Text

Exam 50-390, 391/2001-301 Jan 29 - Feb 6, 2001 - Initial Submittal Ro/Sro Written Exams & Answer Keys
	ML011130392
Person / Time
Site:	Watts Bar
Issue date:	09/13/2000
From:	; NRC/RGN-II
To:	;
References
	-RFPFR, 50-390/01301, 50-391/01301
	Download: ML011130392 (257)
	v • d • e

INITIAL SUBMITTAL WATTS BAR EXAM 50-390, 391/2001-301 Ii JANUARY 29 - FEBRUARY 6, 1i 2001 INITIAL SUBMITTAL RO/SRO WRITTEN EXAMINATION

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION NAME SSN

.0000 180 (0(00D D 35. (00(00@

2. 0000 1 D( 36. 0000 3.0000 2 . (0(D000 3.(D(D (D 2 (00(0(0) 38. 0000

'.4.(i)@0000 2 . 0000 2 . 0000 6.0000 0000 2 . 0000 8-0000 25. 0000 42. 0000 8.0000 26. 0000 43. 0000 1 . (0(000@ 44. 0000 1 . 0000 45. (i)@@@(

1 D( 2 . 0000 13. 0000 3 )0000 14. 0000 31. 0000 48. (0000 15. 0000D( 32 0000 49. (00(0)(0)

160 (0(0(i(i 33 @0000 50. 0000 17(0(000@ 3 . 0000 Page 1

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION NAME SSN 52. 0000 6 . (00(0 0@

53. 0000 70. 0000 8 . (00(0 (0( 7 . 0000 55. 00)(0(0)@ 7 . 0000 56. 0000 7 . 0000 57 0000 74. 0000 91. 0000 58. 0000 75. 0000 92. 0(0(00@

59. 0000 76. 0000 93. 0000 60. 0000 77. (00(00@ 94. (00(00@

61. 0000 7 . 0000 62. 0000 7 . 0000 6 . 0000 64. 0000 81. 0000 98 0000 65. 0000 8 .8 991 0000 0000 66. 0000 83.000 1o.0000))()

67. 0000 84. 0000 68. 0000 8 Page 2

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 1. 005AK3.02 001 Given the following plant conditions:

- Reactor is at 75% with a power increase in progress using control rod The OAC determines that Control Bank D rod H-12 is not moving and is 14 steps below the other rods in D ban Crew is performing AOI-2, "Malfunction of Reactor Control System" to realign control rod H-12 with the ban Which ONE of the following describes how control rod H-12 will be realigned to control bank D and how control bank insertion limit will change following the realignment?

a. Control Bank D will be realigned to control rod H-12 and control bank D insertion limit will be highe ,/b. Control Bank D will be realigned to control rod H-12 and control bank D insertion limit will be lower c. Control rod H-12 will be realigned to Control Bank D and control bank D insertion limit will be lowe d. Control rod H-12 will be realigned to Control Bank D and control bank D insertion limit will be higher.

2. 015AK1.05 001 Given the following plant conditions:

- Reactor power is stable at 30%

- Loop 1 RCP trips Assuming reactor power remains constant, core exit temperature will:

, increase, then stabilize at a higher valu b. decrease, then stabilize at a lower valu c. increase, then return to the original steady-state valu d. decrease, then return to the original steady-state valu Page 1

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 3. 017AK3.03 001 Given the following conditions:

- Unit at 60% powe Confirmed Loop 1 RCP shaft vibration of 25 mil Which ONE of the following statements is correct per AOI-5, "Unscheduled Removal of One RCP", regarding the sequence of actions?

a. RCP should be tripped prior to the reactor trip to minimize pump damag b. The reactor should be tripped prior to tripping the RCP to prevent pressurizer level from dropping below 17%.

c. RCP should be tripped prior to the reactor trip to prevent Reactor Coolant Bus voltage from dropping and tripping additional RCP "d. The reactor should be tripped prior to tripping the RCP to prevent an automatic trip and an unnecessary challenge to a safety system.

4. 017AA1.13 001 Given the following plant conditions:

- Unit was operating at 58% powe Problems with #4 RCP required the pump to be shut down in accordance with AOI-5, "Unscheduled Removal of One RCP".

AO1-5 requires the plant to be in which ONE of the following conditions for restart of #4 RCP?

V < P-1 b. <P- c. < P- d. Mode Page 2

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 5. 024AK1.02 001 Given the following plant conditions:

- Plant was operating at 100% power when a Main Feedwater pump trip resulted in a turbine runbac All systems in automatic and responded as expected to stabilize the plan Control rods inserted beyond the Lo-Lo Rod Insertion limit Operators implemented AOI-34, "Immediate Boration", in accordance with the AR Which ONE of the following indicates the final, stable plant conditions AFTER completion of the boration as compared to those PRIOR to the boration?

Reactor Power Rod Position Tavq Same Higher Higher v Same Higher Same Lower Lower Same Lower Lower Lower Page 3

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 6. 027AK3.02 001 Given the following plant conditions:

- The Unit is at 100% loa Pressurizer pressure channel selector switch, 1-XS-68-340D, is in the PT-68-340 & 334 positio Instrument Maintenance has 1-PT-68-323 (CH 1II)OOS for a loop calibratio PZR Pressure transmitter, 1-PT-68-334 (CH II) has just failed AS I The operating crew implements AO1-18, "Malfunction of Pressurizer Pressure Control System".

Which ONE of the following channels will be selected on 1-XS-68-340D and position of the master controller following completion of AOl-1 8, Malfunction of Pressurizer Pressure Control System?

a. Channel I and IlIl selected with 1-PIC-68-340A in AUT b. Channel I and IlIl selected with 1-PIC-68-340A in MANUA / Channel I and IV selected with 1-PIC-68-340A in AUT d. Channel I and IV selected with 1-PIC-68-340A in MANUA Page 4

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 7. 027AA2.12 001 Given the following plant conditions:

- Plant is operating at 100% powe One pressurizer safety valve failed full OPE Operating crew initiated reactor trip/safety injection and entered the EOP Safety Injection signal is not rese Which ONE of the following is the status of Pressurizer level and pressure control 10 minutes following the reactor trip/safety injection?

a. PZR level indication offscale LO PZR heaters O b. PZR level indication offscale LO PZR heaters OF c. PZR level indication offscale HIG PZR heaters O >/d. PZR level indication offscale HIG PZR heaters OF Page 5

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 8. 057AA1.05 001 Given the following plant conditions:

- Plant is operating at 100% powe A loss of 120V AC Vital Instrument Power Board 1-l occurre The crew implements AOI-25.01, "Loss of I2OVAC Vital Instrument Power Board 1-I".

Which ONE of the following identifies the train selector switches that must be selected for automatic control of feedwater and which loop 1 feedwater/steam flow indications are available?

Feedwater/Steam Flow Feedwater/Steam Flow Selector Switches Indications A train Channel I A train Channel II B train Channel I V B train Channel II Page 6

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 9. 068G2.3.10 001 Given the following:

- Commited Dose Equivalent (CDE) is 1875 mrem

- Deep Dose Equivalent (DDE) is 1620 mrem

- Lens Dose Equivalent (LDE) is 430 mrem

- Commited Effective Dose Equivalent (CEDE) is 260 mrem

- Total Organ Dose Equivalent (TODE) is 3685 mrem

- Shallow Dose Equivalent (SDE) is 295 mrem What is the Total Effective Dose Equivalent (TEDE)?

a. 3980 mrem b. 2170 mrem c. 1915 mrem

>/ mrem 10. 069AK2.03 001 Which ONE of the following conditions concerning the Personnel Airlock would exceed a Limiting Condition for Operation and require entering an Action Statement of Technical Specifications?

a. The lower containment airlock fails its LLRT while control rod unlatching is in progres b. Welding cables are laid through both lower containment airlock doors during RCS fill and vent at the end of an outag c. The lower containment airlock door interlocks are defeated while reactor vessel head is being tensione Yd. The outer and inner doors are opened simultaneously during a normal cooldown prior to aligning RHR to the RC Page 7

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 11. 074EK1.03 001 Given the following plant conditions:

- Inadequate core cooling conditions exist

- Crew is performing FR-C.1, Inadequate Core Cooling Which ONE of the following sets of actions states the proper sequence of the major action categories to be performed for removing decay heat from the core?

a. Rapid secondary depressurization; reinitiation of high head safety injection; RCP restart vb. Reinintiation of high head safety injection; rapid secondary depressurization; RCP restart c. Rapid secondary depressurization; RCP restart; reinitiation of high head safety injection d. RCP restart; rapid secondary depressurization; reinitiation of high head safety injection 12. 076AA1.04 001 Which ONE of the following correctly describes the indication on the main steam line radiation monitors when the MR/HR AUTO pushbutton is lit on the RM-23 readout module?

a. Indicates low range output onl v/b. Indicates high range output onl c. Automatically switches between the low and high range outputs every 45 second d. Automatically switches between low and high range output based upon activity level in order to maintain accurate indicatio Page 8

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 13. EO6EK2.1 001 Given the following plant conditions:

- Operators are responding to a large break LOCA and have determined that degraded core cooling conditions exis The crew has implemented FR-C.2, "Degraded Core Cooling".

- Preparations are in progress to depressurize all intact S/Gs to atmospheric pressure in accordance with FR- Which ONE of the following is the reason the procedure directs all RCPs be stopped prior to performing the depressurization?

a. Reduces the core AP which will enhance the ability of the RHR pumps to inject into the cor b. Minimizes heat input to the S/Gs allowing them to depressurize faste Limits heat removal requirements to the core decay heat onl / Anticipates a loss of RCP #1 seal AP requirements.

14. E07EK2.1 001 Given the following plant conditions:

- A large break LOCA has occurred that resulted in saturated core cooling condition RWST level is 28%

- Crew is performing step 4 of FR-C.3, Saturated Core Cooling to establish SI pump valve alignmen Which ONE of the following identifies valves that should be verified CLOSED during performance of this step?

a. FCV-63-6, 7 and 177, SI pump and Charging pump suction from RH b. FCV-63-47 and 48, SI pump suction valves c. FCV-63-152 and 153, SI pump cold leg injection cross-tie valves

/d. FCV-63-3, 4 and 175 SI pump mini-flow valves Page 9

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 15. E10EA2.1 001 Given the following plant conditions:

- Reactor trip occurred with subsequent loss of RCP Operators have implemented ES-0.2, "Natural Circulation Cooldown".

- A cooldown rate of 250F/hour has been establishe RCS depressurization has been initiated while maintaining subcooling

> 165 0 Operators are monitoring PZR level and RVLIS for void formatio The OAC observes that loss of inventory in the Condensate Storage Tank is imminen Which ONE of the following describes the appropriate procedural actions?

a. Stop the cooldown and remain in ES- b. Raise the cooldown rate and remain in ES- c. Transition to ES-0.3, "Natural Circulation Cooldown With Steam Voids in Vessel (With RVLIS) and lower the cooldown rat vd. Transition to ES-0.3, "Natural Circulation Cooldown With Steam Voids in Vessel (With RVLIS) and raise the cooldown rate.

16. E14EK3.2 001 Which ONE of the following describes the reason for tripping all RCPs during the performance of FR-Z.1, "High Containment Pressure"?

a. Removes heat transferred to the Containment atmosphere from the RCP motor b. Prevents depletion of primary inventory out of the break during a small LOC >/c. Containment Isolation Phase B isolates cooling water to the RCPs and thermal barrier d. Removes additional energy to the RCS during a break and subsequent release to containmen Page 10

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 17. 003AA2.01 001 Given the following plant conditions:

- Unit is stable at 55% powe Recovery of dropped rod D-4 (Control Bank D, Group 1) is in progres D-4 is at 50 step Remaining Bank D rods are at 125 step Which ONE of the following Control Bank D indications will update as withdrawal of the dropped rod continues?

a. Both Bank D step counters and P/A converter b. Both Bank D step counters and Bank Overlap counter

/ Only Group 1 step counter and P/A converter d. Only Group 1 step counter and Bank Overlap counter Page 11

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 18. 007EK2.02 001 Given the following plant conditions:

- Unit 1 operating at 22% powe Reactor Trip Breakers "A" & "B" close Bypass Breaker B is racked in and close "B" Train SSPS Input Error Inhibit Switch is in INHIBIT for surveillance testin Which ONE of the following describes the response of the Reactor Trip and Bypass Breakers if RCS pressure drops below the Low Pressure Reactor trip setpoint with no operator action?

a. Reactor Trip Breakers "A" & "B" open, Bypass Breaker "B" open b. Reactor Trip Breaker "A"opens and "B" remains closed, Bypass Breaker "B" remains close Reactor Trip Breaker "B" opens and "A"remains closed, Bypass Breaker "B" open Reactor Trip Breaker "A"opens and "B" remains closed, Bypass Breaker "B" open Page 12

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 19. 008AK1.01 001 Given the following plant conditions:

- Unit was at 100% powe All systems operating in automatic and all plant parameters at their normal value PCV-68-340 failed partially ope Which ONE of the following identifies the approximate maximum expected temperature of the steam entering the PRT if the PRT pressure does not exceed 45 psig?

a. 228T b. 2500 c. 2750 F Vd. 2900 F 20. 008G2.2.25 001 According to the safety limit technical specification basis for RCS pressure, the maximum transient pressure allowed is:

, % of design pressur b. 110% of normal operating pressur c. 125% of design pressur d. 125% of normal operating pressur Page 13

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 21. 011EK2.02 001 Given the following conditions:

- A large break LOCA occurred

- Operators have just completed swapover to Containment Sump

- A loss of offsite power occurs Which ONE of the following describes the actions required for this condition?

a. Pull to lock Si pumps and CCPs until the RHR pumps have been restarted after the shutdown boards are reenergize v1 Pull to lock the CCPs until the RHR pumps are restarted after the shutdown boards are reenergize c. Ensure both RHR pumps are started by the blackout sequencer after the diesel generators reenergize the shutdown boards then restart the SI pump d. Ensure all ECCS pumps are started by the blackout sequencer when the diesel generators reenergize the shutdown board Page 14

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 22. 029EA1.02 001 Given the following plant conditions:

- ATWS without Safety Injection has occurre Crew has implemented FR-S.1, "Nuclear Power Generation/ATWS", and currently performing step 4 to borate the RC Which ONE of the following identifies the correct Operator action that must be taken in order to align charging pump suction?

a. CLOSE LCV-62-132 and 133, VCT outlet isolation, then OPEN LCV-62-135 and 136, RWST supply to charging pump suctio y OPEN LCV-62-135 and 136, RWST supply to charging pump suction, then CLOSE LCV-62-132 and 133, VCT outlet isolatio c. Verify LCV-62-135 and 136, RWST supply to charging pump suction AUTO OPEN, then CLOSE LCV-62-132 and 133, VCT outlet isolatio d. Verify LCV-62-135 and 136, RWST supply to charging pump suction and LCV-62-132 and 133, VCT outlet isolation AUTO OPE Page 15

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 23. 032AK3.02 001 Given the following plant conditions:

- The Unit is in MODE Source Range Monitor (SRM) NI-132 has failed LOW resulting in a loss of the audio count rate signa WHICH ONE of the following describes the actions necessary to restore the audio count rate signal to the control roo Va. Place the audio count rate CHANNEL SELECTOR switch on the front of the Audio Count Rate Drawer to the SR N31 positio b. Place the audio count rate CHANNEL SELECTOR switch on the front of the Audio Count Rate Drawer to the SR N32 positio c. Place the AMPLIFIER SELECT switch on the rear of the audio count rate drawer assembly to the Al positio Place the AMPLIFIER SELECT switch on the rear of the audio count rate drawer assembly to the A2 positio Page 16

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 24. 033AA1.01 001 Given the following plant conditions:

- A Reactor startup in progres Reactor power is stable at 2 x 10-2% power on the Intermediate Range

- Intermediate Range channel N-135 was declared inoperable and removed from service per AOI-4, "Nuclear instrumentation Malfunction".

