Cover Sheet U.S. Nuclear Regulatory Commission · 2012 HNP NRC SRO 2. Given the following plant...

ES-401 Site-Specific SRO Written Examination Form ES-401-8• Cover Sheet

U.S. Nuclear Regulatory Commission2012 HNP NRC

Site-Specific SRO Written Examination

Applicant Information

Name:

Date: Facility/Unit: Harris Nuclear Plant

Region: I lIlll D IV Reactor Type: W CELl BW LI GE LI

Start Time: Finish Time:

Instructions

Use the answer sheets provided to document your answers. Staple this cover sheeton top of the answer sheets. To pass the examination you must achieve a final gradeof at least 80.00 percent overall, with 70.00 percent or better on the SRO-only itemsif given in conjunction with the RO exam; SRO-only exams given alone require a final gradeof 80.00 percent to pass. You have 8 hours to complete the combined examination,and 3 hours if you are only taking the SRO portion.

Applicant Certification

All work done on this examination is my own. I have neither given nor received aid.

Applicant’s Signature

Results

RO/SRO-OnlylTotal Examination Values 75 / 25 / 100 Points

Applicant’s Scores

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/

_____

/

_____

Points

Applicant’s Grade

_____

/

_____

I

_____

Percent

2012 HNP NRC SRO

1. Given the following plant conditions:- The plant has just tripped following 100 days of operation at 100% power

Which ONE of the following decribes the actions necessary to maintain a constantvalue of Shutdown Margin following the trip?

A. Dilute for —1 0 hours, then borate for the next -70 hours

B. Borate for -1 0 hours, then dilute for the next -P70 hours

C. Dilute for —25 hours, then borate for the next —55 hours

D. Borate for —25 hours, then dilute for the next —55 hours

Monday, February 20, 2012 11:15:04AM 1 Rev. FINAL

2012 HNP NRC SRO

2. Given the following plant conditions:- 1SI-3, BIT Outlet Valve, is under clearance for MOV maintenance.- A Reactor Trip and Safety Injection occurred.- All RCPs are running.- RCS pressure is 1370 psig and stable.- SlfIowisl5OGPM.- Containment pressure is 4.5 psig and slowly rising.- SG pressures are 1020 psig and stable.- The OAC reports lSl-4, BIT Outlet Valve, indicates dual position (red/green light lit).

Which ONE of the following completes the statement below upon transition fromPATH-I?

RCPs (I) be tripped AND SG’s are (2) for subsequent RCS heat removal.

A. (1) should NOT

(2) required

B. (1) should NOT

(2) NOT required

C. (I) should

(2) required

D. (I)should

(2) NOT required


2012 HNP NRC SRO

3. Given the following plant conditions:- The plant is operating at 45% power- RCP ‘C’ #1 seal leakoff is 9 gpm and rising

Which ONE of the following describes the sequence of actions in accordance withAOP-018, Reactor Coolant Pump Abnormal Conditions?

A. Trip the Reactor, secure RCP ‘C’ and then implement PATH-i

B. Trip the Reactor, implement PATH-i, and then secure RCP ‘C’ as time permits

C. Secure RCP ‘C’, shut 1 CS-437, RCP ‘C’ #1 Seal Water Return and then initiate aplant shutdown in accordance with GP-006, Normal Plant Shutdown from PowerOperation to Hot Standby

D. Initiate a plant shutdown in accordance with GP-006, Normal Plant Shutdown fromPower Operation to Hot Standby, secure RCP ‘C’ and then shut 1 CS-437, RCP ‘C’#1 Seal Water Return


2012 HNP NRC SRO

4. Given the following plant conditions:- The plant is in Mode 5- RHR ‘A’ and ‘B’ trains are in service for Shutdown Cooling- The OAC reports Fl-605B1, RHR Hx ‘B’ Header Flow AND PDI-5450B, RHR Pump

‘B’ Diff Pressures are osciWating

Which ONE of the following completes the statement below for actions required to betaken in accordance with AOP-020, Loss of RCS Inventory or Residual Heat Removalwhile Shutdown?

Stop (1) AND shut (2)

A. (1) RHR Pump ‘B’ ONLY

(2) 1 RH-39, RCS Loop ‘C’ to RHR Pump ‘B’

B. (1) BOTH RHR Pumps

(2) IRH-39, RCS Loop ‘C’ to RHR Pump ‘B’

C. (1) RHR Pump ‘B’ ONLY

(2) 1RH-1, RCS Loop ‘A’ to RHR Pump ‘A’ AND IRH-39, RCS Loop ‘C’ to RHRPump ‘B’

D. (1) BOTH RHR Pumps

(2) 1RH-1, RCS Loop ‘A’ to RHR Pump ‘A’ AND 1RH-39, RCS Loop ‘C’ to RHRPump ‘B’


2012 HNP NRC SRO

5. Given the following plant conditions:- The plant is operating at 100% power- COW Pump ‘A’ in service and COW pump ‘B’ in standby- A leak occurs in the CCW system causing COW Surge Tank level to decrease

The following CCW surge tank level indications exist as leakage from the systemcontinues:

LI-670A1 SA Ll-676A1 SBTime0933 39% 41%0935 37% 38%1003 3% 14%1005 0% 3%

In accordance with AOP-014, Loss of Component Cooling Water, what is theEARLIEST time the operating crew is required to place and hold the control switches toSTOP for affected CCW pumps?

A. 0933

B. 0935

C. 1003

D. 1005


2012 HNP NRC SRO

6. Given the following plant conditions:- The plant is operating at 100% power- The OAC reports to the CRS that PRZ pressure is 2260 psig and slowly rising- The crew enters AOP-019, Malfunction of RCS Pressure Control- The OAC identifies that the PRZ group ‘A’ backup heaters are ON and attempts to

secure the heater group from the MCB have failed

In accordance with AOP-019, (1) what action should be taken to control PRZ pressureAND (2) what is the expected response of the Master Pressure Controller output afterthis action is taken?

A. (1) an operator should be dispatched to locally open the malfunctioning heaterbreaker

(2) Master Pressure Controller output increases

B. (1) take local control of the PRZ heaters at the Auxiliary Control Panel (ACP) andsecure the ‘A’ backup heaters from the ACP

(2) Master Pressure Controller output increases

C. (1) an operator should be dispatched to locally open the malfunctioning heaterbreaker

(2) Master Pressure Controller output decreases

D. (1) take local control of the PRZ heaters at the Auxiliary Control Panel (ACP) andsecure the ‘A’ backup heaters from the ACP

(2) Master Pressure Controller output decreases


2012 HNP NRC SRO

7. Given the following plant conditions:- The plant was operating at 100% power- .A Steam Generator Tube Rupture occurred on the SG ‘A’- Offsite power was lost- The crew implemented PATH-i and transitioned to PATH-2 then transitioned to

EPP-017, Post-SGTR Cooldown Using Backfill- A RCS cooldown on natural circ is now required

In accordance with EPP-01 7, which ONE of the following is the preferred order ofdumping steam from the intact SGs to accomplish the cooldown?

1) SG PORV controlled at MCB2) Locally operate SG PORVs3) Condenser steam dump4) TDAFW pump

A. 1,2,3

B. 3,1,2

C. 1,2,4

D. 3,2,4


2012 HNP NRC SRO

8. Given the following plant conditions:- FRP-H.1., Response to a Loss of Secondary Heat Sink, is being implemented- RCS bleed and feed has been initiated- Subsequently, Auxiliary Feedwater capability is restored- All SGs are completely dry and depressurized

Under these conditions, which ONE of the following describes the strategy used tore-establish Feedwater?

A. Feed ONLY one (1) SG to ensure RCS cooldown rates are established withinTechnical Specification limits

B. Feed ONLY one (1) SG to minimize excessive thermal stresses to SG components

C. Feed ALL SGs to establish subcooled conditions in the RCS as soon as possible

D. Feed ALL SGs to allow termination of RCS bleed and feed as soon as possible


2012 HNP NRC SRO

9. Given the following plant conditions:- The plant was operating at 100%- A loss of off-site power has occurred- EDG ‘A’ fails to start- EDG ‘B’ output breaker closes, but trips open- EPP-001, Loss Of AC Power To IA-SA And lB-SB Buses, is being implemented- All other systems are operating as expected

Which ONE of the following completes the statement below?

In accordance with EPP-001, the RCS cooldown during natural circulation is limited toa MAXIMUM rate of (1) AND the cooldown is required to (2)

A. (1)20°F/Hr

(2) minimize RCP seal leakage

B. (1)50°F/Hr

(2) minimize RCP seal leakage

C. (1)20°F/Hr

(2) control Pressurizer level

D. (1)50°F/Hr

(2) control Pressurizer level


2012 HNP NRC SRO

10. Given the following plant conditions:- The plant is operating at 100% power- A Loss of Offsite Power occurs

Which ONE of the following combinations identify the annunciators that are expectedfor this condition?

1) ALB-006 1-2, Charging Pumps ‘A’ Trouble2) ALB-005 8-4, CCW Pumps B! Trip or Close CKT Trouble3) ALB-004 4-5, RHR Pump ‘A’ Low Duff Press4) ALB-017 7-5, Aux Feedwater Pump Turbine Steam Low Press

A. 1,4

B. 1,2

C. 2,3

D. 3,4


2012 HNP NRC SRO

11. Given the following plant conditions:- The plant is operating at 100% power- PRZ Level Control is selected to position 459/460- Instrument Bus S-Il is lost- The crew is implementing AOP-024, Loss of Uninterruptible Power Supply

Which ONE of the following completes the statements below?

Letdown flow will be isolated because (1) went SHUT.

The OAC should control Charging in manual with FK-1 22.1, Charging Flow to (2)with letdown isolated.

A. (1) 1CS-1, Letdown Isolation LCV-460

(2) minimize the PRZ level increase

B. (1) ICS-1, Letdown Isolation LCV-460

(2) prevent gas binding of the CSIP

C. (1) ICS-2, Letdown Isolation LCV-459

(2) minimize the PRZ level increase

D. (1) ICS-2, Letdown Isolation LCV-459

(2) prevent gas binding of the CSIP

Monday, February 20, 2012 11:15:04 AM 11 Rev. FINAL

2012 HNP NRC SRO

12. Given the following plant conditions:- The plant is in Mode 3- MDAFW Pumps ‘A’ and ‘B’ are in service feeding all 3 SGs- EDG ‘B’ is under clearance for maintenance

Subsequently:- All power from 125 VDC Emergency Bus DP-1 B-SB is lost- One minute later a Startup Transformer 1 B lockout occurs


MDAFW Pump ‘B’ breaker indication on the MCB is (1) AND the pump motorbreaker is (2) ?

