sequoyah initial exam 2015-301 final ro written exam.sqn 1503 sro nrc exam 2. given the following...

ES-401 Site-Specific RO Written Examination Form ES-401-7Cover Sheet

U.S. Nuclear Regulatory Commission

Site-Specific RO Written Examination

Applicant Information

Name:

Date: Facility/Unit: Sequoyah Nuclear Station 1 & 2

Region: I El ii X III El IV El Reactor Type: W X CE E] BW El GE El

Start Time: Finish Time:

Instructions

Use the answer sheets provided to document your answers. Staple this cover sheet on top of

the answer sheets. To pass the examination, you must achieve a final grade of at least 80.00

percent. Examination papers will be collected 6 hours after the examination begins.

Applicant Certification

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

Applicant’s Signature

Results

Examination Value

__________

Points

Applicant’s Score

___________

Points

Applicant’s Grade

___________

Percent

ANSWER KEY REPORTfor SQN 1503 RO NRC EXAM Test Form: 0

AnswersID PolnbType 0

I 008 A62.2.37 I 1.00 MCS C2 OO9EAI.14302 1.00 MCS B3 OIIEK3.15303 1.00 MCS A4 022AA2.04304 1.00 MCS B5 025A02.l.285 1.00 MCS D6 027AK2.036 1.00 MCS C7 029EK2.06307 1.00 MCS A8 038EKl.02408 1.00 MCS C9 054AAl.03309 1.00 MCS A10 055EA1.02310 1.00 MCS DII 056AA2.60II 1.00 MCS C12 057AA2.18512 1.00 MCS A13 058 A02.4.50 713 1.00 MCS LI14 077 AK3.0I 14 1.00 MCS BIS W/EO4EKI.3315 1.00 MCS A16 W/EO5EK3.4316 1.00 MCS B17 W/EIIIiK2.23I7 1.00 MCS A18 W/E12 EKI.3 718 1.00 MCS C19 OOIAA2.033I9 . 1.00 MCS A20 028 AK3.03 20 1.00 MCS I)21 051 AAI.0432I 1.00 MCS D22 O6OAAI.0I22 1.00 MCS C23 068AK2.0123 1.00 MCS [324 076A02.I.32324 1.00 MCS A25 W/EO8EKI.2525 1.00 MCS A26 WIEIOEA2.226 1.00 MCS D27 V/IBIS EK3.I 327 1.00 MCS C28 003K5.03528 1.00 MCS A29 00402.4.31 329 3.00 MCS C30 004K2.0330 1.00 MCS C31 005K4.03431 1.00 MCS B32 006K2.0132 1.00 MCS B33 007A3.0I33 1.00 MCS D34 008A1.0I 334 1.00 MCS A35 010K4.0I 335 1.00 MCS A36 012K3.0136 1.00 MCS A37 013K1.0637 1.00 MCS A38 013K2.0138 1.00 MCS C39 022A2.0339 1.00 MCS D40 022K3.0240 3.00 MCS A41 025 K6.0I 54! 1.00 MCS C42 026 A4.05 42 1.00 MCS B43 039A3.0243 1.00 MCS C44 059 K4.05 544 1.00 MCS A45 059 02.4.11 345 1.00 MCS A46 061 K5.0I 546 1.00 MCS B

Thursday, March 19, 2015 12:02:36 PM

ANSWER KEY REPORTfor SQN 1503 RO NRC EXAM Test Form: 0

- Answers

ID Points Type 0

47 061 Ko.02 37 1.00 MCS A

38 062 (32.2.30 448 1.00 MCS C

40 063 K 1.03 349 1.00 MCS C

50 064 K 1.02 350 1.00 MCS 13

51 073 K3.0 I 551 1.00 MCS [3

52 076 A3.02 52 1.00 MCS [3

53 076 K4.03 53 1.00 MCS C

54 078 A4.0 I 53 1.1)0 MCS 1)

55 103 A2,04 155 1.00 MCS 13

56 001 K2.0 I 56 1.00 MCS D

57 015 (32.2.40 357 1.00 MCS I)

58 016 A3.0 I 58 1.00 MCS C

59 028 A2.02 59 1.00 MCS C

60 034 K4.02 560 1.00 MCS A

6! 041 K3.0261 1.00 MCS A

62 071 A 1.06 362 1.00 MCS 13

63 1)72 K 1.03 63 I .00 MCS [3

64 075 K4.OI 364 1.00 MCS B

65 086 A4.0 I 365 1.00 MCS A

66 (32. I .1 566 1.00 MCS D

67 (3 2.1.34 367 1.00 MCS B

68 (32.1.5368 1.00 MCS D

69 (32.2.13 169 1.00 MCS B

70 (32.2.2 370 1.00 MCS A

71 (32.2.41 7! 1.00 MCS C

72 G 2.3.5 72 1.00 MCS D

73 (32.3.773 1.00 MCS C

71 (1 2.4.39 474 1.00 MCS D

75 (32.4.4 475 1.00 MCS A

SFCTION I (75 items) 75.00

Thursday, March 19, 2015 12:02:36 PM 2

Name:

___________________________

SQN 1503 SRO NRC EXAMForm: 0

Version: 0

1. Given the following plant conditions:

- Unit 1 is operating at 100% power.- The following alarm is received:

- PS-68-301 PRESSURIZER RELIEF TANK PRESS HIGH (1-M-5-A, D-1)

- PZR PORV 68-340 acoustic monitor indicates discharge.- The OATC places the PORV Control switch in CLOSE.- PZR Pressure continues to lower with both Red and Green light indication

for the PORV extinguished.- The OATC closes the associated block valve and PZR Pressure stops dropping

and is now at 2110 psig and rising slowly.

Which ONE of the following identifies the MINIMUM required actions in accordancewith Technical Specifications?

A. Maintain power available to associated block valve;Restore RCS pressure to > 2220 psia.

B. Maintain power available to associated block valve;Restore RCS pressure to > 2235 psia.

C. Remove power from the associated block valve;Restore RCS pressure to > 2220 psia.

D. Remove power from the associated block valve;Restore RCS pressure to > 2235 psia.

Thursday, March 19, 2015 10:50:01 AM

SQN 1503 SRO NRC EXAM2. Given the following plant conditions:

- Unit 1 was at 100% power.- The crew manually tripped the reactor and initiated a Safety Injection due toa Small Break LOCA.- RCS pressure is 1300 psig and stable.- Core exit T/Cs are 550° F and stable.- Containment pressure is 2.9 psig and stable.- All SG pressures are 1000 psig and stable.- The crew is preparing to initiate the RCS cooldown in accordance with

ES-i .2, “Post LOCA Cooldown and Depressurization.”

In accordance with ES-i .2, which ONE of the following completes the statementbelow?

RCS cooldown to Cold Shutdown can commence (i) , and the operators arerequired to use the (2)

A. immediatelySteam Dumps

B. immediatelyAtmospheric Reliefs

C. only after verifying adequate shutdown marginSteam Dumps

D. only after verifying adequate shutdown marginAtmospheric Reliefs

Thursday, March 19, 2015 10:50:01 AM 2


- Unit 2 has experienced a large break LOCA.- Conditions are met for entry into ES-i .3, “Transfer to RHR

Containment Sum p.”

