1.04 - Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION : Rod control and information system: BWR-5&6 2.6 Level RO Tier 1

Group 1

General References 3005.01 Explanation The RPC Mode will change based on reactor power. Post transient the mode will automatically change to the light above the low power alarm point being lit at 70% reactor power only.

References to be provided during exam:

None Learning Objective 201002.04 STATE the physical location and function of the following RC&IS system components, controls, indicators, and/or sensors.

.1 Display Selection Matrix

.2 System Mode Matrix

.3 Rod Motion Matrix

.4 Pattern Control Matrix

.5 Rod Select Matrix

.6 Core Map Display

.7 Rod Status-Rod Position

.8 Gang Position Display

.9 LPRM Level

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 23 of 171 15 October 2010

.10 RPC Mode

.11 LPRM Status

.12 RACC Plant Status Display Question Source (New, Modified, Bank)

New Cognitive Level High analysis of data as it applies to the RPC.

10CFR55 Content 55.41 6

55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 24 of 171 15 October 2010 10 ID: CL-ILT-5277 Points: 1.00 Given the following:

- A routine reactor startup is in progress.

- All IRMs are on range 3.

- The main turbine is reset.

- A valid MSIV isolation has occurred.

- The reactor did NOT scram.

- ATWS conditions do NOT exist.

WHICH of the following signals directly caused the MSIV isolation.

A.

Low reactor water level.

B.

High main steam line flow.

C.

Low main condenser vacuum.

D.

High main steam line radiation.

Answer:

B Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 2

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 212000 RPS K1.14 - Knowledge of the physical connections and/or cause-effect relationships between REACTOR PROTECTION SYSTEM and the following: Main Steam 3.6 Level RO Tier 2

Group 1

General References 3101.01 Section 8.1.1.2 Caution page 11 Explanation High Main steam flow group one isolation is never bypassed the other isolations are bypassed in S/U.

Except low level and the stem states a scram condition does not exist.

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 25 of 171 15 October 2010 With the turbine reset the main condenser vacuum is established.

References to be provided during exam:

None Learning Objective 239001.05 Discuss the MAIN STEAM system automatic functions/interlocks including purpose, signals, set points, sensing points, when bypassed, how/when they are.

Question Source (New, Modified, Bank)

Bank Cognitive Level High analysis of plant conditions and interlocks.

10CFR55 Content 55.41 7

55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 26 of 171 15 October 2010 11 ID: CL-ILT-6363 Points: 1.00 Reactor startup is in progress. The reactor is NOT critical.

Predict the effect of a loss of the SRM C High Voltage Power Supply, AND what would be the necessary operator action?

A.

ROD BLOCK. Operator must insert control rods in reverse sequence.

B.

ROD BLOCK. Operator must bypass the affected channel before continuing with the startup.

C.

Single RPS Channel TRIP. Operator must bypass the affected channel before continuing with the startup.

D.

Single RPS Channel TRIP. Operator must suspend startup until repairs are competed.

Answer:

B Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 2

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 215004 Source Range Monitor K3.03 - Knowledge of the effect that a loss or malfunction of the SOURCE RANGE MONITOR (SRM) SYSTEM will have on following: Rod control and information system: Plant-Specific 3.3 Level RO Tier 2

Group 1

General References ARP 5006-2H ARP5005-1K 3306.01 precaution 2.7 Explanation This condition will inop the SRM at the drawer.

Insert rods in reverse sequence is required when a reactivity anomaly exists.

If the CRS deems the repairs are short term the RO may be told to place the start up on hold and maintain reactor power.

The shorting links are not removed there fore this condition will NOT

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 27 of 171 15 October 2010 cause a reactor scram.

References to be provided during exam:

None Learning Objective 215004.03 DESCRIBE the function, operation, interlocks, trips, physical location, and power supplies of the following Source Range Monitoring System components.

.1Detector Drive Motor Assemblies

.2 Pulse Preamplifier

.3 High Voltage Power Supply (HVPS)

.4 Discriminator Module

.5 Computer Module

.6 Display Control Module

.7 Input/Output Module Question Source (New, Modified, Bank)

Bank Cognitive Level High analysis of plant conditions due to loss of power supply to the instrument drawer.

10CFR55 Content 55.41 6

55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 28 of 171 15 October 2010 12 ID: CL-ILT-0419 Points: 1.00 A large pipe break occurs in the Drywell resulting in Drywell pressure exceeding 3.0 psig.

All ECCS systems responded as designed.

If NO operator actions are taken, when will the ADS valves open?

A.

Immediately after exceeding the high Drywell pressure setpoint, RPV Level 3 AND RPV Level 1 signals.

B.

105 seconds after receiving the high Drywell pressure, RPV Level 3 AND RPV Level 1 signals.

C.

Six (6) minutes after receiving the high Drywell pressure, RPV Level 3 AND RPV Level 1 signals.

D.

Six (6) minutes after receiving the high Drywell pressure AND RPV Level 1 signals.

Answer:

B Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 2

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 218000 ADS K4.01 - Knowledge of AUTOMATIC DEPRESSURIZATION SYSTEM design feature(s) and/or interlocks which provide for the following: Prevent inadvertent initiation of ADS logic 3.7 Level RO Tier 2

Group 1

General References MS 3101.01 Explanation Correct: B - Getting a high DW pressure combined with both a RPV Level 3 AND Level 1 signal starts the 105 second timer. ADS will initiate provided the Low Pressure Pump permissive is satisfied.

Incorrect: A - Initiation is delayed by 105 seconds.

Incorrect: C-Six (6) minute time delay is not in effect with a high DW

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 29 of 171 15 October 2010 pressure signal present.

Incorrect: D-Six (6) minute time delay is not in effect with a high DW pressure signal present.

Level 3 is the confirmatory logic to prevent inadvertant initiation.

References to be provided during exam:

None Learning Objective 218000.03 DESCRIBE the function, operation, interlocks, trips, physical location and power supplies of the following AUTOMATIC DEPRESSURIZATION (ADS) System components.

.1 ADS Logic

.2 105 Second Timer

.3 6 Minute Timer Question Source (New, Modified, Bank)

Bank Cognitive Level Low recall of ADS initiation logic.

10CFR55 Content 55.41 7

55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 30 of 171 15 October 2010 13 ID: CL-ILT-7020 Points: 1.00 The plant is operating at rated power, with the following:

- High Drywell Pressure scram occurs and a loss of 345 KV occurs simultaneously

- ERAT fails to pick up Bus 1B1

- All DGs respond as designed How long after the loss of 345KV before the B RHR Pump is expected to start?

A.

5 seconds B.

12 seconds C.

17 seconds D.

22 seconds Answer:

C Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 3

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 264000 EDGs K5.06 - Knowledge of the operational implications of the following concepts as they apply to EMERGENCY GENERATORS (DIESEL/JET) : Load sequencing 3.4 Level RO Tier 2

Group 1

General References 1RH99-sht 001 9080.02 discussion 2.1.3 Explanation C is correct. LPCI Pump B starts 5 seconds after its bus (1B1) is energized. Because the ERAT failed, the pump must wait for the DG to start, come up to speed, and close in on Bus 1B1, a total of 12 seconds. Add to that another 5 seconds (for the 1B1 Power Monitor Relay to sense bus voltage from the DG), for a total elapsed

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 31 of 171 15 October 2010 time of 17 seconds after the loss of 345KV.

References to be provided during exam:

None Learning Objective 264000.05 Discuss the DIESEL GENERATOR/DIESEL FUEL OIL system automatic functions/interlocks including purpose, signals, set points, sensing points, when bypassed, how/when they are.

.1 Local/Remote Panels

.2 Diesel Generators

.3 Air Compressor

.4 Air Receiver

.5 Air Dryers

.6 Fuel Oil Storage Tank

.7 Fuel Oil Day Tank Question Source (New, Modified, Bank)

Bank Cognitive Level High cognitive level analysis of diesel loading during plant transient.

10CFR55 Content 55.41 7

55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 32 of 171 15 October 2010 14 ID: CL-ILT-6956 Points: 1.00 The plant is in Mode 4 with RHR B in Shutdown cooling.

- Reactor coolant temperature is 180 °F.

- Lake temperature is 80 °F.

- Plant cooldown rate is 50 °F/hr.

- 1E12-F003B, RHR B Hx Outlet Valve is 60% open.

- 1E12-F048B, RHR B Hx Bypass Valve is 50% open.

- Decay heat load will LOWER by 60% over the next hour.

Assume that all heat being removed is from decay heat, and ambient losses remain constant.

Which one of the following is the procedurally directed action that will maintain the 50 °F/hr cooldown rate for the next hour?

A.

Throttle open 1E12-F048B, RHR B Hx Bypass Valve.

B.

Throttle shut 1E12-F048B, RHR B Hx Bypass Valve.

C.

Throttle open 1E12-F003B, RHR B Hx Outlet Valve.

D.

Leave components in current status.

Answer:

A Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 1

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 205000 Shutdown Cooling System (RHR Shutdown Cooling Mode)A1.01 Ability to predict and/or monitor changes in parameters associated with operating the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) controls including: Heat exchanger cooling flow 3.3 Level RO Tier 2

Group 1

General References 3312.03 pg 26 8.1.2.21

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 33 of 171 15 October 2010 Explanation To control the cooldown rate you have to bypass the heat exchanger in order to lower the rate at which the plant is cooling down.

References to be provided during exam:

None Learning Objective 203000.02 DESCRIBE the major flow paths for the following modes of the RESIDUAL HEAT REMOVAL System operation.

.1 Shutdown Cooling Mode (both returning to Feedwater and the Upper Containment Pools).

.2 Suppression Pool Cooling Mode

.3 Low Pressure Coolant Injection Mode

.4 Containment Spray Mode

.5 Fuel Pool Cooling Assist Mode

.6 Water Leg Pump (Normal, Minimum Flow, Test).

.7 RHR System SDC Flush Question Source (New, Modified, Bank)

Bank 06 NRC Cognitive Level High cognitive level analysis of plant conditions.

10CFR55 Content 55.41 5

55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 34 of 171 15 October 2010 15 ID: CL-ILT-1235 Points: 1.00 RCIC was operating for a full flow test when a RCIC turbine exhaust pressure trip occurred.

(1) Which one of the following describes the Main Control Room indications for the RCIC Turbine Trip-Throttle Valve (TTV), C002E, indicator lights PRIOR to resetting the turbine trip?

(2) When the cause of the trip is corrected what actions are required to reset the trip throttle valve?

A.

(1) Turbine Trip Valve Stem GREEN light on, and RCIC Turbine Trip Vlv Opr GREEN light on.

(2) Place the TTV to close ONLY.

B.

(1) Turbine Trip Valve Stem RED light on, and RCIC Turbine Trip Vlv Opr RED light on.

(2) TTV must be reset locally.

C.

(1) Turbine Trip Valve Stem GREEN light on, and RCIC Turbine Trip Vlv Opr RED light on.

(2) Place the TTV to close, after it is closed take it to open.

D.

(1) Turbine Trip Valve Stem RED light on, and RCIC Turbine Trip Vlv Opr GREEN light on.

(2) Place the TTV to close, after it is closed take it to open.

Answer:

C Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 3

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 217000 Reactor Core Isolation Cooling System (RCIC)

A2.02 Ability to (a) predict the impacts of the following on the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Turbine trips 3.8 Level RO Tier 2

Group 1

General References 3310.01 page 20 8.1.6.8

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 35 of 171 15 October 2010 Explanation The indications and resets are based on an electrical turbine trip. A mechanical over speed trip is the only trip that is required to be reset locally.

References to be provided during exam:

None Learning Objective 217000.09 DISCUSS the effect:

.1 A total loss or malfunction of the REACTOR CORE ISOLATION COOLING (RI) System has on the plant.

.2 A total loss or malfunction of various plant systems has on the REACTOR CORE ISOLATION COOLING (RI) System.

Question Source (New, Modified, Bank)

Modified Cognitive Level High analysis of plant conditions and resetting of the TTV based on the trip given.

10CFR55 Content 55.41 5

55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 36 of 171 15 October 2010 16 ID: CL-ILT-6456 Points: 1.00 Given the following:

- Division 1 125 VDC is de-energized and unavailable.

How will the manual initiation pushbuttons affect the ADS valve position?

If ONLY the A & E ADS manual initiation pushbuttons are armed and depressed, ADS valves WILL ____(1)____.

If ONLY the B & F ADS manual initiation pushbuttons are armed and depressed, ADS valves WILL ____(2)____.

A.

(1) open (2) open B.

(1) open (2) NOT open C.

(1) NOT open (2) open D.

(1) NOT open (2) NOT open Answer:

C Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 3

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 239002 Relief/Safety Valves K6.04 Knowledge of the effect that a loss or malfunction of the following will have on the RELIEF / SAFETY VALVES : D.C.. power: Plant-Specific 3.0 Level RO Tier 2

Group 1

General References E02-1NB99 Explanation A. Incorrect - See "c.".

B. Incorrect - See "c.".

C. Correct - ADS channels A & E are powered from Div 1 125

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 37 of 171 15 October 2010 VDC.

D. Incorrect - See "c.".

References to be provided during exam:

None Learning Objective 239001.07 Given the MAIN STEAM system, DESCRIBE the systems supporting and the nature of the support.

.1 Condensate System

.2 MSIV Leakage Control System

.3 Reactor Protection System

.4 Containment/Reactor Vessel Isolation Control System

.5 Instrument Air

.6 Steam Bypass and Pressure Control System

.7 AC Electrical Distribution System

.8 DC Electrical Distribution System

.9 Nuclear Steam Supply Shutoff System

.10 Suppression Pool

.11 Remote Shutdown Question Source (New, Modified, Bank)

Bank Cognitive Level High effect of ADS on loss of DC bus 10CFR55 Content 55.41 5

55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 38 of 171 15 October 2010 17 ID: CL-ILT-6997 Points: 1.00 The following plant conditions exist:

Reactor Power is 60%.