A. (1) available

(2) closed

B. (1) not available

(2) closed

C. (1) available

(2) open

D. (1) not available

(2) open


2012 HNP NRC SRO

13. Given the following plant conditions:- The plant is operating at 100% power

The following MCB indications exist:Time 1135 1138 1140

ESW Header APl-9101A SA, A Disch Press 88 psig 86 psig 94 psigFl-9101A1 SA, A Hdr Flow 14550 gpm 11820 gpm 13390 gpm

ESW Header BPI-9101B SB, B Disch Press 89 psig 85 psig 81 psigFl-9101B1 SB, B Hdr Flow 15725 gpm 18550 gpm 13600 gpm

NSW HeaderP1-9302.1, Disch Hdr Press 82 psig 80 psig 112 psigFl-9304, WPB SW Flow 9800 gpm 8250 gpm 11800 gpmFl-9276, Cnmt Coil Units SW Return 1840 gpm 1560 gpm 2900 gpm

AOP-022, Loss of Service Water has been entered and both ESW pumps have beenstarted.


The Service Water line rupture is located in the (1) ESW Header. In accordancewith AOP-022 to isolate the ESW Header leak, the operator will be directed to placeand hold (2) control switch(es) to STOP.

A. (1)’A’

(2) the ESW Pump ‘A’

B. (1)’A’

(2) both ESW Pump ‘A’ and ‘B’

C. (1)’B’

(2) the ESW Pump ‘B’

D. (1)’B’

(2) both ESW Pump ‘A’ and ‘B’


2012 HNP NRC SRO

14. Given the following plant conditions:- The plant is operating at 100% power- IA header pressure lowers as indicated below:

Time IA Header Pressure0750 115 psig0755 95 psig0800 85 psig0805 70 psig0810 6opsig0815 45psig


At (1) an auto shut signal to the Main Feed Reg valves is generated. The reasonthese valves have a back up air supply in the form of air accumulators is to (2)

A. (1) 0800

(2) provide motive force to shut the valves

B. (1) 0800

(2) provide the ability to maintain the valves open for a short period of timefollowing loss of air

C. (1) 0810

(2) provide motive force to shut the valves

D. (1) 0810

(2) provide the ability to maintain the valves open for a short period of timefollowing loss of air


2012 HNP NRC SRO

15. Given the following plant conditions:- The plant is operating at 100% power- Annunciator ALB-22-5-3, Generator Voltage Balance Relay Operated ALARMS- The voltage regulator remains in AUTO- MW and MVAR indications are erratic

Which ONE of the following actions should be taken for these conditions?

A. Null the Voltage Regulator Output Voltage with the Generator Base Adjuster. If theBase Adjuster does not work, Trip the Reactor and enter PATH-i

B. Adjust the Generator Output Voltage to 22KV with the Generator Voltage Adjusterswitch. If the Voltage Adjuster does not work, Trip the Reactor and enter PATH-i

C. Place the Generator Voltage Regulator switch to OFF and use the GeneratorVoltage Adjuster switch to restore Main Generator voltage

D. Operate the Generator Base Adjuster switch to null the Regulator Output BalanceVoltage as close to zero as possible then place the Generator Voltage Regulator inmanual by positioning the control switch to TEST


2012 HNP NRC SRO

16. Given the following plant conditions:- A Reactor Trip and Safety Injection have occurred from 100% power- The crew has transitioned to EPP-013, LOCA Outside Containment- 1 RH-I and 1 RH-2, RCS Loop A to RHR Pump A-SA, BOTH indicate partially OPEN

Which ONE of the following identifies (1) the action required to ALLOW shutting 1 RH-iand 1RH-2 from the MCB AND (2) the parameter used in EPP-013 to determine if thisaction has isolated the break?

A. (1) turn ON the control power switch on the MCB

(2) PRZ level increasing

B. (I) turn ON the control power switch on the MCB

(2) RCS pressure increasing

C. (I) CLOSE the breakers for 1RH-i and 1RH-2 locally

(2) PRZ level increasing

D. (1) CLOSE the breakers for 1RH-i and 1RH-2 locally

(2) RCS pressure increasing


2012 HNP NRC SRO

17. Given the foNowing plant conditions:- The plant was operating at 100% power- MDAFW pump ‘A’ is under clearance- A manual Reactor Trip was initiated due to a loss of both MFPs- The TDAFW pump tripped after starting- MDAFW flow control valves are full open- SG NR levels are 50% and lowering- Containment pressure is 3.5 psig

Which ONE of the following would be the FIRST set of conditions that would requireentry into FRP-H.1, Response to Loss of Secondary Heat Sink?

All SG NR levels are (1) AND total AFW flow is (2)

A. (1)39%

(2) 220 KPPH

B. (1)39%

(2) 200 KPPH

C. (1)24%

(2) 220 KPPH

D. (1)24%

(2) 200 KPPH


2012 HNP NRC SRO

18. Which ONE of the following describes (1) the reason AND (2) the requirements fordepressurizing the RCS in accordance with EPP-012, Loss of Emergency CoolantRecirculation?

A. (1) To minimize RCS break flow

(2) Depressurize the RCS to achieve RCS subcooling between 10°F and 20°F[40°F and 50°F]

B. (1) To increase CSIP injection flow rate

(2) Depressurize the RCS to achieve RCS subcooling between 10°F and 20°F[40°F and 50°F]

C. (1) To minimize RCS break flow

(2) Depressurize the RCS to maintain RCS subcooling just above 60°F [90°F]

D. (1) To increase CSIP injection flow rate

(2) Depressurize the RCS to maintain RCS subcooling just above 60°F [90°F]

Monday, February2o, 2012 11:15:04AM 18 Rev. FINAL

2012 HNP NRC SRO

19. Given the following plant conditions:

Time = 1200- Reactor Power is 89% and stable- Tavg - Tref deviation is 0°F and stable- PRZ level is 55% and stable- Control Bank D DRPI indicates 198 steps

Time =1202- Reactor Power is approximately 90% and rising (no load change is in progress)- Tavg - Tref deviation is approximately +2°F and rising- PRZ level 56% and rising- PRZ spray valves have throttled open- Control Bank D DRPI indicates 204 steps and stepping out at 8 steps per minute

Which ONE of the following describes (1) the event in progress AND (2) the FIRSTaction that must be performed in accordance with AOP-001, Malfunction of RodControl and Indication System?

A. (1) Selected first stage pressure channel high failure

(2) Check that less than 2 control rods are dropped

B. (1) Selected first stage pressure channel high failure

(2) Place the Rod Bank Selector Switch to MAN

C. (1) Continuous spurious control bank withdrawal

(2) Check that less than 2 control rods are dropped

D. (1) Continuous spurious control bank withdrawal

(2) Place the Rod Bank Selector Switch to MAN


2012 HNP NRC SRO

20. Given the following plant conditions:- An irradiated Fuel Assembly was being withdrawn from the core when it was

determined that the assembly was damaged- Containment Area Radiation is rising but monitors are NOT in alarm status- AOP-013, Fuel Handling Accident, has been entered

Which ONE of the following describes the FIRST action required in accordance withAOP-013?

A. Evacuate Containment

B. Initiate Containment Closure

C. Perform radiological surveys of Containment

D. Place the affected fuel assembly in an unobstructed opening in the Reactor Vessel


2012 HNP NRCSRO

21. Given the following plant conditions:- The plant is operating at 100% power- At 0800 a crack occurs on one SG ‘B’ tube, resulting in a 83 gpd tube leak- The crew enters AOP-016, Excessive Primary Plant Leakage

Which ONE of the following completes statement below?

In accordance with AOP-016, Reactor power is required to be reduced to 50% within(1) hour(s) AND the impact of reducing power is that the RCS to SG leak rate

is (2)

A. (1)one

(2) lower

B. (1)one

(2) higher

C. (1)three

(2) lower

D. (1)three

(2) higher

Monday, February2o, 2012 11:15:04AM 21 Rev. FINAL

2012 HNP NRC SRO

22. Given the following plant conditions:- The plant is operating at 45% power- Condenser vacuum is degrading as indicated below:

Time09000905091009150920

Zone 1 Pressure4.4” Hg absolute4.8” Hg absolute5.4” Hg absolute7.2” Hg absolute7.6” Hg absolute

Zone 2 Pressure4.8” Hg absolute5.3” Hg absolute5.9” Hg absolute7.8” Hg absolute8.4” Hg absolute

What is the EARLIEST time that an automatic Turbine/Reactor Trip will be generated?

A. 0905

B. 0910

C. 0915

D. 0920


2012 HNP NRC SRO

23. Given the following plant conditions:- The plant was operating at 100% power- AOP-004, Remote Shutdown, has been entered due to a fire in the MCB- Transfer to the Auxiliary Control Panel (ACP) is complete

Using ACP indicators, which ONE of the following identifies that natural circulation isoccurring?

1) RCS HL indicators: stable2) SG pressure indicators: stable3) RCS HL indicators: at saturation for SG pressure4) RCS CL indicators: at saturation for SG pressure

A. I and 4 ONLY

B. 2and3ONLY

C. I,2,and3ONLY

D. 1,2,and4ONLY


2012 HNP NRC SRO

24. Given the following plant conditions:- The plant is operating at 100% power- Chemistry reports RCS activity is increasing, and the latest sample is

1.4 microcuries per gram DOSE EQUIVALENT 1-131- ALB-026 2-1, Gross Failed Fuel Detector Trouble is received

Which ONE of the following identifies (1) the source of radiation detected by the Gross

Failed Fuel Detector is AND (2) what action will be directed by AOP-032, High RCS

Activity, to reduce RCS activity levels?

A. (1) neutron radiation from delayed neutrons

(2) place the cation demineralizer in service

B. (1) neutron radiation from delayed neutrons

(2) place the second mixed bed demineralizer in service

C. (1) gamma radiation from decay of fission products

(2) place cation demineralizer in service

D. (1) gamma radiation from decay of fission products

(2) place the second mixed bed demineralizer in service


2012 HNPNRCSRO

25. Given the following plant conditions:- The plant was operating at 100% power- The plant has experienced a LOCA- An automatic Reactor Trip and SI have occurred- The crew has transitioned from PATH-i to EPP-009, Post LOCA Cooldown and

Depressurization.

With the above conditions, which ONE of the following describes how voiding can beidentified in the RCS?