Which ONE of the following describes the plant response if an l&C Technician mistakenly removes the control power fuses for N-1 35 during troubleshooting activities?

,/a. The trip bistable deenergizes and a reactor trip occurs because power is below P-1 b. The trip bistable deenergizes, however NO trip occurs because N-135 is bypasse c. The trip bistable energizes, however NO trip occurs because N-135 is bypasse d. The trip bistable energizes and a reactor trip occurs because power is below P-1 Page 17

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 25. 038EK1.01 001 Given the following plant conditions:

- Steam Generator Tube Rupture has occurre Crew has implemented E-3, "Steam Generator Tube Rupture".

- The operators have completed cooldown to target incore temperature of 480 0 Which ONE of the following identifies the pressure that steam dumps will be set to control RCS temperature at 4800 F?

a. 580 - 585 psi ,/b. 550 - 555 psi c. 580 - 585 psi d. 550 - 555 psia.

26. 058AK3.01 001 Given the following plant conditions:

- AUO reports Emergency Diesel Generator (D/G) 1A-A has lost 125V DC control power from it's associated Diesel Battery Distribution Panel

- D/G 1A-A is NOT runnin Which ONE of the following describes how this loss of DC control power would affect D/G operation?

a. D/G would start in response to an automatic or manual start signa vb. D/G cannot be started by automatic or manual start signa c. D/G can only be started manually from local control pane d. D/G can only be started manually from the MCR pane Page 18

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 27. 059AK1.01 001 Given the following plant conditions:

- Plant is operating a 100% powe Plant systems aligned and operating normall Annunciator, CCS HXA 1-RM-90-123 LIQ RAD HIGH, is in alar Which ONE of the following lists the type and source of radiation sensed by the radiation monitor that is in alarm?

,/a. Gamma; Thermal Barrier leakag b. Beta; Thermal Barrier leakag c. Gamma; RCP motor cooler leakag d. Beta; RCP motor cooler leakage.

28. 060AA2.04 001 Given the following plant conditions:

- A Gas Decay Tank release in progress with ABGTS running for dilution air flo A leak occurs on the waste gas compressor which results in a gas release to the Auxiliary Buildin RE-90-1 01, Auxiliary Building Vent Monitor, is in alar Which ONE of the following indicates the effect this leak will have on the plant?

a. Gas Decay Tank release will be terminated; ABGTS will be stoppe b. Gas Decay Tank release will be terminated; ABGTS will continue to ru Gas Decay Tank release will continue; ABGTS will be stoppe / Gas Decay Tank release will continue; ABGTS will continue to ru Page 19

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 29. E01EK3.4 001 Once an operating crew has entered the EOP network, which ONE of the following is the earliest that a transition may be made to ES-0.0, "Rediagnosis"?

>/a. AFTER transition from E-0 and safety injection initiate b. AFTER transition from E-0 and NO safety injection initiate c. BEFORE transition from E-0 and safety injection initiate d. BEFORE transition from E-0 and NO safety injection initiated.

30. E03EK1.3 001 Given the following plant conditions:

- A small break LOCA has occurred

- 1B-B CCP and SIP failed to start and could not be started manuall E-1 is completed and transition to ES-1.2, "Post LOCA Cooldown and Depressurization", mad .9kV Shutdown Board 1A-A is de-energized due to a fault

- The following conditions are noted by the OAC

- RCS pressure is 1600 psig

- Containment pressure is 6 psig Which ONE of the following describes the action that should be taken and the basis for that action?

a. All RCPs should be stopped to limit heat input during the RCS cooldow vb. All RCPs should be stopped because Phase B isolation has occurre c. All RCPs should NOT be stopped because no CCP or SIP is injecting into the RC d. All RCPs should NOT be stopped because the RCS pressure is above 1500 psi Page 20

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 31. E03EK2.2 001 Which ONE of the following is the significance of draining the SG U-tubes and blowing the inverted "loop seal" during a cold leg small break LOCA?

>/a. A steam vent path is established from the core to the break location and mass loss from the system is decrease b. Core cooling will be lost after the loop seal is blown due to increased injection flow being diverted to the break locatio c. RCS pressure control will be lost resulting in a challenge to Pressurized Thermal Shock limit d. The heat sink effect of the water in the "crossover" leg is lost when the loop seal is lost resulting in a degraded core cooling.

32. E05EK2.1 001 Given the following plant conditions:

- Reactor trip and safety injection occurre The crew implemented FR-H.1, "Loss of Secondary Heat Sink" due to heat sink red pat Operators are preparing for main feedwater startu Which ONE of the following lists the minimum actions required to reset Main Feedwater Pump IA?

a. Reset safety injection and cycle reactor trip breaker b. Reset safety injection and reset feedwater isolation signa c. Cycle the reactor trip breakers and reset feedwater isolation signa Yd. Reset safety injection, cycle reactor trip breakers, and reset feedwater isolation signa Page 21

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 33. E11EA1.2 001 Given the following plant conditions:

- Reactor trip and SI occurred at 0200 due to a small LOC At 0300 the crew transitioned to ECA-1.1, "Loss of RHR Sump Recirculation", due to the failure of both RHR pump Crew has reduced ECCS flow to 1 SIP and 1 CCP per ECA- At 0500 the crew is performing step 17 RNO to establish the minimum required ECCS flow to remove decay hea Using Figure 1 from ECA-1.1, which ONE of the following flow rates would satisfy the intent of the RNO?

a. 180 gpm vb. 210 gpm c. 240 gpm d. 280 gpm 34. 036AK1.03 001 Which ONE of the following describes why the baseline count rate used for developing the 1/M plot must be re-calculated following movement of any source bearing fuel assembly ?

a. Re-verify the operability of the source range instrument " Ensures an accurate 1/M plot to monitor subcriticalit c. Determine adequate shutdown margin during refuelin d. Readjust the setpoint for the High Flux at Shutdown alar Page 22

FIGURE 1

.CL 8 8 I 8 8 I-I I . L_ I cm a I

-._ I

- I -

- *1 - -

E

- - --- - - - .

a) .3 I

E 0 --

F~

ir E Ii U

a

'.4

- - - - I E - I -

.

(o C3 a 8 Of

§ 8 l~~

2v 8in

. 2 *- .

cm I,

8_s 0 wdS - *ieu Mona ECAl 11 EC.All 03'05/99 27 of 30

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 35. 056AK3.02 001 Given the following plant conditions:

- A Loss of offsite power has occurre A Natural circulation cooldown is in progres Which ONE of the following describes how the loss of 2 CRDM fans will affect the cooldown?

a. No effect, because the amount of RCS heat removal by running the fans is insignificant compared to that removed by steaming the secondary plan b. Less subcooling is required, and the T-cold cooldown rate will be mor vc. More subcooling is required, and the T-cold cooldown rate will be les d. The upper head will void, since there is not enough cooling available with only two CRDM fans to keep it subcooled.

36. 065AA1.04 001 Following an automatic start due to low instrument air pressure, which ONE of the following describes what will cause Aux Air Compressors to shutdown?

>a. Running unloaded for 5 min b. Running unloaded for 10 min c. Low crankcase oil pressur d. High discharge air temperatur Page 23

- -

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 37. 001K5.28 001 Given the following plant conditions:

- The Unit is at 1% power after an extended shutdow Core burnup is 2000 MWD/MT RCS boron concentration is 1000 pp Control rods at 175 steps

- The STA has determined that 236 pcm of reactivity must be added to increase power to 10%.

Using the attached NUPOP curve and assuming no control rod movement, which ONE of the following identifies the final boron concentration of the RCS after the reactivity change has been made?

,/a. 966 ppm b. 969 ppm c. 1031 ppm d. 1034 ppm 38. 001K6.02 001 Unit is operating at 100% power with all systems in their normal configuration, when Auctioneered High Tavg fails LO Which ONE of the following describes the plant response?

a. Control rods will step in; Charging Flow Control valve, 1-FCV-62-93, open vb. Control rods will step out; Charging Flow Control valve, 1-FCV-62-93, close c. Control rods will not move; Charging Flow Control valve, 1-FCV-62-93, open d. Control rods will not move; Charging Flow Control valve, 1-FCV-62-93, close Page 24

WESTINGHOUSE PROPRIETARY CLASS 2C

- ~

~j~ij~ - ----------------

- .