In accordance with ES-i .3, which ONE of the following completes the statementbelow?

Containment sump level must be a minimum of (1) to initiate auto sumpswap overto ensure (2)

A. (1) 11%(2) containment sump level is high enough to provide adequate suction

head for the RHR pumps

B. (1) 11%(2) sufficient RWST water has been sprayed into the containment

atmosphere to limit post accident Iodine concentration

C. (1) 18%(2) containment sump level is high enough to provide adequate suction

head for the RHR pumps

D. (1) 18%(2) sufficient RWST water has been sprayed into the containment

atmosphere to limit post accident Iodine concentration



- Unit 1 was operating at 100% power when FCV-62-93, Charging Flow Control,malfunctioned to limit total charging flow to 65 gpm.

- The plant is at normal operating temperature, pressure and level- Normal letdown is in service on a 75 gpm orifice- Identified leakage is 10 gpm- Unidentified leakage is .01 gpm- RCP seal leak-off is 3 gpm per pump

If NO operator actions are taken, which ONE of the following is closest to the time it willtake before the following alarm on 1-M-5-A is received:

“LS-68-335E/D PRZR LVL LOW HEATER OFF & LETDOWN SECURED” (E-3)

(Assume PZR is 62 gaII%)

A. 63 minutes

B. 83 minutes

C. 116 minutes

D. 133 minutes



- Unit 1 RCS is in Midloop condition- B Train RHR is in service- Eight SIG Nozzle Dams are installed- Subsequently, Nonessential Control Air Header depressurizes to 0 psig

Which ONE of the following identifies the impact on the plant?

A. RHR flow will lower resulting in a loss of RHR shutdown cooling.

B. CVCS charging will rise resulting in RCS overfill and overflow out the S/G manways.

C. CVCS charging flow will lower and will result in reduced RCS level and possibleRHR pump cavitation.

D. RHR flow will rise but will be limited by valve restraints preventing RHR suctionvortexing and loss of shutdown cooling.



- Unit 2 is at 80% power and raising power when a step load change inpower occurs.

- Pressurizer pressure drops to 2205 psig.- Automatic pressure control responds as designed.- As pressure rises to 2214 psig, 2-PIC-68-340A, PZR Pressure Controller,

output is observed to be 10% and not responding.- The controller is placed in MANUAL with the controller output reading 10%.

Assuming NO further operator action, which ONE of the following identifies thesystem response?

A. All Heater banks remain ON and pressure will be controlled by Spray valvesPCV-68-340B & 340D.

B. Heater banks C & D remain ON, Heater Banks A & B turn OFF and pressure will becontrolled by Spray valves PCV-68-340B & 340D.

C. All Heater banks remain ON and pressure will be controlled by PORV PCV-68-334.

D. Heater banks C & D remain ON, Heater Banks A & B turn OFF and pressure will becontrolled by PORV PCV-68-334.



- Unit 1 at 100% power- A transient occurs that requires a manual reactor trip.- The OATC attempts to trip the reactor but the reactor fails to trip.

Which ONE of the following completes the statements below relative to the failure ofthe reactor trip breakers that would have caused the reactor NOT to trip and the localaction(s) required to trip the reactor? 14L’The Reactor Trip Breaker’s 1 25V DC shunt trip coii1?iled to jj

To locally cause a reactor trip,

___________

Reactor Trip Breaker(s) must be opened.

UI

A. energize only one

B. energize both

C. de-energize only one

D. de-energize both



- A SGTR has occurred in SIG #1 on Unit 1.- The RCS cooldown, depressurization and ECCS flow termination steps of

E-3, “Steam Generator Tube Rupture,” have been completed.- Normal charging and letdown have been established.

- At 0400, plant conditions are:- Pressurizer level 18%- Ruptured S/G NR level 82%- Ruptured SIG pressure 1040 psig- RCS pressure 1000 psig

- At 0415, plant conditions are:- Pressurizer level 22%- RupturedS/GNRlevel 81%- Ruptured S/G pressure 1040 psig- RCS pressure 1000 psig

As directed in E-3, Step 32, “CONTROL RCS pressure and charging flow to minimizeRCS-to-secondary leakage,” which ONE of the following identifies the required actionto be taken?

REFERENCE PROVIDED

A. Lower ruptured S/G pressure and maintain RCS and S/G pressures equal.

B. Raise charging flow.

C. Turn on pressurizer heaters.

D. Depressurize the RCS.



- Unit 1 is at 35% power doing a plant startup.- 1A MEW pump is in service.- The “MEPT B RESET/TRIP handswitch on 1-M-3 has the Green light LIT.- Subsequently the 1A MEW pump trips.

Which ONE of the following identifies:

(1) when the TDAEW pump starts

and

(2) the source of the cooling water for the TDAEW pump bearings?

A. (1) immediately on the MEP trip(2) a stage on the TDAEW pump

B. (1) immediately on the MEP trip(2) the ERCW system

C. (1) when the SG Level Lo-Lo setpoint is reached(2) a stage on the TDAEW pump

D. (1) when the SG Level Lo-Lo setpoint is reached(2) the ERCW system



- Unit 1 has experienced a total loss of power.- The crew has entered ECA-0.0, Loss of All AC Power.”- The crew was unable to start a diesel generator from the main control room.- An AUO has been dispatched to the DG building.

Which ONE of the following identifies the required sequential procedural actions tostart the lA-A DG locally in accordance with ECA-0.0, Appendix F, “Local DGOperation?”

The j) will place the DG mode selector switch in the Pull for Local Transferposition and the AUO (2) required to press the Trip to Local pushbutton beforepressing the Auto Start pushbutton.

A. (1) AUO(2) is NOT

B. (1) AUO(2) is

C. (1) CR0(2) is NOT

D. (1) CR0(2) is



- Unit 2 is at 100% power.- A Loss of Off-Site power occurs.- A blown fuse has caused the normal Loop 2 MSIV valve position

light indication on the handswitch to be lost.

Assuming NO operator action, which ONE of the following completes thestatement below?

The Loop 2 MSIV will (1) and the position of the Loop 2 MSIV ) bedetermined from the MONITOR LIGHTS 2-XX-55-6L panel.

A. (1) remain open indefinitely(2) can

B. (1) remain open indefinitely(2) can NOT

C. (1) eventually fail closed(2) can

D. (1) eventually fail closed(2) can NOT



- Unit 2 is operating at 100% power.- Subsequently,

- 12OVAC VITAL PWR BD 2-Ill UV OR BKR TRIP (2-M-1-C, C-7)alarm is LIT.

- Channel III status lights are LIT

Based on the above conditions, 2-FCV-62-1 35, RWST TO CCP valve will (1)and in accordance with AOP-P.04, “Loss of Unit 2 12OVAC Vital Instrument PowerBoard,” a manual reactor trip (2) required.

A. (1) auto open(2) is

B. (1) auto open(2) is NOT

C. (1) remain closed(2) is

D. (1) remain closed(2) is NOT


SQN 1503 SRO NRC EXAM13. Given the following conditions:

- Both Units are at 100% power.- Subsequently the following alarm is received:

125V DC VITAL CHGR III FAIL! VITAL BAT Ill DISCHARGE (2-M-1-C, C-4)

Which ONE of the following completes both statements below?