A. Rapidly decreasing RCS subcooling

B. Decreasing safety injection flow

C. Increasing RCS pressure

O. Rapidly increasing Pressurizer level


2012 HNP NRC SRO

26. Given the following plant conditions:- The crew is implementing EOP-FRP-P.1, Response to Imminent Pressurized

Thermal Shock- RCS subcooling does not support SI termination but it does support starting an

RCP

Which ONE of the following describes why it is desirable to re-start an RCP underthese conditions?

A. Promote mixing of the Safety Injection water and RCS

B. Supply additional heat input into the RCS

C. Establish PRZ Spray control

D. Promote heat transfer from the SGs to the RCS


2012 HNP NRC SRO

27. Given the following plant conditions:- The plant was operating at beginning of cycle when a large break LOCA occurred- LT-71 62B, Containment Wide Range Level, has increased to 207 inches and

continues to rise- The crew is implementing FRP-J.2, Response to Containment Flooding

Which ONE of the following completes the below statement describing why theContainment sump is sampled at this point?

The crew must determine if. .

A. the Containment Spray Additive Tank should be isolated.

B. the water is suitable for transfer to tanks outside Containment.

C. Emergency Service Water to Containment should be isolated.

D. the Containment sump contains enough boron to prevent a post-LOCA reactivitytransient which could result in a loss of subcriticality.


2012 HNP NRC SRO

28. Given the following plant conditions:- The plant is operating at 15% power- Steam Dumps are being transferred to Tavg control- ALB-009-5-1, Pressurizer High-Low Press, ALARMS

Two minutes later, RCS Pressure is 2150 psig and is decreasing.- The OAC attempts to shut I RC-I 03, PCV-444D: PRZ Spray Loop ‘B’, but it does

not respond

Which ONE of the following describes the actions required for this condition inaccordance with AOP-01 9, Malfunction of RCS Pressure Control?

A. Trip the Reactor then secure ONLY the RCP ‘B’ to stop the pressure decrease

B. Trip the Reactor then secure BOTH the RCP ‘A’ and ‘B’ to stop the pressuredecrease

C. Stop the RCP ‘B’ and if RCS pressure continues to decreases to <2000 psig thenTrip the Reactor

D. Stop BOTH the RCP ‘A’ and ‘B’ and if RCS pressure continues to decreases to<2000 psig then Trip the Reactor

Monday, February2O, 2012 11:15:04AM 28 Rev. FINAL

2012 HNP NRC SRO

29. Given the following plant conditions:- The plant is operating at 100% power- CSIP ‘A’ has been out of service for maintenance for the past 8 hours- At 0800, the CSIP ‘B’ trips due to a motor fault- CSIP ‘C’ is not available

Based on the conditions above, in accordance with Technical Specifications, the crewmust initiate action to shutdown the plant (1) ,with the plant reaching Mode 3 nolater than (2)

A. (1)byO900

(2) 1400

B. (1)byO900

(2)1500

C. (1) immediately

(2) 1400

D. (1) immediately

(2) 1500


2012 HNP NRC SRO

30. Given the following plant conditions:- PATH-2 is being implemented- The RCS has been depressurized, and SI flow is terminated- After normal miniflow is realigned, PATH-2 directs the crew to transfer CSIP suction

to the VCT (Level is 38%)

If the RO takes the RWST to CSIP valves to shut prior to opening the VCT outlets,what will be the impact?

The RWST supply valves will .

A. shut causing a loss of suction to the running CSIP.

B. not shut since the VCT outlets are closed.

C. shut once the VCT outlets automatically open.

D. not shut since the alternate miniflow isolations are open.


2012 HNP NRC SRO

31. Given the following plant conditions:- The plant was operating at 100% power

Time0515 LOCA occurs and the operators enter PATH-i0525 RHR Pump ‘B’ tripped on overcurrent0550 Cold Leg Recirc is established in accordance with EPP-01 0, Transfer To Cold

Leg Recirculation0555 CSIP ‘B’ was secured due to a gear drive failure and resultant oil fire0600 RHR Pump ‘A’ tripped on overcurrent

In accordance with EPP-012, Loss Of Emergency Coolant Recirculation, which ONE ofthe following (1) represents the time used to calculate minimum SI flow requiredAND (2) the reason for calculating this minimum SI Flow?

A. (1)0515

(2) to ensure the existence of an adequate vessel inventory such that core coolingis ensured.

B. (1) 0515

(2) to match decay heat in order to further decrease SI pump flow and delay RWSTdepletion.

C. (1)0550

(2) to ensure the existence of an adequate vessel inventory such that core coolingis ensured.

D. (1)0550

(2) to match decay heat in order to further decrease SI pump flow and delay RWSTdepletion.


2012 HNP NRC SRO

32. Given the following plant conditions:- RHR ‘A’ train is in service for Shutdown Cooling- The Instrument Air supply line to I RH-30, RHR Heat XCHG A Out Flow Control

Valve, becomes severed and is completely detached- 1 RH-30, has a demand of 50%

Which ONE of the following describes the effect on the RHR system?

A. RHR pump ‘A’ will reach runout conditions.

B. RHR pump ‘A’ will operate at shutoff head.

C. RHR Heat Exchanger ‘A’ outlet temperature rises.

D. RHR Heat Exchanger ‘A’ outlet temperature lowers.


2012 HNP NRC SRO

33. Given the following plant conditions:- EPP-009, Post LOCA Cooldown and Depressurization, is in progress- RCS temperature is 500°F with a cooldown rate of 75°F per hour in progress- RCS pressure is 1600 psig and lowering- Subcooling is 50°F and increasing- Containment pressure is 4 psig- One RCP is running

- The crew secures one CSIP and aligns normal charging flow

Which ONE of the following describes (1) the reason RCS subcooling LOWERS whenthe crew stops one CSIP AND (2) the HIGHEST value of RCS subcooling that requiresaction to realign the CSIP flow through the BIT?

A. (1) RCS temperature rise

(2) 39°F

B. (1) RCS temperature rise

(2) 9°F

C. (1) RCS pressure reduction

(2) 39°F

D. (1) RCS pressure reduction

(2) 9°F


2012 HNP NRC SRO

34. Given the following plant conditions:- A Large Break LOCA occurred 2 hours ago- EPP-010, Transfer to Cold Leg Recirculation has been completed- CSIP ‘B’ has just tripped


After CSIP ‘B’ trips the flow rate through FI-940, Alternate Header Flow, will (1)and flow rate through Fl-943, Normal Header Flow, will (2)

A. (1) remain at zero flow

(2) decrease to approximately half the previous value

B. (1) decrease to approximately half the previous value

(2) remain at zero flow

C. (1) decrease to zero

(2) remain constant

D. (1) remain constant

(2) decrease to zero


2012 HNP NRCSRO

35. Given the following plant conditions:- The plant is operating at 100% power- A Pressurizer PORV has a slow leak- The respective PORV isolation valve cannot be closed- ALB-009-8-1, Pressurizer Relief Tank High-Low Level Press or Temp, is in ALARM

PRT Level is 73%PRT Temperature is 128°FPRT Pressure is 6.3 psig

Which ONE of the following parameters (pressure I temperature) (1) is causing thealarm, AND (2) what action is required to be performed in accordance withALB-009-8-1?

A. (1) Pressure

(2) Vent the PRT as necessary to control pressure

B. (1) Pressure

(2) Drain the PRT as necessary to control pressure while maintaining level withinthe normal band

C. (1) Temperature

(2) Recirculate the PRT contents through the RCDT Heat Exchanger to lowertemperature

D. (1) Temperature

(2) Drain PRT to the low end of the normal band and then refill with demin waterto lower temperature


2012 HNP NRC SRO

36. Given the following plant conditions:- The plant is operating at 100% power- Annunciator ALB 005-6-1, CCW Surge Tank High-Low Level is in ALARM- CCW Surge Tank Level Ll-670A.1 (Train A) reads 60%- CCW Surge Tank Level Ll-676A.1 (Train B) reads 35%- CCW Pump A Discharge Temp Tl-671 reads 95°F- CCW Header A Pressure P1-649 SA reads 96 psig- CCW Header B Pressure P 1-650 SB reads 48 psig- CCW Hx A Outlet Header Flow Fl-652.1 reads 11,500 gpm

Which ONE of the following actions would automatically occur as a result of theseindications?

A. CCW Pump ‘B’ will start

B. CCW Holdup Tank Transfer Pump will trip

C. IDW-15, CCW Surge Tank Make Up, will open

D. 1CC-252, CCW Return Isolation from the RCP Thermal Barrier, will shut


2012 HNP NRC SRO

37. Given the following plant conditions:- The plant was operating at 100% power- A Large Break LOCA has occurred- The crew is implementing PATH-I


ICC-147, CCW From RHR Heat Exchanger A-SA will be opened (1) ANDI CC-99, CCW Heat Exchanger’A To Non-Essential Supply and 1CC-i 28, CCWNon-Essential Return To Header A will be shut (2)

A. (1) manually

(2) automatically

B. (1) automatically

(2) manually

C. (1) manually

(2) manually

D. (1) automatically

(2) automatically


2012 I-INP NRC SRO

38. Given the following plant conditions:- The plant is in Mode 3 at normal operating pressure- PZR Pressure Control is in AUTO- PZR Pressure Channel indications are:

P1-444: 2050 psig- P1-445: 2500 psig- P1-455: 2050 psig- P1-456: 1950 psig- P1-457: 2050 psig

Assuming NO operator actions, which ONE of the following describes the expectedconditions of the PZR PORVs and spray valves?

A. PORV IRC-114 (PCV-444B) - CLOSED

PORVs 1RC-1l6 (PCV-445B) and IRC-118 (PCV-445A) - OPEN

Spray Valves PCV-444C and PCV-444D - OPEN

B. PORV IRC-114 (PCV-444B) - OPEN

PORVs 1RC-116 (PCV-445B) and IRC-118 (PCV-445A) - CLOSED

Spray Valves PCV-444C and PCV-444D - OPEN

C. PORV 1 RC-1 14 (PCV-444B) - CLOSED

PORV 1 RC-1 16 (PCV-445B) and I RC-1 18 (PCV-445A) - OPEN

Spray Valves PCV-444C and PCV-444D - CLOSED

D. PORV 1RC-114 (PCV-444B) - OPEN

PORVs 1 RC-1 16 (PCV-445B) and I RC-1 18 (PCV-445A) - CLOSED

Spray Valves PCV-444C and PCV-444D - CLOSED


2012 HNP NRC SRO

39. Given the following plant conditions:- The plant was operating at 100% power- Offsite power was lost resulting in a Reactor Trip

Which ONE of the following operator actions or plant conditions are required to CLOSEthe Reactor Trip breakers?