-7.05 __T___ _ .- tlII1

~~~~~

- --- -- A - --- --

n ~ ~ rr~~~- - - - - - - -r-3t

-- t

[34 P4 - r rt 60 0 80 1000 100 1400 1600 1800 2000 0 200 40 BORON CONCENTRATION (PPM)

Figure 6-22 Differential Boron Worth Versus Boron Concentration at BOL, MOL, and EOL, HZP, With No Xenon Burnup Dependent Parameters 6- 27 WCAP-15562 (Rev. 0)

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 39. 003A1.08 001 Given the following plant conditions:

- The Unit is operating at 100% powe All systems are operating norma Annunciatior "RCP #1 Seal Outlet Temp Hi" alarm actuate The operator verifies that ALL RCP seal temperatures are 180 0 F risin Which ONE of the following is the most probable cause of this alarm?

a. The Charging Pump suction has swapped to the RWS b. The operator has just placed Excess Letdown in service at maximum flow rat >/c. The Letdown Heat Exchanger temperature control valve 1-TCV-70-192 has failed close d. A loss of control air to charging flow control valve 1-FCV-62-93.

40. 003G2.4.6 001 Which ONE of the following describes why the RCPs are tripped if the low pressure trip criteria is reached during a small-break LOCA?

a. Eliminate heat input from the RCPs into the RC b. Limit hydrogen buildup which could preclude core coolin c. Steam may be present in the RCS which will cause RCP impeller damage from cavitatio '/d. Excessive depletion of RCS water inventory might lead to core uncovery if RCPs are tripped later in the acciden Page 25

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 41. 004K3.01 001 Given the following conditions:

- Reactor power 35%.

- Turbine load 32%

- Control Rods are in AUTOMATI CVCS Mixed Bed A was placed in service resulting in a T-avg increase to 571' Which ONE of the following describes the response of the rod control system?

(assume no operator action)

a. Rods will step in at 8 steps per minut / Rods will step in at 40 steps per minut c. Rods will step in at 64 steps per minut d. Rods will step in at 72 steps per minut Page 26

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 42. 004K2.03 001 Given the following plant conditions:

- The unit is at 100% power with IA-A CCP is in operatio A loss of offsite power occurs

- All appropriate loads sequence onto the Shutdown Boards

- The crew has implemented E-0, "Reactor Trip or Safety Injection"

- While the immediate actions are being completed, a safety injection signal (SI) is receive Which ONE of the following describes the response of the Centrifugal Charging Pumps (CCPs)?

a. 1A-A CCP load sheds on the SI signal, and both CCPs auto sequence on the shutdown board b. 1A-A CCP load sheds on the SI signal, and must be restarted manually by the operato c. 1A-A CCP does not load shed on the Si signal; and 1B-B CCP auto sequences on the shutdown board ./d. Both CCPs remain energized and running following the SI signa Page 27

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 43. 013K2.01 001 Given the following:

- 1A-A and 1B-B Si Pump breakers are "Racked In".

- A fuse blows in the NORMAL DC Trip circuit for the 1A-A Si pum A safety injection (SI) actuation occur Which ONE of the following describes the response of the Si Pumps to the Si signal?

a. 1B-B SI Pump will auto start, but 1A-A Si Pump will not auto start until the control power supply is transferre b. 1B-B SI Pump will auto start, but 1A-A Si Pump will not auto start and must be started from the MCR handswitc / Both SI Pumps will auto start, but the 1A-A Si Pump cannot be stopped from the MC d. Both Si Pumps will auto start, but the 1A-A SI Pump cannot be stopped mechanically at the breaker.

44. 013K4.08 001 Which ONE of the following describes the logic for Safety Injection (SI) actuation handswitches and reset pushbuttons?

a. Each actuation handswitch initiates both trains of S Each reset pushbutton resets both trains of S y Each actuation handswitch initiates both trains of S Each reset pushbutton resets only it's associated train of S c. Each actuation handswitch initiates only it's associated train of S Each reset pushbutton resets only it's associated train of S d. Each actuation handswitch initiates only it's associated train of S Each reset pushbutton resets both trains of S Page 28

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 45. 015A2.03 001 Given the following plant conditions:

- Unit is operating at 75% power

- A plant transient has resulted in a xenon oscillation

- Control rods are currently at 216 steps on D bank Which ONE of the following is the effect of the xenon oscillation on NIS and the action required to dampen the oscillation?

"a. The oscillation affects AFD and is dampened by inserting control rods at its most positive pea b. The oscillation affects AFD and is dampened by inserting control rods at its most negative pea c. The oscillation affects QPTR and is dampened by dropping turbine load at its highest valu d. The oscillation affects QPTR and is dampened by dropping turbine load at its lowest valu . 015K6.01 001 Given the following plant conditions:

- Plant is at 25% power with shutdown in progres Power range upper detector, N43A, fails HIG Which ONE of the following identifies the method used to block the "At Power" reactor trips when turbine load is reduced to < 10%?

a. Manually blocked when 3/4 operable power range channels < 10% powe vb. Auto blocked when 3/4 power range channels < 10% powe c. Manually blocked when 2/4 power range channels < 10% powe d. Auto blocked when 2/4 power range channels < 10% powe Page 29

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 47. 017A3.01 001 Given the following plant conditions:

- A small break LOCA has occurre The crew responded IAW EOPs and tripped the RCPs when require The crew is currently in ES-1.2, "Post LOCA Cooldown And Depressurization".

- RCS pressure is 1490 psi Wide range Tc's are 505'F and decreasing slowl Wide range Th's are 515'F and decreasing slowl Core exit thermocouples (CETC) are 551OF and stabl Containment pressure is 1.5 psi SG levels are being maintained at 38%.

- SG pressures are 715 psig and decreasing slowl Which ONE of the following describes the status of natural circulation for the existing plant conditions?

, Cannot be assured, since there is inadequate sub-coolin b. Cannot be assured, since SG parameters are not satisfie c. Cannot be assured, since CETCs are not decreasin d. Exists since all natural circulation criteria are met.

48. 017K1.01 001 Which ONE of the following lists functions/components that receive input from the Core Exit Thermocouples?

va. ICCM plasma display, ICS, RVLIS recorde b. ICS, Rod Insertion Limit computer, RVLIS recorde c. ICCM plasma display, OTAT calculator, RVLIS recorde d. Core quadrant average temperature, ICS, OPAT calculato Page 30

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 49. 022K4.03 001 Given the following plant conditions:

- Reactor trip & Safety Injection occurred due to Large Break LOC Containment 0B isolation has occurre All systems responded normall Which ONE of the following describes the response of the Lower Compartment Coolers when 0B is reset?

a. Fans in A-P-AUTO star Cooler ERCW isolation valves ope v' Fans in A-P-AUTO star Cooler ERCW isolation valves remain close Fans in A-P-AUTO remain of Cooler ERCW isolation valves ope Fans in A-P-AUTO remain of Cooler ERCW isolation valves remain close . 022A4.02 001 Given the following plant conditions:

- Main Steam Line Break occurred inside containment causing a reactor trip and safety injectio Operators have implemented the EOP Containment pressure is 3.2 psig and droppin OAC observes the "INSTR ROOM COOLER A/B FLOW LOW" alarm LI Which ONE of the following ESFAS signals caused the Incore Instrument Room Cooling fans, circ pump, and chiller to shut down?

a. Containment vent isolation (CVI). A containment isolatio c. 0B containment isolatio d. Aux. Building Isolation (ABI)

Page 31

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 51. 025A3.02 001 Given the following plant conditions:

- Large break LOCA has occurred causing a reactor trip and safety injectio OAC observes annunciator "Glycol Exp Tank Level Hi/Hi-Hi is LI Which ONE of the following describes the most likely reason the annunciator is LIT?

a. 0A closes the glycol containment isolation valves; glycol inside containment heats up and relief valves on the containment side of the isolation valves relieve glycol into the glycol expansion tan vb. 0A closes the glycol containment isolation valves; glycol inside containment heats up and expands into the glycol expansion tan B closes the glycol containment isolation valves; glycol inside containment heats up and relief valves on the containment side of the isolation valves relieve glycol into the glycol expansion tan d. 0B closes the glycol containment isolation valves; glycol inside containment heats up and expands into the glycol expansion tan Page 32

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 52. 056K1.03 001 Given the following plant conditions:

- Plant startup in progres Tavg is being maintained at 5570 F by Steam dump Operators are preparing to take the reactor critica Standby Main Feedwater Pump in service supplying the SG Which ONE of the following is the reason why a Condensate Booster Pump should NOT be operated at this time?

a. To prevent overfeeding steam generator v/b. To prevent lifting the high pressure feedwater heater relief valve c. To prevent overpressurizaton and damage to the SG's feedwater preheat sectio d. To prevent overpressurization and damage to the Standby Main Feedwater Pump suction piping.

53. 059K3.04 001 Given the following conditions:

- Unit is operating at 100% powe FCV-2-35, Condensate Short Cycle valve fails OPEN Which ONE of the following describes the effect on reactor power and the correct operator response?

Reactor power will:

a. Increase; Borate the RC vb. Increase; Reduce turbine loa c. Decrease; Dilute the RC d. Decrease; Raise turbine loa Page 33

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 54. 059A4.12 001 Given the following plant conditions:

- The plant was operating at 85% RTP when a loss of offsite power occurre The Emergency Diesel Generators started and re-energized the Shutdown Board The operators have implemented the EOP #4 SG PORV developed a large packing leak after opening following the reactor tri The CRO has determined that the bypass feedwater isolation valves are CLOSE Which ONE of the following signals caused the bypass feedwater isolation valves to CLOSE?

a. North valve vault level increasing to 4 inches due to the PORV packing lea b. Lo-Lo S/G level as #4 S/G blows dry following MSIV isolatio >/c. Tavg decreasing to 5640 F following the reactor tri d. AFW start signal following the blackout.

55. 061K5.02 001 Which ONE of the following describes the decay heat sources and design basis for the Auxiliary Feedwater (AFW) System during a loss of offsite power?

a. Prevents relief through the PZR safety valves by removing core decay heat onl b. Prevents relief through the S/G safety valves by removing core decay heat onl / Prevents relief through the PZR safety valves by removing core decay heat and stored RCS hea d. Prevents relief through the S/G safety valves by removing core decay heat and RCP hea Page 34

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 56. 071A1.06 001 Given the following plant conditions:

- Unit is at 100% powe "A" Waste Gas Compressor is in servic Pressure in the "in service" Waste Gas Decay Tank (WGDT) is 60 psi No WGDT release is in progress

- The relief valve on the "in service" WGDT begins to experience seat leakag Which ONE of the following will provide the best indication that the relief valve on the WGDT is leaking?

a. Increasing count rates on RM-90-101A, Auxiliary Building Vent Monito Y Increasing count rates on RM-90-400, Shield Building Vent Monito c. FCV 77-119, Plant Vent Flow Control valve, isolates due to high radiatio d. The Waste Gas Vent Header pressure increases causing the Waste Gas Compressor to run continuousl Page 35

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 57. 071G2.4.18 001 Given the following plant conditions:

- Loss of all Shutdown power occurred resulting in a reactor tri Operators have implemented ECA-0.0, "Loss of Shutdown Power".

- RCS pressure is 280 psi When RCS pressure could not be maintained > 280 psig, the Unit Supervisor directed the OAC to vent nitrogen from the accumulator Which ONE of the following identifies the basis for venting nitrogen from the accumulators?

a. Prevents injection of additional inventory into the RCS which could result in a water solid condition and further degradation of the RCS pressure boundar b. Prevents erratic RVLIS indications due to pressure pulses as the accumulators alternately start/stop injecting during RCS depressurizatio c. Prevents sudden cooldown of the RCS cold legs by allowing accumulator injection to proceed more slowly along with depressurization of the RC vd. Prevents injection of nitrogen into the RCS which may impede further RCS pressure contro Page 36

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 58. 072K1.02 001 Given the following plant conditions:

- A source check is being performed on Spent Fuel Pool Monitor (RE-90-102).

- Auto Block handswitches are in the OFF positio Which ONE of the following will occur when the control switch is placed in

"SOURCE CHECK"?

a. The fuel handling area ventilation system is diverted to the suction of the EGTS syste b. The green light on the monitor goes out indicating that the monitor is being source checke >/c. Auxiliary Building Ventilation isolates, but no Auxiliary Building isolation signal is generate d. A Containment Ventilation Isolation signal is generated.

59. 072A2.03 001 Given the following plant conditions:

- Plant is operating at 100% power

- Annunciator window 174E, "1-RR-90-1 Area Monitors Instr Malf' is in alar Which ONE of the following conditions would cause the annunciation?

, Internal power supply blown fuse on 1-RM-90-1, Spent Fuel Pit Area radiation monito b. Vent Isolation Rad Mon Block switch, 0-HS-90-136A1, selected to 1-130 and pulle c. Function switch for 1-RM-90-102, Spent Fuel Pit monitor, in the Alarm Adj positio d. 1-RM-90-6, CCS HXs radiation monitor becomes saturated (offscale high).

Page 37

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 60. 002K1.02 001 Given the following plant conditions:

- The reactor is at 100% power

- Rod control is in automati Power Range nuclear instrument N-42 fails HIG Which ONE of the following describes the rod control and plant response?

a. Rods move in until the power mismatch rate signal decays, then move out to the original position to correct the temperature erro / Rods move in until the power mismatch rate signal decays, then remain at the new position with a reduced T-av c. Rods move out until the power mismatch rate signal decays, then move in to the original position to correct the temperature erro d. Rods move out until the high power rod block is reached, then remain at the new position with a higher T-avg.

61. 002K4.05 001 Given the following plant conditions:

- Unit was at 100% powe A spurious Safety Injection occur Operators are responding per the EOP network and have just transitioned to ES-1.1, "Si Termination".

- Annunciators "PRT LEVEL HI/LO, PRESS HI, and TEMP HI" alar Assuming all systems function as designed, which ONE of the following describes the probable cause of this alarm?

a. Pressurizer PORVs, 1-PCV-68-340 and 334, have lifte b. CVCS Letdown Header Relief valve, 1-RLF-62-662 has lifte c. RHR Pump Discharge Relief valve, 1-RLF-63-620, has lifte / RCP #1 Seal Leakoff Relief Valve, 1-RLF-62-636, has lifte Page 38

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 62. 010K6.04 001 Given the following plant conditions:

- Operating at 100% powe PZR PORV, PCV 68-340, is leaking throug PRT pressure increases resulting in rupture of the PRT diaphrag What effect will the rupture of the PRT diaphragm have on PRT temperature and leakage through the PORV?

PRT Temp PORV Leakage Rises Rises Rises Drops V Drops Rises Drops Drops 63. 010A3.01 001 Given the following plant conditions:

- Unit is operating at 100% powe PZR PORV testing is in progress

- While Operators are raising PRT level to reduce PRT Oxygen content the PRT PRESS Hi alarm annunciate Which ONE of the following automatic actions will occur?

, The WDS vent header control valve PCV-68-301 will CLOS b. The primary water supply valve, FCV-68-303 will CLOS c. The PRT drain valve to RCDT FCV-68-310 will OPE d. The PRT nitrogen supply isolation valve FCV-68-305 will CLOS Page 39

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 64. 012K5.02 001 Which ONE of the following would result in the OPAT reactor protection trip setpoint being reduced? Consider each parameter independentl a. AT increasin vb. Tavg increasin c. PRZ pressure decreasin d. Reactor Power decreasing.

65. 012A2.04 001 Given the following plant conditions:

- The operating crew is responding to a reactor trip due to a loss of 120V AC Vital Instrument Power Bd PZR pressure transmitter 68-334 (Channel II) failed LO Which ONE of the following describes the plant response?

a. Both trains of SSPS Si master relays would actuate AND both trains of ECCS equipment auto star /b. Both trains of SSPS Si master relays would actuate BUT only "B" train ECCS equipment auto star c. Only the "B" train SSPS SI master relays would actuate BUT both trains of ECCS equipment auto star d. Only the "B" train SSPS SI master relays would actuate AND only "B" train ECCS equipment auto star Page 40

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 66. 016K3.03 001 Given the following plant conditions:

- Unit is in Mode 3 with Tavg at 5570 Steam Dump Mode selector switch in the STEAM PRESSURE mod Pressure transmitter, 1-PT-1-33, fails HIGH Which ONE of the following describes the effect on the Steam Dump system?

a. Only six valves will open and remain ope b. Only six valves will open and then close when Tavg decreases to 550' c. Twelve valves will open and will remain ope / Twelve valves will open and then close when Tavg decreases to 5500F.

67. 016K5.01 001 Which ONE of the following correctly describes the operation of the Median Signal Select (MSS) circuitry associated with Steam Generator (S/G) controls and protection?

a. The (MSS) averages three channels from each S/G and assigns all control and protection functions to the average value b. The (MSS) looks at all three channels of each S/G, selects the median channel and assigns all protection and control functions to that channe c. The (MSS) compares the Median value of all S/Gs, averages them, then uses this value for all control functions and allows all channels to retain their separation as protection channel >/ The (MSS) looks at all three channels of each S/G, selects the median channel for control and allows all channels to retain their separation as protection channel Page 41

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 68. 026A2.09 001 Given the following plant conditions:

- Large break LOCA has occurre Swapover to containment sump was unsuccessful and crew has implemented ECA-1.1, "Loss of RHR Sump Recirculation".

- Containment Spray has been aligned to the containment sum Unit Supervisor has directed the OAC to initiate makeup to the RWS Which ONE of the following lists the preferred makeup source to the RWST?

a. Transfer water from the Holdup Tan b. Transfer water from the Spent Fuel Pi v'c. Align Containment Spray to the RWS d. Align CVCS blender to makeup.

69. 029A1.02 001 Given the following plant conditions:

- Plant is in MODE 6 with refueling in progres During movement of an irradiated fuel assembly from the core it is dropped and severely damage The containment airborne radioactivity increase Which ONE of the following describes the ESF actuation that would occur?

a. Phase A Containment Isolation from high radiation detected by upper containment radiation monitor, 1-RM-90-11 b. Phase A Containment Isolation from high radiation detected by Containment Purge Exhaust radiation monitor, 1-RM-90-13 c. Containment Vent Isolation from high radiation detected by upper containment radiation monitor, 1-RM-90-11 vd. Containment Vent Isolation from high radiation detected by Containment Purge Exhaust radiation monitor, 1-RM-90-13 Page 42

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 70. 035G2.4.34 001 Given the following plant conditions:

- Operators are performing AO1-27, "MCR Inaccessibility".

- Crew is ready to transfer controls back to MC Auxiliary Feedwater level controllers in the Aux. Control Room (ACR)

are in automatic controlling S/G levels at 38%.

Which ONE of the following actions should be performed to prevent sudden changes in S/G levels when the controllers are transferred to the Main Control room (MCR)?

a. Place MCR controller in automatic, this will allow it to automatically track the corresponding controller in the AC b. Plant conditions must be established to allow modulating components to be full open or closed prior to transfe c. Place ACR and MCR controller in manual, when transferred to NORMAL, Eagle 21 control will match the two controller's output P Place the MCR controller in manual and adjust the controller output to match the output of the ACR controller then transfe Page 43

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 71. 035K4.06 001 Given the following plant conditions:

- The unit is operating at 100% power

- The controlling #3 SIG pressure transmitter fails LO Which ONE of the following describes the effect this will have on indicated steam flow and the initial #3 S/G FW Reg valve response?

Indicated Steam Flow Valve Response Drop FCV will open

' Drop FCV will close Rise FCV will open Rise FCV will close 72. 039A1.03 001 Given the following plant conditions:

- Startup in progres Operators are warming the main steam lines using the MSIV bypasse The OAC observes that the RCS has cooled down 108'F in the past hou The CRO observes that the main steam lines have heated up 102'F in the past hou Which ONE of the following indicates the actions that should be taken by the operators and why?

, Close the MSIV bypass valves; RCS cooldown limit was exceede b. Close the MSIV bypass valves; main steam line heat-up limit was exceede c. Close the MSIV bypass valves; both RCS and main steam line limits were exceede d. Leave MSIV bypass valves open; NO RCS or main steam line limits were exceede Page 44

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 73. 039A3.02 001 Given the following plant conditions:

- Reactor coolant system pressure has decreased to 1930 psig during a plant cooldow The operator has placed the Low Steam Line Pressure Block switches HS-63-135 A & B to BLOC Which ONE of the following describes the status of the Safety Injection and Main Steam Line isolation signals?

a. Only the low steamline pressure MSIV isolation is blocked; low steamline pressure Si is operationa b. Only the low steamline pressure Si signal is blocked; low steam line pressure MSIV isolation is operationa c. Both the high steamline pressure negative rate MSIV isolation and high steamline pressure negative rate Si signal are operationa Vd. Both the low steam line pressure MSIV isolation and low steam line pressure Si signal are blocke Page 45

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 74. 063K2.01 001 Given the following plant conditions:

- Reactor tripped on lo-lo SG leve All MSIVs are close All feedwater reg and bypass reg valves are close Turbine Driven AFW pump is the ONLY AFW pump runnin All DGs are running unloade Which ONE of the following correctly lists the 125V DC Vital Battery Board(s) that is/are deenergized?

a. Only Board b. Only Board l1 v' Board I and 1 d. Board I and l1l.

75. 064K2.03 001 Given the following plant conditions:

- Unit at 100% powe A-A D/G Battery Abnormal annunciation is in alarm

- An AUO is dispatched and confirms that the power supply to the 1A-A D/G Battery Charger is deenergize A loss of the bus from which ONE of the following power supplies would account for this condition?

a. 1A1-A480V Shutdown Board 4 A2-A 480V Diesel Aux Board c. 120V Vital Instrument Power Board I-Ill d. 1A1-A 480V Reactor MOV Board Page 46

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 76. 064K6.08 001 Given the following plant conditions:

- Plant is at 100% power

- IA-A Diesel Generator (D/G) running for a surveillance tes Which ONE of the following identifies how fuel oil makeup occurs to the 1A-A D/G Day Tanks while the D/G is running?

,/ Automatically from the 7-day tanks using the D/G mounted fuel oil transfer pump b. Manually from the 7-day tanks using the D/G mounted fuel oil transfer pump c. Automatically from the south (No. 1) Fuel Oil Storage Tank using the D/G building transfer pum d. Manually from the south (No. 1) Fuel Oil Storage Tank using the D/G building transfer pump.

77. 073K1.01 001 Given the following plant conditions:

- Unit is at 100% power

- High radiation alarms are in on Steam Generator Blowdown (SGBD)

radiation monitors 1-RM-90-120 and 12 Which ONE of the following describes the SGBD System response?

a. The SGBD Containment isolation valves, FCV-15-181 through 184, clos vb. The SGBD Cooling Tower blowdown isolation valve, FCV-15-44, close c. The SGBD to Condensate Header isolation Valve, FCV-15-6, close d. The SGBD flow control valve, FCV-15-43, close Page 47

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 78. 075K3.07 001 Given the following conditions:

- A loss of offsite power has occurre Tavg is 5570 Steam Dump controls are in the Steam Pressure mod Steam dump demand is manually increased to begin cooldow Steam Dump valves will NOT ope Which ONE of the following explains why the Steam Dump valves will NOT open?

a. P-4, Reactor Trip, has not been actuate vb. C-9, Condenser Available, interlock is not me c. P-12, Lo-Lo Tavg, has disarmed the Steam Dump syste d. C-7, Load Rejection controller, has not been actuated.

79. 075A4.01 001 Given the following plant conditions:

- Reactor trip and safety injection occurred while the plant was operating at 100% powe Four ERCW pumps were running in their normal alignment before the SI occurre Which ONE of the following identifies ERCW pump status after the SI and the effect it has on the Condenser Circulating Water (CCW) system make-up?

a. Four ERCW pumps running; CCW make-up is provided only from ERCW since RCW bypass strainer is isolate b. Eight ERCW pumps running; CCW make-up is provided only from RCW since ERCW is routed through the overflow structur ,/c. Four ERCW pumps running; CCW make-up provided from both RCW and ERC d. Eight ERCW pumps running; CCW make-up is not required since the unit is trippe Page 48

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 80. 005K4.07 001 Given the following plant conditions:

- Unit was operating at 100% powe A large break LOCA resulted in a reactor trip and safety injectio Alignment to Cold Leg Recirculation is in progres FCV-63-8, 1A-A RHR Pump to CCP suction, will NOT open from the Control Roo Assuming all other equipment functions as expected, which ONE of the following would prevent the valve from opening?

a. Sl pump minimum flow valve 1-FCV-63-175 ope b. RHR pump suction from RWST 1-FCV-63-1 ope v/c. Containment sump suction valve 1-FCV-63-72 close d. The A train safety injection signal has been reset.

81. 005A2.01 001 Given the following plant conditions:

- Plant is at 100% powe While making plant rounds the Auxiliary Building NAUO discovered that the 1A-A RHR Pump discharge flow indicating switch, 1-FIS-74-12, is indicating 1500 gpm flo An inadvertent safety injection occurs (SI).

Which ONE of the following identifies the impact of this instrument failure on 1A-A RHR pump mini-flow valve?

PRIOR to pump start AFTER Pump start Open Open v Closed Closed Closed Open Open Closed Page 49

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 82. 027K2.01 001 Given the following plant conditions

- Unit is at 100% powe A-A 6.9 KV Shutdown Board is out of service for maintenanc A reactor trip and safety injection (SI) is initiated due to a large break LOC Automatic and manual "B" train Safety Injection fails to actuat With no further operator action, which ONE of the following describes the status of the Emergency Gas Treatment System (EGTS)?

a. Both trains are running b. Only "A"train is running c. Only "B" train is running Vd. Neither train is running Page 50

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 83. 028K6.01 001 Given the following plant conditions:

- A large break LOCA occurs from 100% powe "B" Hydrogen recombiner is tagged ou "A" Hydrogen Recombiner has been placed in servic Subsequently the "A" Hydrogen Recombiner trips on overcurren Which ONE of the following indicates how the concentration of hydrogen will be controlled inside containment if the "A" Hydrogen Recombiner trips?

a. Containment Purge Supply and Exhaust fans are placed in service to dilute the hydrogen concentration in containmen b. A continuous vent path is provided that allows hydrogen to vent to the annulus and then be removed by EGT / Air Return Fans create a mixing effect and the hydrogen igniters will burn hydrogen to maintain it below an explosive concentratio d. Emergency Gas Treatment System will remove hydrogen which collects in the containment dome and discharge to the shield building vent.

84. 034K4.01 001 Which ONE of the following describes a feature of the Refueling Machine designed to prevent the accidental release of a fuel assembly?

a. Gripper is mechanically engaged and disengaged by remote operating handle on bridge and requires no power or air to operat Y Gripper requires air to disengage, however a mechanical latch prevents gripper release under load even if air is applie c. Gripper disengages upon loss of air, however a mechanical latch prevents griper release under load even if air is remove d. When gripper is engaged, operators mechanically lock gripper in place with extension shaft which must be unlocked before gripper can releas Page 51

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 85. 034A1.02 001 Given the following plant conditions:

- Core load is in progres A failure of the Reactor Cavity Seal occurre Cavity level is currently el. 748' and dropping slowl Which ONE of the following actions is required per AO1-29, "Dropped or Damaged Fuel or Refueling Cavity Seal Failure"?

a. Align RHR suction to the RWST and discharge to the RCS through the hot leg vb. Align CCP suction to RWST and discharge to the RCS through normal chargin c. Start one SI pump in the cold leg injection flowpath for cavity makeu d. Align Refueling Water Purification pumps suction to RWST and discharge directly to refueling cavit Page 52

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 86. 045A1.05 001 Given the following plant conditions:

- Unit 1 at 20% RTP

- Turbine trip occurs without a Reactor tri The Steam Dump System is in T-avg Mod Rod Control is in Automatic Which ONE of the following describes the effect of the Turbine trip on the Steam Dump and the Rod Control Systems? Assume no operator action ,/a. The Steam Dump System will maintain T-avg at 5620 F with all Control Rods fully inserte b. The Steam Dump System will maintain T-avg at 5570 F with all Control Rods fully inserte c. The Steam Dump System will maintain T-avg at 5620 F with Control Rods maintaining ;1 5% Reactor power due to C- d. The Steam Dump System will maintain T-avg at 5570 F with Control Rods maintaining z1 5% Reactor power due to C-5.

87. 078K1.05 001 Which ONE of the following describes the source of instrument air and the effect of a loss of instrument air on the Main Steam Isolation Valves (MSIVs)?

/ Non-essential air; MSIVs fail CLOSE b. Non-essential air; MSIVs fail OPE c. Essential air; MSIVs fail CLOSE d. Essential air; MSIVs fail OPE Page 53

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 88. G2.1.7 001 Given the following plant conditions:

- Unit at 100% RTP

- A S/G #1 safety valve begins leaking and power increases to 105% RT The crew enters AOI-38 and reduces turbine load to 90% with the valve position limite This load reduction caused reactor power to decrease to 95% RT Which ONE of the following would be the correct crew response per AOI-38 if the flow increased through the leaking safety valve causing the reactor power to return to 101 %?

a. Decrease turbine load at 5%/min to reduce reactor power to <100% and continue AOI-3 b. Use the valve position limiter to maintain power <100% and continue AOI-3 >/c. Trip the reactor, close the MSIVs and bypasses, and go to E- d. Trip the reactor, initiate Si, close the MSIVs and bypasses and go to E- Page 54

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 89. G2.1.17 001 Given the following plant conditions:

- Inadvertent Safety Injection (SI) has occurre The operating crew implemented the EOPs and is currently performing ES-1.1, "SI Termination".

- The Unit Supervisor (US) directs the Operator at the Controls (OAC) to

"OPEN charging isolation 1-FCV-62-90 and 1-FCV-62-91".

Which ONE of the following communication exchanges between the OAC and US would meet the minimum expectations of Watts Bar Communication Guidelines for repeat back?

a. OAC - "Opening 1-FCV-62-90 and 1-FCV-62-91".

US - No response require b. OAC - "Opening the valves".

US - No response require ,/c. OAC - "Opening 1-FCV-62-90 and 1-FCV-62-91".

US - "That is correct".

d. OAC - "Opening the valves".

US - "That is correct".

Page 55

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 90. G2.1.19 001 Given the following plant conditions:

- Unit is at 100% power with automatic VCT make-up is in progres A VCT level transmitter failure resulted in make-up stopping with level at 34%.

Which ONE of the following identifies additional indications and effects of this failure?

Indications Effects Control board meter indicates 100% 1-LCV-62-118 full diverted Control board meter indicates 0% 1-LCV-62-118 aligned to VCT V ICS computer indicates 100% 1-LCV-62-118 full diverted ICS computer indicates 0% 1-LCV-62-118 aligned to VCT 91. G2.2.1 001 Given the following plant conditions:

- Unit is in Mode 3

- Reactor trip breakers are closed

- RCS Tavg is 5590F

- A dilution to obtain the calculated critical boron concentration in progres Which ONE of the following is allowed per GO-2, "Reactor Startup"?

a. Testing of one SR b. Stopping of an operating RC c. Withdrawal of the Shutdown Rod Energization of the PZR backup heater Page 56

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 92. G2.2.13 001 Given the following plant conditions:

- Unit is operating at 100% power

- 1-FCV-62-93, Charging Flow Control Valve, is being tagged as a boundary isolation valve for a clearance on the CVCS charging heade Which ONE of the following is an acceptable for tagging the valve?

a. Tag the air isolation valve in the open position and tag the handswitch in the closed position for 1-FCV-62-9 vb. Close the valve, install a jacking device, isolate the air supply for 1-FCV-62-93, and tag the jacking devic c. Dog 1-FCV-62-93 closed with its handwheel, tag the valve handwheel, and tag the air isolation valv d. Isolate and de-pressurize the air supply for 1-FCV-62-93 and tag the air isolation valve.

93. G2.2.26 001 Given the following plant conditions:

- Unit is in Mode Refueling operations are in progres The 30th fuel assembly is being loaded into the cor According to FHI-7, "Fuel Handling and Movement", which ONE of the following would require fuel loading operations to be stopped immediately?

a. An unanticipated increase in count rate by a factor of two occurs on any responding nuclear channel during any single loading ste vb. Communications is lost between Containment and the Control Roo c. Water in the Spent Fuel Pit in not clear enough to view the Fuel top Nozzles without supplemental lightin d. Boron concentration decreases by more than 10 ppm as determined by two successive samples of Reactor Coolan Page 57

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 94. G2.2.28 001 Given the following plant conditions:

- Unit is in Mode Refueling operations are in progres An irradiated fuel assembly cannot be placed in its specified core locatio Which ONE of the following describes an approved location for the fuel assembly per FHI-7, Fuel Handling and Movement?

a. Fuel assembly can be placed in the New Fuel Elevator, but the elevator must be full down with power remove b. Fuel assembly may be placed in a free-standing core location as long as no other fuel assembly is free-standin c. Fuel assembly must be returned to the SFP until an alternate core location is determine Vd. Fuel assembly may be temporarily stored in the RCCA change fixtur Page 58

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 95. G2.3.1 001 The following conditions are encountered after a survey of a pump room in the Auxiliary building:

- General area radiation level in the room 70 mrem/hr

- Radiation level 30 cm from the pump casing 350 mrem/hr

- Contamination levels 800 dpm/100cm 2 beta 0 dpm/100cm2 alpha Which ONE of the following identifies the correct radiological postings required to reflect current radiological conditions for this room?

a. Radiation Are A High Radiation Are c. Radiation Area; Contamination Are d. High Radiation Area; Contamination Area.

96. G2.3.11 001 Which ONE of the following identifies the first radiation monitor that should respond to a SGTR and the effect on the monitor?

a. Condenser Vacuum Exhaust Monitor RM-90-119 and the monitor will be automatically isolate vb. Condenser Vacuum Exhaust Monitor RM-90-119 and the monitor will NOT be automatically isolate c. Steam Generator Blowdown Sample Monitor RM-90-120/121 and the monitor will be automatically isolate d. Steam Generator Blowdown Sample Monitor RM-90-120/121 and the monitor will NOT be automatically isolate Page 59

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 97. G2.4.1 001 Given the following conditions:

- Unit 1 in MODE 1 at 10% RT Turbine at 1800 rpm at no load (generator PCB open).

- Loss of offsite power occur Emergency Diesels fails to re-energize Shutdown Board Which ONE of the following describes the correct usage of the Emergency Instructions?

/ Go directly to ECA-0.0 without entering E- b. Implement ECA-0.0 in conjunction with E- c. Go to ECA-0.0 from E-0 after verifying reactor and turbine tri d. Complete E-0 IMMEDIATE ACTIONS then go immediately to ECA-0.0.

98. G2.4.19 001 A step in ES-1.3, "Transfer to RHR Containment Sump", reads as follows:

ISOLATE SI pump miniflow:

CLOSE FCV-63- * CLOSE FCV-63-17 * CLOSE FCV-63- The bullets ("'") indicate that:

a. The actions must be performed in the specified sequence, but once a step is in progress, the next step may be starte b. The actions must be performed and completed in the specified sequenc c. These actions should have been completed, so only verification may be require sd. These actions must all be completed, but any sequence of completion is allowe Page 60

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 99. G2.4.34 001 Given the following plant conditions:

- Control room was abandoned due to a fir All controls have been transferred in accordance with AO1-30.2, Fire Safe Shutdow The plant is being maintained in Hot Standby RCS temperature is being controlled using 1 and RCS pressure is controlled using (2) ?

a. (1) Condenser steam dumps; (2) PZR back-up heater group b. (1) Condenser steam dumps; (2) PZR back-up heater groups A-A and B- c. (1) Atmospheric steam dumps; (2) PZR back-up heater group >/ (1) Atmospheric steam dumps; (2) PZR back-up heater groups A-A and B- Page 61

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 100. G2.4.48 001 Following Safety Injection reset during ES-1.1 the following conditions exist:

- Tavg is 560 0 PRZ level is 45%.

- PRZ pressure is 2230 psi Which ONE of the following describes the PZR heater status the OAC would observe?

a. Control group ID OF Backup group 1C OF Backup group 1A-A OF Backup group 1B-B OF b. Control group iD O Backup group 1C OF Backup group 1A-A OF Backup group 1B-B OF vc. Control group 1D OF Backup group 1C O Backup group 1A-A OF Backup group 1B-B OF d. Control group ID OF Backup group 1C OF Backup group 1A-A O Backup group 1B-B O Page 62

U.S. Nuclear Regulatory Commission Site-Specific Written Examination Applicant Information Name: Region: I / 1l / II l IV Date: 01/26/2001 Facility/Unit: Watts Bar Unit 1 License Level: (RO) SRO Reactor Type: W/ CE / BW / GE Start Time: Finish Time:

Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. The passing grade requires a final grade of at least 80.00 percent. Examination papers will be collected five hours after the examination start Applicant Certification All work done on this examination is my own. I have neither given nor received ai Applicant's Signature Results Examination Value Points Applicant's Score Points Applicant's Grade Percent

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION NAME SSN_

1* 0000 180 (000(i(i) 35. 0(000 2. 0000 1 . 0000 3.QQ(Q(D 2 (D(D000 210 (00(0(i) 3 . 0000 39. 0000@@

6. 0000(D 23. 0000 400 (0(00@

7. G(Do(D 2 . 0( 000 8. @@@@( 25. 0000 4 .. ace@@o 2 (000 D 43 (i)(i)(i)

00 (0 (00 44. (i)@@@(

2 . 0D000 1(i). (BD@( i)D 120(0(0(D0 29. 0(0(0(0 46. (0)(00(0)

30. 0(0(00( 47 ( (Q(D(

13.0000 1 . 0000 480 (i)00 15. ( (00 (0 3 (0(000 4 (D)(g(i)

1 (0(0(i 3 D@ 50. 0000D 17. 0000 3 D@ 51. (0000@

Page 1

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION NAME SSN .

5 . 0000 8 (0(0)(0)

53. 0000 7 . (0000@

5 (0(0(0 710 0(0(0(i 88. (0(0 (00H 5 . 0000 8 . 0000 73. 0000Do 90- 0000 5 . 0000 9 . 0000 7 . 0000 5 . 0000 9 . 00(0(0 .07 (D0 9 . 0 000 7 . 0000 6 . 0000 96. 0000 63. 0(0(0(0 80. 0000 97. 0000@@

6 . 0000@ 98. 0000 6 . 0000 99. (000 6 (0(0(i 8 o00.000 6 (0(0(00 8 . 0000 8 Page 2

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 1. Given the following plant conditions:

- Reactor is at 75% with a power increase in progress using control rod The OAC determines that Control Bank D rod H-12 is not moving and is 14 steps below the other rods in D ban Crew is performing AOI-2, "Malfunction of Reactor Control System" to realign control rod H-12 with the ban Which ONE of the following describes how control rod H-12 will be realigned to control bank D and how control bank insertion limit will change following the realignment?

a. Control Bank D will be realigned to control rod H-12 and control bank D insertion limit will be highe b. Control Bank D will be realigned to control rod H-12 and control bank D insertion limit will be lower c. Control rod H-12 will be realigned to Control Bank D and control bank D insertion limit will be lowe d. Control rod H-12 will be realigned to Control Bank D and control bank D insertion limit will be higher.

2. Given the following plant conditions:

- Reactor power is stable at 30%

- Loop 1 RCP trips Assuming reactor power remains constant, core exit temperature will:

a. increase, then stabilize at a higher valu b. decrease, then stabilize at a lower valu c. increase, then return to the original steady-state valu d. decrease, then return to the original steady-state valu Page 1

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 3. Given the following conditions:

- Unit at 60% powe Confirmed Loop 1 RCP shaft vibration of 25 mil Which ONE of the following statements is correct per A01-5, "Unscheduled Removal of One RCP", regarding the sequence of actions?

a. RCP should be tripped prior to the reactor trip to minimize pump damag b. The reactor should be tripped prior to tripping the RCP to prevent pressurizer level from dropping below 17%.

c. RCP should be tripped prior to the reactor trip to prevent Reactor Coolant Bus voltage from dropping and tripping additional RCP d. The reactor should be tripped prior to tripping the RCP to prevent an automatic trip and an unnecessary challenge to a safety system.

4. Given the following plant conditions:

- Unit was operating at 58% powe Problems with #4 RCP required the pump to be shut down in accordance with A01-5, "Unscheduled Removal of One RCP".

AO1-5 requires the plant to be in which ONE of the following conditions for restart of #4 RCP?

a. <P-1 < P- c. < P- d. Mode Page 2

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 5. Given the following plant conditions:

- Plant was operating at 100% power when a Main Feedwater pump trip resulted in a turbine runbac All systems in automatic and responded as expected to stabilize the plan Control rods inserted beyond the Lo-Lo Rod Insertion limit Operators implemented A01-34, "Immediate Boration", in accordance with the AR Which ONE of the following indicates the final, stable plant conditions AFTER completion of the boration as compared to those PRIOR to the boration?

Reactor Power Rod Position Tavg Same Higher Higher Same Higher Same Lower Lower Same Lower Lower Lower Page 3

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 6. Given the following plant conditions:

- The Unit is at 100% loa Pressurizer pressure channel selector switch, 1-XS-68-340D, is in the PT-68-340 & 334 positio Instrument Maintenance has 1-PT-68-323 (CH ll) OOS for a loop calibratio PZR Pressure transmitter, 1-PT-68-334 (CH II) has just failed AS I The operating crew implements AOl-18, "Malfunction of Pressurizer Pressure Control System".

Which ONE of the following channels will be selected on 1-XS-68-340D and position of the master controller following completion of AOl-1 8, Malfunction of Pressurizer Pressure Control System?

a. Channel I and IlIl selected with 1-PIC-68-340A in AUT b. Channel I and Ill selected with 1-PIC-68-340A in MANUA c. Channel I and IV selected with 1-PIC-68-340A in AUT d. Channel I and IV selected with 1-PIC-68-340A in MANUA Page 4

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 7. Given the following plant conditions:

- Plant is operating at 100% powe One pressurizer safety valve failed full OPE Operating crew initiated reactor trip/safety injection and entered the EOP Safety Injection signal is not rese Which ONE of the following is the status of Pressurizer level and pressure control 10 minutes following the reactor trip/safety injection?

a. PZR level indication offscale LO PZR heaters O b. PZR level indication offscale LO PZR heaters OF c. PZR level indication offscale HIG PZR heaters O d. PZR level indication offscale HIG PZR heaters OF Page 5

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 8. Given the following plant conditions:

- Plant is operating at 100% powe A loss of 120V AC Vital Instrument Power Board 1-i occurre The crew implements AO1-25.01, "Loss of 120V AC Vital Instrument Power Board 1-1".

Which ONE of the following identifies the train selector switches that must be selected for automatic control of feedwater and which loop 1 feedwater/steam flow indications are available?

Feedwater/Steam Flow Feedwater/Steam Flow Selector Switches Indications A train Channel I A train Channel II B train Channel I B train Channel II 9. Given the following:

- Commited Dose Equivalent (CDE) is 1875 mrem

- Deep Dose Equivalent (DDE) is 1620 mrem

- Lens Dose Equivalent (LDE) is 430 mrem

- Commited Effective Dose Equivalent (CEDE) is 260 mrem

- Total Organ Dose Equivalent (TODE) is 3685 mrem

- Shallow Dose Equivalent (SDE) is 295 mrem What is the Total Effective Dose Equivalent (TEDE)?

a. 3980 mrem b. 2170 mrem c. 1915 mrem d. 1880 mrem Page 6

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 10. Which ONE of the following conditions concerning the Personnel Airlock would exceed a Limiting Condition for Operation and require entering an Action Statement of Technical Specifications?

a. The lower containment airlock fails its LLRT while control rod unlatching is in progres b. Welding cables are laid through both lower containment airlock doors during RCS fill and vent at the end of an outag c. The lower containment airlock door interlocks are defeated while reactor vessel head is being tensione d. The outer and inner doors are opened simultaneously during a normal cooldown prior to aligning RHR to the RCS.

11. Given the following plant conditions:

- Inadequate core cooling conditions exist

- Crew is performing FR-C.1, Inadequate Core Cooling Which ONE of the following sets of actions states the proper sequence of the major action categories to be performed for removing decay heat from the core?

a. Rapid secondary depressurization; reinitiation of high head safety injection; RCP restart b. Reinintiation of high head safety injection; rapid secondary depressurization; RCP restart c. Rapid secondary depressurization; RCP restart; reinitiation of high head safety injection d. RCP restart; rapid secondary depressurization; reinitiation of high head safety injection Page 7

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 12. Which ONE of the following correctly describes the indication on the main steam line radiation monitors when the MR/HR AUTO pushbutton is lit on the RM-23 readout module?

a. Indicates low range output onl b. Indicates high range output onl c. Automatically switches between the low and high range outputs every 45 second d. Automatically switches between low and high range output based upon i activity level in order to maintain accurate indication.

13. Given the following plant conditions:

- Operators are responding to a large break LOCA and have determined that degraded core cooling conditions exis The crew has implemented FR-C.2, "Degraded Core Cooling".

- Preparations are in progress to depressurize all intact S/Gs to atmospheric pressure in accordance with FR- Which ONE of the following is the reason the procedure directs all RCPs be stopped prior to performing the depressurization?

a. Reduces the core AP which will enhance the ability of the RHR pumps to inject into the cor b. Minimizes heat input to the S/Gs allowing them to depressurize faste c. Limits heat removal requirements to the core decay heat onl d. Anticipates a loss of RCP #1 seal AP requirement Page 8

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 14. Given the following plant conditions:

- A large break LOCA has occurred that resulted in saturated core cooling condition RWST level is 28%

- Crew is performing step 4 of FR-C.3, Saturated Core Cooling to establish SI pump valve alignmen Which ONE of the following identifies valves that should be verified CLOSED during performance of this step?

a. FCV-63-6, 7 and 177, SI pump and Charging pump suction from RH b. FCV-63-47 and 48, SI pump suction valves c. FCV-63-152 and 153, SI pump cold leg injection cross-tie valves d. FCV-63-3, 4 and 175 SI pump mini-flow valves 15. Given the following plant conditions:

- Reactor trip occurred with subsequent loss of RCP Operators have implemented ES-0.2, "Natural Circulation Cooldown".

- A cooldown rate of 25 0F/hour has been establishe RCS depressurization has been initiated while maintaining subcooling

> 165 0 Operators are monitoring PZR level and RVLIS for void formatio The OAC observes that loss of inventory in the Condensate Storage Tank is imminen Which ONE of the following describes the appropriate procedural actions?

a. Stop the cooldown and remain in ES- b. Raise the cooldown rate and remain in ES- c. Transition to ES-0.3, "Natural Circulation Cooldown With Steam Voids in Vessel (With RVLIS) and lower the cooldown rat d. Transition to ES-0.3, "Natural Circulation Cooldown With Steam Voids in Vessel (With RVLIS) and raise the cooldown rat Page 9

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 16. Which ONE of the following describes the reason for tripping all RCPs during the performance of FR-Z.1, "High Containment Pressure"?

a. Removes heat transferred to the Containment atmosphere from the RCP motor b. Prevents depletion of primary inventory out of the break during a small LOC c. Containment Isolation Phase B isolates cooling water to the RCPs and thermal barrier d. Removes additional energy to the RCS during a break and subsequent release to containment.

17. Given the following plant conditions:

- Unit is stable at 55% powe Recovery of dropped rod D-4 (Control Bank D, Group 1) is in progres D-4 is at 50 step Remaining Bank D rods are at 125 step Which ONE of the following Control Bank D indications will update as withdrawal of the dropped rod continues?

a. Both Bank D step counters and P/A converter b. Both Bank D step counters and Bank Overlap counter c. Only Group 1 step counter and P/A converter d. Only Group 1 step counter and Bank Overlap counter Page 10

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 18. Given the following plant conditions:

- Unit 1 operating at 22% powe Reactor Trip Breakers "A" & "B" close Bypass Breaker B is racked in and close "B" Train SSPS Input Error Inhibit Switch is in INHIBIT for surveillance testin Which ONE of the following describes the response of the Reactor Trip and Bypass Breakers if RCS pressure drops below the Low Pressure Reactor trip setpoint with no operator action?

a. Reactor Trip Breakers "A" & "B" open, Bypass Breaker "B" open b. Reactor Trip Breaker "A" opens and "B" remains closed, Bypass Breaker "B" remains close c. Reactor Trip Breaker "B" opens and "A" remains closed, Bypass Breaker "B" open d. Reactor Trip Breaker "A" opens and "B" remains closed, Bypass Breaker "B" opens.