In accordance with 2-SI-OPS-000-003.W, “Weekly Shift Log,” the minimum allowableTech Spec limit for the Vital Battery Board DC voltage is (1)

In accordance with 2-AR-Mi-C, C-4, 125V DC VITAL CHGR III FAIL ! VITAL BAT IIIDISCHARGE,” downscale (zero or below) deflection of EI-57-94, Vital Battery BD IIIAmps, indicates current flow from the )

A. (1) 125VDC(2) battery

B. (1) 125VDC(2) charger

C. (1) 119VDC(2) battery

D. (1) 119VDC(2) charger



- Unit-i is operating at 80% power.- Due to grid disturbances the crew had entered AOP-P.07, “Degraded Grid

Conditions or Generator Voltage Regulator Malfunction.”- Grid frequency has held steady at 59 Hz for twenty minutes.- The Unit Supervisor directs the OATC to trip the reactor.

In accordance with AOP-P.07, “Degraded Grid Conditions or Generator VoltageRegulator Malfunction,” which ONE of the following identifies the reason for thisrequired action?

A. The Tech Spec limit for frequency on a D/G has been exceeded.

B. To prevent exceeding 25% of lifetime limit of off-frequency operation of LP turbine.

C. The auto reactor trip setpoint for RCP Underfrequency has been exceeded.

D. To prevent exceeding improper bearing loading and turbine misalignment.



- Unit 2 is at 100% power.- Subsequently a LOCA outside containment occurs.- The crew trips the reactor and initiates safety injection.- The crew has transitioned to ECA-1 .2, “LOCA Outside Containment.”

In accordance with ECA-1 .2, which ONE of the following completes the statementbelow?

The first action that will be performed to isolate the leak is to close Li) valvesone at a time and the operators will check (2) to determine if the LOCA has beenisolated.

A. (1) RHR cold leg injection(2) RCS pressure

B. (1) RHR cold leg injection(2) RVLIS level

C. (1) Safety Injection pump cold leg injection(2) RCS pressure

D. (1) Safety Injection pump cold leg injection(2) RVLIS level

Thursday, March 19, 2015 10:50:01 AM 1 5


- FR-H.1, “Loss Of Secondary Heat Sink”, is in progress.- RCS feed and bleed is in progress.- Auxiliary Feedwater (AFW) is now available.- All Steam generators (S/Gs) indicate 8% Wide Rancie level and 90 psig.- Core exit T/Cs are stable at 552°F.

Which ONE of the following identifies an acceptable method of re-establishing feedflow under these conditions and the reason why?

A. Establish maximum available feed flow to one S/G to ensure Core Coolinghas been re-established.

B. Feed one S/G at a rate of 50 to 100 gpm to minimize thermal stresses to theS/G components.

C. Feed one S/G at a rate of 50 to 100 gpm to establish a controllable cooldownrate.

D. Feed all S/Gs at greater than or equal to 50 gpm to prevent S/G dryout.



- At 0900, Unit 2 reactor trips.- At 0920 a small break LOCA occurs.- At 0950 the crew transitioned to ECA-1 .1, “Loss of RHR Sump

Recirculation”, due to the failure of both RF-IR pumps.- Crew has reduced ECCS flow to 1 SIP and 1 CCP per ECA-1.1.- SI flow cannot be terminated due to lack of subcooling.- At 1030 the crew is performing ECA-1.1 Step 21 RNO to establish the

minimum required ECCS flow to remove decay heat.

Which ONE of the following completes the statements below?

The minimum flow rate that meets the intent of ECA-1.1, Step 21 RNO, is (1)

AND

ECCS pumps (2) be stopped or started to meet this requirement.

REFERENCE PROVIDED

A. (1) 325 gpm(2) can

B. (1) 325gpm(2) can NOT

C. (1) 400 gpm(2) can

D. (1) 400 gpm(2) can NOT



- Unit 2 is operating at 100% power.- A steam line break occurs in the common header

downstream of the MSIV5.- MSIV’s can NOT be closed.- The crew has implemented ECA-2.1, “Uncontrolled Depressurization of

All Steam Generators.”- T-cold cooldown rate is 200°F/hr.- RCS pressure is 1200 psig.- AFW flow has been reduced to 50 gpm per SG.- Subsequently, RCS T-hots are rising.

In accordance with ECA-2.1, which ONE of the following is the required proceduralaction under these conditions?

The operators are required to fl

and

The 1250 psig RCP trip criteria (2) apply

A. (1) Reduce RCS pressure(2) does

B. (1) Reduce RCS pressure(2) does NOT

C. (1) Raise MDAFW flow(2) does

D. (1) Raise MDAFW flow(2) does NOT



- Unit 1 is operating at 92% power.- Rod control in AUTO.- Control bank D rods are at 216 steps.- Maximum rate, continuous outward rod motion is observed on control bank D.- The following annuciator has just been received:

ZB-442C BANK D AUTO ROD WITHDRAWAL BLOCKED (1-M-4-B, C-7)

In accordance with AOP-C.01, “Rod Control System Malfunctions,” which ONE of thefollowing identifies the FIRST action to be taken?

A. Place rod control in MANUAL and verify rod motion stops.

B. Verify the Bank D Auto Rod Withdrawal Blocked has stopped outward rod motion.

C. Immediately insert control bank D back to 216 steps.

D. Manually trip the reactor and go to E-0, “Reactor Trip or Safety Injection”.



- Unit 2 was tripped from 100% power.- The crew is performing a plant cooldown in accordance with ES-0.2 “Natural

Circulation Cooldown.”- All steps have been completed up to Step 14, INITIATE RCS depressurization.

- The following plant conditions exist:

- Core exit T/Cs = 520° F- RCS pressure = 1900 psig

- While depressurizing the RCS, a PZR PORV fails OPEN.- Subsequently the following plant conditions are observed:

- RCS pressure is 800 psig and stable.- Core exit T/Cs remain at 520° F.- PZR level is 70% and rising rapidly.


Current PZR level indication jJ an accurate indication of RCS inventory.

The reason PZR level is rapidly rising is due to (2)

A. (1) is(2) automatic Safety Injection actuation

B. (1) is(2) drawing a bubble in the reactor vessel head

C. (1) is NOT(2) automatic Safety Injection actuation

D. (1) is NOT(2) drawing a bubble in the reactor vessel head



- Unit 1 is operating at 28% power.- Condenser pressure is 1 .9 psia and rising.


In accordance with AOP-S.02, “Loss of Condenser Vacuum,” a Main Turbine tripCl) required.

If a turbine trip occurs, in accordance with AOP-S.06, “Turbine Trip Below P-9(50% Power) control rods will be positioned to L

A. (1) is NOT(2) stabilize power with Tave = Tref

B. (1) is NOT(2) stabilize power at approximately 13 -15%

C. (1) is(2) stabilize power with Tave = Tref

D. (1) is(2) stabilize power at approximately 13 -15%



- Unit 1 and 2 are at 100% power.- The following high radiation alarm is received:

1-RA-90-1A AUX BLDG AREA RAD MON HIGH RAD (0-M-12-A, A-7)

- Subsequently, the following alarm is received:

0-RA-90-1O1AAUX BLDG VENT MONITOR HI RAD (0-M-12-B, B-1)

- No other rad monitors are in alarm.

Which ONE of the following is a potential cause of the above indication?