Reactor Recirculation Pumps are in fast speed.

TDRFPs A and B are in service, with flow through each feed pump approximately equal.

The amber Control Signal Failure light for TDRFP A on 1H13-P680 has just turned on.

Then a trip of a Reactor Recirculation pump occurs.

There are NO scram signals generated within the next 30 seconds.

With NO operator action over the next 30 seconds, describe the expected response of 'A' TDRFP (consider all parameters that effect the pump):

A.

flow will rise.

B.

flow will lower.

C.

flow will NOT change.

D.

will trip on low suction pressure.

Answer:

A Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 1

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 259002 Reactor Water Level Control System A3.10 Ability to monitor automatic operations of the REACTOR WATER LEVEL CONTROL SYSTEM including: TDRFP lockup: TDRFP 3.1 Level RO Tier 2

Group 1

General References 3103.01 5002.03 Explanation

a. Suction pressure will raise and even though the speed is locked, the flow will raise Distracters

b. Flow will rise due to rising suction pressure

c. Flow will rise due to rising suction pressure

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 39 of 171 15 October 2010

d. Suction pressure will rise References to be provided during exam:

None Learning Objective 259002.15 G iven FEEDWATER CONTROL System initial conditions, PREDICT how the system and/or plant parameters will respond to the manipulation of the following controls.

.1 Control signal failure to the Feed Reg Valve (1FW004)

.2 Control signal failure to a Turbine Driven Reactor Feedwater Pump

.3 Reactor Feedwater Pump Flow Controller failure

.4 Reactor water level signal failure (high/low/as is) to the Startup Level Controller

.5 Reactor water level signal failure (high/low/as is) to the Master Level Controller

.6 Feedwater flow signal failure to the Master Level Controller

.7 Steam flow signal failure to the Master Level Controller

.8 Startup Level Controller failure

.9 Master Level Controller failure

.10 Loss of 125VDC Question Source (New, Modified, Bank)

Bank Cognitive Level High cognitive level analysis of plant response.

10CFR55 Content 55.41 55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 40 of 171 15 October 2010 18 ID: CL-ILT-6046 Points: 1.00 The SERVICE AIR HEADER PRESSURE gauge on P800 has three colored bands: Green, Yellow, and Red.

WITHOUT operator action, which ONE of the following describes the expected status of Plant Air components ONE MINUTE after an operator sees the reading on the gauge drop into the RED band because of a significant air leak?

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 41 of 171 15 October 2010 A.

TWO service air compressors are running; one or more automatic ring header

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 42 of 171 15 October 2010 isolations are CLOSED.

B.

ONLY ONE service air compressor is running; all automatic ring header isolations are OPEN.

C.

TWO service air compressors are running; all automatic ring header isolations are OPEN.

D.

ALL THREE service air compressors are running; one or more automatic ring header isolations are CLOSED.

Answer:

A Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 1

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 300000 Instrument Air System (IAS) A4.01Ability to manually operate and / or monitor in the control room:

Pressure gauges 2.6 Level RO Tier 2

Group 1

General References 5041-5C 3214.01 Explanation The RED band covers pressures at or below 70 psig (observed in both the MCR and Simulator configurations). Per CPS 5041-6B, the standby air compressor should have auto-started at 80 psig (lowering); therefore, two are now running. Per CPS 5041-5C, the ring header isolations should close at 70 psig (lowering). The stem uses one minute as a way to ensure that all portions of the Plant Air system have had sufficient time to sense the lowered pressure, and to ensure that all affected ring header auto isolations have closed as a result.

During normal plant operation one are compressor is in pull to lock.

References to be provided during exam:

None Learning 300000.09 DISCUSS the effect:

A total loss or malfunction of the Service and Instrument Air System

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 43 of 171 15 October 2010 Objective has on the plant.

A total loss or malfunction of various plant systems has on the Service and Instrument Air System.

Question Source (New, Modified, Bank)

Bank Cognitive Level High cognitive level analysis of plant response for given conditions.

10CFR55 Content 55.41 7

55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 44 of 171 15 October 2010 19 ID: CL-ILT-0050 Points: 1.00 A plant transient resulted in automatically starting the Low Pressure Core Spray (LPCS) System.

The following conditions exist:

• The LPCS automatic initiation signal from a low RPV level has NOT been reset.

• Reactor pressure is 190 psig and trending down slowly

• The LPCS to CONTAINMENT OUTBOARD ISOLATION VALVE, 1E12-F005, is CLOSED for level control by the operator.

• Drywell pressure 1.2 psig and trending down

. RPV water level indicates +55 inches on Narrow range instruments and trending down slowly.

Establishing LPCS injection flow requires..........

A.

No operator actions. The LPCS to CONTAINMENT OUTBOARD ISOLATION VALVE, 1E12-F005 will re-open when the Reactor Water Level 8 signal clears.

B.

No operator actions. The LPCS to CONTAINMENT OUTBOARD ISOLATION VALVE, 1E12-F005 will re-open when the Reactor Water Level 1 signal occurs.

C.

manually opening LPCS to CONTAINMENT OUTBOARD ISOLATION VALVE, 1E12-F005.

D.

depressing LPCS/LPCI 'A' Manual Initiation push button.

Answer:

C Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 3

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 209001 Low Pressure Core Spray System A4.03 Ability to manually operate and/or monitor in the control room:

Injection valves 3.7 Level RO Tier 2

Group 1

General References 3313.01 step 8.1.4

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 45 of 171 15 October 2010 Explanation When an initiation signal is present and the operator manually closes the injection valve the valve will not cycle open again unless the operator manually opens the valve. The automatic functions for the valve are overridden.

References to be provided during exam:

None Learning Objective 209001.03 DESCRIBE the function, operation, interlocks, trips, and power supplies of the following LPCS System components.

.1 Standby (P&ID M05-1073)

.2 Injection (P&ID M05-1073)

.3 Full Flow Test (P&ID M05-1073)

.4 Water Leg Pump (P&ID M05-1073)

.5 LPCS Injection (E02-1LP99)

Question Source (New, Modified, Bank)

Bank Cognitive Level High cognitive level based on plant conditions.

10CFR55 Content 55.41 7

55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 46 of 171 15 October 2010 20 ID: CL-ILT-6464M Points: 1.00 Turbine building temperature is 200F due to steam leak.

No automatic isolations have occurred.

What action(s) is/ are required to isolate the leak?

Arm and depress the CRVICS ____________ pushbuttons:

A.

"A" and "C" B.

"B" and "D" C.

"A" and "B" D.

"A" and "D" Answer:

D Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 4

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 223002 Primary Containment Isolation System/Nuclear Steam Supply Shut-Off 2.4.49 Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.

4.6 Level RO Tier 2

Group 1

General References 5067-8D 4001.01 Explanation A. Incorrect - No MSIVs will close B. Incorrect - No MSIVs will close C. Incorrect - No MSIVs will close D. Correct - Requires both the Div. 1 and Div. 4 PBs to close the outboard valves.

References to be provided during exam:

None Learning 223002.15Given CRVICS System initial conditions, PREDICT how

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 47 of 171 15 October 2010 Objective the system and/or plant parameters will respond to the manipulation of the following controls-Manual Pushbuttons Question Source (New, Modified, Bank)

Modified Cognitive Level Low recall of plant conditions both push buttons need to be depressed to perform a Group 1.

10CFR55 Content 55.41 10 55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 48 of 171 15 October 2010 21 ID: CL-ILT-6984 Points: 1.00 Standby Gas Treatment (VG) System has automatically initiated.

- The VG initiation signal is valid.

- The 'B' train of VG has been returned to Standby.

- All other plant conditions and systems are as expected.

Refer the attached figure and determine:

(1) VG inlet flow is...

(2) As a result of this inlet flow, Secondary Containment D/P is

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 49 of 171 15 October 2010 A.

(1) High

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 50 of 171 15 October 2010 (2) Too far from 0" H20 B.

(1) High (2) Too close to 0" H20 C.

(1) Low (2) Too far from 0" H20 D.

(1) Low (2) Too close to 0" H20 Answer:

D Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 4

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 261000 SGTS 2.1.31 Ability to locate control room switches, controls, and indications, and to determine that they correctly reflect the desired plant lineup.

4.6 Level RO Tier 2

Group 1

General References 3319.01 9067.01 Explanation D is correct flow should be ~4000 cfm and the low flow will not create the desired building D/P due to inleakage.

A is incorrect flow is too low B is incorrect flow is too low C is incorrect D/P is low not high References to be provided during exam:

None Learning Objective 261000.01 STATE the purpose(s) of the VG SBGT STANDBY GAS TREATMENT System including applicable design bases.

Question Source (New, Modified, Bank) bank

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 51 of 171 15 October 2010 Cognitive Level High picture used to interpret in the system analysis 10CFR55 Content 55.41 10 55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 52 of 171 15 October 2010 22 ID: CL-ILT-5340 Points: 1.00 Instrument Air pressure has been lost to the Standby Liquid Control (SLC) Storage Tank bubbler tube.

The SLC Storage Tank level indicator on MCR panel 1H13-P601......

A.

fails as is.

B.

fails upscale high.

C.

fails downscale low.

D.

indicates mid scale.

Answer:

C Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 3

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 211000 Standby Liquid Control System K5.06 Knowledge of the operational implications of the following concepts as they apply to STANDBY LIQUID CONTROL SYSTEM Tank level measurement 3.0 Level RO Tier 2

Group 1

General References 3314.01 check list 001 5066-6f Explanation Upon a loss of air to the measurement tube there will be no back pressure. With no back pressure the indication in the control room will indicate low.

If the line were to be clogged the indication will indicate high.

Air is used for the tank level instrument References to be provided during exam:

None Learning Objective 211000.07 Given the STANDBY LIQUID CONTROL system, DESCRIBE the systems supporting and the nature of the support.

.1 AC Electrical Distribution

.2 Service and Instrument Air (SA/IA)

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 53 of 171 15 October 2010

.3 Makeup Condensate (MC)

Question Source (New, Modified, Bank)

Bank Cognitive Level High analysis of the failure mode and the response.

10CFR55 Content 55.41 5

55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 54 of 171 15 October 2010 23 ID: CL-ILT-4874 Points: 1.00 All four Containment Continuous Purge Exhaust Radiation monitors read 120 mR/hr.

What is the expected status of the following?

(1) FB Sply (2)Standby Gas Treatment Outbd Isol System Accident Range Dmprs 1VF09Y. Monitor (AXM), 0RIX-PR008.

(1) (2)

A.

SHUT RUNNING B.

SHUT IN STANDBY C.

OPEN RUNNING D.

OPEN IN STANDBY Answer:

A Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 1

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 272000 Radiation Monitoring System A3.09 Ability to monitor automatic operations of the RADIATION MONITORING SYSTEM including: Containment isolation indications 3.6 Level RO Tier 2

Group 2

General References 5140.65 4001.02 C001 3404.01 Explanation A is correct, 1VF09Y shuts as Fuel Building Vents ISOLATE, the AXM 0RIX-PR008 is RUNNING.

B is wrong, AXM 0RIX-PR008 is RUNNING.

C is wrong, 1VF09Y shuts.

D is wrong, 1VF09Y shuts, AXM 0RIX-PR008 is RUNNING..

References to be provided None

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 55 of 171 15 October 2010 during exam:

Learning Objective 290001.03 DESCRIBE the function, operation, interlocks, trips, and power supplies of the following FUEL BUILDING HVAC AND SECONDARY CONTAINMENT System components.

.1 Supply Air Heating Coil

.2 Supply Air Cooling Coil

.3 Supply Air Fans

.4 VF Supply Flow Cont. Damper

.5 VF & VG Automatic Dampers

.6 Fire Dampers

.7 VF Exhaust Fans Question Source (New, Modified, Bank)

Bank Previous NRC exam 08-01 Cognitive Level High cognitive analysis of plant response.

10CFR55 Content 55.41 7

55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 56 of 171 15 October 2010 24 ID: CL-ILT-6673 Points: 1.00 The unit was operating at full power when a loss of feed water causes RPV water level to lower to

-20".

Which of the following sets of Control Rod positions do NOT satisfy the SHUTDOWN CRITERIA given that ALL other rods are at position 00?

24-45 24-29 32-33 36-21 36-05 A.

02 00 02 02 02 B.

02 00 00 00 04 C.

00 00 00 00 06 D.

00 10 00 00 00 Answer:

B Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 2

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 214000 Rod Position Information System 2.4.1 Knowledge of EOP entry conditions and immediate action steps.

4.6 Level RO Tier 2

Group 2

General References EOP Definition page 4-4 Explanation All rods are in to at least 02, OR No more than 1 rod out past 02, with all other rods in at 00, References to be provided during exam:

None Learning Objective DB410001.01 Given specific plant conditions, determine if CPS No.

4100.01, REACTOR SCRAM should be used.

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 57 of 171 15 October 2010 Question Source (New, Modified, Bank)

Bank Cognitive Level Low recall of definition.

10CFR55 Content 55.41 10 55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 58 of 171 15 October 2010 25 ID: CL-ILT-4844 Points: 1.00 In accordance with 3703.01, CORE ALTERATIONS, a fuel move is considered complete when the fuel bundle has been placed in the correct location and the ____________.