19. Given the following plant conditions:

- Unit was at 100% powe All systems operating in automatic and all plant parameters at their normal value PCV-68-340 failed partially ope Which ONE of the following identifies the approximate maximum expected temperature of the steam entering the PRT if the PRT pressure does not exceed 45 psig?

a. 2280 b. 2500 c. 2750 F d. 2900 F Page 11

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 20. According to the safety limit technical specification basis for RCS pressure, the maximum transient pressure allowed is:

a. 110% of design pressur b. 110% of normal operating pressur c. 125% of design pressur d. 125% of normal operating pressure.

21. Given the following conditions:

- A large break LOCA occurred

- Operators have just completed swapover to Containment Sump

- A loss of offsite power occurs Which ONE of the following describes the actions required for this condition?

a. Pull to lock SI pumps and CCPs until the RHR pumps have been restarted after the shutdown boards are reenergize b. Pull to lock the CCPs until the RHR pumps are restarted after the shutdown boards are reenergize c. Ensure both RHR pumps are started by the blackout sequencer after the diesel generators reenergize the shutdown boards then restart the SI pump d. Ensure all ECCS pumps are started by the blackout sequencer when the diesel generators reenergize the shutdown board Page 12

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 22. Given the following plant conditions:

- ATWS without Safety Injection has occurre Crew has implemented FR-S.1, "Nuclear Power Generation/ATWS", and currently performing step 4 to borate the RC Which ONE of the following identifies the correct Operator action that must be taken in order to align charging pump suction?

a. CLOSE LCV-62-132 and 133, VCT outlet isolation, then OPEN LCV-62-135 and 136, RWST supply to charging pump suctio b. OPEN LCV-62-135 and 136, RWST supply to charging pump suction, then CLOSE LCV-62-132 and 133, VCT outlet isolatio c. Verify LCV-62-135 and 136, RWST supply to charging pump suction AUTO OPEN, then CLOSE LCV-62-132 and 133, VCT outlet isolatio d. Verify LCV-62-135 and 136, RWST supply to charging pump suction and LCV-62-132 and 133, VCT outlet isolation AUTO OPEN.

23. Given the following plant conditions:

- The Unit is in MODE Source Range Monitor (SRM) NI-132 has failed LOW resulting in a loss of the audio count rate signa WHICH ONE of the following describes the actions necessary to restore the audio count rate signal to the control roo a. Place the audio count rate CHANNEL SELECTOR switch on the front of the Audio Count Rate Drawer to the SR N31 positio b. Place the audio count rate CHANNEL SELECTOR switch on the front of the Audio Count Rate Drawer to the SR N32 positio c. Place the AMPLIFIER SELECT switch on the rear of the audio count rate drawer assembly to the Al positio d. Place the AMPLIFIER SELECT switch on the rear of the audio count rate drawer assembly to the A2 positio Page 13

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 24. Given the following plant conditions:

- A Reactor startup in progres Reactor power is stable at 2 x 10-2% power on the Intermediate Range

- Intermediate Range channel N-135 was declared inoperable and removed from service per AO1-4, "Nuclear instrumentation Malfunction".

Which ONE of the following describes the plant response if an l&C Technician mistakenly removes the control power fuses for N-1 35 during troubleshooting activities?

a. The trip bistable deenergizes and a reactor trip occurs because power is below P-1 b. The trip bistable deenergizes, however NO trip occurs because N-135 is bypasse c. The trip bistable energizes, however NO trip occurs because N-1 35 is bypasse d. The trip bistable energizes and a reactor trip occurs because power is below P-10.

25. Given the following plant conditions:

- Steam Generator Tube Rupture has occurre Crew has implemented E-3, "Steam Generator Tube Rupture".

- The operators have completed cooldown to target incore temperature of 480 0 Which ONE of the following identifies the pressure that steam dumps will be set to control RCS temperature at 480'F?

a. 580 - 585 psi b. 550 - 555 psi psi d. 550 - 555 psi Page 14

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 26. Given the following plant conditions:

- AUO reports Emergency Diesel Generator (DIG) 1A-A has lost 125V DC control power from it's associated Diesel Battery Distribution Panel

- D/G 1A-A is NOT runnin Which ONE of the following describes how this loss of DC control power would affect D/G operation?

a. D/G would start in response to an automatic or manual start signa b. D/G cannot be started by automatic or manual start signa c. D/G can only be started manually from local control pane d. D/G can only be started manually from the MCR panel.

27. Given the following plant conditions:

- Plant is operating a 100% powe Plant systems aligned and operating normall Annunciator, CCS HXA 1-RM-90-123 LIQ RAD HIGH, is in alar Which ONE of the following lists the type and source of radiation sensed by the radiation monitor that is in alarm?

a. Gamma; Thermal Barrier leakag b. Beta; Thermal Barrier leakag c. Gamma; RCP motor cooler leakag d. Beta; RCP motor cooler leakag Page 15

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 28. Given the following plant conditions:

- A Gas Decay Tank release in progress with ABGTS running for dilution air flo A leak occurs on the waste gas compressor which results in a gas release to the Auxiliary Buildin O-RE-90-101, Auxiliary Building Vent Monitor, is in alar Which ONE of the following indicates the effect this leak will have on the plant?

a. Gas Decay Tank release will be terminated; ABGTS will be stoppe b. Gas Decay Tank release will be terminated; ABGTS will continue to ru c. Gas Decay Tank release will continue; ABGTS will be stoppe d. Gas Decay Tank release will continue; ABGTS will continue to run.

29. Once an operating crew has entered the EOP network, which ONE of the following is the earliest that a transition may be made to ES-0.0, "Rediagnosis"?

a. AFTER transition from E-0 and safety injection initiate b. AFTER transition from E-0 and NO safety injection initiate c. BEFORE transition from E-0 and safety injection initiate d. BEFORE transition from E-0 and NO safety injection initiate Page 16

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 30. Given the following plant conditions:

- A small break LOCA has occurred

- 1B-B CCP and SIP failed to start and could not be started manuall E-1 is completed and transition to ES-1.2, "Post LOCA Cooldown and Depressurization", mad .9kV Shutdown Board 1A-A is de-energized due to a fault

- The following conditions are noted by the OAC

- RCS pressure is 1600 psig

- Containment pressure is 6 psig Which ONE of the following describes the action that should be taken and the basis for that action?

a. All RCPs should be stopped to limit heat input during the RCS cooldow b. All RCPs should be stopped because Phase B isolation has occurre c. All RCPs should NOT be stopped because no CCP or SIP is injecting into the RC d. All RCPs should NOT be stopped because the RCS pressure is above 1500 psi . Which ONE of the following is the significance of draining the SG U-tubes and blowing the inverted "loop seal" during a cold leg small break LOCA?

a. A steam vent path is established from the core to the break location and mass loss from the system is decrease b. Core cooling will be lost after the loop seal is blown due to increased injection flow being diverted to the break locatio c. RCS pressure control will be lost resulting in a challenge to Pressurized Thermal Shock limit d. The heat sink effect of the water in the "crossover' leg is lost when the loop seal is lost resulting in a degraded core coolin Page 17

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 32. Given the following plant conditions:

- Reactor trip and safety injection occurre The crew implemented FR-H.1, "Loss of Secondary Heat Sink" due to heat sink red pat Operators are preparing for main feedwater startu Which ONE of the following lists the minimum actions required to reset Main Feedwater Pump 1A?

a. Reset safety injection and cycle reactor trip breaker b. Reset safety injection and reset feedwater isolation signa c. Cycle the reactor trip breakers and reset feedwater isolation signa d. Reset safety injection, cycle reactor trip breakers, and reset feedwater isolation signal.

33. Given the following plant conditions:

- Reactor trip and SI occurred at 0200 due to a small LOC At 0300 the crew transitioned to ECA-1.1, "Loss of RHR Sump Recirculation", due to the failure of both RHR pump Crew has reduced ECCS flow to 1 SIP and 1 CCP per ECA- At 0500 the crew is performing step 17 RNO to establish the minimum required ECCS flow to remove decay hea Using Figure 1 from ECA-1.1, which ONE of the following flow rates would satisfy the intent of the RNO?

a. 180 gpm b. 210 gpm c. 240 gpm d. 280 gpm Page 18

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 34. Which ONE of the following describes why the baseline count rate used for developing the 1/M plot must be re-calculated following movement of any source bearing fuel assembly ?

a. Re-verify the operability of the source range instrument b. Ensures an accurate 1/M plot to monitor subcriticalit c. Determine adequate shutdown margin during refuelin d. Readjust the setpoint for the High Flux at Shutdown alarm.

35. Given the following plant conditions:

- A Loss of offsite power has occurre A Natural circulation cooldown is in progres Which ONE of the following describes how the loss of 2 CRDM fans will affect the cooldown?

a. No effect, because the amount of RCS heat removal by running the fans is insignificant compared to that removed by steaming the secondary plan b. Less subcooling is required, and the T-cold cooldown rate will be mor c. More subcooling is required, and the T-cold cooldown rate will be les d. The upper head will void, since there is not enough cooling available with only two CRDM fans to keep it subcoole Page 19

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 36. Following an automatic start due to low instrument air pressure, which ONE of the following describes what will cause Aux Air Compressors to shutdown?

a. Running unloaded for 5 min b. Running unloaded for 10 min c. Low crankcase oil pressur d. High discharge air temperature.

37. Given the following plant conditions:

- The Unit is at 1%power after an extended shutdow Core burnup is 2000 MWD/MT RCS boron concentration is 1000 pp Control rods at 175 steps

- The STA has determined that 236 pcm of reactivity must be added to increase power to 10%.

Using the attached NUPOP curve and assuming no control rod movement, which ONE of the following identifies the final boron concentration of the RCS after the reactivity change has been made?

a. 966 ppm b. 969 ppm c. 1031 ppm d. 1034 ppm Page 20

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 38. Unit is operating at 100% power with all systems in their normal configuration, when Auctioneered High Tavg fails LO Which ONE of the following describes the plant response?

a. Control rods will step in; Charging Flow Control valve, 1-FCV-62-93, open b. Control rods will step out; Charging Flow Control valve, 1-FCV-62-93, close c. Control rods will not move; Charging Flow Control valve, 1-FCV-62-93, open d. Control rods will not move; Charging Flow Control valve, 1-FCV-62-93, closes.

39. Given the following plant conditions:

- The Unit is operating at 100% powe All systems are operating norma Annunciatior "RCP #1 Seal Outlet Temp Hi" alarm actuate The operator verifies that ALL RCP seal temperatures are 180'F risin Which ONE of the following is the most probable cause of this alarm?

a. The Charging Pump suction has swapped to the RWS b. The operator has just placed Excess Letdown in service at maximum flow rat c. The Letdown Heat Exchanger temperature control valve 1-TCV-70-192 has failed close d. A loss of control air to charging flow control valve 1-FCV-62-9 Page 21

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 40. Which ONE of the following describes why the RCPs are tripped if the low pressure trip criteria is reached during a small-break LOCA?

a. Eliminate heat input from the RCPs into the RC b. Limit hydrogen buildup which could preclude core coolin Steam may be present in the RCS which will cause RCP impeller damage from cavitatio d. Excessive depletion of RCS water inventory might lead to core uncovery if RCPs are tripped later in the accident.

41. Given the following conditions:

- Reactor power 35%.

- Turbine load 32%

- Control Rods are in AUTOMATI CVCS Mixed Bed A was placed in service resulting in a T-avg increase to 571' Which ONE of the following describes the response of the rod control system?

(assume no operator action)

a. Rods will step in at 8 steps per minut b. Rods will step in at 40 steps per minut c. Rods will step in at 64 steps per minut d. Rods will step in at 72 steps per minut Page 22

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 42. Given the following plant conditions:

- The unit is at 100% power with 1A-A CCP is in operatio A loss of offsite power occurs

- All appropriate loads sequence onto the Shutdown Boards

- The crew has implemented E-0, "Reactor Trip or Safety Injection"

- While the immediate actions are being completed, a safety injection signal (SI) is receive Which ONE of the following describes the response of the Centrifugal Charging Pumps (CCPs)?

a. 1A-A CCP load sheds on the SI signal, and both CCPs auto sequence on the shutdown board b. 1A-A CCP load sheds on the SI signal, and must be restarted manually by the operato c. 1A-A CCP does not load shed on the SI signal, and 1B-B CCP auto sequences on the shutdown board d. Both CCPs remain energized and running following the SI signa Page 23

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 43. Given the following:

- 1A-A and IB-B Si Pump breakers are "Racked In".

- A fuse blows in the NORMAL DC Trip circuit for the 1A-A Si pum A safety injection (SI) actuation occur Which ONE of the following describes the response of the SI Pumps to the Si signal?

a. 1B-B SI Pump will auto start, but 1A-A SI Pump will not auto start until the control power supply is transferre b. 1B-B Si Pump will auto start, but 1A-A SI Pump will not auto start and must be started from the MCR handswitc c. Both Si Pumps will auto start, but the lA-A Si Pump cannot be stopped from the MC d. Both Si Pumps will auto start, but the IA-A SI Pump cannot be stopped mechanically at the breaker.

44. Which ONE of the following describes the logic for Safety Injection (SI) actuation handswitches and reset pushbuttons?

a. Each actuation handswitch initiates both trains of S Each reset pushbutton resets both trains of S b. Each actuation handswitch initiates both trains of S Each reset pushbutton resets only it's associated train of S c. Each actuation handswitch initiates only it's associated train of S Each reset pushbutton resets only it's associated train of S d. Each actuation handswitch initiates only it's associated train of S Each reset pushbutton resets both trains of S Page 24

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 45. Given the following plant conditions:

- Unit is operating at 75% power

- A plant transient has resulted in a xenon oscillation

- Control rods are currently at 216 steps on D bank Which ONE of the following is the effect of the xenon oscillation on NIS and the action required to dampen the oscillation?

a. The oscillation affects AFD and is dampened by inserting control rods at its most positive pea b. The oscillation affects AFD and is dampened by inserting control rods at its most negative pea c. The oscillation affects QPTR and is dampened by dropping turbine load at its highest valu d. The oscillation affects QPTR and is dampened by dropping turbine load at its lowest value.

46. Given the following plant conditions:

- Plant is at 25% power with shutdown in progres Power range upper detector, N43A, fails HIG Which ONE of the following identifies the method used to block the "At Power" reactor trips when turbine load is reduced to < 10%?

a. Manually blocked when 3/4 operable power range channels < 10% powe b. Auto blocked when 3/4 power range channels < 10% powe c. Manually blocked when 2/4 power range channels < 10% powe d. Auto blocked when 2/4 power range channels < 10% powe Page 25

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 47. Given the following plant conditions:

- A small break LOCA has occurre The crew responded IAW EOPs and tripped the RCPs when require The crew is currently in ES-1.2, "Post LOCA Cooldown And Depressurization".

- RCS pressure is 1490 psi Wide range Tc's are 505'F and decreasing slowl Wide range Th's are 515 0 F and decreasing slowl Core exit thermocouples (CETC) are 551 OF and stabl Containment pressure is 1.5 psi SG levels are being maintained at 38%.

- SG pressures are 715 psig and decreasing slowl Which ONE of the following describes the status of natural circulation for the existing plant conditions?

a. Cannot be assured, since there is inadequate sub-coolin b. Cannot be assured, since SG parameters are not satisfie c. Cannot be assured, since CETCs are not decreasin d. Exists since all natural circulation criteria are met.

48. Which ONE of the following lists functions/components that receive input from the Core Exit Thermocouples?