A. Dropped fuel assembly in the SFP

B. Gas Decay Tank relief valve fails open

C. Gas Decay Tank pressure indicator sensing line breaks

D. An RCS leak into the CCS



- The main control room had to be evacuated and the crew is implementingAOP-C.04, “Control Room Inaccessibility.”

- The crew is cooling down Unit I to Cold Shutdown, in accordance withAOP-C.04, Section 2.1, “Plant Cooldown from Auxiliary Control Room.”

Which ONE of the following identifies 1-L-10 panel indications that can be monitoreddirectly from inside the Aux Control Room, that the crew will use to continuouslymonitor the RCS and PZR cooldown?

A. lncore T/CsTHOTPZR liquid temperature

B. PZR Pressurelncore T/CsTCQLD

C. PZR liquid temperatureSG Press/TsatTCOLD

D. SG Press/TsatTHOTPZR Pressure



- Unit 1 is operating at 100% power.- Chemistry reports that RCS activity level has risen to the Administrative Limit

since the last sample.- The crew enters AOP-R.06, ‘High RCS Activity.”

In accordance with 1-SO-62-9, “CVCS Purification System,” which ONE of thefollowing identifies the MAXIMUM flow that can be established through the CVCSMixed Bed ion exchanger and the reason for this flow limit?

Maximum Flow Reason toThrough Mix Bed Limit Flow

A. 120 gpm prevent demineralizer channeling

B. 120 gpm prevent lifting letdown relief valve

C. 180 gpm prevent demineralizer channeling

D. 180 gpm prevent lifting letdown relief valve



- Unit 1 is operating at 100% power- Subsequently, Unit 1 has experienced a large steam break 1 (one) hour ago.- The crew is performing FR-P.1, Pressurized Thermal Shock.”

- Current plant conditions are:- Loop #1 RCS Tcold is 250°F and slowly rising- Loops #2, #3 and #4 Tcolds are 280°F and slowly rising- PZR pressure is 2000 psig and slowly rising- PZR level is 90% and rising- CCPs are injecting via the CCPIT

Based on current plant conditions, which ONE of the following conpletes thestatements below?

In accordance with FR-P.1, stop (1)

1-FR-0, “Unit 1 Status Trees” is indicating f) for Pressurized Thermal Shock.

REFERENCE PROVIDED

A. (1) one CCP(2) RED

B. (1) one CCP(2) ORANGE

C. (1) both CCPs(2) RED

D. (1) both CCPs(2) ORANGE



- Unit 2 reactor trip occurred with subsequent loss of RCPs.- Operators have implemented ES-0.2, ‘Natural Circulation Cooldown.”- A cooldown rate of 25°F/hour has been established.- RCS depressurization has been initiated.- The Shift Manager has determined that cooldown shall proceed as quickly as

possible due to reduced CST inventory.

Which ONE of the following identifies the procedure that maximizes the allowablecooldown rate for the provided circumstances and maximum cooldown rate allowed bythe procedure?

A. ES-0.2, “Natural Circulation Cooldown”The cooldown limit is 50°F/hr

B. ES-0.2, “Natural Circulation Cooldown”The cooldown limit is 100°F/hr

C. ES-0.3,”Natural Circulation Cooldown With Steam Voids in Vessel (with RVLIS)”The cooldown limit is 50°F/hr

D. ES-0.3, “Natural Circulation Cooldown With Steam Voids in Vessel (with RVLIS)”The cooldown limit is 100°F/hr



- Large Break LOCA is in progress on Unit 2.- Containment pressure is 1.9 psig and stable.- The STA reports an ORANGE condition on the CONTAINMENT (FR-Z)

Safety Function Status Tree due to high level in the containment sump.

Which ONE of the following...

(1) describes the action(s) that will be directed by FR-Z.2, “Containment Flooding,’

and

(2) what is the concern if these actions are not successful?

A. (1) Transfer water from Containment Sump to the RWST using spray pump.(2) Components needed for plant recovery could be damaged and rendered

inoperable.

B. (1) Transfer water from Containment Sump to the RWST using spray pump.(2) Water reaching the bottom of the reactor vessel could result in thermal

shock and vessel failure.

C. (1) Identify and isolate the source of excess water and determine its activity.(2) Components needed for plant recovery could be damaged and rendered

inoperable.

D. (1) Identify and isolate the source of excess water and determine its activity.(2) Water reaching the bottom of the reactor vessel could result in thermal

shock and vessel failure.



- Unit 1 is operating at 30% power.- Loop 3 RCP trips.

Which ONE of the following describes the INITIAL response with NO operator action?

Loop 3 Tavg will (1) and #3 S/G level will (2)

A. (1) lower(2) lower

B. (1) lower(2) remain the same

C. (1) rise(2) lower

D. (1) rise(2) remain the same



- Unit 1 is operating at 100% power.- LS-62-129A1B VOLUME CONTROL TANK LEVEL HI-LOW, alarms on

(1-M-6, A-3)- Ll-62-129, VCT Level, indicates 35% and lowering.- Ll-62-130, VCT Level, indicates 100% on ICS.

Which ONE of the following identifies the effect on the plant?

A. Suction to the operating CCP will align to the RWST when VCT level lowers to 7%

B. Suction to the operating CCP will align to the RWST when VCT level lowers to 13%

C. VCT level will continue to lower until the operator manually aligns LCV-62-118,Letdown Divert to HUT, to the VCT position

D. Auto makeup will initiate to the VCT when VCT level lowers to 20% and will raiseVCT level back to 41%



- Unit 1 is in Mode 3 performing a plant shutdown- Both Unit 1 USST5 are out of service- An electrical fault occurs which results in a loss of the 1A Start Bus

Which ONE of the following identifies (1) the pump that lost power and (2) if the pumpwill automatically start if power is restored?

Lfl L1

A. lA-A CCP will start

B. 1A-ACCP willNOTstart

C. lB-B CCP will start

D. lB-B CCP wil NOT start



- Unit 1 is in Mode 4 on RHR with a cooldown to Mode 5 in progress.- Both trains of RHR are in service.- The flow is 2500 gpm per train.- RCS cooldown rate is 25°F/hr.- The OAC turns the dial for 1-HIC-74-32A, RHR Hx Bypass Flow Controller, from

20% to 40%.

Assuming NO other operator action is taken, which ONE of the following identifies theeffect on RCS cooldown rate and on indicated RHR system flow to the RCS cold legs?

RCS Cooldown Rate Indicated RHR Flow

A. Rises Remains Constant

B. Rises Lowers

C. Lowers Remains Constant

D. Lowers Lowers



- Unit 2 is at 100% power.- An automatic reactor trip and Safety Injection occur.- Concurrent with the reactor trip, the 2B 6.9Kv Unit Board de-energizes due to a

differential fault.

Which ONE of the following completes the statement below?

The U) RHR pump is load shed and it will restart (2) seconds after the DGties to the affected 6.9Kv SDBD.

Ii)

A. 2A-A 5

B. 2A-A 10

C. 2B-B 5

D. 2B-B 10


SQN 1503 SRO NRC EXAM33. Which ONE of the following identifies the pressure that relief valve 63-637,

RHR Pump Discharge,” will start relieving and the tank where the flowthrough the valve will be routed?