A.

slack cable light is LIT B.

hoist loaded light goes OUT C.

grapple has been RELEASED D.

orientation has been DOUBLE VERIFIED Answer:

C Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 3

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 2.1.36 Knowledge of procedures and limitations involved in core alterations.

3.0 Level RO Tier 3

Group 1

General References 3703.01 Explanation The fuel move is completed when the grapple is released from the fuel bundle.

References to be provided during exam:

None Learning Objective LP86610.01.08 In accordance with CPS No. 3703.01, CORE ALTERATIONS

.01 Define Completed Fuel Move

.02 Describe who is responsible for performing in-core coordinate verification.

.03 Describe three (3) methods used to verify in-core coordinates.

Question Source (New, Modified, Bank)

Bank

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 59 of 171 15 October 2010 Cognitive Level Low definition of when a fuel move is completed.

10CFR55 Content 55.41 3.0 55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 60 of 171 15 October 2010 26 ID: CL-ILT-9928 Points: 1.00 While performing a 9030 surveillance there is a {CS} next to the step.

The {CS} denotes what?

A.

Critical step B.

Clearance step C.

Calibration step D.

Concurrent step Answer:

A Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 1

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 2.2.12 Knowledge of surveillance procedures.

3.7 Level RO Tier 3

Group 2

General References 9030.01 Explanation

{CS} is a critical step.

References to be provided during exam:

None Learning Objective LP85802.2.2.12 Knowledge of surveillance procedures.

Question Source (New, Modified, Bank)

New Cognitive Level Low definition.

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 61 of 171 15 October 2010 10CFR55 Content 55.41 10 55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 62 of 171 15 October 2010 27 ID: CL-ILT-5252 Points: 1.00 Given the following:

- Reactor has been shutdown due to a steam leak in the drywell.

- Recirculation pumps are tripped.

- Drywell temperature 210 degrees F.

- Drywell pressure 2.4 psig.

- RPV is depressurized.

Which ONE of the following level instruments is most accurate provided actual RPV water level is in the indicating range?

A.

Narrow Range B.

Wide Range C.

Shutdown Range D.

Fuel Zone Range Answer:

D Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 4

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 2.4.9 Knowledge of low power/shutdown implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies.

3.8 Level RO Tier 3

Group 4

General References EOP-Detail A 4411.07 Explanation Fuel Zone Range References to be provided during exam:

None Learning 216000.16 EVALUATE the following Nuclear Boiler indications/responses and DETERMINE if the indication/ response is expected and normal.

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 63 of 171 15 October 2010 Objective

.1 Rapid Reactor Vessel depressurization

.2 Reactor Vessel heatup

.3 Reactor Vessel cooldown

.4 Increasing Containment temperature

.5 Increasing Drywell temperature

.6 Reactor Recirc Jet Pump flow

.7 Rapid Changes in Void Fraction

.8 Steam flow changes

.9 Shutting 1B21-F454A/B, RPV Pressure / Level Transmitter Reference Line Isolation Valve.

.10 Valving in or out a level transmitter Question Source (New, Modified, Bank)

Bank Cognitive Level High analysis of Detail A 10CFR55 Content 55.41 10 55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 64 of 171 15 October 2010 28 ID: CL-ILT-9927 Points: 1.00 The plant is operating at rated conditions.

The attached figure shows the status of the Div 2 and Div 4 DC busses.

Which one of the following describes the status of the Batteries?

Div 2 is __(1)__

Div 4 is __(2)__

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 65 of 171 15 October 2010 A.

(1) on a Float Charge

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 66 of 171 15 October 2010 (2) Discharging B.

(1) on a Float Charge (2) early in an Equalize Charge C.

(1) Discharging (2) on a Float Charge D.

(1) Discharging (2) early in an Equalize Charge Answer:

A Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 1

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 263000 D.C. Electrical Distribution A1.01 Ability to predict and/or monitor changes in parameters associated with operating the D.C. ELECTRICAL DISTRIBUTION controls including: Battery charging/discharging rate 2.5 Level RO Tier 2

Group 1

General References USAR 8.3.2.1.2 8433.01 Explanation A is correct, negative Amps and low Voltage shows the Div 4 battery is discharging. Div 2 indicates a normal condition with the battery on a Float charge.

B is incorrect, negative Amps and low Voltage shows the Div 4 battery is discharging.

C is incorrect, negative Amps and low Voltage shows the Div 4 battery is discharging.

D is incorrect, Div 2 indicates a normal condition with the battery on a Float charge.

References to be provided during exam:

None Learning Objective 263000.16 E VALUATE the following BATTERY & DC DISTRIBUTION indications/responses and DETERMINE if the

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 67 of 171 15 October 2010 indication/ response is expected and normal.

Question Source (New, Modified, Bank)

Modified Cognitive Level High analysis of indications 10CFR55 Content 55.41 5

55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 68 of 171 15 October 2010 29 ID: CL-ILT-9904 Points: 1.00 The plant is operating at 75% power with channel ONE of the main generator auto voltage regulator (AVR) in control.

An electrical transient has occured causing the AVR to transfer.

If a fault occurs on channel TWO of the AVR this will cause a____________.

A.

a turbine/ generator trip and reactor scram.

B.

transfer to channel ONE in manual control and control generator output voltage C.

transfer to channel TWO in manual and regulate the exciter field current.

D.

loss of ability to trip the exciter field breaker from the main control room.

Answer:

C Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 3

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 700000 Generator Voltage and Electric Grid Disturbances AA1.02 Ability to operate and/or monitor the following as they apply to GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES: Turbine/generator controls 3.8 Level RO Tier 1

Group 1

General References 3105.05 page 21 Explanation AVR is normally on channel 1 then if a fault occurs it will transfer to channel 2 in automatic, if a subsequent fault occurs it will transfer to channel two in manual mode and regulate exciter field current References to be provided during exam:

None Learning Objective 245002.15 Given MAIN GENERATOR System initial conditions, PREDICT how the system and/or plant parameters will respond to

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 69 of 171 15 October 2010 the manipulation of the following controls.

Question Source (New, Modified, Bank)

New Cognitive Level High analysis of a faulted condition and response of plant system.

10CFR55 Content 55.41 5

55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 70 of 171 15 October 2010 30 ID: CL-ILT-0956 Points: 1.00 The Service Air Filter/Dryer units automatic bypass valve will open when their outlet pressure reaches.....

A.

60 psig B.

70 psig C.

80 psig D.

90 psig Answer:

B Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 2

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 295019 Partial or Total Loss of Inst. Air AA1.02 - Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR :

Instrument air system valves: Plant-Specific 3.3 Level RO Tier 1

Group 1

General References 3214.01 Caution page 26 Explanation A. Incorrect - 70 psig is the set point B. Correct - A Filter/Dryer unit dryer section is automatically bypassed when dryer outlet pressure falls to <70 psig or on a loss of control air.

C. Incorrect - 70 psig is the set point D. Incorrect - 70 psig is the set point References to be provided during exam:

None Learning Objective 300000.03 DESCRIBE the function, operation, interlocks, trips, and power supplies of the following Service and Instrument Air System components.

.1 Service Air Compressors

.2 Lube Oil System

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 71 of 171 15 October 2010

.3 Vibration Monitor

.4 Main Service Air Receivers

.5 Service Air Dryers

.6 Makeup Water Pump House Air Receivers

.7 Circulating Water Screen House Air Receivers

.8 Ring Headers

.9 Ring Header Isolation Valves

.10 Containment Service Air Header Isolation Valves

.11 Containment Instrument Air Header Isolation Valves

.12 ADS Air Amplifiers

.13 Compressed Gas Inboard Isolation Valves

.14 Compressed Gas Outboard Isolation Valves

.15 ADS Backup Air Bottles

.16 Fuel Pool Gate Seal Backup Bottles Question Source (New, Modified, Bank)

Bank Cognitive Level Low recall of the setpoint for the operation of system valves.

10CFR55 Content 55.41 4

55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 72 of 171 15 October 2010 31 ID: CL-ILT-6322 Points: 1.00 A plant startup is in progress with the Main Generator synchronized to the grid and the 4.16kV and 6.9kV Buses still being supplied by the Reserve Auxiliary Transformers (RAT A,B,C).

If an OVER CURRENT condition exists on the 345kV North Bus which of the following describes the impact upon the inplant 4.16kV and 6.9kV Buses?

A.

ALL 4.16kV and 6.9kV Buses automatically transfer to an alternate source.

B.

There is no interruption of offsite power to any 4.16kV and 6.9kV Buses since the 138kV line is available.

C.

Non-Divisional 4.16kV and 6.9kV Buses are de-energized. Divisional 4.16kV Buses transfer to an alternate source.

D.

Non-Divisional 4.16kV and 6.9kV Buses transfer to an alternate source.

Divisional 4.16kV Buses will deenergize until the Diesel Generators start and load.

Answer:

C Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 3

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 262001 AC Electrical Distribution K4.01 - Knowledge of A.C.

ELECTRICAL DISTRIBUTION design feature(s) and/or interlocks which provide for the following: Bus lockouts 3.0 Level RO Tier 2

Group 1

General References 5010-4A Explanation A. Incorrect - 138kV supply does not power the 4.16kV and 6.9kV Buses.

B. Incorrect - When North bus is lost there is nothing to transfer to if the power to the plant is from the RAT for the Non-Essential buses.

C. Correct - Loss of the North Bus results in a loss of the RAT.

Non-Divisional buses will not transfer to the UAT and will be deenergized. Divisional buses will transfer to the ERAT.

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 73 of 171 15 October 2010 D. Incorrect - When North bus is lost there is nothing to transfer to if the power to the plant is from the RAT for the Non-Essential buses. The EDGs do not start when the ERAT is available.

References to be provided during exam:

None Learning Objective EVALUATE the following Auxiliary Power indications/responses and DETERMINE if the indication/ response is expected and normal.

.1 UAT Lockout

.2 RAT Lockout

.3 Transformer Lockout

.4 4.16 kV Bus Loss of Power

.5 Trip of DG Output Breaker Question Source (New, Modified, Bank)

Bank Cognitive Level High analysis of plant conditions and the effect of bus lockouts on operation.

10CFR55 Content 55.41 7

55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 74 of 171 15 October 2010 32 ID: CL-ILT-7029 Points: 1.00 Which of the following is the MAXIMUM emergency exposure limit for "Protecting Valuable Property"?

A.

5 Rem B.

10 Rem C.

25 Rem D.

35 Rem Answer:

B Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 2

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 3 Generic Radiation Control 2.3.4 Knowledge of the radiation exposure limits under normal or emergency conditions 3.2 Level RO Tier 3

Group G

General References EP-AA-113 Explanation

b. is correct, limit when a lower dose is not practical

a. is incorrect, this is the normal limit.

c. is incorrect, this is the limit for "Life Saving or Protection of Large Populations".

d. is incorrect, this would be a voluntary once in a lifetime exposure for "Life Saving".

References to be provided during exam:

None Learning Objective LP85803.2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions.

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 75 of 171 15 October 2010 Question Source (New, Modified, Bank)

Bank Cognitive Level Low recall of limit for given condition 10CFR55 Content 55.41 55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 76 of 171 15 October 2010 33 ID: CL-ILT-6080 Points: 1.00 Using the provided references, answer the following.

ASSUME the following when answering this question:

• Main Power Transformer MVA is EQUAL TO Main Generator MVA The plant is operating at power, with degraded grid conditions, and the following:

• Main Generator terminal voltage is 20,020 Volts

• Main Generator is operating at a 0.9 power factor with POSITIVE (+) VARs

• C Phase Main Power Transformer (MPT C) is operating with NO operable cooling banks

• Outdoor air temperature is 95°F

• MPT C oil and winding temperatures are slowly rising

• Operators have just reduced Main Generator real load (MWe) to lower the MVA load to the MAXIMUM PERMISSIBLE MVAs for these degraded conditions Which ONE of the following identifies the MAXIMUM amount of time that the Main Generator is permitted to operate with this MVA load?

A.

8 minutes B.

18 minutes C.

25 minutes D.

30 minutes Answer:

B Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 2

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc.

3.9 Level RO Tier 3

Group 1

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 77 of 171 15 October 2010 General References 3105.05 3504.01 Explanation Per CPS 3105.05, Section 8.5.2. VARs to the grid translates to a lagging power factor. At 20,020 volts, the generator is operating at 91% of rated (.91 x 22,000 = 20,020). Section 8.5.2.2 Table shows rated voltage is 22,000. Operators determine that the maximum allowable MVA load is 91% of rated MVA. Section 8.5.2.2 Table shows Rated MVA is 1265 MVA. Therefore, the maximum allowable MVAs is 1151 MVA (.91 x 1265 = 1151). Per CPS 3504.01, Section 8.3.1, operators recognize that the degraded cooling condition on MPT C is the limiting concern. Operators determine that Table 1 applies (given that no operable cooling banks are available). Per the notes of Section 8.3.1, at 95°F air temperature, operators default to the higher temperature value (104°F), and the higher MVA load value (1282.2 MVA). The resulting time limit at this MVA load is 18 minutes.

References to be provided during exam:

3105.05,3504.01 Learning Objective 245002.11 EVALUATE given key MAIN GENERATOR System parameters, if needed DETERMINE a course of action to correct or mitigate the following abnormal condition(s):

.1 Trip Signal

.2 Isolation Signal

.3 Auto Start Signal

.4 Condition/Lineup Question Source (New, Modified, Bank)

Modified Cognitive Level High analysis of the plant and use of procedures.

10CFR55 Content 55.41 10 55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 78 of 171 15 October 2010 34 ID: CL-ILT-9909 Points: 1.00 One RHR shutdown cooling subsystem is required to be OPERABLE and in operation when in MODE 5 and.