a. ICCM plasma display, ICS, RVLIS recorde b. ICS, Rod Insertion Limit computer, RVLIS recorde c. ICCM plasma display, OTAT calculator, RVLIS recorde d. Core quadrant average temperature, ICS, OPAT calculato Page 26

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 49. Given the following plant conditions:

- Reactor trip & Safety Injection occurred due to Large Break LOC Containment 0B isolation has occurre All systems responded normall Which ONE of the following describes the response of the Lower Compartment Coolers when 0B is reset?

a. Fans in A-P-AUTO star Cooler ERCW isolation valves ope b. Fans in A-P-AUTO star Cooler ERCW isolation valves remain close c. Fans in A-P-AUTO remain of Cooler ERCW isolation valves ope d. Fans in A-P-AUTO remain of Cooler ERCW isolation valves remain closed.

50. Given the following plant conditions:

- Main Steam Line Break occurred inside containment causing a reactor trip and safety injectio Operators have implemented the EOP Containment pressure is 3.2 psig and droppin OAC observes the "INSTR ROOM COOLER A/B FLOW LOW" alarm LI Which ONE of the following ESFAS signals caused the Incore Instrument Room Cooling fans, circ pump, and chiller to shut down?

a. Containment vent isolation (CVI).

b. 0A containment isolatio c. 0B containment isolatio d. Aux. Building Isolation (ABI)

Page 27

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 51. Given the following plant conditions:

- Large break LOCA has occurred causing a reactor trip and safety injectio OAC observes annunciator "Glycol Exp Tank Level Hi/Hi-Hi is LI Which ONE of the following describes the most likely reason the annunciator is LIT?

a. 0A closes the glycol containment isolation valves; glycol inside containment heats up and relief valves on the containment side of the isolation valves relieve glycol into the glycol expansion tan b. 0A closes the glycol containment isolation valves; glycol inside containment heats up and expands into the glycol expansion tan c. 0B closes the glycol containment isolation valves; glycol inside containment heats up and relief valves on the containment side of the isolation valves relieve glycol into the glycol expansion tan d. 0B closes the glycol containment isolation valves; glycol inside containment heats up and expands into the glycol expansion tan Page 28

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 52. Given the following plant conditions:

- Plant startup in progres Tavg is being maintained at 5570 F by Steam dump Operators are preparing to take the reactor critica Standby Main Feedwater Pump in service supplying the SG Which ONE of the following is the reason why a Condensate Booster Pump should NOT be operated at this time?

a. To prevent overfeeding steam generator b. To prevent lifting the high pressure feedwater heater relief valve c. To prevent overpressurizaton and damage to the SG's feedwater preheat sectio d. To prevent overpressurization and damage to the Standby Main Feedwater Pump suction piping.

53. Given the following conditions:

- Unit is operating at 100% powe FCV-2-35, Condensate Short Cycle valve fails OPEN Which ONE of the following describes the effect on reactor power and the correct operator response?

Reactor power will:

a. Increase; Borate the RC b. Increase; Reduce turbine loa c. Decrease; Dilute the RC d. Decrease; Raise turbine loa Page 29

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 54. Given the following plant conditions:

- The plant was operating at 85% RTP when a loss of offsite power occurre The Emergency Diesel Generators started and re-energized the Shutdown Board The operators have implemented the EOP #4 SG PORV developed a large packing leak after opening following the reactor tri The CRO has determined that the bypass feedwater isolation valves are CLOSE Which ONE of the following signals caused the bypass feedwater isolation valves to CLOSE?

a. North valve vault level increasing to 4 inches due to the PORV packing lea b. Lo-Lo S/G level as #4 SIG blows dry following MSIV isolatio c. Tavg decreasing to 5640 F following the reactor tri d. AFW start signal following the blackout.

55. Which ONE of the following describes the decay heat sources and design basis for the Auxiliary Feedwater (AFW) System during a loss of offsite power?

a. Prevents relief through the PZR safety valves by removing core decay heat onl b. Prevents relief through the S/G safety valves by removing core decay heat onl c. Prevents relief through the PZR safety valves by removing core decay heat and stored RCS hea d. Prevents relief through the S/G safety valves by removing core decay heat and RCP hea Page 30

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 56. Given the following plant conditions:

- Unit is at 100% powe "A" Waste Gas Compressor is in servic Pressure in the "in service" Waste Gas Decay Tank (WGDT) is 60 psi No WGDT release is in progress

- The relief valve on the "in service" WGDT begins to experience seat leakag Which ONE of the following will provide the best indication that the relief valve on the WGDT is leaking?

a. Increasing count rates on RM-90-101A, Auxiliary Building Vent Monito b. Increasing count rates on RM-90-400, Shield Building Vent Monito c. FCV 77-119, Plant Vent Flow Control valve, isolates due to high radiatio d. The Waste Gas Vent Header pressure increases causing the Waste Gas Compressor to run continuousl Page 31

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 57. Given the following plant conditions:

- Loss of all Shutdown power occurred resulting in a reactor tri Operators have implemented ECA-0.0, "Loss of Shutdown Power".

- RCS pressure is 280 psi When RCS pressure could not be maintained > 280 psig, the Unit Supervisor directed the OAC to vent nitrogen from the accumulator Which ONE of the following identifies the basis for venting nitrogen from the accumulators?

a. Prevents injection of additional inventory into the RCS which could result in a water solid condition and further degradation of the RCS pressure boundar b. Prevents erratic RVLIS indications due to pressure pulses as the accumulators alternately start/stop injecting during RCS depressurizatio c. Prevents sudden cooldown of the RCS cold legs by allowing accumulator injection to proceed more slowly along with depressurization of the RC d. Prevents injection of nitrogen into the RCS which may impede further RCS pressure control.

58. Given the following plant conditions:

- A source check is being performed on Spent Fuel Pool Monitor (RE-90-102).

- Auto Block handswitches are in the OFF positio Which ONE of the following will occur when the control switch is placed in

"SOURCE CHECK"?

a. The fuel handling area ventilation system is diverted to the suction of the EGTS syste b. The green light on the monitor goes out indicating that the monitor is being source checke c. Auxiliary Building Ventilation isolates, but no Auxiliary Building isolation signal is generate d. A Containment Ventilation Isolation signal is generate Page 32

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 59. Given the following plant conditions:

- Plant is operating at 100% power

- Annunciator window 174E, "1-RR-90-1 Area Monitors Instr Malf" is in alar Which ONE of the following conditions would cause the annunciation?

a. Internal power supply blown fuse on 1-RM-90-1, Spent Fuel Pit Area radiation monito b. Vent Isolation Rad Mon Block switch, 0-HS-90-136A1, selected to 1-130 and pulle c. Function switch for 1-RM-90-102, Spent Fuel Pit monitor, in the Alarm Adj positio d. 1-RM-90-6, CCS HXs radiation monitor becomes saturated (offscale high).

60. Given the following plant conditions:

- The reactor is at 100% power

- Rod control is in automati Power Range nuclear instrument N-42 fails HIG Which ONE of the following describes the rod control and plant response?

a. Rods move in until the power mismatch rate signal decays, then move out to the original position to correct the temperature erro b. Rods move in until the power mismatch rate signal decays, then remain at the new position with a reduced T-av c. Rods move out until the power mismatch rate signal decays, then move in to the original position to correct the temperature erro d. Rods move out until the high power rod block is reached, then remain at the new position with a higher T-av Page 33

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 61. Given the following plant conditions:

- Unit was at 100% powe A spurious Safety Injection occur Operators are responding per the EOP network and have just transitioned to ES-1.1, "Si Termination".

- Annunciators "PRT LEVEL HI/LO, PRESS Hi, and TEMP Hi" alar Assuming all systems function as designed, which ONE of the following describes the probable cause of this alarm?

a. Pressurizer PORVs, 1-PCV-68-340 and 334, have lifte b. CVCS Letdown Header Relief valve, 1-RLF-62-662 has lifte c. RHR Pump Discharge Relief valve, 1-RLF-63-620, has lifte d. RCP #1 Seal Leakoff Relief Valve, 1-RLF-62-636, has lifted.

62. Given the following plant conditions:

- Operating at 100% powe PZR PORV, PCV 68-340, is leaking throug PRT pressure increases resulting in rupture of the PRT diaphrag What effect will the rupture of the PRT diaphragm have on PRT temperature and leakage through the PORV?

PRT Temp PORV Leakage Rises Rises Rises Drops Drops Rises Drops Drops Page 34

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 63. Given the following plant conditions:

- Unit is operating at 100% powe PZR PORV testing is in progress

- While Operators are raising PRT level to reduce PRT Oxygen content the PRT PRESS HI alarm annunciate Which ONE of the following automatic actions will occur?

a. The WDS vent header control valve PCV-68-301 will CLOS b. The primary water supply valve, FCV-68-303 will CLOS c. The PRT drain valve to RCDT FCV-68-310 will OPE d. The PRT nitrogen supply isolation valve FCV-68-305 will CLOSE.

64. Which ONE of the following would result in the OPAT reactor protection trip setpoint being reduced? Consider each parameter independentl a. AT increasin b. Tavg increasin c. PRZ pressure decreasin d. Reactor Power decreasin Page 35

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 65. Given the following plant conditions:

- The operating crew is responding to a reactor trip due to a loss of 120V AC Vital Instrument Power Bd PZR pressure transmitter 68-334 (Channel II) failed LO Which ONE of the following describes the plant response?

a. Both trains of SSPS SI master relays would actuate AND both trains of ECCS equipment auto star b. Both trains of SSPS SI master relays would actuate BUT only "B" train ECCS equipment auto star c. Only the "B" train SSPS SI master relays would actuate BUT both trains of ECCS equipment auto star d. Only the "B" train SSPS SI master relays would actuate AND only "B" train ECCS equipment auto start.

66. Given the following plant conditions:

- Unit is in Mode 3 with Tavg at 5570 Steam Dump Mode selector switch in the STEAM PRESSURE mod Pressure transmitter, 1-PT-1-33, fails HIGH Which ONE of the following describes the effect on the Steam Dump system?

a. Only six valves will open and remain ope b. Only six valves will open and then close when Tavg decreases to 550' c. Twelve valves will open and will remain ope d. Twelve valves will open and then close when Tavg decreases to 5500 Page 36

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 67. Which ONE of the following correctly describes the operation of the Median Signal Select (MSS) circuitry associated with Steam Generator (S/G) controls and protection?

a. The (MSS) averages three channels from each S/G and assigns all control and protection functions to the average value b. The (MSS) looks at all three channels of each S/G, selects the median channel and assigns all protection and control functions to that channe c. The (MSS) compares the Median value of all S/Gs, averages them, then uses this value for all control functions and allows all channels to retain their separation as protection channel d. The (MSS) looks at all three channels of each S/G, selects the median channel for control and allows all channels to retain their separation as protection channels.

68. Given the following plant conditions:

- Large break LOCA has occurre Swapover to containment sump was unsuccessful and crew has implemented ECA-1.1, "Loss of RHR Sump Recirculation".

- Containment Spray has been aligned to the containment sum Unit Supervisor has directed the OAC to initiate makeup to the RWS Which ONE of the following lists the preferred makeup source to the RWST?

a. Transfer water from the Holdup Tan b. Transfer water from the Spent Fuel Pi c. Align Containment Spray to the RWS d. Align CVCS blender to makeu Page 37

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 69. Given the following plant conditions:

- Plant is in MODE 6 with refueling in progres During movement of an irradiated fuel assembly from the core it is dropped and severely damage The containment airborne radioactivity increase Which ONE of the following describes the ESF actuation that would occur?

a. Phase A Containment Isolation from high radiation detected by upper containment radiation monitor, 1-RM-90-1 1 b. Phase A Containment Isolation from high radiation detected by Containment Purge Exhaust radiation monitor, 1-RM-90-13 c. Containment Vent Isolation from high radiation detected by upper containment radiation monitor, 1-RM-90-1 1 d. Containment Vent Isolation from high radiation detected by Containment Purge Exhaust radiation monitor, 1-RM-90-13 Page 38

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 70. Given the following plant conditions:

- Operators are performing AOI-27, "MCR Inaccessibility".

- Crew is ready to transfer controls back to MC Auxiliary Feedwater level controllers in the Aux. Control Room (ACR)

are in automatic controlling S/G levels at 38%.

Which ONE of the following actions should be performed to prevent sudden changes in S/G levels when the controllers are transferred to the Main Control room (MCR)?

a. Place MCR controller in automatic, this will allow it to automatically track the corresponding controller in the AC b. Plant conditions must be established to allow modulating components to be full open or closed prior to transfe c. Place ACR and MCR controller in manual, when transferred to NORMAL, Eagle 21 control will match the two controller's output d. Place the MCR controller in manual and adjust the controller output to match the output of the ACR controller then transfer.

71. Given the following plant conditions:

- The unit is operating at 100% power

- The controlling #3 S/G pressure transmitter fails LO Which ONE of the following describes the effect this will have on indicated steam flow and the initial #3 S/G FW Reg valve response?

Indicated Steam Flow Valve Response Drop FCV will open Drop FCV will close Rise FCV will open Rise FCV will close Page 39

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 72. Given the following plant conditions:

- Startup in progres Operators are warming the main steam lines using the MSIV bypasse The OAC observes that the RCS has cooled down 108'F in the past hou The CRO observes that the main steam lines have heated up 102'F in the past hou Which ONE of the following indicates the actions that should be taken by the operators and why?

a. Close the MSIV bypass valves; RCS cooldown limit was exceede b. Close the MSIV bypass valves; main steam line heat-up limit was exceede c. Close the MSIV bypass valves; both RCS and main steam line limits were exceede d. Leave MSIV bypass valves open; NO RCS or main steam line limits were exceede Page 40

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 73. Given the following plant conditions:

- Reactor coolant system pressure has decreased to 1930 psig during a plant cooldow The operator has placed the Low Steam Line Pressure Block switches HS-63-135 A & B to BLOC Which ONE of the following describes the status of the Safety Injection and Main Steam Line isolation signals?

a. Only the low steamline pressure MSIV isolation is blocked; low steamline pressure Si is operationa b. Only the low steamline pressure Si signal is blocked; low steam line pressure MSIV isolation is operationa c. Both the high steamline pressure negative rate MSIV isolation and high steamline pressure negative rate Si signal are operationa d. Both the low steam line pressure MSIV isolation and low steam line pressure SI signal are blocked.

74. Given the following plant conditions:

- Reactor tripped on lo-lo SG leve All MSIVs are close All feedwater reg and bypass reg valves are close Turbine Driven AFW pump is the ONLY AFW pump runnin All DGs are running unloade Which ONE of the following correctly lists the 125V DC Vital Battery Board(s) that is/are deenergized?

a. Only Board b. Only Board l1 c. Board I and 1 d. Board I and l1 Page 41

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 75. Given the following plant conditions:

- Unit at 100% powe A-A DIG Battery Abnormal annunciation is in alarm

- An AUO is dispatched and confirms that the power supply to the 1A-A D/G Battery Charger is deenergize A loss of the bus from which ONE of the following power supplies would account for this condition?

a. 1A1-A480VShutdown Board b. 1A2-A 480V Diesel Aux Board VVital Instrument Power Board I-il d. 1A1-A 480V Reactor MOV Board 76. Given the following plant conditions:

- Plant is at 100% power

- lA-A Diesel Generator (D/G) running for a surveillance tes Which ONE of the following identifies how fuel oil makeup occurs to the 1A-A D/G Day Tanks while the D/G is running?