Pressure Tank

A. 550 psig RCDT

B. 550 psig PRT

C. 600 psig RCDT

D. 600 psig PRT


SQN 1503 SRO NRC EXAM34. Given the following conditions:

- Both Units are at 100% power.- SEP temperature is 122°F.- SEP temperature has risen 4°E over the last 2 shifts.- SEP HX A is in service with:

- 2600 gpm SEPC flow, and- 2300 gpm CCS flow


To stabilize SFP temperatures, the crew will raise fj) flow to SEP HX A,and the flow will be limited to NO more than (2)

(2)

A. CCS 3300 gpm

B. CCS 3500 gpm

C. SFPC 3300 gpm

D. SFPC 3500 gpm



- Unit 1 is in Mode 3.- RCS Tavg is 527°F and pressurizer pressure is 1800 psig.- #3 RCP is the only RCP currently in operation.

Which ONE of the following would result in annunciator TS-68-316, 317PRESSURIZER SPRAY LINES TEMP LOW, (1-M-5-A, C-2) being cleared?

A. RCP#2is started

B. RCS Tavg is raised to 547°F

C. Auxiliary Spray is placed in service

D. Turn on Pressurizer heaters and raise pressure to 1900 psig



- Unit 1 is at 100% power.- MIG is performing the Monthly Functional Test of Train ‘A’ SSPS.- BYA (Train A bypass breaker) is racked in and closed.- RTA (Train A reactor trip breaker) is racked in and closed.- RTB (Train B reactor trip breaker) is racked in and closed.

- Subsequently, One 48V DC power supply to Unit 1 ‘B’ train SSPS fails.

Which ONE of the following identifies the effect this failure will have on the breakers?

A. RTA, RTB and BYA Open

B. RTA, RTR and BYA all remain Closed

C. RTA and BYA Open; RTB remains Closed

D. RTA and BYA remain Closed; RTB Opens



- A Large break LOCA has occurred on Unit 1.- “B” train Safety Injection signal failed to actuate both Automatically and

Manually.- The following alarms are LIT:

LS-63-176 CNTMT LEVEL HI RHR RECIRC, (1-M-6-C, E-4)LS-63-50A RWST LVL LO, (1-M-6-E, E-3)

- RWST level indications are reported as:

- LT-63-50: Off scale High - LT-63-51: 26%- LT-63-52: 28% - LT-63-53: 26%

Which ONE of the following identifies the expected condition of 1-FCV-63-72, CNTMTSUMP SUCT TO RHR PUMP 1A and 1-FCV-63-73, CNTMT SUMP SUCT TO RHRPUMP 1 B, assuming NO operator action?

A. 1-FCV-63-72 will open and 1-FCV-63-73 will remain closed.

B. 1-FCV-63-72 will remain closed and 1-FCV-63-73 will open.

C. 1-FCV-63-72 and 1-FCV-63-73 will both remain closed.

D. 1-FCV-63-72 and 1-FCV-63-73 will both open.



- Unit 1 is at 100% power- A loss of 12OVAC Vital Instrument Power Board 1-ifi has occurred- Subsequently, an SI occurs on Unit 1

Which ONE of the following identifies the plant response?

A. Only the “B” train SSPS SI master relays would actuate AND both trainsof ECCS equipment would start.

B. Only the “B” train SSPS SI master relays would actuate AND only “B”train ECCS equipment would start.

C. SI master relays on both trains of SSPS would actuate AND both trains ofECCS equipment would start.

D. SI master relays on both trains of SSPS would actuate AND only “B” trainECCS equipment would start.



- Unit 1 is at 100% power.- The following alarm is received:

MOTOR TRIP OUT PNL 1-M-9 (1-M-6-E, E-5)

- The RO determines that Lower Compartment Cooling Fan 1 B-B control switchWHITE light is LIT.

- Fans iC-A and lA-A are running.

Which ONE of the following describes the primary concern related to this failure, andthe procedural actions required?

A. Lower Ice Condenser doors may open due to high DP;Stop one Upper Compartment Cooling fan to equalize pressure in accordance withthe alarm response procedures.

B. Lower Ice Condenser doors may open due to high DP;Start any Lower Compartment Cooling fan in standby using the alarm response and0-SO-30-5, “Lower Compartment Cooling.”

C. PZR Enclosure may heat up and cause PZR Safety Valves to leak;If the in-service fans’ TCVs are not full open, then lower the TCV setpoints to getmore cooling.

D. PZR Enclosure may heat up and cause PZR Safety Valves to leak;Start any Lower Compartment Cooling fan in standby using the alarm response and0-S0-30-5, “Lower Compartment Cooling.”

Thursday, March 19, 2015 10:50:02AM 39


- Unit 2 is operating at 100% power.- Due to a loss of Lower Compartment Cooling, lower containment

temperature has risen from 105°F to 125°F.- Actions are in progress to restore cooling.

If the temperature continues to rise in containment, which ONE of the followingdescribes the effect on pressurizer level indication?

The controlling pressurizer level will indicate (1) than actual due toreference leg density (2)

A. (1) higher(2) lowering

B. (1) higher(2) rising

C. (1) lower(2) lowering

D. (1) lower(2) rising



- Unit 1 is in Mode 3

Which ONE of the following completes the statement below in accordance with LCO3.6.5.3, “Ice Condenser Doors?”

With one or more ice condenser

____

doors INOPERABLE due to being physicallyrestrained from opening, restore to OPERABLE status within 1 hour or be in at leastHOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following30 hours.

A. Top deck

B. Intermediate deck

C. Inlet

D. Access



- Unit 1 is operating at 100% power- Subsequently, a LOCA occurs- Containment pressure peaked at 3.0 psig- Current containment pressure is 1 .8 psig and stable

Which ONE of the following identifies the MINIMUM action(s) necessary to allow 1 B-BContainment Spray Pump to be stopped and prevent it from automatically re-starting?

A. Reset the Train B Phase B signal and then the Train B Containment Spray signal

B. Reset the Train B Containment Spray signal ONLY

C. Simultaneously Reset BOTH Trains of Phase B

D. Reset the Train B Phase B ONLY



- A plant cooldown is in progress on Unit 2.- RCS pressure is 1850 psig.- RCS temperature is 505°F.- All required actions have been taken for the cooldown in accordance with

0-GO-7, “Unit Shutdown From Hot Standby To Cold Shutdown.”

An event occurs:

- RCS pressure is4&psig and lowering atlO psi per second.- S/G pressures are Opsig and lowering at 25 psi per second.- Containment pressure is 1 .2 psig and rising.

Which ONE of the following describes the current automatic ESF actuation status?

A. Safety Injection AND Main Steam Line Isolation have occurred.

B. Safety Injection has occurred; Main Steam Line Isolation has NOT occurred.

C. Main Steam Line Isolation has occurred; Safety Injection has NOT occurred.

D. NEITHER Main Steam Isolation NOR Safety Injection have occurred.



- Unit 1 is operating at 100% power.- Main Steam Header Pressure transmitter, 1-PT-1-33B is in BYPASS.


Loss of

____

will cause the MFP Master Controller to transfer from Auto to Manual.