A.

water level is < 22 ft 8 inches above the RPV flange with irradiated fuel in the vessel.

B.

water level is > 22 ft 8 inches above the RPV flange with irradiated fuel in the vessel.

C.

water level is > 23 ft above irradiated fuel seated in the vessel.

D.

water level is > 23 ft 8 inches above the RPV flange with irradiated fuel in the vessel.

Answer:

B Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 2

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 295031 Reactor water level low 2.2.39 Knowledge of less than or equal to one hour Technical Specification action statements for systems.

7 Level RO Tier 1

Group 1

General References Tech spec 3.9.8 Explanation Per technical specifications.

References to be provided during exam:

None Learning Objective 203000.13 Given RESIDUAL HEAT REMOVAL System key parameter indications and plant conditions, DETERMINE if the Tech Spec LCOs have been met for one hour or less LCOs.

Question Source (New, Modified, Bank)

New

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 79 of 171 15 October 2010 Cognitive Level Low recall of one hour or less technical specification actions.

10CFR55 Content 55.41 7

55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 80 of 171 15 October 2010 35 ID: CL-ILT-9916 Points: 1.00 When is it permissible to operate VC in the manual purge mode?

A.

When both trains of VC cooling capacity are lost and outside air temperature is greater than control room temperature.

B.

When both trains of VC cooling capacity are lost and outside air temperature is less than control room temperature.

C.

When either train of VC cooling capacity is lost and outside air temperature is less than control room temperature.

D.

When one train of VC cooling capacity is lost the other train is placed in standby for emergency operation as long as control room temperature can be maintained.

Answer:

B Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 2

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 290003 Control Room HVAC K5. 03 Knowledge of the operational implications of the following concepts as they apply to CONTROL ROOM HVAC Temperature control 2.6 Level RO Tier 2

Group 2

General References Precaution 2.5 3402.01 3402.01 step 8.2 Explanation VC is allowed to be operated in the manual purge mode ONLY when BOTH trains are lost and outside air temperature is less than CR temperature. If either train is available then manual purge mode is not to be used IAW precaution 2.5 of 3402.01 Control Room HVAC References to be provided during exam:

None Learning Objective 290003.09 DISCUSS the effect:

a. A total loss or malfunction of the CONTROL ROOM HVAC System

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 81 of 171 15 October 2010 has on the plant.

Question Source (New, Modified, Bank)

New Cognitive Level Low recall of precaution 10CFR55 Content 55.41 5

55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 82 of 171 15 October 2010 36 ID: CL-ILT-6239 Points: 1.00 The following conditions exist:

An ATWS is in progress.

Reactor power is 5% and stable.

Suppression pool temperature is 118F and slowly going up.

Initiating SLC under these conditions ensures that ___(1)___ Shutdown Boron Weight will be injected before Suppression pool Temperature exceeds the ___(2)___.

A.

(1) Hot (2) Boron Injection Temperature B.

(1) Cold (2) Boron Injection Temperature C.

(1) Hot (2) Heat Capacity Temperature Limit D.

(1) Cold (2) Heat Capacity Temperature Limit Answer:

C Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 1

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown EA2.04 Ability to determine and/or interpret the following as they apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN : Suppression pool temperature 4.0 Level RO Tier 1

Group 1

General References EOP-6 bases Explanation EOP Technical Bases states that the Boron Injection Initiation Temperature is the highest suppression pool temperature at which

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 83 of 171 15 October 2010 initiation of boron injection will permit injection of the Hot Shutdown Boron Weight of boron before suppression pool temperature exceeds the Heat Capacity Temperature Limit References to be provided during exam:

None Learning Objective Given a diagram of EOP-1A:

.01 Describe the conditions to exit/transfer from EOP-1A

.02 State the bases for each individual step/action of EOP-1A

.03 Discuss the importance of verifying that the appropriate automatic actions of EOP-1A occur as required

.04 List the available methods to be used to stabilize/control RPV pressure in EOP-1A

.05 List the Preferred ATWS level control systems.

Question Source (New, Modified, Bank)

Bank Cognitive Level Low recall of bases for high suppression pool temperature.

10CFR55 Content 55.41 10 55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 84 of 171 15 October 2010 37 ID: CL-ILT-9908 Points: 1.00 During normal operations which of the following is LOWEST reactor pressure, provided, that would require technical specification LCO action entry is (1) and when must it be restored with in? (2)

A.

(1) 1325 psig (2) 60 min B.

(1) 1103 psig (2) 30 min C.

(1) 1055 psig (2) 15 min D.

(1) 1035 psig (2) 15 min Answer:

C Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 3

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 295025 High Reactor Pressure 2.2.42 Ability to recognize system parameters that are entry-level conditions for Technical Specifications.

3.9 Level RO Tier 1

Group 1

General References Tech spec 3.4.12 Explanation At 1035 psig no action is required per technical specifications.

Technical specification entry is 1045 psig At 1065 psig the reactor would have scrammed and 1103 is the pressure set point for lo-low set activation.

1325 is the technical specification for test pressure for the RPV.

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 85 of 171 15 October 2010 References to be provided during exam:

None Learning Objective 239001.12 Given MAIN STEAM System operability status OR key parameter indications, plant conditions, and a copy of Tech Specs, DETERMINE if Tech Spec Limiting Condition for Operations have been met, and required actions if any.

Question Source (New, Modified, Bank)

New Cognitive Level Low recall of technical specification entry conditions.

10CFR55 Content 55.41 7

55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 86 of 171 15 October 2010 38 ID: CL-ILT-0741 Points: 1.00 If the hand switches for 1B21-F051G Main Steam safety/relief valve (located on MCR panels H13-P601 and H13-P642) are placed in the OFF position, which mode(s) of operation will still cause this SRV to actuate?

A.

Safety mode AND relief mode.

B.

Safety mode AND ADS mode.

C.

Safety mode ONLY.

D.

ADS mode ONLY.

Answer:

B Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 2

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 218000 Automatic Depressurization System K1.06 Knowledge of the physical connections and/or cause effect relationships between AUTOMATIC DEPRESSURIZATION SYSTEM and the following: Safety/relief valves 3.9 Level RO Tier 2

Group 1

General References 5067-5C E02-1NB-99 sht 110 3101.01 (8.2.1 NOTE)

Explanation With both switches in the off position the solenoids are INOP for the associated valve for the pressure relief function.

References to be provided during exam:

None Learning Objective 239001.15 Given MAIN STEAM System initial conditions, PREDICT how the system and/or plant parameters will respond to the manipulation of the following controls.

Question Source (New, Modified, Bank)

Bank

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 87 of 171 15 October 2010 Cognitive Level Low due to recall of logic.

10CFR55 Content 55.41 9

55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 88 of 171 15 October 2010 39 ID: CL-LC-1055 Points: 1.00 The plant is operating at rated power, with the following:

- Loss of condenser vacuum occurs and the plant responds as designed

- Crew enters EOP-1, stabilizes pressure with SRVs and initiates RCIC to control level

- Reactor pressure stabilizes at 800 psig

- Reactor water level stabilizes at 35 inches NR

- THEN, a RCIC flow controller failure occurs and results in a lowering reactor water level

- Reactor water level eventually drops to 0 inches WR following the RCIC failure How are EOPs executed for this condition?

A.

Re-entry at the top of EOP-1 is required.

B.

Only re-entry at the start of the level leg is required.

C.

Re-entry at the start of both the level and pressure legs is required.

D.

Only re-assessment of the preferred and alternate injection systems is required.

Answer:

A Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 1

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 2.4.14 Knowledge of general guidelines for EOP usage.

3.8 Level RO Tier 3

Group 4

General References CPS 1005.09 8.13.3 step 3 Explanation A is correct. An EOP shall be reentered upon each receipt of an entry condition.

Distracters:

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 89 of 171 15 October 2010 B is incorrect because reentry into EOP-1 is required.

C is incorrect because reentry into EOP-1 is required.

D is incorrect because reentry into EOP-1 is required.

References to be provided during exam:

None Learning Objective LP87551.01.03 Explain the principles associated with the selection/specification of EOP entry conditions.

Question Source (New, Modified, Bank)

Bank Cognitive Level Low reentry conditions for EOP's 10CFR55 Content 55.41 10 55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 90 of 171 15 October 2010 40 ID: CL-ILT-9913 Points: 1.00 Reactor startup is in progress.

- "D" Main steam line radiation monitor has failed upscale.

UPS 1A output voltage is 0 Volts due to a fault on the bus.

What is the impact?

A.

IRM "F" fails down scale B.

Inboard MSIV indication is lost C.

Main Condenser vacuum pump trip D.

TB MCC 1 M shunt trips are disabled Answer:

C Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 3

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 262002 Uninterruptable Power Supply (A.C./D.C.) K3.17 Knowledge of the effect that a loss or malfunction of the UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) will have on following: Process monitoring: Plant-Specific 2.9 Level RO Tier 2

Group 1

General References 3509.01 C001 Page 32 3509.01 C002 Page 34 for distractors Explanation UPS A will cause a loss of MSL A radiation monitor. Loss of both MSL radiation monitors will cause a trip of the mechanical vacuum pumps during startup. Main steam line header pressure is to low to use the air ejectors. The other components are powered from UPS B.

References to be provided during exam:

None Learning 262002.08 Given the UPS system, DESCRIBE the systems

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 91 of 171 15 October 2010 Objective supported and the nature of the support.

Question Source (New, Modified, Bank)

New Cognitive Level High analysis of loss of UPS bus conditions during start up.

10CFR55 Content 55.41 11 55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 92 of 171 15 October 2010 41 ID: CL-ILT-2177 Points: 1.00 Which ONE of the following conditions would indicate core shroud cracking above the top guide and require entry into CPS No. 4008.02, CORE SHROUD CRACKING?

Reactor power lowers,.......

A.

total core flow lowers, RR pump suction temperature rises, core inlet subcooling lowers.

B.

total core flow lowers, RR pump suction temperature lowers, core inlet subcooling rises.

C.

total core flow rises, RR pump suction temperature lowers, core inlet subcooling lowers.

D.

total core flow rises, RR pump suction temperature rises, core inlet subcooling lowers.

Answer:

D Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 4

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 290002 Reactor Vessel Internals K3.07 Knowledge of the effect that a loss or malfunction of the REACTOR VESSEL INTERNALS will have on following: Nuclear boiler instrumentation 3.1 Level RO Tier 2

Group 2

General References 4008.02 Explanation

a. Incorrect - Total core flow lowering is incorrect. RR flow resistance is reduced by the flow that no longer experiences the pressure drop across the dryer-separator

b. Incorrect - Due to total core flow for reason given in (a) above.

Core inlet subcooling also incorrect. Lowering of power and flow plus heating due to leakage flow cause subcooling reduction.

c. Incorrect - RR pump suction temperature increases due to power reduction and lowered FW flow along with higher temperature

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 93 of 171 15 October 2010 leakage flow.

d. Per 4008.02 section 1.1 References to be provided during exam:

None Learning Objective PB400802.01.01 Given specific plant conditions, determine if CPS No. 4008.02 CORE SHROUD CRACKING should be used.

Question Source (New, Modified, Bank)

Bank Cognitive Level High cognitive analysis of the plant conditions.

10CFR55 Content 55.41 7

55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 94 of 171 15 October 2010 42 ID: CL-ILT-6305 Points: 1.00 Plant conditions are as follows:

• A Loss Of Coolant Accident has occurred.

• Drywell pressure is 4.4 psig and rising at 0.1 psig / 10 min.

• Containment pressure is 2.8 psid and rising at 0.05 psid / 20 min.

With respect to CONTAINMENT PURGE MODE, Standby Gas Treatment Train (VG) train 'A' is:

A.

Available; currently in standby but the VG Exhaust Fan 'A' (0VG02CA) must be manually started and aligned to Containment Purge by opening the VG Train 'A' Drywell Purge Inlet Damper (1VG01YA).

B.

Available; currently running due to high Drywell pressure but must be manually aligned to Containment Purge by opening the VG Train 'A' Drywell Purge Inlet Damper (1VG01YA).

C.

Unavailable; currently running due to high Drywell pressure, but the VG Train 'A' Drywell Purge Inlet Damper (1VG01YA) isolated on high Containment pressure.

D.

Unavailable; the VG Exhaust Fan 'A' (0VG02CA) tripped on high Containment pressure.

Answer:

C Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 3

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 261000 Standby Gas Treatment System K6.09 Knowledge of the effect that a loss or malfunction of the following will have on the STANDBY GAS TREATMENT SYSTEM :

Primary containment high pressure: Plant-Specific 3.1 Level RO Tier 2

Group 1

General References 5064-3E 3319.01 page 12 Explanation A. Incorrect - Unavailable.

B. Incorrect - Unavailable.

C. Correct - 1VG01YA isolates at 2.56 psid containment pressure.

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 95 of 171 15 October 2010

d. Incorrect - VG Exhaust Fan 'A' (0VG02CA) does NOT trip on high Containment pressure.

References to be provided during exam:

None Learning Objective 261000.03 DESCRIBE the function, operation, interlocks, trips, and power supplies of the following VG SBGT STANDBY GAS TREATMENT System components.

.1 Normal Mode

.2 Containment Purge

.3 Cooling Fan Operation

.4 System Initiation

.5 Containment HVAC Isolation Valve Radiation Interlock Bypass Switches

.6 System Initiation Reset

.7 Containment Pressure High Interlock Question Source (New, Modified, Bank)

Bank Cognitive Level High cognitive analysis of plant systems and automatic actions associated with the transient.

10CFR55 Content 55.41 7

55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 96 of 171 15 October 2010 43 ID: CL-ILT-5957 Points: 1.00 The Division 1 Battery Room Ventilation System will maintain a...