1) Reset the Main Turbine Trip2) RCP Bus voltage must be restored to greater than 5148Volts3) ALL steam generator levels must be restored to greater than 25%4) Reset the PR High flux rate trips

A. 1,2

B. 1,3

C. 2,4

D. 3,4


2012 HNP NRC SRO

40. Given the following plant conditions:- The plant is operating at 100% power- Containment Pressure Channel IV pressure indication was oscillating and has been

removed from service in accordance with OWP-ESF, Engineered Safety FeatureActuation.

Which ONE of the following identifies the logic from the remaining channels for HI-iand Hl-3 Containment Pressure actuations AFTER Channel IV is REMOVED fromservice?

HI-I SI Actuation HI-3 CNMT Spray Actuation

A. 1/2 2/3

B. 1/2 1/3

C. 2/3 2/3

D. 2/3 1/3


2012 HNP NRC SRO

41. Given the following plant conditions:- The plant was operating at 100% power- A Small Break LOCA has occurred- Containment pressure is 3.8 psig and increasing- Containment temperature is 137°F and increasing


Containment Fan Coolers will be running in (1) speed with the post-accidentdampers (2)

A. (1)SLOW

(2) OPEN

B. (1)SLOW

(2) SHUT

C. (1)HIGH

(2) SHUT

D. (1)HIGH

(2) OPEN


2012 HNP NRC SRO

42. Given the following plant conditions:- The plant was operating at 100% power- MCC-1A22-SA is under clearance for breaker inspection- RHR Pump ‘A’ is under clearance for breaker repairs- A LOCA has occurred- Containment pressure is 14 psig- RWST level is 34% and decreasing- The crew is implementing PATH-i when power is lost to the 480V AC Emergency

Bus 1B3-SB- The CRS has transitioned to EPP-012, Loss of Emergency Coolant Recirculation

Given the current plant conditions, (1) spray pump(s) is/are running AND inaccordance with step 7 of EPP-01 2, (2) is the required number of ContainmentSpray Pumps.

Reference Provided

(1) (2) —

A. two two

B. two one

C. one two

D. one one


2012 HNP NRC SRO

43. Given the following plant conditions:- The plant was operating at 100% power- A Main Steam line break has occurred inside Containment- SPDS is displaying RED on the INTEGRITY Critical Safety Function (CSF)


The parameters used by SPDS to determine the INTEGRITY CSF are the (1)Tcold AND the (2) RCS Pressure.

A. (1) lowest

(2) lowest

B. (1) highest

(2) highest

C. (1) lowest

(2) highest

D. (1) highest

(2) lowest


2012 HNP NRC SRO

44. Given the following plant conditions:- The plant is operating at 85% power- A Loss of Main Feedwater Pump ‘B’ occurs- The crew enters AOP-0I0, Feedwater Malfunctions

Which ONE of the following describes (1) the plant response AND (2) the actionrequired in accordance with AOP-010?

A. (1) Automatic turbine runback is initiated

(2) Isolate Steam Generator Blowdown

8. (1) Automatic turbine runback is initiated

(2) Trip the Reactor and go to PATH-I

C. (I) Automatic turbine runback is NOT initiated

(2) Isolate Steam Generator Blowdown

D. (I) Automatic turbine runback is NOT initiated

(2) Trip the Reactor and go to PATH-i


2012 HNP NRC SRO

45. Given the following plant conditions:- The plant is operating at 100% power- Annunciator ALB-014-7-4, SG A, B, C Backleakage High Temp, has alarmed and

has been verified as valid by local pyrometer readings indicating > 212°F

Under these conditions why would establishing AFW flow to the Steam Generators bean undesirable action?

Rapid introduction of Auxiliary feed flow could result in. .

A. AFW Pump run out conditions.

B. thermal binding of AFW system valves.

C. accelerated water induced corrosion of AFW piping.

D. water hammer in AFW piping.


2012 HNP NRC SRO

46. Given the following plant conditions:- The plant is operating at 100% power- Loss of Instrument Bus 1 DP-1A-S1 has occurred- The crew is implementing AOP-024, Loss of Uninterruptible Power Supply- Recovery actions are in progress in accordance with OP-I 56.02, AC Electrical

Distribution- The crew has de-energized the associated Process Instrumentation Cabinet (PlC)

in preparation for energizing Instrument Bus I DP-IA-S1- The crew is evaluating bistable status prior to energizing the bus

Which ONE of the following describes the reason for checking bistable status prior toenergizing the instrument bus and PlC?

A. A Reactor Trip may occur when the PlC is re-energized if another bistable for thesame parameter is already tripped.

B. An ESF actuation may occur when the PlC is re-energized because the energize toactuate bistables may experience a momentary trip.

C. To ensure that each parameter for process or protection goes to its required statewhen the bus is re-energized.

D. To ensure all bistable lights are out, which indicates the PlC normal and alternatesupply breakers are open.


2012 HNP NRC SRO

47. Given the following plant conditions:- The plant is operating at 50% power- Aux Bus I D deenergizes and is locked out

Which ONE of the following loads will be energized following this event?(Assume no operator action)

A. Heater Drain Pump 1A

B. Containment fan coil Unit AH-37 IA

C. Service water booster Pump IA-SA

D. Pressurizer backup heater Group A


2012 HNP NRC SRO

48. Given the following plant conditions:- The plant is operating at 100% power- DP-1A-SA is being powered by the IA-SA Battery Charger with the 1 B-SA Battery

Charger in standby

The following occurs:- 1A-SA Battery Charger trips- ALB-01 5-4-4, 125 VDC EMER Bus A Trouble, ALARMS

Which ONE of the following (1) would be a cause of the Battery Charger trip AND(2) what is currently powering DP-1A-SA?

A. (1) Low DC voltage

(2) 1A-SA Battery

B. (1) Low DC voltage

(2) 1 B-SA Battery Charger

C. (1) High DC voltage

(2) 1A-SA Battery

D. (1) High DCvoltage

(2) 1 B-SA Battery Charger


2012 HNP NRC SRO

49. Given the following plant conditions:- OST-1823, 1A-SA Emergency Diesel Generator Operability Test 18 Month Interval,

is being performed- EDG ‘A’ is running carrying Bus IA-SA in lsochronous mode- ESW ‘A’ Pump trips

The crew enters AOP-022, Loss Of Service Water, and I SW-39, Normal SWSupply to Header A, will not OPEN


In accordance with AOP-022, the EDG ‘A’ (1) switch must be used to secure theDiesel AND when the control switch is released the Diesel will (2)

A. (1) EMERGENCY STOP

(2) Automatically restart due to undervoltage (86UV)

B. (1)EMERGENCY STOP

(2) not restart until the EDG trip signals are reset

C. (1) START/STOP

(2) Automatically restart due to undervoltage (86UV)

D. (1) START/STOP

(2) not restart until the EDG trip signals are reset


2012 HNP NRC SRO


Which ONE of the following will DIRECTLY initiate an emergency start of the ‘A’Emergency Diesel Generator?

A. BKR 1 05-SA, Emergency Bus A-SA to Aux Bus ‘D’ Tie, opening

B. 86UV undervoltage lockout on Aux Bus ‘D’ activating

C. BKR 101, SUT XFMR ‘A’ to Aux Bus ‘D’, opening concurrent with a generatorlockout

D. Safeguards Sequencer ‘A’ starting


2012 HNP NRC SRO

51. Given the following plant conditions:- The plant is operating at 100% power- Annunciator ALB-0l0-3-4, WPB Effluent Rad Monitor Trouble has alarmed- RM-1l indicates REM*1WV3546, WPB Stack 5 PIG Monitor is in HIGH alarm

Which ONE of the following valves will automatically shut?

A. 3LHS-296, Treated LHS Tk Disch Isol Valve

B. 3WG-229, WG Decay Tanks E & F to Plant Vent Vlv

C. 3FD-421, WMT Disch lsol Vlv

D. 3SWT-149, Sample Tk Environmental Disch Isol VIv

Monday, February 20, 2012 11:15:04AM 51 Rev. F(NAL

2012 HNP NRC SRO

52. Given the following plant conditions:- The plant is operating at 100% power- An overcurrent fault causes I B35-SB to be deenergized

How wilt the supply and return cross-tie valves between NSW and ESW be configured

following an automatic start of the ESW pump ‘B’?

A. BOTH 1 SW-40, Normal SW Supply to Header B, AND 1 SW-274, Header B Return

to Normal Header, will shut.

B. NEITHER I SW-40, Normal SW Supply to Header B, NOR I SW-274, Header B

Return to Normal Header, will shut.

C. ISW-40, Normal SW Supply to Header B, will shut; 1SW-274, Header B Return to

Normal Header, will NOT shut.

D. ISW-40, Normal SW Supply to Header B, will NOT shut; ISW-274, Header B

Return to Normal Header, will shut.


2012 HNP NRC SRO

53. Given the following plant conditions:- The plant is operating at 100% power- Annunciator ALB-002-8-1, Instrument Air Low Pressure, has alarmed- Air header pressure is lowering as indicated on the MCB meters

Which ONE of the following is an expected plant response for this situation?

A. 1SA-506, Service Air Header Isolation Valve, automatically shuts at 90 psig

B. The RCS letdown system automatically isolates at 85 psig

C. The Main Feedwater Reg valves automatically shut at 75 psig

D. The Main Feedwater Isolation valves automatically isolate at 60 psig


2012 HNP NRC SRO

54. Given the following plant conditions:- The plant is operating at 100% power- Compressor ‘B’ is running in Lead- Compressor ‘A’ is the Lag unit- Compressor ‘C’ is the Standby unit- A service air pipe ruptures resulting in lowering Instrument Air header pressure

Which ONE of the following statements describes the response of the Instrument AirSystem following the reduction in header pressure?

A. At 95 psig Compressor ‘A’ wiN autostart from its internal pressure switch, run for15 minutes, and if unloaded, wiN shutdown.

B. At 96 psig Compressor ‘A’ receives an autostart signal from the CAS Control PanelSequencer.

C. At 98 psig the CAS Control Panel Sequencer will shift to the ‘A’ compressor runningas Lead, with ‘B’ as Lag and the ‘C’ in Standby.