A. 2/3 Main Steam or 2/3 Feed Water pressure channels

B. 2/3 Feed Water pressure channels ONLY

C. 2/3 Main Steam pressure channels ONLY

D. the average Steam flow signal



- Unit 1 is holding at 70% power.- 1 C Condensate Booster pump is tagged for maintenance.- Subsequently, the lB MFW pump trips.


In accordance with AOP-S.01, “Loss of Normal Feedwater,” the I B MEW pump turbinecondenser inlet and outlet valves will fjJ isolate and the highest listed power thatwould NOT exceed maximum power allowed under these conditions is (2)

A. (1) automatically(2) 54% power

B. (1) automatically(2) 59% power

C. (1) NOT automatically(2) 54% power

D. (1) NOT automatically(2) 59% power



- Unit 2 is performing a startup following a refueling outage and in currentlyoperating at 50% power.

- Subsequently a reactor trip occurs.- The crew has just entered ES-0.1, “Reactor Trip Response.”- The following parameters are observed:

PZR level is 25% and slowly lowering.All S/G levels are between 12% and 18% NR and slowly rising.S/G pressures are approximately 990 psig and slowly lowering.All RCP5 are running.Tavg is 545°F and slowly lowering.RCS pressure is 2020 psig and slowly lowering.

- NO operator actions have been taken.

In accordance with ES-0.1, which ONE of following is required?

A. Emergency borate

B. Throttle Auxiliary Feedwater flow

C. Close MSIVs and bypass valves

D. Initiate Safety Injection



- Unit2isinModel.- The TDAFW Pump is tagged out of service.- A Loss of Feedwater causes a reactor trip.- Concurrent with the trip, 2B-B 6.9kV SDBD de-energizes on Differential fault.

Assuming NO operator actions have been taken, which ONE of the following describesthe Auxiliary Feedwater alignment and approximate flowrate?

A. 1 and 2 S/Gs being fed at 220 GPM each

B. 1 and 2 S/Gs being fed at 440 GPM each

C. ALL S/Gs being fed at 110 GPM each

D. ALL S/Gs being fed at 220 GPM each



- Both units are operating at 100% power- At 0200 on Feb 10th, the weekly performance of 0-Sl-OPS-082-007.W, “AC

Electrical Power Source Operability Verification,” is completed

- At 0901, a disturbance in the switchyard results in the following:- 6.9kV Shutdown Boards lA-A and 2A-A voltage dropped to 5300v- 6.9kV Shutdown Boards 1 B-B and 2B-B voltage dropped to 5700v

- At 0902:- All EDG5 are running- All shutdown boards are at normal voltage- SELD reports that the grid remains QUALIFIED


(1) The requirements of LCO 3.8.1.1 AC Sources, fiL met.

(2) The next required performance of 0-SI-OPS-082-007.W is (2)

A. (1) are(2) by 1001 on Feb 10th

B. (1) are(2) by 0200 on Feb 17th

C. (1) are NOT(2) by 1001 on Feb 10th

D. (1) are NOT(2) by 0200 on Feb 17th



- Both Units are operating at 100% power.- Offsite power is lost.- lA-A and 2B-B diesel generators start and load.- 1 B-B and 2A-A diesel generators do NOT start.- NO operator action has yet been taken.

Which ONE of the following describes the effect of this failure on the 125V DC system?

A. Vital boards I and II are energized by their battery.

B. Vital boards I and IV are energized by their battery.

C. Vital boards II and Ill are energized by their battery.

D. All vital 125V DC boards are energized from a battery charger powered from anoperating diesel.



- Both Units are at 100% power.- A loss of off-site power occurs


The Jacket Cooling Water flow through the heat exchanger for each EDG will beinitiated when the EDG (1) and the EDG f) trip if the High Jacket WaterTemp Alarm is received.

A. (1) startsto rotate(2) will

B. (1) starts to rotate(2) will NOT

C. (1) reaches200rpm(2) will

D. (1) reaches 200 rpm(2) will NOT



- Unit 1 is operating at 100% power.- A release of the ‘C’ Waste Gas Decay Tank through the Unit 1 Shield Building

stack is in progress.

Which ONE of the following predicts how 0-FCV-77-1 19, Gas Decay Tanks DischargeRadiation Isolation valve, will be affected if

(1) 0-RA-90-118B WDS GAS EFF MON INSTR MALFUNC (0-M-12-B, C-4) alarms

or

(2) if the ‘A’ ABGTS fan trips?

Instrument Malfunction

A. automatically closes

B. automatically closes

C. will NOT automatically close

D. wil NOT automatically close

ABGTS fan trip

will NOT automatically close

automatically closes

will NOT automatically close

automatically closes



- Both Units are at 100% power- An inadvertent Safety Injection occurs on Unit 2

Which ONE of the following identifies the expected ERCW system response?

A. ERCW to the lower compartment coolers receive a CLOSE signal.

B. ERCW supply valves to DG5 receive an OPEN signal.

C. ERCW to incore instrument room coolers receive a CLOSE signal.

D. ERCW to CNTMT Spray Heat Exchangers receive an OPEN signal.



- Unit 1 was at 100% power when a manual Safety Injection was initiated.

Which ONE of the following identifies the automatic response of the ERCW system?

1-FCV-67-146, CCS HX 1A1 and 1A2 ERCW Return to Header B jJ and0-FCV-67-152, CCS HX5 OB1 and 0B2 Discharge to B Discharge Header (2)

A. (1) CLOSES(2) REPOSITIONS to 35% position

B. (1) remains AS IS(2) remains CLOSED

C. (1) remains AS IS(2) REPOSITIONS to 35% position

D. (1) OPENS fully(2) remains CLOSED



- A large air leak has been reported in the Turbine Building- The following indications are noted on panel 1-M-15 in the Control Room:

- Aux Cont Air Hdr A Press 90 psig and slowly rising- Aux Cont Air Hdr B Press 90 psig and slowly rising- Cont Air Hdr Press 95 psig and slowly rising- Serv Air Hdr Press 75 psig and slowly lowering


Service Air Isolation valve 0-PCV-33-4 is jJ and Aux Air Compressors A & Bare (2)

A. (1) open(2) running

B. (1) open(2) off

C. (1) closed(2) running

D. (1) closed(2) off



- Unit 1 is in Mode 6.- An inadvertent dilution is in progress.- Source Range audible count rate is rising.


Containment evacuation will be required when SR counts increase (1) timesabove background and the alarm received would sound like (2)

A.(1)3(2) an undulating siren

B. (1) 3(2) a steady buzzing sound

C.(1) 5(2) an undulating siren

D.(1) 5(2) a steady buzzing sound



- Unit 1 is operating at 100% power.- 480v Common Emergency Transformer is tagged out for replacement.- 6900kV Unit Board 1 D is de-energized by relay operation.

Which ONE of the following describes the effect on the Control Rod Drive MG Sets?

A. Both MG sets lose power to the motor.

B. Neither MG set loses power to the motor.

C. Only 1A MG set ‘oses power to the motor.

D. Only 1 B MG set loses power to the motor.



- Unit 1 is in Mode 2 during a plant startup- Reactor power at 5 x 1 Q5% on N-35 and N-36- Intermediate Range N-35 fails LOW.

Which ONE of the following identifies the required action(s), if any, for this failure?