A.

negative pressure to ensure hydrogen gas is removed from the battery room and remains below the flammability limit.

B.

positive pressure to ensure hydrogen gas is removed from the battery room and remains below the flammability limit.

C.

negative pressure to ensure the overall Auxiliary Building HVAC system flow is balanced.

D.

positive pressure to ensure the overall Auxiliary Building HVAC system flow is balanced.

Answer:

A Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 1

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 263000 DC Electrical Distribution K5.01 - Knowledge of the operational implications of the following concepts as they apply to D.C. ELECTRICAL DISTRIBUTION : Hydrogen generation during battery charging.

2.6 Level RO Tier 2

Group 1

General References 3503.01 3412.01 Explanation With out VX running during battery charging hydrogen levels in the room may exceed 4%.

References to be provided during exam:

None Learning Objective 263000.10 EXPLAIN the reasons for given BATTERY & DC DISTRIBUTION System operating limits and precautions.

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 97 of 171 15 October 2010 Question Source (New, Modified, Bank)

Bank Cognitive Level Low the purpose of VX and hydrogen removal.

10CFR55 Content 55.41 8

55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 98 of 171 15 October 2010 44 ID: CL-ILT-6517 Points: 1.00 The plant was operating at 80% power when a steam bypass and pressure control system failure occurs resulting in the following pant conditions:

• Reactor pressure lowered to 650 psig and indicated power on the APRMs lowered to 75%.

• The Group 1 isolation failed to actuate.

• The Reactor Mode Switch is placed into SHUTDOWN.

. A manual Group 1 isolation is performed.

What occurred during this event?

A.

Fuel clad integrity safety limit was violated.

B.

Likelihood of thermal hydraulic instabilities was increased.

C.

Linear heat generation rate limit for some fuel was exceeded.

D.

Average planar linear heat generation rate limit was exceeded.

Answer:

A Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 1

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 2.2.22 Knowledge of limiting conditions for operations and safety limits.

4.0 Level RO Tier 3

Group 2

General References 2.1.1.1 Tech spec bases for safety limits Explanation A. Correct - The scenario given represents the violation of the fuel clad integrity safety limit. Reactor power is greater than 21.6% with reactor pressure less than 785 psig.

B. Incorrect - The likelihood of thermal hydraulic instabilities is not increased by this event.

C. Incorrect - This reduction in power is global resulting in a power reduction for each core bundle. This would increase the margin to

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 99 of 171 15 October 2010 LHGR limit.

D. Incorrect - With the global reduction in power average linear heat generation rate would decrease and put operation further away from the limit.

References to be provided during exam:

None Learning Objective 215005.01STATE the purpose(s) of the AVERAGE POWER RANGE MONITOR System including applicable design bases.

Question Source (New, Modified, Bank)

Bank Cognitive Level High due to analysis of plant conditions and applicability of safety limits.

10CFR55 Content 55.41 5

55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 100 of 171 15 October 2010 45 ID: CL-ILT-9905 Points: 1.00 The plant is operating with generator output of 515 MWe when a turbine trip occurs.

The reactor plant will (1).

The bases for this is (2).

A.

(1) not scram (2) that thermal limits do NOT apply at this power B.

(1) scram (2) to prevent violating LHGR C.

(1) scram (2) to prevent violating MCPR D.

(1) scram (2) to prevent violating APLHGR Answer:

C Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 3

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 295005 Main Turbine Generator Trip AK3.01Knowledge of the reasons for the following responses as they apply to MAIN TURBINE GENERATOR TRIP: Reactor SCRAM 3.8 Level RO Tier 1

Group 1

General References ufsar 15.2.3.3.3.3 3305.01 Technical Specification 2.1.1.2 Explanation When reactor power is above 33% based on first stage shell pressure a turbine trip will cause a reactor scram.

References to be provided during exam:

None Learning 245002.15 Given MAIN GENERATOR System initial conditions,

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 101 of 171 15 October 2010 Objective PREDICT how the system and/or plant parameters will respond to the manipulation of the following controls.

Question Source (New, Modified, Bank)

New Cognitive Level High plant response to a turbine trip and the reason for the turbine trip.

10CFR55 Content 55.41 5

55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 102 of 171 15 October 2010 46 ID: CL-ILT-9906 Points: 1.00 Reactor start up is in progress reactor power is 5%.

Suppression pool water is 19.3 ft.

RCIC testing is in progress for PMT.

Suppression pool temperature is 104F.

EOP-6 PRIMARY CONTAINMENT CONTROL is in progress and suppression pool cooling is maximized by:

A.

Place RHR A and B in suppression pool cooling with SX flow aligned to the heat exchanger and raise suppression pool water level two feet.

B.

Place RHR A and B in suppression pool cooling with SX flow aligned to the heat exchanger and suspend RCIC testing.

C.

Place RHR A and B in suppression pool cooling with SX flow aligned to the heat exchanger ONLY.

D.

Start RHR A and RHR B in suppression pool cooling ONLY.

Answer:

B Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 2

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 295026 Suppression Pool High Water Temperature EK2.01 Knowledge of the interrelations between SUPPRESSION POOL HIGH WATER TEMPERATURE and the following:

Suppression pool cooling 3.9 Level RO Tier 1

Group 1

General References EOP-6 bases Tech spec 3.6.2.1 Explanation EOP-6 bases states to maximize suppression pool cooling this is done by using SX as the cooling medium.

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 103 of 171 15 October 2010 RCIC testing is a required action by technical specification 3.6.2.1 References to be provided during exam:

None Learning Objective 295027 High Containment Temperature (Mark III Containment Only)EK2.04 Knowledge of the interrelations between HIGH CONTAINMENT TEMPERATURE (MARK III CONTAINMENT ONLY) and the following: SPDS / ERIS / CRIDS / GDS: Mark-III Question Source (New, Modified, Bank)

New Cognitive Level Low level knowledge of EOP bases 10CFR55 Content 55.41 7

55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 104 of 171 15 October 2010 47 ID: CL-ILT-9907 Points: 1.00 EOP-6 PRIMARY CONTAINMENT CONTROL requires a blowdown on high drywell temperature.

(1) At what temperature is the blowdown required?

(2) Why? To prevent...

A.

(1) 122F (2) loss of RPV water level indication B.

(1) 150F (2) exceeding drywell design temperature C.

(1) 330F (2) exceeding drywell design temperature D.

(1) 350F (2) exceeding drywell design pressure Answer:

C Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 3

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 295028 High Drywell Temperature EK3.01 Knowledge of the reasons for the following responses as they apply to HIGH DRYWELL TEMPERATURE:Emergency depressurization 3.6 Level RO Tier 1

Group 1

General References EOP-6 Bases Explanation The mark 5/6 containment the dry well is included in the primary containment.

The drywell containment temperature high design temperature is higher than the containment design temperature.

References to be provided None

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 105 of 171 15 October 2010 during exam:

Learning Objective LP87558.01.13 Given the following Primary Containment parameter trends and a diagram of EOP-6, determine the value at which reactor Blowdown is required, and when it would be appropriate to Blowdown in terms of approaching (cannot be held above/below) this value:

.01 Increasing Drywell Temperature (before 330°F)

.02 Decreasing Low Suppression Pool Level (cannot be held above 15 ft 1 in)

.03 Containment Temperature (cannot be held below 185°F)

Question Source (New, Modified, Bank)

New Cognitive Level Low recall of bases.

10CFR55 Content 55.41 5

55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 106 of 171 15 October 2010 48 ID: CL-ILT-9910 Points: 1.00 EOP-8 SECONDARY CONTAINMENT CONTROL requires a reactor scram when

-An area above max safe for an area water level AND

-A primary system discharging into secondary containment AND

-CANNOT be isolated.

What is the reason for this?

A scram............

A.

reduces the rate of energy production and thus heat input, radioactivity release, and break flow into the secondary containment.

B.

allows for anticipation of a blowdown due to reactor level since the leak cannot be isolated.

C.

allows for blowdown when one radiation area also exceeds max safe.

D.

is required to lower reactor pressure vessel pressure to aid in leak isolation.

Answer:

A Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 1

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 295036 Secondary Containment High Sump/Area Water Level EK1.01 Knowledge of the operational implications of the following concepts as they apply to SECONDARY CONTAINMENT HIGH SUMP/AREA WATER LEVEL :

Radiation releases 2.9 Level RO Tier 1

Group 2

General References EOP-8 bases page 9-12 Explanation EOP-8 bases for secondary containment

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 107 of 171 15 October 2010 References to be provided during exam:

None Learning Objective LP87559.01.07 Given EOP-8 and the following increasing Secondary Containment parameters, state when a Reactor Scram is required:

.01 Temperature (Table T).

.02 Radiation Level (Table U)

.03 Water Level (Table W)

Question Source (New, Modified, Bank)

New Cognitive Level Low recall of EOP bases.

10CFR55 Content 55.41 13 55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 108 of 171 15 October 2010 49 ID: CL-ILT-6469 Points: 1.00 Due to severe weather the plant has scrammed and a loss of all off site power has occurred.

What position will the 1B21-F065A & B RPV Feedwater Isolation Valves be placed in and why?

A.

Shut to provide long-term leakage protection when feedwater is unavailable B.

Open to ensure a feedwater flow path is available when power is restored C.

Shut to prevent thermal transients on the feedwater nozzles D.

Open to provide an RPV return path for shutdown cooling Answer:

A Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 1

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 295003 Partial or Complete Loss of A.C. Power AK3.06 Knowledge of the reasons for the following responses as they apply to PARTIAL OR COMPLETE LOSS OF A.C.

Containment isolation 3.7 Level RO Tier 1

Group 1

General References 4200.01 Step 4.3.2 Explanation A is correct B is wrong; the valves should be shut.

C is wrong; feedwater is not available so thermal transients cannot occur.

D is wrong; the valves should be shut.

References to be provided during exam:

None Learning Objective DB420001.01.03 Describe the operational implications of the following:

.1 Load shedding

.2 Under/degraded voltage effects on electrical loads

.3 Station Blackout

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 109 of 171 15 October 2010

.4 Restoration of AC power

.5 Transferring buses with a ground fault present Question Source (New, Modified, Bank)

Bank Cognitive Level High analysis of plant conditions.

10CFR55 Content 55.41 5

55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 110 of 171 15 October 2010 50 ID: CL-ILT-7023 Points: 1.00 Which ONE of the following is protected by performing an Emergency Depressurization due to a high Suppression Pool water level?

A.

RPV design pressure.

B.

Containment design pressure.

C.

Containment design temperature.

D.

Drywell to Containment design differential pressure.

Answer:

B Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 2

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 295029 High Suppression Pool Water Level EK3.01 Knowledge of the reasons for the following responses as they apply to HIGH SUPPRESSION POOL WATER LEVEL Emergency depressurization 3.5 Level RO Tier 1

Group 2

General References EOP-Bases Explanation a is incorrect - SRVs will operate and prevent over pressurizing the RPV regardless of the condition of the tailpipe.

c is incorrect - If SRV tail pipe failure occurs containment temperature will rise but the limiting factor requiring blowdown is preventing exceeding containment design pressure.

d is incorrect - Vacuum breakers and weir wall vent holes prevent exceeding drywell to containment differential pressure limit.

References to be provided during exam:

None Learning LP87550.01.01 Recall the definition and bases for the following EOP Variables and Curves:

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 111 of 171 15 October 2010 Objective

.01 Adequate Core Cooling

.02 Shutdown Criteria

.03 Subcritical

.04 DELETED

.05 DELETED

.06 Condenser available as a heat sink

.07 Primary System

.08 High Pressure Melt Ejection

.09 Direct Containment Heating

.10 Core-Concrete Interactions

.11 ECCS Design Criteria (10CFR50.46)

.12 RPV Breach Signature

.13 Indications of level greater that the Main Steam Lines

.14 Indications of Core Damage

.15 Boron Injection Initiation Temperature

.16 Cold Shutdown Boron

.17 Hot Shutdown Boron Weight

.18 Containment Spray Initiation Limit

.19 Decay Heat Removal Pressure

.20 DELETED

.21 DELETED

.22 Detail A

.23 Heat Capacity Limit

.24 Maximum Pressure Suppression Primary Containment Water Level

.25 Minimum Steam Cooling Pressure

.26 Minimum Number of SRVs Required for Decay Heat Removal

.27 Minimum Number of SRVs Required for Emergency Depressurization

.28 Minimum Steam Cooling RPV Water Level

.29 Net Positive Suction Head

.30 Pressure Suppression Pressure

.31 Primary Containment Pressure Limit

.32 SRV Tail Pipe Limit

.33 Vortex Limit

.34 Core Uncovery Limit Question Source (New, Modified, Bank)

Bank Cognitive Level Low cognitive level bases for Emergency depressurization.

10CFR55 Content 55.41 5

55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 112 of 171 15 October 2010 51 ID: CL-ILT-6995 Points: 1.00 The Div 3 Diesel Generator is paralleled with the Reserve Aux Transformer (RAT) for post maintenance testing.

Which one of the attached figures shows a Diesel Generator loading that requires adjustment?

Note: Consider each figure separately, consider Appendix B limitations only and Appendix B, DG 1C Reactive Load Capability Curve, is attached.

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 113 of 171 15 October 2010

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 114 of 171 15 October 2010 A.

a B.

b C.

c D.

d Answer:

C Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 3

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 2.2.44 Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.

4.2 Level RO Tier 3

Group 2

General References 3506.01 Explanation

c. is correct, the DG has excessive VARS for the KW load

a. is incorrect, both VARS and KW are just at the limits.

b. is incorrect, this loading is allowed but may be chosen because the Main Generator is not allowed to be operated with a leading power factor

d. is incorrect, this VAR loading is allowed at this reduced KW load.