D. At 101 psig system air header pressure Compressor ‘C’ will autostart.


2012 HNP NRC SRO

55. Which ONE of the following components forces air within Containment between theReactor Vessel and the concrete wall which surrounds the Reactor Vessel?

A. Reactor Support Cooling Fans, S-4 A-SA

B. Containment Fan Coil Units, AH-2 A-SA

C. Primary Shield Cooling Fans, S-2 A-SA

D. Containment Fan Coolers, AH-37 IA


2012 HNP NRC SRO

56. Given the following plant conditions:- The plant was operating at 100% power- A Large Break LOCA occurred one hour ago- Only one Train of ECCS equipment is available

Under these conditions, in accordance with the WOG Mitigating Core DamageAssessment, which ONE of the following is the PRIMARY reason Source Range countrate may indicate HIGHER than expected?

A. The Source Range detectors are not accurate indicators under adverseContainment conditions

B. Attenuation of neutrons in the downcomer has been reduced by voiding

C. Attenuation of neutrons in the central portions of the core has been reduced byvoiding

D. RHR suction has swapped to the Containment Recirc Sump which contains a lowerboron concentration than the ECCS injection


2012 HNP NRC SRO

57. Given the following plant conditions:- The plant is operating at 100% power- Breaker 102, Unit Aux Xfmr A To Aux Bus D, is opened to isolate an electrical fault

caused by a fire.

Which ONE of the following loads will de-energize AND automatically re-energize?

A. NSW Pump ‘A’

B. NSW Pump ‘B’

C CSIP’A’

D. CSIP’B’


2012 HNP NRC SRO


A DRPI Data A and Data B failure occurs on the Shutdown Bank ‘C’ ControlRod E-2

- RPI General Warning and Rod bottom LED’s are lit for Control Rod E-2

Which ONE of the following ERFIS functions will be affected by this failure?

A. AFD Monitor

B. Rod Deviation Monitor

C. Rod Insertion Limit Alarm

D. QPTR Alarm


2012 HNP NRC SRO

59. Given the following plant conditions:- The plant is operating at 100% power- Core Exit Thermocouples G2 and K5 have failed due to open circuits- PT-456, Pressurizer Pressure Channel Il, fails HIGH


Based on the above conditions, the input from these thermocouples (G2, K5) to theInadequate Core Cooling Monitor (ICCM) will be (1) AND the subcooling marginwill be (2)

A. (1) failed low;

(2) calculated by an operator.

B. (1)failed high;

(2) calculated by an operator.

C. (1)failed low;

(2) calculated by ICCM.

D. (1)failed high;

(2) calculated by ICCM.


2012 HNP NRC SRO

60. Given the following plant conditions:- The plant is operating at 100% power- ARR Fan S-IA is in operation in Containment- The following alarm is received:

ALB-028-1-4, CNMT BLDG ARR CHAR FILTER TROUBLE

- ARR Fan S-lA switch indication is OFF and ARR Fan S-lB switch indication is ON

Which ONE of the following (1) describes the cause of the condition AND (2) the

procedure reference to correct this event?

A. (1) High z\P across the filter train

(2) FPP-002, Fire Emergency

B. (I) High AP across the filter train

(2) AOP-036, Safe Shutdown Following A Fire

C. (I) High charcoal filter temperature

(2) FPP-002, Fire Emergency

D. (1) High charcoal filter temperature

(2) AOP-036, Safe Shutdown Following A Fire


2012 HNP NRC SRO

61. Which ONE of the following completes the statements below?

AH-81 B, Containment Pre-entry Purge Makeup Fan, will trip when Containment

pressure increases to (1) INWG.

ICB-6, Vacuum Relief SB CIV, receives an open signal at (2) INWG.

A. (1)-0.25

(2) -1 .50

B. (1) -0.25

(2) -2.25

C. (1)-0.225

(2)-1.50

D. (1)-0.225

(2)-2.25


2012 HNP NRC SRO

62. Given the following conditions:- The plant is operating at 100% power- The suction pipe from Spent Fuel Pool ‘B’ to the Spent Fuel Pool Cooling Pump

completely severs- Spent Fuel Pool area radiation monitor RM-1 FR-3566A-SA is in HIGH alarm and

monitor RM-1 FR-3567B-SB is in ALERT


Level in the Spent Fuel Pool will decrease and stabilize at (1) feet above the fuelassemblies.

This condition will cause (2) train(s) of Fuel Handling Ventilation EmergencyExhaust to automatically start.

A. (1)18

(2) ‘A’

B. (1)18

(2) both ‘A’ and ‘B’

C. (1)23

(2) ‘A’

D. (1)23

(2) both ‘A’ and ‘B’


2012 HNP NRC SRO

63. Given the following plant conditions:- The plant is operating at 7% power- Feedwater Reg Bypass Valv&s are controlling SG level in automatic- AFW pumps are all secured

Which of the following completes the statement below?(Assume NO operator action)

If LT-496, SG ‘C’ level channel 3, fails low, SG ‘C’ level will increase to(1) , at which time a (2) will occur.

A. (1)78%

(2) MFWI

B. (1)78%

(2) MSLI

C. (1)73%

(2) MFWI

D. (1)73%

(2) MSLI


2012 HNP NRC SRO

64. Given the following plant conditions:- The plant is operating at 100% power- Treated L&HS Tank ‘A’ contains radioactive liquid that is required to be released.


In accordance with OP-I 20.1 0.04,Treated Laundry And Hot Shower Tanks, the

Treated L&HS Tank ‘A’ should be discharged to the (1) AND a new release

permit is required if (2) before discharging the remaining contents of the tank.

A. (1) Waste Neutralization Settling basin

(2) a valid High alarm on radiation monitor REM-3540 occurs

B. (I) Waste Neutralization Settling basin

(2) release flow rate on WP Computer point FA809 exceeds 80% of the Max

Effluent Flow Rate

C. (1) Cooling Tower Blowdown line

(2) a valid High alarm on radiation monitor REM-3540 occurs

D. (1) Cooling Tower Blowdown line

(2) release flow rate on WP Computer point FA809 exceeds 80% of the Max

Effluent Flow Rate


2012 HNP NRC SRO

65. Given the following plant conditions:- The plant is operating at 100% power- Instrument Air header pressure is 70 psig and lowering slowly

Which ONE of the following describes (1) the location where ISA-506, Instrument Airfrom Service Air Isolation Valve, position is indicated AND (2) the status of theInstrument Air Header Low Pressure alarm?

A. (1)SLB-3

(2) Alarm is NOT lit.

B. (1) AEP-1

(2) Alarm is NOT lit.

C. (1)SLB-3

(2) Alarm is lit.

D. (1)AEP-1

(2) Alarm is lit.


2012 HNP NRC SRO

66. Which ONE of the following would require suspension of Core Alterations?

A. Train ‘A’ Fuel Handling Building Emergency Exhaust unit is OPERABLE and in

operation; Train ‘B’ has just been declared INOPERABLE

B. Source Range audible indication inside Containment becomes unavailable

C. Reactor Cavity water level is 23 feet 3 inches above the vessel flange with only one

RHR loop operable and in operation

D. The Containment equipment hatch can be closed with 8 bolts


2012 HNP NRC SRO

67. Given the following plant conditions:- The plant is operating at 90% power- VCT level is 38%- VCT Level Transmitter, LT-1 12 fails high

Which ONE of the following completes the statement below?(Assume NO operator actions)

VCT level on LI-i 15 will (1) AND VCT Auto Makeup will be (2)

A. (1) lower

(2) available

B. (1)lower

(2) unavailable

C. (1) remain unchanged

(2) available

D. (1) remain unchanged

(2) unavailable


2012 HNP NRC SRO

68. Given the following plant conditions:- Mode 6, Refueling is in progress

Which ONE of the following lists the Key Safety Functions per OMP-003, OutageShutdown Risk Management?

A. Subcriticality, Core Cooling, Integrity, Inventory, Containment

B. Decay Heat Removal, Inventory, Electrical Power, Reactivity Control, Containment

C. Residual Heat Removal, Inventory, Cavity Level, Electrical Power, Auxiliary FeedWater

D. Decay Heat Removal, Reactivity Control, Integrity, Containment, Residual HeatRemoval


2012 HNP NRC SRO

69. While in Mode I, in accordance with Technical Specifications, the action for exceedinga Reactor Coolant System pressure of (1) requires the crew to (2)

A. (1) 2735 psig

(2) be in HOT STANDBY with the Reactor Coolant System pressure within its limitswithin 1 hour

B. (1) 2485 psig

(2) be in HOT STANDBY with the Reactor Coolant System pressure within its limitswithin 1 hour

C. (1) 2735 psig

(2) reduce the Reactor Coolant System pressure within its limits within 5 minutes

D. (1)2485psig

(2) reduce the Reactor Coolant System pressure within its limits within 5 minutes


2012 HNP NRC SRO

70. Given the following plant conditions:- A Refueling Outage is in progress- You have been assigned a task in the RCA and are preparing to sign on to the

Operations RWP- The survey map records the radiation levels as 1050 mRem/hour in the general

area

Which ONE of the following describes theapproval authority?

Area Classification

________________________

A. Very High Radiation Area

B. Very High Radiation Area

C. Locked High Radiation Area

D. Locked High Radiation Area

classification of this area and the MINIMUM

Individual Approving Entry

Lead Radiation Control Technician

Radiation Control Supervisor

Lead Radiation Control Technician

Radiation Control Supervisor


2012 HNP NRC SRO

71. Given the following plant conditions:- The plant is operating at 100% power- ALB-0l0-4-5, RAD Monitor System Trouble, has ALARMED- Both REM-O1LT-3502ASA, CNMT RCS Leak Detection Monitor, AND

RM-1 CR-3561A-SA, CNMT Vent Isolation, are in HIGH ALARM

Which ONE of the following sets of actions are required in accordance withannunciator panel procedures and AOP-005, Radiation Monitoring System?

A. Verify Normal Containment Purge isolated;

Monitor PRZ level and CNMT conditions

B. Verify Normal Containment Purge isolated;

Verify equipment alignment in accordance with OMM-004, Post-Trip/SafeguardsActuation Review

C. Verify Containment Ventilation Isolation;

Monitor PRZ level and CNMT conditions

D. Verify Containment Ventilation Isolation;

Verify equipment alignment in accordance with OMM-004, Post-Trip/SafeguardsActuation Review


2012 HNP NRC SRO

72. Which ONE of the following identifies (l)the 10 CFR 20 annual limit for TEDE AND(2) identifies the Emergency Exposure Limit for life saving activities in accordance withPEP-330, Radiological Consequences?