A. Power must remain at or above its current value but below 5% until N-35 is returnedto OPERABLE.

B. Enter E-0, “Reactor Trip or Safety Injection,” and manually place SRM TRIPRESET: BLOCK switches to RESET.

C. Place the level trip switch for N-35 to BYPASS and continue with plant startup.

D. Restore N-35 to OPERABLE prior to increasing power above the P-6 setpoint.



- Unit 1 is at 60% power.

- Rod control is in MANUAL.

- Charging flow control valve 1-FCV-62-93A is in MANUAL.

- A temperature instrument failure results in a greater than 5% differencebetween Actual and Program pressurizer level.

Assuming NO operator action, which ONE of the following identifies the RTD failure?

A. Thot RTD #1 failed High

B. Thot RTD #1 failed Low

C. Tcold RTD #1 failed High

D. Tcold RTD #1 failed Low



- Unit 2 was operating at 100% power when a large-break LOCA occurred.

- Containment hydrogen concentration reads 0.4% on both hydrogen analyzers.

Which ONE of the following identifies the operation of the hydrogen igniters andhydrogen recombiners, in accordance with E-1, Loss of Reactor or SecondaryCoolant,” if containment hydrogen concentration remains at 0.4% throughout theaccident?

Hydrogen igniters will be (1) and Hydrogen recombiners will C2)

A. (1) off(2) remain in standby

B. (1) off(2) be placed in service

C. (1) on(2) remain in standby

D. (1) on(2) be placed in service


SQN 1503 SRO NRC EXAM60. In accordance with FHI-3, “Movement of Fuel,” which ONE of the following is a

Unit 2 interlock, which will allow raising the upender on the SEP side?

A. Conveyor at PIT

B. Wafer Valve OPEN

C. ConveyoratRx

D. The SFP Bridge Crane gripper tube must be “FULL UP”



- Unit 1 is at 100% power when turbine impulse pressure PT-1-73 fails high.- Thirty (30) seconds after the failure, a reactor trip is initiated by operator action.

Which ONE of the following identifies the expected response of the steam dumpsystem?

The steam dumps will

A. attempt to maintain the RCS Tavg at 552° F with the reactor trip controller.

B. attempt to maintain the RCS Tavg at 552° F with the load rejection controller.

C. attempt to maintain the RCS Tavg at 547°F with the load rejection controller.

D. fully open and remain open until RCS Tavg decreases below 540°F.


SQN 1503 SRO NRC EXAM62. Given the following plant conditions;

- Both Units are operating at 100% power.- Waste Gas Decay Tank (WGDT) ‘C’ is being released.- ABGTS fan ‘A’ is tagged for maintenance.- Neither of the Waste Gas Compressors are running.

Which ONE of the following identifies how readings on the listed radiationmonitors will respond to an increase in the radiation level of the gas beingreleased?

0-RM-90-1 01Aux Building Vent Monitor Shield Building Vent Monitors

A. Remain constant 1-RM-90-400 rises

B. Remain constant 2-RM-90-400 rises

C. Rise 1-RM-90-400 rises

D. Rise 2-RM-90-400 rises



- Both Units are operating at 100% power.- 0-RM-90-103A, Spent Fuel Pit Radiation Monitor, fails HIGH.

Which ONE of the following indentifies the expected plant response?

A. ONLY Train B Aux Building Isolation dampers close;ONLY Train B Aux Building General Supply, Exhaust and Fuel Handling exhaustfans trip.

B. ONLY Train B Aux Building Isolation dampers close;ALL Aux Building General Supply, Exhaust and Fuel Handling exhaust fans trip.

C. BOTH Train A and Train B Aux Building Isolation dampers close;ONLY Train B Aux Building General Supply, Exhaust and Fuel handling exhaustfans trip.

D. BOTH Train A and Train B Aux Building Isolation dampers close;ALL Aux Building General Supply, Exhaust, and Fuel handling exhaust fans trip.


SQN 1503 SRO NRC EXAM64. Which ONE of the following is a direct input to the ‘C-9 CONDENSER AVAILABLE’

permissive on 1-XA-55-4A, BYPASS AND PERMISSIVE panel on 1-M-4?

A. At least one CCW pump breaker closed and its discharge valve >5% open.

B. At least one CCW pump breaker must be closed.

C. At least one CCW pump discharge valve must be fully open.

D. At least 5 of 6 waterboxes must have both the inlet and outlet MOV5 open.


SQN 1503 SRO NRC EXAM65. Given the foHowing plant conditions:

- The Electric Fire Pump is out of service for maintainence.- A scrap lumber fire exists on site but is not affecting any plant equipment

or structures.- The Fire Brigade Leader calls the MCR and requests the Diesel Fire Pump

be started.

Which ONE of the following identifies,

(1) the action required to startthe diesel fire pump

and

(2) the effect on the High Pressure Fire Protection system if the pump were tooverspeed after starting with the overspeed trip mechanism failing to function?

A. (1) The MCR operator can start the pump from the MCR.(2) HPFP header pressure would increase and remain high.

B. (1) The MCR operator can start the pump from the MCR.(2) if HPFP header pressure remains> 135 psig for 3 minutes, the pump

automatically shuts down.

C. (1) The MCR operator can NOT start the pump from the MCR, an AUO wouldhave to start the pump locally.

(2) HPFP header pressure would increase and remain high.

D. (1) The MCR operator can NOT start the pump from the MCR, an AUO wouldhave to start the pump locally.

(2) if HPFP header pressure remains> 135 psig for 3 minutes, the pumpautomatically shuts down.


SQN 1503 SRO NRC EXAM66. AB2 AUO is performing the following procedure step:

(2) ENSURE SFPC Pump B-B is VENTED by momentarily opening (0-78-5081,SFPC pump B-B Casing Vent and VERIFYING flow.

The AUO determines that the step is NOT applicable.

In accordance with OPDP-1, “Conduct of Operations,” what is the minimum approval,if any, required to N/A the step?

A. The AB2 AUO can N/A, no other approval is required

B. OATC

C. Unit Supervisor

D. Shift Manager


Gross Activity

bOlE microcuries/gram

<bOlE microcuries/gram

501E microcuries/gram

< 50/E microcuries/gram

Dose Equivalent 1-131

<0.10 microcuries/gram




SQN 1503 SRO NRC EXAM67. In accordance with Technical Specifications, which ONE of the following identifies the

specific activity limits for the primary coolant in Mode 1?

A.

B.

C.

D.



- Unit 1 is at 100% power- Unit 2 is in Mode 3- Fuel handling is NOT in progress

In accordance with OPDP-1 “Conduct of Operations,” which ONE of the followingwould meet the minimum requirements for Operations shift staffing requirements forSROs and RO5?

(EXCLUDING the SM and the unexpected absence allowance)

A. 2SROs3 UO5

B. 2SRO54UOs

C. 4SROs3UO5

D. 4SROs4 UOs



- Unit 1 in Mode 5.- 1-FCV-62-93, Charging Flow Control Valve, is selected as a

boundary isolation valve for a clearance on the CVCS charging header.

In accordance with NPG-SPP-1O.2, “Clearance Procedure to Safely Control Energy”,which ONE of the following is an acceptable method for tagging 1-FCV-62-93CLOSED?