References to be provided during exam:

None Learning Objective 264000.11 EVALUATE given key DIESEL GENERATOR/DIESEL FUEL OIL System parameters, if needed DETERMINE a course of action to correct or mitigate the following abnormal condition(s):

.1 High Crankcase Pressure

.2 Overspeed

.3 Overcrank

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 115 of 171 15 October 2010

.4 Low Oil Pressure

.5 High Water Temperature

.6 Reverse Power

.7 Loss of Excitation

.8 Overcurrent

.9 Generator Ground Fault

.10 Differential Current Question Source (New, Modified, Bank)

Bank Cognitive Level High analysis of indications and interpreting procedure graph.

10CFR55 Content 55.41 5

55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 116 of 171 15 October 2010 52 ID: CL-ILT-4880M Points: 1.00 EOP-6 PRIMARY CONTAINMENT CONTROL, HYDROGEN CONTROL LEG directs operation of mixing compressors.

The reason is because the mixing compressors ____________________________.

A.

lower drywell pressure in the event hydrogen igniters are NOT available.

B.

are an ignition source, and are used in the event that hydrogen igniters have failed to ignite hydrogen.

C.

catalytically recombine hydrogen and oxygen, reducing the concentration of hydrogen in the drywell.

D.

remove hydrogen as it is generated before a combustible mixture can accumulate when operated in conjunction with hydrogen igniters.

Answer:

D Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 4

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 500000 High Containment Hydrogen Concentration EK2.03 Knowledge of the interrelations between HIGH CONTAINMENT HYDROGEN CONCENTRATIONS the following:Containment Atmosphere Control System 3.3 Level RO Tier 1

Group 2

General References EOP6 bases Explanation D is correct, redistribute hydrogen throughout the containment and drywell, reducing localized concentration.

A is wrong, but describes operation of hydrogen recombiners.

B is wrong, but describes why hydrogen must be below Deflagration Limit prior to starting mixers.

C is wrong, but mixers do lower drywell pressure during operation.

References to be provided during exam:

None

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 117 of 171 15 October 2010 Learning Objective LP87558.01.15 Describe any limitations on the use of HG to control high Drywell pressure.

Question Source (New, Modified, Bank)

Bank Cognitive Level Low recall of system purpose and EOP bases.

10CFR55 Content 55.41 7

55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 118 of 171 15 October 2010 53 ID: CL-ILT-7021 Points: 1.00 The plant is operating at rated power.

An over current condition of 4160V 1B1 has occurred.

The attached figures show the status of Reactor Water Cleanup.

Which of the following actions will positively isolate the leak with the MINIMUM impact on plant operation?

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 119 of 171 15 October 2010

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 120 of 171 15 October 2010 A.

Close 1G33-F001, 1G33-F040 and 1G33-F053.

B.

Close 1G33-F004, 1G33-F039 and 1G33-F054.

C.

Arm and Depress the A CRVICS MANUAL INITIATION push-button.

D.

Arm and Depress the A and B CRVICS MANUAL INITIATION push-buttons.

Answer:

B Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 2

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 204000 Reactor Water Cleanup System A2.06 Ability to (a) predict the impacts of the following on the REACTOR WATER CLEANUP SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: A.C. failure 2.5 Level RO Tier 2

Group 2

General References 4001.C001 Bus outage check list for 4160 1B1 Explanation b is correct, This closes one valve in each RWCU containment isolation and will stop the leak into secondary containment.

a. is incorrect, this will stop flow to the leak from RWCU suction but will not stop back flow from the Feedwater system.

c. is incorrect, this will close most of the plant Outboard isolation valves and effect many plant systems.

d. in incorrect, this will close most of the plant Outboard and Inboard isolation valves and effect many plant systems.

References to be provided during exam:

None Learning Objective 204000.03 DESCRIBE the function, operation, interlocks, trips, physical location, and power supplies of the following RWCU System components.

.1 Suction Valves

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 121 of 171 15 October 2010

.2 Containment Isolation Valves

.3 RWCU Pump

.4 RWCU Heat Exchangers

.5 Reject Flow Controller

.6 Filter Demineralizers (FD)

.7 FD Support Equipment

.8 Durability Monitor Question Source (New, Modified, Bank)

Bank Cognitive Level High analysis of cleanup graphic and effect of power supply failure.

10CFR55 Content 55.41 5

55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 122 of 171 15 October 2010 54 ID: CL-ILT-6988 Points: 1.00 Plant conditions are as follows:

- Plant is operating at Rated Thermal Power.

- All Scram Solenoid Energized (BLUE) lights are lit.

- The B NSPS Solenoid Bus is powered from Alternate Power for maintenance.

- The Alternate Power is lost.

How many Scram Solenoid Energized (BLUE) lights on P-680 will deenergize?

A.

0 B.

2 C.

4 D.

8 Answer:

C Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 3

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 201001 Control Rod Drive Hydraulic System K2.02 Knowledge of electrical power supplies to the following: Scram valve solenoids 3.6 Level RO Tier 2

Group 2

General References 3509.01 Explanation A. Incorrect - The transfer to the inverter is manual.

B. Incorrect - 4 lights will deenergize.

C. Correct - The transfer to the inverter is manual which will deenergize solenoid bus. The B bus powers half of the RPS solenoids and thus half or 4 lights will deenergize.

D. Incorrect - 4 lights will deenergize.

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 123 of 171 15 October 2010 References to be provided during exam:

None Learning Objective 700004.09 DISCUSS the effect:

A total loss or malfunction of the NSPS System has on the plant A total loss or malfunction of various plant systems has on the NSPS System.

.1 Inverter Sync Loss

.2 Inverter Fault

.3 Loss of NSPS Buss

.4 Loss of NSPS Solenoid Power Question Source (New, Modified, Bank)

Bank Cognitive Level High analysis of bus loss and effect to scram solenoids 10CFR55 Content 55.41 7

55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 124 of 171 15 October 2010 55 ID: CL-ILT-0733 Points: 1.00 Plant conditions are as follows:

• The Reactor is operating at 78% Rated Thermal Power.

• The Main Steam Line Tunnel temperature alarm has just been received and now has a valid reading of 166F on recorder 1TR CM point 18.

Which of the following systems would IMMEDIATELY isolate in response to this high temperature?

A.

None.

B.

Main Steam and RWCU.

C.

Main Steam and RCIC.

D.

Main Steam, RWCU and RCIC.

Answer:

B Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 2

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 295032 High Secondary Containment Area Temperature EK2.04 Knowledge of the interrelations between HIGH SECONDARY CONTAINMENT AREA TEMPERATURE and the following: PCIS/NSSSS 3.6 Level RO Tier 1

Group 2

General References 351401 C006 Auto isolation check list Explanation A. Incorrect - FW does not isolate on High MSL Tunnel temp.

B. Correct - Main Steam, RWCU isolate at 156°F.

C. Incorrect - RCIC has a 25 min timer so it would not have isolated yet.

D. Incorrect - RCIC has a 25 min timer so it would not have isolated yet.

References to be provided None

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 125 of 171 15 October 2010 during exam:

Learning Objective LP87559.01.04 Given a diagram of EOP-8, explain the use and/or function of the following inserts:

.01 Table S, Area Cooler Delta T Limits.

.02 Table T, Area Temperature Limits.

.03 Table U, Area Radiation Limits.

.04 Table V, Floor Drain Sump Levels.

.05 Table W, Max Safe Area Water Levels.

Question Source (New, Modified, Bank)

Bank Cognitive Level High analysis of plant conditions.

10CFR55 Content 55.41 7

55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 126 of 171 15 October 2010 56 ID: CL-ILT-9912 Points: 1.00 A fault has occured on Division 2 DC bus and voltage is 0 Volts.

If a LOCA signal is received, in addition to LPCS and RHR 'A', which ECCS system(s) is/are available to inject automatically?

A.

None.

B.

HPCS.

C.

RHR B, AND HPCS.

D.

RHR C, AND HPCS.

Answer:

B Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 2

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 295004 Partial or Complete Loss of D.C. Power AK 1.03 Knowledge of the operational implications of the following concepts as they apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER : Electrical bus divisional separation 2.9 Level RO Tier 1

Group 1

General References 4201.01 C002 Explanation Division II provides control power to the RHR B and RHR C pump breakers.

LPCS and RHR A control power is from Division I HPCS is provided from Division III & IV References to be provided during exam:

None Learning 263000.08 Given the BATTERY & DC DISTRIBUTION system, DESCRIBE

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 127 of 171 15 October 2010 Objective the systems supported and the nature of the support.

.1 Nuclear System Protection System (NSPS)

.2 Reactor Core Isolation Cooling System (RCIC)

.3 Auxiliary Power System

.4 Remote Shutdown System

.5 Turbine Lube Oil System

.6 Seal Oil System

.7 Diesel Generator System

.8 Main Steam System Question Source (New, Modified, Bank)

New Cognitive Level High analysis of availability of systems.

10CFR55 Content 55.41 7

55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 128 of 171 15 October 2010 57 ID: CL-ILT-9914 Points: 1.00 The plant is at 93% reactor power.

"A" RPS solenoid inverter experienced an internal short causing it to be inoperable.

What is required per technical specification 3.8.7, Inverters Operating?

A.

Transfer RPS bus to alternate source ONLY.

B.

Transfer RPS bus to alternate source OR verify frequency greater than 57 Hertz ONLY.

C.

Transfer RPS bus to alternate source AND verify frequency greater than or equal to 57 Hertz OR de-energize the bus.

D.

Transfer RPS bus to alternate source AND verify frequency greater than 57 Hertz AND declare HPCS inoperable immediately.

Answer:

C Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 3

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 212000 Reactor Protection System Generic 2.2.36 Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operations.

3.1 Level RO Tier 2

Group 1

General References Tech spec 3.8.7 Explanation References to be provided during exam:

None Learning Objective 212000.11 EVALUATE given key Reactor Protection System (RPS) and Alternate Rod Insertion (ARI) System parameters, if needed DETERMINE a course of action to correct or mitigate the following

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 129 of 171 15 October 2010 abnormal condition(s):

Question Source (New, Modified, Bank)

New Cognitive Level Low recall of technical specification actions one hour.

10CFR55 Content 55.41 6

55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 130 of 171 15 October 2010 58 ID: CL-ILT-9915 Points: 1.00 Plant is operating at rated power.

You are the "B" RO A contractor calls you and says they are in the 737 air lock coming from the Fuel Building and CANNOT egress into the Auxiliary Building.

What is the cause for them NOT being able to exit into the Auxiliary Building?

A.

The Fuel Building d/p is -0.75" H20 B.

The Fuel Building door is NOT closed.

C.

The Auxiliary Building door is NOT closed D.

The Auxiliary Building door is NOT vented Answer:

B Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 2

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 290001 Secondary Containment K4.01 Knowledge of SECONDARY CONTAINMENT design feature(s) and/or interlocks which provide for the following: Personnel access without breaching secondary containment: Plant-System 3.5 Level RO Tier 2

Group 2

General References Skill of the craft Explanation The fuel building door is not closed.

The contractor is inside the airlock there for the auxiliary building door had to be closed or the fuel building door would not have opened.

Fuel building d/p is normally -.77" H2O There is no vent on this air lock, only the air locks going into primary

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 131 of 171 15 October 2010 containment.

References to be provided during exam:

None Learning Objective 290001.02 DESCRIBE the major flowpaths for the following modes of the FUEL BUILDING HVAC AND SECONDARY CONTAINMENT System operation.

.1 General arrangement of Secondary Containment

.2 Secondary Containment Airlock Operation

.3 Fuel Building Ventilation Flowpath

.4 SBGT Train Flow Path Question Source (New, Modified, Bank)

New Cognitive Level Low how do the doors work for secondary containment.

10CFR55 Content 55.41 7

55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 132 of 171 15 October 2010 59 ID: CL-ILT-9917 Points: 1.00 An EOP-6 caution for suppression pool level states:

Operating RHR with pool level below 11ft may damage system If suppression pool level reaches 11 ft the operators should consider all of the following EXCEPT......

A.

immediate catastrophic failure of the RHR pump B.

consequences of NOT operating the RHR pump C.

availability of other systems D.

trend of plant parameters Answer:

A Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 1

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 223001 Primary Containment System and Auxiliaries Generic 2.4.20 Knowledge of the operational implications of EOP warnings, cautions, and notes.

3.8 Level RO Tier 2

Group 2

General References EOP-6 bases Detail Z USFAR 6.3-8 Explanation All are true except catastrophic failure of the RHR pump References to be provided during exam:

None Learning Objective LP87558.01.08 Given a diagram of EOP-6, explain the use and/or function of the following inserts:

.01 Detail A, RPV Water Level Instruments

.02 Detail Z, NPSH/Vortex Limits

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 133 of 171 15 October 2010 Question Source (New, Modified, Bank)

New Cognitive Level Low EOP bases for low suppression pool water level.

10CFR55 Content 55.41 10 55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 134 of 171 15 October 2010 60 ID: CL-ILT-9918 Points: 1.00 Per CPS 3112.01 CONDENSER VACUUM it is NOT permissible to use the mechanical vacuum pumps to take a suction on the main condenser with the mode switch in RUN.

The reason for this is:

A.

This would provide an untreated radiological hazard.

B.

This would bypass the main condenser low vacuum scram.

C.

The high radiation trip is bypassed for the mechanical vacuum pumps.

D.

The main condenser suction line CANNOT accommodate the excessive flows from the SJAE's and the vacuum pumps.