A. (1)4rem

(2) 10 rem

B. (1)5rem

(2) 10 rem

C. (1)4rem

(2) 25 rem

D. (1)5rem

(2) 25 rem


2012 HNP NRC SRO

73. Given the following plant conditions:- The plant was operating at 100% power- A loss of Component Cooling Water has occurred- The Reactor was tripped in accordance with AOP-014, Loss of Component Cooling

Water- The crew has entered PATH-i

Under these conditions which ONE of the following describes the continued use ofAOP-014?

A. Is NOTallowed during EOP performance

B. Is ONLY to be used concurrently with actions of PATH-I, and ONLY where directedby the EOP procedure

C. May be used concurrently with EOPs ONLY if referencing the AOP does NOT resultin delaying accident mitigation

D. Must be continued without interruption following the verification of PATH-iimmediate actions


2012 HNP NRC SRO

74. Given the following plant ôonditions:- The plant is in Mode 6 with Refueling in progress- A fire occurred inside Containment

Per FPP-003, Fire Investigation Report, who is responsible for initiating the FireInvestigation Report and providing it to the Shift Manager?

A. Refueling SRO

B. Control Room Supervisor

C. Site Incident Commander

D. Containment Coordinator


2012 F-INP NRC SRO

75. Which ONE of the following is (1) the LOWEST classification that REQUIRESaccountability to be completed AND (2) the LOWEST classification that REQUIRESactivation of the Emergency Response Organization?

A. (1)Alert

(2) Alert

B. (1)Alert

(2) Site Area Emergency

C. (1) Site Area Emergency

(2) Alert

D. (1) Site Area Emergency

(2) Site Area Emergency


2012 HNP NRC SRO

76. Given the following plant conditions:- The plant is operating at 45% power- The crew is performing AOP-01 8, Reactor Coolant Pump Abnormal Conditions, due

to rising temperatures on RCP ‘A’- The following conditions exist for RCP ‘A’

Time Pump Radial Bearing Temp Motor Stator Winding Temp0800 208°F 289°F0805 218°F 297°F0810 226°F 303°F0815 232°F 308°F

Which ONE of the following identifies (1) the FIRST limit to be exceeded, AND (2) aftersecuring RCP ‘A’ what actions are required to be directed by the CRS?

A. (1) Motor Stator Winding temperature

(2) Shutdown the Reactor in accordance with GP-006, Normal Plant ShutdownFrom Power Operation To Hot Standby

B. (1) Motor Stator Winding temperature

(2) Reduce power to approximately 25% and maintain that power

C. (1) Pump Radial Bearing temperature

(2) Shutdown the Reactor in accordance with GP-006, Normal Plant ShutdownFrom Power Operation To Hot Standby

D. (1) Pump Radial Bearing temperature

(2) Reduce power to approximately 25% and maintain that power


2012 HNP NRC SRO

77. Given the following plant conditions:- The plant is operating at 50% power- The crew is implementing AOP-01 8, Reactor Coolant Pump Abnormal Conditions,

and have determined that RCP ‘B’ trip limits have been exceeded- A Reactor Trip from the MCB is unsuccessful

Which ONE of the completes the statements below?

In accordance with FRP-S.1, Response To Nuclear Power Generation/ATWS,continue operating ALL RCPs until (1) then trip the RCP ‘B’. The basis forcontinued RCP operation is that it (2)

A. (1) a transition is made to PATH-i

(2) provides RCS pressure control preventing an overpressure condition

B. (1) a transition is made to PATH-I

(2) could be beneficial by temporarily cooling the core under voided RCSconditions

C. (1)poweris<5%

(2) provides RCS pressure control preventing an overpressure condition

D. (1)poweris<5%

(2) could be beneficial by temporarily cooling the core under voided RCSconditions


2012 HNP NRC SRO

78. Given the following plant conditions:- The plant is operating at 100% power- CVPETS radiation monitor is in alarm- Pressurizer level is lowering at the rate of 1 .4%/minute- CVCS conditions are:

- Charging flow is 137 gpm- Letdown flow is 106 gpm- RCP seal injection flows are:

‘A’ - 9.1 gpm, ‘B’ - 9.7 gpm, and ‘C’ - 9.2 gpm- RCP No.1 seal return flows are:

‘A’ - 2.9 gpm, ‘B’ - 2.5 gpm, and ‘C’ - 3.6 gpm


For the event described above, the magnitude of the leakage should be evaluated as aSteam Generator Tube (1)

The FSAR analysis for this event assumes the contaminated secondary fluid isreleased directly to the atmosphere due to failure of a SG (2) in the openposition.

A. (1) leak

(2) PORV

B. (1) leak

(2) Safety

C. (1) rupture

(2) PORV

D. (1) rupture

(2) Safety


2012 HNP NRC SRO

79. Given the following plant conditions:- The plant was operating at 100% power- The ASI pump is under clearance- A loss of Offsite Power has occurred- EDG ‘A’ and ‘B’ started but neither EDG output breaker, 106 nor 126, will close

In accordance with EPP-001, Loss of AC Power to 1A-SA and lB-SB Busses, whichONE of the following is (1) the MINIMUM pressure that the intact SGs will bedepressurized to AND (2) what will this pressure reduction accomplish?

A. (1) 130 psig

(2) Reduces the AP across RCP seals to minimize leakage and loss of RCSinventory.

B. (1)l3opsig

(2) Maximizes Natural Circulation flow to allow Reactor Vessel Head to cool sinceCRDM cooling fans are unavailable.

C. (1)l8opsig

(2) Reduces the AP across RCP seals to minimize leakage and loss of RCSinventory.

D. (1)l8opsig

(2) Maximizes Natural Circulation flow to allow Reactor Vessel Head to cool sinceCRDM cooling fans are unavailable.


2012 HNP NRC SRO

80. Given the following plant conditions:- The plant is operating at 100% power- ALB-015-5-4, 125 VDC EMER BUS B Trouble ALARMS- The DC Voltmeter reads 128 VDC locally

Which ONE of the following states (1) the MINIMUM total terminal voltage required to

maintain the Battery OPERABLE in accordance with Technical Specifications,

AND (2) the actions required for these conditions?

A. (1) 129 VDC

(2) Restore the inoperable D.C. electrical source to OPERABLE status within 2hours.

B. (1)129VDC

(2) Restore the inoperable D.C. electrical source to OPERABLE status within 8

hours.

C. (1) 132 VDC


hours.

D. (1)132VDC


hours.


2012 HNP NRC SRO

81. Given the following plant conditions:- The plant was operating at 100% power- A Grid voltage problem results in a LOSP and a Reactor Trip- EDG ‘A’ Fails to start- Subsequently a Small Break LOCA occurs and the crew actuates Safety Injection


Instrumentation from Group (1) is a list of Post Accident indicators located on theMain Control Board that will be available for monitoring plant conditions whileperforming recovery actions.

IF any of the Post Accident indicators were to fail with the plant in Mode 3 the ACTIONrequired by Technical Specifation 3.3.3.6 is to restore the inoperable channels toOPERABLE status within (2)

Group ONEFl-414, RCS Flow Loop AP1-455.1, PRZ PressureLl-7162A, CNMT WR Sump LevelPl-7160A, WR CNMT PressureFl-I 22A.l, Charging Line Flow

A. (I)ONE

(2) 48 hours

B. (I)TWO

(2) 48 hours

C. (1)ONE

(2) 7 days

D. (I)TWO

(2) 7 days

Group TWOTl-420.I, RCS Cold Leg Temp Loop BP1-403.1, WR RCS PressureLl-7160B, NR CNMT Sump LevelLl-487.1, WR SG B LevelFl-2050B1, AFW to SG B Flow


2012 HNP NRC SRO

82. Given the following plant conditions:- The plant is operating at 80% after a load rejection.- It has been determined that two control rods in Bank ‘DT are misaligned by

approximately 20 steps- BOTH rods are stuck and immovable- The AC dispatched to investigate reports no blown fuses or obvious electrical

problems at the Rod Control Cabinets- All rods have been verified above the Rod Insertion limits

Which ONE of the following actions are required in accordance with TechnicalSpecifications and AOP-001, Malfunction of Rod Control and Indication System?

Check SDM within limits of the COLR within one hour and...

A. place the unit in MODE 3 within 6 hours.

B. place the unit in MODE 4 within 24 hours.

C. power may be maintained at the current value if a power distribution map based onmovable incore detectors is verified to be within limits.

D. power may be maintained at the current value if reevaluation of accident analysisresults remain valid for the current condition.


2012 HNP NRC SRO

83. Given the following plant conditions:- A start up is in progress in accordance with GP-004, Reactor Startup

- Rx Power is being raised to 10-8 Amps- ALB-01 3-2-3, Source Range Loss of Detector Voltage, is received when the Source

Range detectors are blocked


In accordance with APP-ALB-013, Main Control Board, the CRS should direct the crewto CONTINUE operation, (1) because Reactor power is (2)

A. (1) in accordance with GP-004

(2) above P-6

B. (1) in accordance with GP-004

(2) below P-6

C. (1) REFER to OWP-RP, Reactor Protection

(2) above P-6

D. (1) REFER to OWP-RP, Reactor Protection

(2) below P-6


2012 HNP NRC SRO

84. Given the following plant conditions:- The plant was operating at 100% power- A LOCA has occurred- The CRS has transitioned from PATH-i to FRP-P.1, Response to Imminent

Pressurized Thermal Shock

Thirty (30) minutes after the initiating event, the following conditions are observed:

- RCS pressure has lowered to 600 psig and is now stable- Tcolds have lowered to 235°F and are now stable

The CRS is now at the step to determine if a RCS Soak is required. Which ONE of the

following identifies requirements for this event in accordance with FRP-P.1?

Soak Requirement Subsequent Cooldown Limit

A. Soak required <50°F in any 60 minute period

B. Soak required <100°F in any 60 minute period

C. Soak NOT required <50°F in any 60 minute period

D., Soak NOT required <100°F in any 60 minute period


2012 HNP NRC SRO

85. Given the following plant conditions:- The CRS is evaluating FRPs for implementation.- Containment pressure is 0.8 psig- The following Steam Generator conditions exist:

- SG’A’Pressure=ll75psig- SG ‘A’ Level 79%- SG ‘B’ Pressure = 1235 psig- SG ‘B’ Level = 65%

SG ‘C’ Pressure = 1100 psig- SG ‘C’ Level = 23%

Which ONE of the following identifies the FRP terminus that is CURRENTLY displayedon the CSF-3, Heat Sink, Critical Safety Function Status Tree?