A. Install a temporary accumulator.

B. Install a temporary jacking device.

C. Dog the valve closed with its handwheel.

D. Isolate the air supply.



- Unit 2 is at 40% power.- A steam leak develops on the common main steam header.- The crew is preparing for a 1%/minute rapid shutdown.- The turbine controls are in MANUAL due to an EHC circuit card failure.- The following indications are present on the EHC control panel:

- VALVE POSITION LIMIT light is DARK- OPERAUTO light is DARK- TURB MANUAL light is LIT

In accordance with AOP-C.03, “Rapid Shutdown or Load Reduction,” which ONE of thefollowing identifies how Turbine load will be reduced?

A. Intermittently depressing the GV LOWER pushbutton.

B. Intermittently depressing the Valve Position Limiter (VPL) lower pushbutton.

C. Press OPER AUTO pushbutton, set the load rate to 1%, adjust the setter to 20, anddepress the GO pushbutton.

D. Turbine load cannot be reduced, a Turbine trip will be required.



- Unit 1 was operating at 100% when a Large Break LOCA occurs.- It has been 2 hours since the start of the event- Containment pressure is 6 psig and stable for the last 30 minutes.- The Containment Air Return Fan 1 B-B did NOT auto start and is NOT in

service.- Control power fuse (1-FU2-30-39B) for Containment Air Return Fan lB-B has

blown.- The associated MCR handswitch (1-HS-30-39A) is in A-Auto.- The OSC has dispatched a team to replace the blown control power fuse.

Using the associated electrical print in the reference package, which ONE of thefollowing identifies:

(1) when the Air Return Fan will Automatically start after the fuse is replaced,

and

(2) where a copy of the current revision of an electrical print is required to be verified?

REFERENCE PROVIDED

A. (1) immediately(2) BSL

B. (1) immediately(2) Maximo

C. (1) after a 10 minute time delay(2) BSL

D. (1) after a 10 minute time delay(2) Maximo



- A source check is to be performed on CCS radiation monitor 1-RE-90-123.


The source check is verified by observing the (1) on 0-M-12.

The isolation function of the Surge Tank’s vent

___________

be manually blockedduring the source check in accordance with 1-SO-90-1, “Liquid Process RadiationMonitors.”

A. (1) analog rate meter trending upscale(2) can

B. (1) analog rate meter trending upscale(2) can NOT

C. (1) bargraph display responds upscale(2) can

D. (1) bargraph display responds upscale(2) can NOT


SQN 1503 SRO NRC EXAM73. Which ONE of the following identifies when Radiation Protection approval is required

prior to accessing overhead areas in the Auxiliary Building?

Areas greater than

A. 4 feet off the floor except for permanently installed platforms.

B. 4 feet off the floor including permanently installed platforms.

C. 6 feet off the floor except for permanently installed platforms.

D. 6 feet off the floor including permanently installed platforms.



- An off-shift RO is in the Cafeteria eating lunch with an AUO; the AUO who isassigned as an OSC responder.

- The off-shift ROis assigned to support the WCC.- A Site Area Emergency has been declared due to an earthquake.

In accordance with EPIP-8 “Personnel Accountability And Evacuation,” which ONE ofthe following identifies responsibilities of the RO and the AUO following the initiation ofAssembly and Accountability.

A. RO - Swipe badge in the MCR card reader and report to the MCR.AUO - Swipe badge in the Cafeteria card reader and report to the OSC.

B. RO - Swipe badge in the MCR card reader and report to the MCR.AUO - Swipe badge in the MCR card reader, report to the MCR and wait to be

transferred to the OSC by SED.

C. RO - Swipe badge in the Cafeteria card reader and await further instructions.AUO - Swipe badge in the MCR card reader and report to the OSC.

D. RO - Swipe badge in the Cafeteria card reader and await further instructions.AUO - Swipe badge in the Cafeteria card reader and report to the OSC.


SQN 1503 SRO NRC EXAM75. Given the following plant conditions on Unit 1:

- RCS pressure is 340 psig.- RCS temperature is 210°F.- 1 B-B RHR pump is in service.- lA-A DG is tagged for maintenance.- Subsequenfly, a loss of Off-Site power occurs.- lB-B DG fails to start.

Which ONE of the following identifies the required plant procedure, in accordance withEPM-4, “Users Guide?”

A. ECA-0.0, “Loss of All AC Power”

B. AOP-P.01, “Loss of Offsite Power”

C. AOP-R.03, “RHR System Malfunctions”

D. AOP-P.05, “Loss of Unit 1 Shutdown Boards”

References for 1503 NRC RO Exam

1. Steam Tables

2. Mollier Diagram

3. E-3, Steam Generator Tube Rupture, step 32 rev 21

4. ECA-1 .1, Loss of ECCS Sump Recirculation, Curve 9, rev 14 (page 47 of 57)

5. 1-FR-O, Curve 1 PTS limit, rev 2 (page 8 of 16)

6. 1 ,2-45N779-1 Wiring Diagrams 480V Shutdown Aux Power Schematic Diagram— sheet 1 rev 5

7. 1 ,2-45N779-5 Wiring Diagrams 480V Shutdown Aux Power Schematic Diagram

- sheet 5 rev 19

SQN STEAM GENERATOR TUBE RUPTURE E-3Rev. 21

I STEP I ACTION/EXPECTED RESPONSE J I RESPONSE NOT OBTAINED

32. CONTROL RCS pressure and chargingflow to minimize RCS-to-secondaryleakage:

a. PERFORM appropriate action(s)from table:

RUPTURED SIGLEVELRISING

RUPTURED SIGLEVEL

DROPPING

RUPTURED S/GLEVEL

GREATER THAN84% [80% ADVJAND STABLE

(step continued on next page)

PZR LEVEL

Less than 20% • RAISE charging RAISE charging • RAISE charging[35% ADVJ flow, flow, flow.

• DEPRESSURIZE MAINTAIN RCSRCS USING and RupturedSubstep 32.b. S/G(s) pressures

equal.

Between DEPRESSURIZE TURN ON MAINTAIN RCS20% [35% ADV] RCS USING pressurizer heaters. and Rupturedand 50% Substep 32.b. S/G(s) pressures

equal.

Between • REDUCE charging TURN ON MAINTAiN RCS50% and 65% flow, pressurizer heaters. and Ruptured

• DEPRESSURIZE S/G(s) pressuresRCS USING equal.Substep 32.b.

Greater than 65% REDUCE charging TURN ON MAINTAiN RCSflow, pressurizer heaters. and Ruptured

SIG(s) pressuresequal.

Page 33 of 53

ECA-tiSON LOSS OF ECCS SUMP RECIRCULATION

Rev.14

C,4,4-

0LL

U,0()w

CURVE 9

Minimum ECCS Ftow For Decay Heat vs Time After Trip

10000

Date/lime

CCPIT Flow (Fl-63.170)

SI Pump A Flow (FI-63-151)

SI Pump B Flow (Fl-63-20)

RHR A Flow (FI-63-91A or B)

RHR B Flow (FI-63-92A or B)

Total ECCS Flow

I 10 30 100 1000 3ooTime After Trip (Minutes)

Page 43 of 53

UNIT I SQN1-FR-O

CURVE I PTS LIMITS Rev. 23000

2500

2000

0

U

1500UI

Cl)C)

1 000

500

0500

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sequoyah initial exam 2015-301 final ro written exam.sqn 1503 sro nrc exam 2. given the following...

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