Answer:

A Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 1

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 2.3.11 Ability to control radiation releases 3.8 Level RO Tier 3

Group General References 3112.01 step 4.1, and 4.2 Explanation OG is bypassed with the mechanical vacuum pumps this path provides a radiological hazard.

References to be provided during exam:

None Learning Objective 271001.10 Given a Condenser Air Removal System lineup and various plant conditions, evaluate the system indications/responses.

Determine EXPLAIN the reasons for given CONDENSER AIR REMOVAL System operating limits and precautions.

.1 Operating Condenser Vacuum Pumps > 5% power

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 135 of 171 15 October 2010 Question Source (New, Modified, Bank)

New Cognitive Level Low recall of precaution and limitation 10CFR55 Content 55.41 12 55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 136 of 171 15 October 2010 61 ID: CL-ILT-9930 Points: 1.00 A reactor scram has occured from rated conditions.

All rods are in.

All immediate actions are completed.

What mode of operation is the FWLC system controlling the reactor water level?

A.

Master level controller in three element control at 35 inches reactor water level.

B.

Start up level controller and is being controlled at controller setting of 20 inches.

C.

Setpoint set down and must be manually reset controlling at 10 inches reactor water level.

D.

Single element control on the loop flow controller and must be set to 20 inches reactor water level.

Answer:

B Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 2

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 295001 Reactor Feedwater system A4.08 Ability to manually operate and/or monitor in the control room FWRV position 3.3 Level RO Tier 2

Group 2

General References 3103.01 Explanation When the reactor scrams from 97% power level shrinks to level 3.

When reactor water level reaches level 3 setpoint set down re-sets the setpoint to 10 inches below the set point for reactor water level and must be manually reset.

S/U level controller does not have control of the FW 004 valve.

The loop flow controller must me transferred to manually and does

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 137 of 171 15 October 2010 not control automatically.

Master level controller is not in control setpoint set down is.

References to be provided during exam:

None Learning Objective 259002.04 STATE the physical location and function of the following FEEDWATER CONTROL system components, controls, indicators, and/or sensors.

.1 Narrow Range Reactor Water Level Instrumentation

.2 Reactor Water Level Channel Selector Switch

.3 Upset Range Reactor Water Level Instrumentation

.4 Other Reactor Water Level indications (not part of the FWC system)

.5 FWC System Steam Programming Function

.6 Feed Pump Discharge Flow Instrumentation

.7 Feedwater Inlet Flow Instrumentation

.8 Main Steam Flow Instrumentation

.9 Wide Range Pressure Instrumentation

.10 Narrow Range Pressure Instrumentation

.11 Main Turbine First Stage Pressure Instrumentation

.12 Flow Controller, FC-FW231

.13 RFPT Manual Potentiometers

.14 RFPT Auto/Manual Transfer Switches

.15 Startup Mode Actuator Select Switch

.16 Startup Level Controller

.17 Master Level Controller

.18 Setpoint Set down Logic

.19 Reactor Feed Pump (RFP) Loop Flow Controllers Question Source (New, Modified, Bank)

New Cognitive Level High the analysis of plant conditions and knowledge that the shrink transient will cause a level 3 scram and initiate setpoint set down to control reactor water level.

10CFR55 Content 55.41 7

55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 138 of 171 15 October 2010 62 ID: CL-ILT-9921 Points: 1.00 While at 25% power the plant experiences a turbine trip.

What is the expected plant response?

A.

Reactor has scrammed.

B.

Rod withdrawal limiter limits rod withdraw to two notches.

C.

Rod withdrawal limiter limits rod withdraw to four notches.

D.

Rod insertion and withdrawal limits are being enforced by the rod pattern controller.

Answer:

D Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 4

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 201005 Rod Control and Information System (RCIS)

A1.01Ability to predict and/or monitor changes in parameters associated with operating the ROD CONTROL AND INFORMATION SYSTEM (RCIS) controls including:

First stage shell pressure/turbine load: BWR-6 3.2 Level RO Tier 2

Group 2

General References 3304.02 Explanation A is incorrect RPC will enforce a 4 notch limit the reactor will scram when FFSp is greater then 33.3%

B is incorrect rods can be with drawn there is no rod with draw block generated solely from the turbine trip.

C is incorrect two inch rod with draw is activated by the HPSP D is correct, Turbine Trip at 26% implies, < LPSP signal activates Rod Pattern Controller.

References to be provided during exam:

None

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 139 of 171 15 October 2010 Learning Objective 201002.06 Given an RC&IS System annunciator, DESCRIBE the condition causing the alarm and any automatic actions. EXPLAIN the operational implications of the annunciator..

Given an RC&IS System Annunciator, DESCRIBE:

a. The condition causing the annunciator

b. Any automatic actions

c. Any operational implications

.1 Scram Discharge Volume Not Drained

.2 CRD Hydr Temp Hi

.3 Accumulator Trouble

.4 Rod Out Block

.5 RC&IS Inop

.6 Low Power Alarm Point

.7 Rod Drift

.8 Rod Overtravel

.9 Bypass Valve Open Check LPSP Question Source (New, Modified, Bank)

Bank Cognitive Level High analysis of the effect of the FSSP to the RPS and RCIS system and the response of the entire plant.

10CFR55 Content 55.41 5

55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 140 of 171 15 October 2010 63 ID: CL-ILT-9933 Points: 1.00 Based upon plant risk, CCW pumps are aligned in a non-preferred line up.

A trip of 4160V 1'B' occurs What is the plant impact?

A.

Fuel Pool Cooling and Clean Up pump 1'A' trips B.

DG 1'B' immersion heater trips C.

WO chiller 1'C' trips D.

None Answer:

D Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 4

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 400000 Component Cooling Water K2.01 - Knowledge of electrical power supplies to the following: CCW pumps 2.9 Level RO Tier 2

Group 1

General References 3203.01 Electrical lineup.

Explanation A non preferred line up A&C CCW pumps are running.

A Loss of 1B 4160 V bus will have no effect on this line up.

References to be provided during exam:

None Learning Objective 262001.02 DESCRIBE the major flowpaths for the following modes of the Auxiliary Power System operation.

.1 UAT/RAT to 6.9 & 4.1kv Loads

.2 ERAT/RAT/DG to 4.1kv Loads

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 141 of 171 15 October 2010 Question Source (New, Modified, Bank)

New Cognitive Level High recall of power supplies.

10CFR55 Content 55.41 4

55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 142 of 171 15 October 2010 64 ID: CL-ILT-9923 Points: 1.00 You are the 'A' RO SPDS

SUMMARY

DISPLAY screen is selected at 1H13-P680 Actual plant conditions are as follows:

Drywell pressure is 0.8 psig Drywell temperature is 132F Containment temperature is 132F Suppression pool temperature is 85F How will SPDS (Safety parameter display system) respond?

A.

SPDS PRI-CMNT icon box will back light red ONLY B.

SDPS will generate an SPDS CSF 5004-3F alarm ONLY C.

SDPS display will switch to PRI-CNMT display automatically D.

PRI-CMNT icon box will back light red and SPDS CSF 5004-3F alarm Answer:

D Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 4

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 295027 High Containment Temperature (Mark III Containment Only)EK2.04 Knowledge of the interrelations between HIGH CONTAINMENT TEMPERATURE (MARK III CONTAINMENT ONLY) and the following: SPDS / ERIS /

CRIDS / GDS: Mark-III 2.6 Level RO Tier 1

Group 1

General References SPDS display Explanation SPDS

SUMMARY

DISPLAY will change from green to red for primary containment and audible alarm will sound to alert the operator.

Screens do not switch automatically.

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 143 of 171 15 October 2010 References to be provided during exam:

None Learning Objective LP87558.01.10 Given a slow rate of change in the following Containment parameters, describe the normal means of controlling these conditions per EOP-6:

.01 Increasing Drywell temperature

.02 Increasing Suppression Pool temperature

.03 Increasing Suppression Pool water level

.04 Decreasing Suppression Pool water level

.05 Increasing Containment temperatures

.06 Increasing Drywell and/or Containment Pressure (HG; VR/VQ; VG)

Question Source (New, Modified, Bank)

Bank Cognitive Level High analysis of plant conditions and SPDS response.

10CFR55 Content 55.41 7

55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 144 of 171 15 October 2010 65 ID: CL-ILT-9901 Points: 1.00 SLC is normally lined up for injection via (1).

The reason for this is (2).

A.

(1) HPCS injection sparger (2) improved mixing B.

(1) HPCS injection sparger (2) provides for higher boron injection flow rate C.

(1) below core plate d/p sensing line (2) rapid reactor response to chemical S/D D.

(1) below core plate d/p sensing line (2) back up indication of injection based on pressure indications on P-680 Answer:

A Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 1

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 209002 HPCS K1.05 - Knowledge of the physical connections and/or cause-effect relationships between HIGH PRESSURE CORE SPRAY SYSTEM (HPCS) and the following: Standby liquid control system: Plant-Specific 2.8 Level RO Tier 2

Group 1

General References M05-1077 Sht. X USFAR Explanation SLC is lined up through the HPCS sparger for improved mixing.

References to be provided during exam:

None Learning Objective Given the HIGH PRESSURE CORE SPRAY system, DESCRIBE the systems supported and the nature of the support.

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 145 of 171 15 October 2010 Question Source (New, Modified, Bank)

New Cognitive Level Low due to system connection.

10CFR55 Content 55.41 6

55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 146 of 171 15 October 2010 66 ID: CL-ILT-9903 Points: 1.00 The plant is operating at 20% power when output of the APRM Reactor Recirc flow summer fails upscale.

What is the impact on the plant?

A.

OPRM scram will be generated.

B.

FLOW REFERENCE UPSCALE rod withdrawal block ONLY.

C.

Core flow indication on P-680 is invalid and core plate d/p must be used.

D.

RR cavitation interlock is bypassed, RR pumps can be shifted to fast speed, and RR FCV Damage may occur.

Answer:

B Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 2

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 202001 Recirculation K1.23 - Knowledge of the physical connections and/or cause-effect relationships between RECIRCULATION SYSTEM and the following: Average power range monitor flow converters: Plant-Specific 3.4 Level RO Tier 2

Group 2

General References ARP 5004-2K Explanation Flow upscale rod block will be initiated from the input to the flow converter at > 113%.

Cavitation interlock measures feed water flow not recirc flow.

Core plate d/p is only used when in single loop operation.

OPRM takes input from multiple LPRM channels one flow channels failure will not cause a scram.

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 147 of 171 15 October 2010 References to be provided during exam:

None Learning Objective DESCRIBE the function, operation, interlocks, trips, and power supplies of the following AVERAGE POWER RANGE MONITOR System components.

.1 Local Power Range Monitor (LPRM) Detector

.2 LPRM High Voltage Power Supply

.3 LPRM Card

.4 LPRM Multiplexer

.5 LPRM Count Circuit

.6 APRM Averaging Amplifier

.7 APRM Meter

.8 APRM Meter Function Switch

.9 APRM Inop Circuit

.10 APRM Flow Channel

.11 APRM Trip Reference Card

.12 Reactor Mode Switch

.13 NSPS Sensor Bypass Switches Question Source (New, Modified, Bank)

Bank Cognitive Level High analysis of failure mechanism and affect on the unit.

10CFR55 Content 55.41 7

55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 148 of 171 15 October 2010 67 ID: CL-ILT-6658M Points: 1.00 A plant transient has occured.

No Reactor Recirc Pumps running.

Actual Reactor Water Level is +66 inches from narrow range reference 0 inches.

Which instruments are available to read reactor water level?

A.

WR and NR B.

Upset and NR C.

Upset and SD D.

WR and Fuel Zone Answer:

C Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 3

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 295008 High Reactor Water Level AA2.01 Ability to determine and/or interpret the following as they apply to HIGH REACTOR WATER LEVEL : Reactor water level 3.9 Level RO Tier 1

Group 2

General References 4411.07 Att. A Explanation Upset and Shut down ranges will read reactor water level. All other instruments are off scale high.

References to be provided during exam:

None Learning Objective 216000.16 EVALUATE the following Nuclear Boiler indications/responses and DETERMINE if the indication/ response is expected and normal.

.1 Rapid Reactor Vessel depressurization

.2 Reactor Vessel heatup

.3 Reactor Vessel cooldown

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 149 of 171 15 October 2010

.4 Increasing Containment temperature

.5 Increasing Drywell temperature

.6 Reactor Recirc Jet Pump flow

.7 Rapid Changes in Void Fraction

.8 Steam flow changes

.9 Shutting 1B21-F454A/B, RPV Pressure / Level Transmitter Reference Line Isolation Valve.

.10 Valving in or out a level transmitter Question Source (New, Modified, Bank)

Bank Cognitive Level High analysis of plant conditions.

10CFR55 Content 55.41 10 55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 150 of 171 15 October 2010 68 ID: CL-ILT-0157 Points: 1.00 During refueling operations a MINIMUM water level is required to be maintained above the top of the Reactor Vessel Flange.

From the following, choose the bases for this requirement.

A.

Ensures 99% of the total Iodine fission product activity released from the pellet to clad gap of a dropped fuel assembly's rods is retained by the cavity water.

B.

Provides an absorption volume sufficient to remove 99% of Operationally released fission product gases and particulates.

C.

Ensures a sufficient water level to shield personnel from the gamma radiation emitted from irradiated fuel.

D.

Ensures the dryer and separator remain covered.

Answer:

A Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 1

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 295023 Refueling Accidents AK2.02 Knowledge of the interrelations between REFUELING ACCIDENTS and the following: Fuel pool cooling and cleanup system 2.9 Level RO Tier 1

Group 1

General References Tech spec 3.9.6 Bases USAR 15.7.4 Explanation A. Correct - Ensures 99% of the total Iodine fission product activity released from the pellet to clad gap of a dropped fuel assembly's rods is retained by the cavity water.