A. FRP-H.2, Response to Steam Generator Overpressure

B. FRP-H.3, Response to Steam Generator High Level

C. FRP-H.4, Response to Loss of Normal Steam Release Capability

D. FRP-H.5, Response to Steam Generator Low Level


2012 HNP NRC SRO

86. Given the following plant conditions:- The plant was operating at 100% power- ALB-015-2-2, PlC 1-2-3-4-9-10-13-14 Power Failure, is intermittently alarming and

clearing- Troubleshooting reveals the PlC Cabinet 3 Card C3-845 for the Channel Ill, SF/FF

trip bistable 478B, has an open circuit


The CRS is required to implement (1) in order to replace the defective card ANDthe Technical Specifications required action is to place the channel in the trippedcondition within (2) hours.

A. (1) OWP - RP, Reactor Protection

(2) 6

B. (1) OWP - RP, Reactor Protecfion

(2) 4

C. (1) OWP - ESF, Engineered Safety Feature Actuation

(2)6

D. (1) OWP - ESF, Engineered Safety Feature Actuation

(2)4


2012 HNP NRC SRO

87. Given the following plant conditions:- The plant was operating at 100% power- A LOCA has occurred- Emergency Bus 1A-SA is deenergized- All RCP’s are operating- Containment pressure is 7 psig and increasing- CSIP ‘B’ tripped on overcurrent


Based on the RCS depressurization, the ESFAS system will start the Sequencer ‘B’ inprogram (1’) AND in accordance with PATH-IN the SRO should direct the BOP tocontrol AFW pump ‘B’ flow to maintain SG level, (2)

A. (1)’B’

(2) between 25% and 50%

B. (1)’B’


C. (1)’C’


D. (1)’C’



2012 HNP NRC SRO

88. Given the following plant conditions:- The plant is in Mode 3- The Motor Driven Auxiliary Feedwater (MDAFW) pumps are feeding the SGs


Shutting (1) would render BOTH MDAFW pumps inoperable AND in accordanceWith Technical Specifiations the plant must be in Mode 4 within (2) hours, if thevalve could not be reopened.

A. (1) FK-2051-1A1 SA, AFW FW A Regulator 1AF-49

(2)6

B. (1) FK-2051-IA1 SA, AFW FWA Regulator 1AF-49

(2) 12

C. (1) 1AF-55 SB, Aux FWA Isolation

(2) 6

D. (1) IAF-55 SB, Aux FW A Isolation

(2) 12


2012 HNP NRC SRO

89. Given the following plant conditions:- The plant is operating at 100% power- The following annunciators are received in the Control Room:

ALB-002-6-1, SERV WTR Supply HDR A Low PressALB-002-7-i, SERV WTR Supply HDR B Low PressALB-002-7-2, SERV WTR Pumps Discharge Low Press

- Ll-1931, Cooling Tower Basin Level, is lowering- P1-9302.1, NSW Disch Hdr Press, is lowering- PI-9101A1 SA, ESWA Disch Press, is lowering- Pl-9101B1 SB, ESW B Disch Press, is lowering

- Both ESW pumps aUtomatically start and align to their respective header- Pl-9101A1 SA, ESWA Disch Press stabilizes- Pl-9101B1 SB, ESW B Disch Press stabilizes- ALB-002-7-2 remains locked in and the Cooling Tower Basin Level continues to

lower.

Which ONE of the following describes (1) the location of the leak, AND (2) theprocedures required mitigate this event after the crew trips the Reactor?

A. (1) Normal Service Water System

(2) Go to PATH-i, transition to EPP-004, Reactor Trip Response, AND continuewith AOP-006, Turbine Generator Trouble, as time allows

B. (1) Emergency Service Water System

(2) Go to PATH-I, transition to EPP-004, Reactor Trip Response, AND continuewith AOP-006, Turbine Generator Trouble, as time allows

C. (1) Normal Service Water System

(2) Go to PATH-i, transition to EPP-004, Reactor Trip Response, AND continuewith AOP-022, Loss Of Service Water, as time allows

D. (1) Emergency Service Water System

(2) Go to PATH-i, transition to EPP-004, Reactor Trip Response, AND continuewith AOP-022, Loss Of Service Water, as time allows


2012 HNP NRC SRO

90. Given the following plant conditions:- The plant is operating at 100% power- The Compressed Air system (CAS) Control Panel is set for Air Compressor ‘C’ in

LEAD (Sequence 3)- A Valve Shift failure is present on Air Dryer 1 C-NNS- Instrument Air Header pressure indicates 110 psig

Which ONE of the following describes (1) the impact of this failure AND (2) theprocedure the CRS will implement to address this failure?

A. (1) High Air Dryer zP will cause a Loss of Instrument Air.

(2) Bypass Air Dryer 1 C-NNS in accordance with AOP-01 7, Loss of Instrument Air.

B. (1) Instrument Air will have a higher than desired moisture content.

(2) Shift the CAS Control Panel to Air Compressor IA! in LEAD (Sequence 1) andisolate Air Dryer I C-NNS in accordance with OP-I 51.01, Compressed Air.

C. (1) Instrument Air will have a higher than desired moisture content.

(2) Bypass Air Dryer 1 C-NNS in accordance with AOP-0I 7, Loss of Instrument Air.

D. (1) High Air Dryer AP will cause a Loss of Instrument Air.

(2) Shift the CAS Control Panel to Air Compressor ‘A’ in LEAD (Sequence 1) andisolate Air Dryer 1C-NNS lAW OP-151 .01, Compressed Air.


2012 HNP NRC SRO


An event occurs resulting in the following indications:- RCS Tavg is approximately 572°F and lowering- Reactor Power is lowering- First Stage Pressure Transmitter PT-446 indicates 0 psig- First Stage Pressure Transmitter PT-447 indicates 310 psig and stable- Main Generator Load is 450 MWe and stable- Control Bank D is inserting at 72 steps per minute

Which ONE of the following describes (1) the procedure entry required to mitigate theevent AND (2) the Technical Specification reason for the actions taken within theprocedure?

A. (1)AOP-001, Malfunction of Rod Control and Indication System

(2) to prevent violating Rod Insertion limits

B. (1) AOP-001, Malfunction of Rod Control and Indication System

(2) to prevent an out of spec negative AFD

C. (1) AOP-006, Turbine Generator Trouble

(2) to prevent violating Rod Insertion limits

D. (1) AOP-006, Turbine Generator Trouble

(2) to prevent an out of spec negative AFD


2012 HNP NRC SRO

92. Given the following plant conditions:- The crew is performing FRP-C.1, Response to Inadequate Core Cooling- All RCPs are stopped- NO CSIPs or RHR Pumps are available- SG NR levels are “A” 20%, “B” = 15%, “C” = 15%

Current Plant Conditions:- Core Exit TCs are reading 1250°F- RVLIS Full Range is 27%- The crew has depressurized intact SGs to 130 psig and were unsuccessful in

reducing RCS temperature

Which ONE of the following (1) identifies the actions the CRS should take forprocedure implementation AND (2) the action to mitigate this event?

A. (1) Transition to SACRG-1, Severe Accident Control Room Guideline InitialResponse;

(2) Start one RCP

B. (1) Transition to SACRG-1, Severe Accident Control Room Guideline InitialResponse;

(2) Open PRZ PORVs and Block Valves

C. (1) Remain in FRP-C.1;

(2) Start one RCP

D. (1) Remain in FRP-C.1;

(2) Open PRZ PORVs and Block Valves


2012 HNP NRC SRO

93. Given the following plant conditions:- The plant is operating at 100% power- Operators are aligning a Waste Gas release in accordance with O

Gas System- The total concentration for the WGDT to be released is abov,,ttje value for waiving

the requirement to check the stability class- The weather is degrading due to a temperature inversio- ERFIS indicated Stability Class ‘B’ when the permit wa’prepared but now indicates

Stability Class ‘E’. //

Which ONE of the following describes (1) the imp’of the stability change on theplanned release AND (2) in accordance with OP/-NGGC-1 000, Fleet Conduct OfOperations, who is responsible to review and1gn the Batch Gaseous Effluent Permitto authorize the release? /A. (1) The release is on hold until )Ømit with the current stability class is

(2)TheCRS

B. (1) The release is on ho%’until it is predicted that the Stability Class will be aStability Class ‘C’ irvThe next 4 to 6 hours.

on hold until a new permit with the current stability class is

release is on hold until it is predicted that the Stability Class will be aility Class ‘C’ in the next 4 to 6 hours.

0.07, Waste

(2) The CRS

C. (1)Therei

(2)The

D. (1)

Manager

The Shift Manager


2012 HNP NRC SRO

94. Given the following plant conditions:- The plant is in Mode 6 with Refueling in progress

Current plant conditions are:- Fuel movement has stopped due to a problem with the gripper tube top limit switch

on the Manipulator Crane- The Main Control Room has been informed that initial troubleshooting is in progress- The troubleshooting team desires to operate TS-3, Bridge Left Interlock Bypass, in

order to move the bridge while the gripper tube is not at the top limit

In accordance with FHP-020, Refueling Operations, which ONE of the followingidentifies (1) the individual required to approve this action AND (2) the individual thatmust concur with this approval?

A. (1) the CRS

(2) the Maintenance Outage Manager - Refueling

B. (1) the CRS

(2) the Shift Manager

C. (1) the SRO-Fuel Handling

(2) the Maintenance Outage Manager - Refueling

D. (1) the SRO-FueI Handling

(2) the Shift Manager


2012 HNP NRC SRO

95. Which ONE of the following is the basis for reducing Tavg to less than 500°F if thespecific activity of the Reactor Coolant is not within the limits of LCO 3.4.8, RCSSpecific Activity?

A. Minimize the release of activity in the event of a LOCA outside Containment

B. Minimize a release of activity should a SGTR occur by preventing the SGatmospheric reliefs from automatically lifting

C. Ensure that the 1-hour dose at the SITE BOUNDARY will not exceed a smallfraction of the 10 CFR Part 100 dose guideline limits in the event of a SGTR

D. Ensure that the 1-hour dose at the SITE BOUNDARY will not exceed a smallfraction of the 10 CFR Part 20 dose guideline limits in the event of a LOCA


2012 HNP NRC SRO

96. Given the following plant conditions:- The plant is operating at 100% power- The low flow input from AH-1 A-SB to annunciator ALB-029-3-2, Containment Fan

Coolers AH-1 Low flow - OIL, is failed causing the annunciator to be lit whenconditions are not valid

- Repair of the failed low flow input is not expected to occur for at least one month- To enable this annunciator to function for AH-1 B-SB low flow and the overload

condition on either fan, leads will be lifted to disable the annunciator input from theAH-1 A-SB low flow output

In accordance with OPS-NGGC-1 000, Fleet Conduct of Operations, the annuciatorshould be flagged (1)

In accordance with OPS-NGGC-1 308, Plant Status Control, (2) tags should beplaced on the lifted leads.

A. (1)blue

(2) Equipment Control

B. (1)blue

(2) Off Normal

C. (1)yellow

(2) Equipment Control

D. (1) yellow

(2) Off Normal


2012 HNP NRC SRO

97. Given the following plant conditions:- The plant is in Mode 6 with core offload in progress- A fuel assembly has just been unlatched in the Containment upender- The Fuel Handling SRO has reported that Refueling Cavity Level is rapidly lowering- The MCR crew is implementing AOP-031, Loss of Refueling Cavity Integrity- The CRS has directed the upender to be lowered and the fuel assembly transferred

to the Fuel Handling Building

Prior to lowering the upender, the following occurs:- ALL CNMT Ventilation Isolation radiation monitors are in ALERT- HP reports radiation levels on the manipulator crane of 162 mR/hr and increasing

Which ONE of the following describes the required action(s) the Refueling SRO mustdirect the Refuel Team to perform in accordance with AOP-031?

A. Lower the upender and transfer the assembly to the Fuel Handling Building thenevacuate ONLY unnecessary personnel

B. Leave the fuel assembly in the upender and evacuate ONLY personnel on theRefueling Manipulator crane

C. Lower the upender and transfer the assembly to the Fuel Handling Building thenevacuate ALL personnel

D. Leave the fuel assembly in the upender and evacuate ALL personnel


2012 HNP NRC SRO

98. The crew is implementing PATH-2. The CRS is at the step to isolate flow from theruptured SG and is about to direct the RO to adjust the ruptured SG PORV controllersetpoint.


The CRS should direct the RO to set the ruptured SG PORV controller setpoint to(1) and the basis for setting the controller to the new setpoint is to 2

A. (1) 1135 psig (87%)

(2) prevent lifting the SG code safety valves

B. (1) 1145 psig (88%)

(2) prevent lifting the SG code safety valves

C. (1) 1135 psig (87%)

(2) minimize RCS to ruptured SG iW

D. (1) 1145 psig (88%)

(2) minimize RCS to ruptured SG AP


2012 HNP NRC SRO

99. Which ONE of the following events requires 1 hour notification to the NRC inaccordance with AP417, Reportabliity Determination And Notification?

A. A required action which deviates from Technical Specifications Is performed

B. An inadvertent Safety Injection results in ECCS discharge into the RCS

C. An Inadvertent Auxiliary Feedwater pump start at 100% Reactor power

0. A required Reactor Trip due to a loss of Main Feedwater

Monday. February 20, 2012 11:15:05AM 99 Rev. FINAL

2012 HNP NRC SRO

100. Given the following plant conditions:- The plant is in Mode 5- RCP ‘B’ is in service- Safety Bus 1 B-SB is de-energized for a Bus Outage- Breaker 104, AUX BUS 1D TO EMERGENCY BUS A-SA, trips open- EDG ‘A’ starts, but Breaker 106, DIESEL GEN A-SA, fails to close


Given the above conditions the CRS will enter (1) to trip the RCP ‘B’ AND(2) to restore power.

Procedure Titles:AOP-018, Reactor Coolant Pump Abnormal ConditionsAOP-025, Loss of One Emergency AC Bus (6.9kv) Or One Emergency DC Bus (125V)EOP-EPP-001, Loss Of AC PowerTo 1A-SAAnd lB-SB Buses

A. (1) AOP-025

(2) GO TO EOP-EPP-001

B. (1) AOP-025

(2) REFER TO EOP-EPP-001

C. (1)AOP-018

(2) GO TO EOP-EPP-001

D. (1)AOP-018

(2) REFER TO EOP-EPP-001

You have completed the test!


LOSS OF EMERGENCY COOLANT RECIRCULATION

INSTRUCTIONS RESPONSE NOT OBTAINED

7. Determine CNMT SprayRequirements:

EJ a. Spray pump suction - ALIGNED D a. GO TO Step 8.TO RWST

D b. Determine required number ofCNMT spray pumps from Table:

CONTAINMENT SPRAY REQUIREMENTS

TOTAL # OF REQUIRED #RWST CONTAINMENT FAN COOLER OF CNNTLEVEL PRESSURE UNITS RUNNING SPRAY PUMPS

GREATER THAN 45 PSIG N/A 2GREATER

THAN 23.4% BETWEEN 0 OR 1 210 PSIG AND 45 PSIG

20R3 1

4 0

LESS THAN 10 PSIG N/A 0

GREATER THAN 45 PSIG N/A 2

BETWEEN 3% BETWEEN 0 • 1 OR 2 1AND 23.4% 10 PSIG AND 45 PSIG30R4 0

LESS THAN 10 PSIG N/A 0

LESS THAN3% N/A N/A 0

c. Verify spray pumps - REQUIREDNUMBER RUNNING

d. Shut CNMT spray pump dischargevalve(s) for the pump(s) stopped inStep 7c:

D 1CT-50 (A CT Pump)D ICT-88 (B CT Pump)

EOP-EPP-012 Rev. 27 I Page 6 of 63

2012 HNP NRC SRO WRITTEN EXAM

ANSWER KEY

Answers# ID Points Type 0

1 2O12NRCROI 1.00 MCS A2 2012NR.CRO2 1.00 MCS A3 2O12NRCRO3 1.00 MCS C4 2O12NRCRO4 1.00 MCS D5 2O12NRCRO5 1.00 MCS C6 2OI2NRCRO6 1.00 MCS C7 2O12NRCRO7 1.00 MCS C8 2OI2NRCRO8 1.00 MCS B9 2O12NRCRO9 1.00 MCS D10 2O12NRCRO1O 1.00 MCS A11 2O12NRCRO1I 1.00 MCS A12 2O12NRCRO12 1.00 MCS B13 2012 NRC RO 13 1.00 MCS C14 2O12NRCRO14 1.00 MCS C15 2O12NRCRO15 1.00 MCS D16 2O12NRCRO16 1.00 MCS D17 2O12NRCROI7 1.00 MCS B18 2O12NRCRO18 1.00 MCS A19 2O12NRCRO19 1.00 MCS C20 2O12NRCRO2O 1.00 MCS D21 2O12NRCRO21 1.00 MCS A22 2012NRCR022 1.00 MCS B23 2012NRCR023 1.00 MCS D24 2O12NRC RU 24 1.00 MCS A25 2012NRCR025 1.00 MCS D26 2O12NRC RU 26 1.00 MCS A27 2012NRCR027 1.00 MCS B28 2012 NRC RU 28 1.00 MCS C29 2012NRCR029 1.00 MCS B30 2O12NRCRO3O 1.00 MCS A31 2O12NRCRO31 1.00 MCS B32 2O12NRC RU 32 1.00 MCS D33 2012NRCR033 1.00 MCS C34 2012NRCR034 1.00 MCS D35 2012NRCR035 1.00 MCS C36 2012NRCR036 1.00 MCS A37 2012NRCR037 1.00 MCS C38 2012NRCR038 1.00 MCS C39 2012NRCR039 1.00 MCS D40 2O12NRCRO4O 1.00 MCS A41 2O12NRCRO41 1.00 MCS A42 2012 NRC RU 42 1.00 MCS A43 2012NRCR043 1.00 MCS C44 2012 NRC RU 44 1.00 MCS A45 2012NRCR045 1.00 MCS D46 2012NRCR046 1.00 MCS B47 2012NRCR047 1.00 MCS C48 2012NRCR048 1.00 MCS C

Points Type 0

1.00 MCS B1.00 MCS A1.00 MCS B1.00 MCS B1.00 MCS A1.00 MCS D1.00 MCS C1.00 MCS B1.00 MCS C1.00 MCS B1.00 MCS C1.00 MCS C

1.00 MCS D1.00 MCS A1.00 MCS A1.00 MCS C1.00 MCS C1.00 MCS B1.00 MCS A1.00 MCS B1.00 MCS A1.00 MCS D1.00 MCS A1.00 MCS D1.00 MCS C1.00 MCS C1.00 MCS C1.00 MCS A1.00 MCS D1.00 MCS C1.00 MCS C1.00 MCS A1.00 MCS D1.00 MCS A1.00 MCS A1.00 MCS A1.00 MCS A1.00 MCS A1.00 MCS D1.00 MCS C1.00 MCS C1.00 MCS B1.00 MCS A1.00 MCS D (‘-.

1.00 MCS D1.00 MCS B1.00 MCS D

# ID

49 2012NRCR04950 2O12NRCRO5O51 2O12NRCRO5I52 2012NRCR05253 2012NRCR05354 2012NRCR05455 2012NRCR05556 2012NRCR05657 2012NRCR05758 2012NRCR05859 2012NRCR05960 2O12NRCRO6O61 2OI2NRCRO6162 2012NRCR06263 2012NRCR06364 2012NRCR06465 2012NRCR06566 2012NRCR06667 2012NRCR06768 2012NRCR06869 2012NRCR06970 2O12NRCRO7O71 2OI2NRCRO7I72 2012NRCR07273 2012NRCR07374 2012NRCR07475 2012NRCR07576 2OI2NRCSRO177 2O12NRCSRO278 2O12NRCSRO379 2O12NRCSRO480 2O12NRCSRO581 2OI2NRCSRO682 2O12NRCSRO783 2O12NRCSRO884 2OI2NRCSRO9

85 2O12NRCSROIO86 2O12NRCSRO1187 2O12NRCSROI288 2O12NRCSRO1389 2OI2NRCSROI490 2O12NRCSRO1591 2O12NRCSRO1692 2O12NRCSRO17

—932RGRO-4-94 2O12NRCSRO1995 2OI2NRCSRO2O96 2O12NRCSRO21

Answers# ID Points Type 0

97 2OI2NRCSRO22 1.00 MCS D98 2O12NRCSRO23 1.00 MCS B

99 2012 NRC SRO 24 1.00 MCS A100 2012 NRC SRO 25 1.00 MCS B

SECTION 1 (100 items) 100.00

Cover Sheet U.S. Nuclear Regulatory Commission · 2012 HNP NRC SRO 2. Given the following plant...

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