B. Incorrect - See "a".

C. Incorrect - See "a".

d. Incorrect - See "a".

References to be provided during exam:

None Learning Given plant conditions during Shutdown and/or Refueling Modes,

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 151 of 171 15 October 2010 Objective DETERMINE the applicable actions in accordance with ITS/ORMs..

Question Source (New, Modified, Bank)

Bank Cognitive Level Low recall of bases 10CFR55 Content 55.41 7

55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 152 of 171 15 October 2010 69 ID: CL-ILT-9920 Points: 1.00 A reactor startup is in progress Using the figure below

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 153 of 171 15 October 2010 Depressing the down button on IRM F will cause which of the following annunciators?

A.

RPS CH IRM UPSC TRIP OR INOP and IRM UPSC ONLY B.

SRM RETRACT NOT PERMITTED and IRM UPSC ONLY C.

RPS CH IRM UPSC TRIP OR INOP ONLY D.

SRM RETRACT NOT PERMITTED ONLY Answer:

A Answer Explanation:

QID: 09-1 NRO Answer 1

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 215003 Intermediate Range Monitor (IRM) System A3.01 Ability to monitor automatic operations of the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM including: Meters and recorders 3.3 Level RO Tier 2

Group 1

General References 3306.01 precaution 2.8 Explanation A. Correct - Ranging down on IRM F will cause the indication to increase by a factor of 3.16 which equals approx. 110/125 The annunciator is set at 108/125.

B. Incorrect - This annunciator would alarm if the IRM was at 120/125.

C. Incorrect - SRM A is below 100cps but none of the IRMs are below range 3.

D. Incorrect - IRM UPSC would be in but the RETRACT PERMITTED would not be.

References to be provided during exam:

None Learning 215003.05 Discuss the IRM system automatic functions/interlocks

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 154 of 171 15 October 2010 Objective including purpose, signals, set points, sensing points, when bypassed, how/when they are.

.1 Scrams

.2 Control Rod Withdrawal Blocks Question Source (New, Modified, Bank)

New Cognitive Level High cognitive analysis of plant conditions.

10CFR55 Content 55.41 2

55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 155 of 171 15 October 2010 70 ID: CL-ILT-9919 Points: 1.00 The plant is shutdown for refueling.

Final preparations are being made to install the drywell head.

Fuel pool cooling is in a normal line up.

Reactor cavity gate seal regulator fails low.

CRIVICS system functional test is in progress.

What will be the impact of performing this test?

A.

Radiation levels will rise in the refuel building.

B.

Dryer pool will leak into the vessel pool.

C.

Refuel bridge upward hoist movement is prevented.

D.

Reactor water level will lower below the flange level.

Answer:

B Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 2

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 295020 Inadvertent Containment Isolation 2.4.11 Knowledge of abnormal condition procedures.

4.0 Level RO Tier 1

Group 2

General References OPEX IR 9061.04 Step 5.4.34 Explanation When the surveillance is performed air will be isolated to containment. With the back up regulator failed this will result in water in the vessel pool. This event happened during the refuel outage.

References to be provided during exam:

None Learning Objective 223002.15 Given CRVICS System initial conditions, PREDICT how the system and/or plant parameters will respond to the manipulation of the following controls.

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 156 of 171 15 October 2010

.1 Manual Isolation Pushbuttons Question Source (New, Modified, Bank)

New Cognitive Level High analysis of plant realignment during isolations.

10CFR55 Content 55.41 4

55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 157 of 171 15 October 2010 71 ID: CL-ILT-9911 Points: 1.00 Using the attached figures determine the status of the SLC system.

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 158 of 171 15 October 2010

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 159 of 171 15 October 2010

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 160 of 171 15 October 2010 A.

'A' SLC pump has NOT been started, 'B' SLC pump is injecting through 'B' squib

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 161 of 171 15 October 2010 valve only.

B.

'A' SLC pump has been started and tripped, 'B' SLC pump is injecting through

'A' squib valve only.

C.

'A' SLC pump has been started and tripped, 'B' SLC pump is injecting through

'B' squib valve only.

D.

'A' SLC pump has been started and will inject, 'B' SLC pump is injecting through

'A' squib valve only.

Answer:

B Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 2

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 211000 Standby Liquid Control System A1.10 Ability to predict and/or monitor changes in parameters associated with operating the STANDBY LIQUID CONTROL SYSTEM controls including: Lights and alarms 3.7 Level RO Tier 2

Group 1

General References 5067-7F Explanation

'B' SLC pump has started however the squib valve for 'B' did NOT fire as indicated by the continuity light being lit.

'A' SLC pump started and tripped as indicated by the suction valve being fully open and the amber light lit above the pump. During the start sequence the amber light is out until the breakers closes. 'A' SLC continuity light is lit and discharge pressure is well below the relief valve setpoint.

Answer is 'B' SLC pump injecting through A squib valve.

References to be provided during exam:

None Learning 211000.06

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 162 of 171 15 October 2010 Objective Given an STANDBY LIQUID CONTROL System Annunciator, DESCRIBE:

a. The condition causing the annunciator

b. Any automatic actions

c. Any operational implications Question Source (New, Modified, Bank)

New Cognitive Level High analysis of lights and alarms 10CFR55 Content 55.41 6

55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 163 of 171 15 October 2010 72 ID: CL-ILT-9926 Points: 1.00 The plant is operating at 90% power when a fault causes the Division 4 NSPS bus to de-energize.

What is the plant impact?

A.

HPCS pump start logic disabled.

B.

APRM logic shifts to 1 of 3 logic.

C.

HPCS minimum flow logic disabled.

D.

Outboard MSIV 'A' solenoids de-energize.

Answer:

B Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 2

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 215005 APRM / LPRM K2.02 - Knowledge of electrical power supplies to the following: APRM channels 2.6 Level RO Tier 2

Group 1

General References 3509.01C004 Explanation Per 3509 C006 impact list HPCS logic is for division 3 NSPS not the division 4 (there are HPCS function on division 4)

Outboard isolation A solenoids are powered from division one and Division 4 is only for isolation logic.

References to be provided during exam:

None Learning Objective DESCRIBE the function, operation, interlocks, trips, and power supplies of the following AVERAGE POWER RANGE MONITOR System components.

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 164 of 171 15 October 2010

.1 Local Power Range Monitor (LPRM) Detector

.2 LPRM High Voltage Power Supply

.3 LPRM Card

.4 LPRM Multiplexer

.5 LPRM Count Circuit

.6 APRM Averaging Amplifier

.7 APRM Meter

.8 APRM Meter Function Switch

.9 APRM Inop Circuit

.10 APRM Flow Channel

.11 APRM Trip Reference Card

.12 Reactor Mode Switch.

.13 NSPS Sensor Bypass Switches Question Source (New, Modified, Bank)

New Cognitive Level High analysis of plant response due to plant conditions.

10CFR55 Content 55.41 6

55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 165 of 171 15 October 2010 73 ID: CL-ILT-9924 Points: 1.00 Plant is operating at 98%

Screen house MCC 'A' trips.

How does the fire protection system respond?

A.

'A' fire pump starts on low pressure ONLY B.

'A' fire pump starts on loss of control power C.

'B' fire pump starts on loss of control power D.

'A' and 'B' fire pumps start on low pressure Answer:

B Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 2

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 286000 Fire Protection System K6.01Knowledge of the effect that a loss or malfunction of the following will have on the FIRE PROTECTION SYSTEM A.C. electrical distribution: Plant-Specific 3.1 Level RO Tier 2

Group 2

General References OPEX Explanation

'A' fire pump starts automatically on loss of its control power.

Make up water pump house MCC A is the power supply to the jockey pump and if it is lost then the fire pump would start on low pressure

'B' fire pump does not lose control power so it will not start.

References to be provided during exam:

None

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 166 of 171 15 October 2010 Learning Objective 286000.07 Given the FP FD FIRE PROTECTION - DETECTION system, DESCRIBE the systems supporting and the nature of the support.

.1 AC Electrical Distribution (AP)

.2 DC Distribution Systems (DC)

.3 Screenwash (SW)

.4 Containment and Reactor Vessel Isolation Control (CRVICS)

.5 Filtered Water (TW)

.6 Potable Water Question Source (New, Modified, Bank)

New Cognitive Level Low plant response due to loss of control power.

10CFR55 Content 55.41 55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 167 of 171 15 October 2010 74 ID: CL-ILT-9925 Points: 1.00 A Locked High Radiation Area is found uncontrolled and accessible.

WHICH ONE of the following shall be immediately performed?

A.

inform the Shift Manager and search the area for personnel B.

inform RP Supervision and initiate access control of area C.

inform Security and initiate an audit of Level II Keys D.

inform Work Control Supervisor and evacuate area Answer:

B Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 2

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO Generic 2.3.12 Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high radiation areas, aligning filters, etc.

3.2 Level RO Tier 3

Group 3

General References RP-AA-460 Explanation If an HRA/LHRA/VHRA cannot be controlled by a barricade or locked door, then consistent with step 4.1.1.2. above, it may be controlled by direct surveillance of the boundary. However, in those situations, the area must still be posted in accordance with RP-AA-376.

Any individual who determines that an HRA/LHRA/VHRA is not being controlled adequately shall notify RP immediately (while maintaining positive control over the area to the extent possible during this notification period).

After notifying RP, the individual shall return to the area and maintain positive HRA/LHRA/VHRA access control of the area, without personal endangerment, until an RP representative arrives.

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 168 of 171 15 October 2010 In addition, the incident shall be documented as part of the Corrective Action Program.

References to be provided during exam:

None Learning Objective Generic 2.3.12 Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high radiation areas, aligning filters, etc.

Question Source (New, Modified, Bank)

New Cognitive Level Low recall of actions for an unlocked LHRA door 10CFR55 Content 55.41 12 55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 169 of 171 15 October 2010 75 ID: CL-ILT-0125 Points: 1.00

-The Reactor is in cold shutdown with the 'A' Loop of RHR in Shutdown Cooling.

-RHR Loop 'B' is inoperable.

-A break results in a loss of Reactor coolant inventory with water level at -150" (Wide Range) and lowering.

From the following, choose the operator actions required to place the 'A' Loop of RHR in the LPCI injection mode.

A.

Close the Shutdown Cooling Suction Valve (1E12-F006A), open the Suppression Pool Suction Valve (1E12-F004A) and manually start the 'A' RHR pump.

B.

Arm and depress the LPCS/LPCI "A" initiation pushbutton and open the LPCI Fm RHR A(B) Shutoff Valve (1E12-F042A).

C.

Close the Shutdown Cooling Suction Valve (1E12-F006A), open the Suppression Pool Suction Valve (1E12-F004A) and open the LPCI Fm RHR A(B) Shutoff Valve (1E12-F042A).

D.

Arm and depress the LPCS/LPCI "A" initiation pushbutton, then Close the Shutdown Cooling Suction Valve (1E12-F006A) and open the Suppression Pool Suction Valve (1E12-F004A).

Answer:

A Answer Explanation:

QID: 09-1 NRO1 Question # /

Answer 1

Developer/Date: TRF Knowledge and Ability Reference Information K&A Importance Rating RO SRO 203000 RHR/LPCI: Injection Mode A2.16 Ability to (a) predict the impacts of the following on the RHR/LPCI:

INJECTION MODE (PLANT SPECIFIC) ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of coolant accident 4.4 Level RO Tier 2

Group 1

General References Prints for logic

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 170 of 171 15 October 2010 Explanation A - Correct - The Suction valves must be swapped to allow the RHR pump to be started.

B - Incorrect - The Pump will not start with the F006 A open and level L3 also suction will not auto swap to SP suction C - Incorrect - Pump must be started due to the trip from the F008 &

9 Isolation D - Incorrect - Suction valve will not transfer.

References to be provided during exam:

None Learning Objective 203000.03 DESCRIBE the function, operation, interlocks, trips, physical locations, and power supplies of the following RESIDUAL HEAT REMOVAL System components.

.1 Suppression Pool Suction Strainer

.2 RHR Pumps

.3 RHR Heat Exchangers

.4 B/C Water Leg Pump

.5 Containment Spray Header and Nozzles

.6 Suppression Pool Suction Valves F004A, F004B.

.7 RH Shutdown Cooling Suction Valves F006A and F006B

.8 Shutdown Cooling Inboard and Outboard Isolation Valves F009 and F008

.9 RH B Supply to Reactor Head Spray Valve F023

.10 RH C Full Flow Test Valve F021

.11 RH A (B) Full Flow Test Valves F024A and F024B

.12 RH A (B) Containment Outboard Isolation Valves F027A and F027B

.13 RH A(B) Containment Spray A(B) Shutoff Valves F028A and F028B

.14 RH A(B) to Containment Pool Cooling Shutoff Valves F037A and F037B

.15 LPCI From RH Shutoff Valves F042A, F042B, and F042C

.16 LPCI From RH Testable Check Valves F041A, F041B, and F041C

.17 RH Heat Exchanger Inlet Valves F047A and F047B

.18 RH Heat Exchanger Outlet Valves F003A and F003B

.19 RH B Radwaste First and Second Isolation Valves F049 and F040

.20 RH Heat Exchanger Bypass Valves Question Source (New, Modified, Bank)

Bank Cognitive Level High cognitive level analysis of plant response.

10CFR55 Content 55.41 5

55.43 Time to Complete: 1-2 minutes

EXAMINATION ANSWER KEY 0901 NRC Exam Final CPS OPS MASTER Page: 171 of 171 15 October 2010