a. Automatically from the 7-day tanks using the D/G mounted fuel oil transfer pump b. Manually from the 7-day tanks using the D/G mounted fuel oil transfer pump c. Automatically from the south (No. 1) Fuel Oil Storage Tank using the D/G building transfer pum d. Manually from the south (No. 1) Fuel Oil Storage Tank using the D/G building transfer pum Page 42

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 77. Given the following plant conditions:

- Unit is at 100% power

- High radiation alarms are in on Steam Generator Blowdown (SGBD)

radiation monitors 1-RM-90-120 and 12 Which ONE of the following describes the SGBD System response?

a. The SGBD Containment isolation valves, FCV-15-181 through 184, clos b. The SGBD Cooling Tower blowdown isolation valve, FCV-15-44, close c. The SGBD to Condensate Header isolation Valve, FCV-15-6, close d. The SGBD flow control valve, FCV-15-43, closes.

78. Given the following conditions:

- A loss of offsite power has occurre Tavg is 5570 Steam Dump controls are in the Steam Pressure mod Steam dump demand is manually increased to begin cooldow Steam Dump valves will NOT ope Which ONE of the following explains why the Steam Dump valves will NOT open?

a. P-4, Reactor Trip, has not been actuate b. C-9, Condenser Available, interlock is not me c. P-12, Lo-Lo Tavg, has disarmed the Steam Dump syste d. C-7, Load Rejection controller, has not been actuate Page 43

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 79. Given the following plant conditions:

- Reactor trip and safety injection occurred while the plant was operating at 100% powe Four ERCW pumps were running in their normal alignment before the SI occurre Which ONE of the following identifies ERCW pump status after the SI and the effect it has on the Condenser Circulating Water (CCW) system make-up?

a. Four ERCW pumps running; CCW make-up is provided only from ERCW since RCW bypass strainer is isolate b. Eight ERCW pumps running; CCW make-up is provided only from RCW since ERCW is routed through the overflow structur Four ERCW pumps running; CCW make-up provided from both RCW and ERC d. Eight ERCW pumps running; CCW make-up is not required since the unit is tripped.

80. Given the following plant conditions:

- Unit was operating at 100% powe A large break LOCA resulted in a reactor trip and safety injectio Alignment to Cold Leg Recirculation is in progres FCV-63-8, 1A-A RHR Pump to CCP suction, will NOT open from the Control Roo Assuming all other equipment functions as expected, which ONE of the following would prevent the valve from opening?

a. Sl pump minimum flow valve 1-FCV-63-175 ope b. RHR pump suction from RWST 1-FCV-63-1 ope c. Containment sump suction valve 1-FCV-63-72 close d. The A train safety injection signal has been rese Page 44

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 81. Given the following plant conditions:

- Plant is at 100% powe While making plant rounds the Auxiliary Building NAUO discovered that the 1A-A RHR Pump discharge flow indicating switch, 1-FIS-74-12, is indicating 1500 gpm flo An inadvertent safety injection occurs (SI).

Which ONE of the following identifies the impact of this instrument failure on 1A-A RHR pump mini-flow valve?

PRIOR to pump start AFTER Pump start Open Open Closed Closed Closed Open Open Closed 82. Given the following plant conditions

- Unit is at 100% powe A-A 6.9 KV Shutdown Board is out of service for maintenanc A reactor trip and safety injection (SI) is initiated due to a large break LOC Automatic and manual "B" train Safety Injection fails to actuat With no further operator action, which ONE of the following describes the status of the Emergency Gas Treatment System (EGTS)?

a. Both trains are running b. Only "A" train is running c. Only "B" train is running d. Neither train is running Page 45

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 83. Given the following plant conditions:

- A large break LOCA occurs from 100% powe "B" Hydrogen recombiner is tagged ou "A" Hydrogen Recombiner has been placed in servic Subsequently the "A" Hydrogen Recombiner trips on overcurren Which ONE of the following indicates how the concentration of hydrogen will be controlled inside containment if the "A" Hydrogen Recombiner trips?

a. Containment Purge Supply and Exhaust fans are placed in service to dilute the hydrogen concentration in containmen b. A continuous vent path is provided that allows hydrogen to vent to the annulus and then be removed by EGT c. Air Return Fans create a mixing effect and the hydrogen igniters will burn hydrogen to maintain it below an explosive concentratio d. Emergency Gas Treatment System will remove hydrogen which collects in the containment dome and discharge to the shield building vent.

84. Which ONE of the following describes a feature of the Refueling Machine designed to prevent the accidental release of a fuel assembly?

a. Gripper is mechanically engaged and disengaged by remote operating handle on bridge and requires no power or air to operat b. Gripper requires air to disengage, however a mechanical latch prevents gripper release under load even if air is applie c. Gripper disengages upon loss of air, however a mechanical latch prevents griper release under load even if air is remove d. When gripper is engaged, operators mechanically lock gripper in place with extension shaft which must be unlocked before gripper can releas Page 46

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 85. Given the following plant conditions:

- Core load is in progres A failure of the Reactor Cavity Seal occurre Cavity level is currently el. 748' and dropping slowl Which ONE of the following actions is required per AO1-29, "Dropped or Damaged Fuel or Refueling Cavity Seal Failure"?

a. Align RHR suction to the RWST and discharge to the RCS through the hot leg b. Align CCP suction to RWST and discharge to the RCS through normal chargin c. Start one Si pump in the cold leg injection flowpath for cavity makeu d. Align Refueling Water Purification pumps suction to RWST and discharge directly to refueling cavity.

86. Given the following plant conditions:

- Unit 1 at 20% RTP

- Turbine trip occurs without a Reactor tri The Steam Dump System is in T-avg Mod Rod Control is in Automatic Which ONE of the following describes the effect of the Turbine trip on the Steam Dump and the Rod Control Systems? Assume no operator action a. The Steam Dump System will maintain T-avg at 562° F with all Control Rods fully inserte b. The Steam Dump System will maintain T-avg at 5570 F with all Control Rods fully inserte c. The Steam Dump System will maintain T-avg at 562° F with Control Rods maintaining z1 5% Reactor power due to C- d. The Steam Dump System will maintain T-avg at 5570 F with Control Rods maintaining ~1 5% Reactor power due to C- Page 47

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 87. Which ONE of the following describes the source of instrument air and the effect of a loss of instrument air on the Main Steam Isolation Valves (MSIVs)?

a. Non-essential air; MSIVs fail CLOSE b. Non-essential air; MSIVs fail OPE c. Essential air; MSIVs fail CLOSE d. Essential air; MSIVs fail OPEN.

88. Given the following plant conditions:

- Unit at 100% RTP

- A S/G #1 safety valve begins leaking and power increases to 105% RT The crew enters AOI-38 and reduces turbine load to 90% with the valve position limite This load reduction caused reactor power to decrease to 95% RT Which ONE of the following would be the correct crew response per AOI-38 if the flow increased through the leaking safety valve causing the reactor power to return to 101%?

a. Decrease turbine load at 5%/min to reduce reactor power to <100% and continue AOI-3 b. Use the valve position limiter to maintain power <100% and continue AOI-3 c. Trip the reactor, close the MSIVs and bypasses, and go to E- d. Trip the reactor, initiate Si, close the MSIVs and bypasses and go to E- Page 48

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 89. Given the following plant conditions:

- Inadvertent Safety Injection (SI) has occurre The operating crew implemented the EOPs and is currently performing ES-1.1, "SI Termination".

- The Unit Supervisor (US) directs the Operator at the Controls (OAC) to

"OPEN charging isolation 1-FCV-62-90 and 1-FCV-62-91".

Which ONE of the following communication exchanges between the OAC and US would meet the minimum expectations of Watts Bar Communication Guidelines for repeat back?

a. OAC - "Opening 1-FCV-62-90 and 1-FCV-62-91".

US - No response require b. OAC - "Opening the valves".

US - No response require c. OAC - "Opening 1-FCV-62-90 and 1-FCV-62-9 1".

US - "That is correct". OAC - "Opening the valves".

US - "That is correct".

Page 49

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 90. Given the following plant conditions:

- Unit is at 100% power with automatic VCT make-up is in progres A VCT level transmitter failure resulted in make-up stopping with level at 34%.

Which ONE of the following identifies additional indications and effects of this failure?

Indications Effects Control board meter indicates 100% 1-LCV-62-118 full diverted Control board meter indicates 0% 1-LCV-62-118 aligned to VCT ICS computer indicates 100% 1-LCV-62-118 full diverted ICS computer indicates 0% 1-LCV-62-118 aligned to VCT 91. Given the following plant conditions:

- Unit is in Mode 3

- Reactor trip breakers are closed

- RCS Tavg is 5590 F

- A dilution to obtain the calculated critical boron concentration in progres Which ONE of the following is allowed per GO-2, "Reactor Startup"?

a. Testing of one SR b. Stopping of an operating RC c. Withdrawal of the Shutdown Rod d. Energization of the PZR backup heater Page 50

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 92. Given the following plant conditions:

- Unit is operating at 100% power

- l-FCV-62-93, Charging Flow Control Valve, is being tagged as a boundary isolation valve for a clearance on the CVCS charging heade Which ONE of the following is an acceptable for tagging the valve?

a. Tag the air isolation valve in the open position and tag the handswitch in the closed position for 1-FCV-62-9 b. Close the valve, install a jacking device, isolate the air supply for 1-FCV-62-93, and tag the jacking devic c. Dog 1-FCV-62-93 closed with its handwheel, tag the valve handwheel, and tag the air isolation valv d. Isolate and de-pressurize the air supply for 1-FCV-62-93 and tag the air isolation valve.

93. Given the following plant conditions:

- Unit is in Mode Refueling operations are in progres The 30th fuel assembly is being loaded into the cor According to FHI-7, "Fuel Handling and Movement", which ONE of the following would require fuel loading operations to be stopped immediately?

a. An unanticipated increase in count rate by a factor of two occurs on any responding nuclear channel during any single loading ste b. Communications is lost between Containment and the Control Roo c. Water in the Spent Fuel Pit in not clear enough to view the Fuel top Nozzles without supplemental lightin d. Boron concentration decreases by more than 10 ppm as determined by two successive samples of Reactor Coolan Page 51

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 94. Given the following plant conditions:

- Unit is in Mode Refueling operations are in progres An irradiated fuel assembly cannot be placed in its specified core locatio Which ONE of the following describes an approved location for the fuel assembly per FHI-7, Fuel Handling and Movement?

a. Fuel assembly can be placed in the New Fuel Elevator, but the elevator must be full down with power remove b. Fuel assembly may be placed in a free-standing core location as long as no other fuel assembly is free-standin c. Fuel assembly must be returned to the SFP until an alternate core location is determine d. Fuel assembly may be temporarily stored in the RCCA change fixture.

95. The following conditions are encountered after a survey of a pump room in the Auxiliary building:

- General area radiation level in the room 70 mrem/hr

- Radiation level 30 cm from the pump casing 350 mrem/hr

- Contamination levels 800 dpm/100cm2 beta 0 dpm/1 00cm 2 alpha Which ONE of the following identifies the correct radiological postings required to reflect current radiological conditions for this room?

a. Radiation Are b. High Radiation Are c. Radiation Area; Contamination Are d. High Radiation Area; Contamination Are Page 52

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 96. Which ONE of the following identifies the first radiation monitor that should respond to a SGTR and the effect on the monitor?

a. Condenser Vacuum Exhaust Monitor RM-90-119 and the monitor will be automatically isolate b. Condenser Vacuum Exhaust Monitor RM-90-119 and the monitor will NOT be automatically isolate c. Steam Generator Blowdown Sample Monitor RM-90-1201121 and the monitor will be automatically isolate d. Steam Generator Blowdown Sample Monitor RM-90-120/121 and the monitor will NOT be automatically isolated.

97. Given the following conditions:

- Unit 1 in MODE 1 at 10% RT Turbine at 1800 rpm at no load (generator PCB open).

- Loss of offsite power occur Emergency Diesels fails to re-energize Shutdown Board Which ONE of the following describes the correct usage of the Emergency Instructions?

a. Go directly to ECA-0.0 without entering E- b. Implement ECA-0.0 in conjunction with E- c. Go to ECA-0.0 from E-0 after verifying reactor and turbine tri d. Complete E-0 IMMEDIATE ACTIONS then go immediately to ECA- Page 53

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 98. A step in ES-1.3, "Transfer to RHR Containment Sump", reads as follows:

ISOLATE SI pump miniflow:

CLOSE FCV-63- * CLOSE FCV-63-17 * CLOSE FCV-63- The bullets ("*") indicate that:.

a. The actions must be performed in the specified sequence, but once a step is in progress, the next step may be starte b. The actions must be performed and completed in the specified sequenc c. These actions should have been completed, so only verification may be require d. These actions must all be completed, but any sequence of completion is allowed.

99. Given the following plant conditions:

- Control room was abandoned due to a fir All controls have been transferred in accordance with AC1-30.2, Fire Safe Shutdow The plant is being maintained in Hot Standby RCS temperature is being controlled using (1) and RCS pressure is controlled using (2) ?

a. (1) Condenser steam dumps; (2) PZR back-up heater group b. (1) Condenser steam dumps; (2) PZR back-up heater groups A-A and B- c. (1) Atmospheric steam dumps; (2) PZR back-up heater group d. (1) Atmospheric steam dumps; (2) PZR back-up heater groups A-A and B- Page 54

WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION 100. Following Safety Injection reset during ES-1.1 the following conditions exist:

- Tavg is 560 0 PRZ level is 45%.

- PRZ pressure is 2230 psi Which ONE of the following describes the PZR heater status the OAC would observe?

a. Control group 1D OF Backup group 1C OF Backup group 1A-A OF Backup group 1B-B OF b. Control group 1D O Backup group 1C OF Backup group 1A-A OF Backup group 1B-B OF c. Control group 1D OF Backup group 1C O Backup group 1A-A OF Backup group lB-B OF d. Control group 1D OF Backup group 1C OF Backup group 1A-A O Backup group 1B-B O Page 55

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION NAME SSN .

1.0000 1 (0(0(00 3 . 0000 3 I 0000 2 . 00)(0(0)

4.(i)(^)(i)~

2 . (0000@

5-0000 2 . 0000 23. 0(0(00@ 40. (0(00(0)

24. (0O(0(0 4 (000(0(

8. 0000 2 . 0000 2 . 0000 lo.0000 100 (00(0(i) 4 @ 2 . (0000@

1 . 0000 46. (0000 1 .000 14. 0000 31. 0000 48.000 150( 0(i)

0 32. 0(00(0( 4 (0o(0 3 (0(00(0) 50 0 0(0(i)

1 . 0000 51. (i)@ D@D Page 1

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION NAME -

SSN_

52. (0000@ 6 (00(0(D 86. (0)@@0 5 (D (D(D( 7 . 0000 5 (00 7 . 0(0(0(0)

55. (i)(i)(i)(i) 7 ((000 8 (000@

5 . @0000 90. 0000 57 0000 740 (0(00D@ 91. (0000@

5 . 0(000 9 (0(00 5 (D(D(D( 7 . (00)@@

6 . 00(00@@ 9 Z 61. 0(0(0(0 78. 0000 95. (D(D)(D@

62. 0000 7 D 96. (00)00 63. 0000 80. 0000 97. (i)@@0 64. (0(000(i 810000 98. (0000 65. 0000 8 . 0000 8 . 0000 67. 0000 84. 0(0(00 68. 0000 85. 0000 Page 2

---

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 1. 005AK3.02 001 Given the following plant conditions:

- Reactor is at 75% with a power increase in progress using control rod The OAC determines that Control Bank D rod H-12 is not moving and is 14 steps below the other rods in D ban Crew is performing AO1-2, "Malfunction of Reactor Control System" to realign control rod H-12 with the ban Which ONE of the following describes how control rod H-12 will be realigned to control bank D and how control bank insertion limit will change following the realignment?

a. Control Bank D will be realigned to control rod H-12 and control bank D insertion limit will be highe vt. Control Bank D will be realigned to control rod H-12 and control bank D insertion limit will be lower c. Control rod H-12 will be realigned to Control Bank D and control bank D insertion limit will be lowe d. Control rod H-1 2 will be realigned to Control Bank D and control bank D insertion limit will be highe Page 1

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 2. 011 EK2.02 001 Given the following conditions:

- A large break LOCA occurred

- Operators have just completed swapover to Containment Sump

- A loss of offsite power occurs Which ONE of the following describes the actions required for this condition?

a. Pull to lock SI pumps and CCPs until the RHR pumps have been restarted after the shutdown boards are reenergize ' Pull to lock the CCPs until the RHR pumps are restarted after the shutdown boards are reenergize c. Ensure both RHR pumps are started by the blackout sequencer after the diesel generators reenergize the shutdown boards then restart the SI pump d. Ensure all ECCS pumps are started by the blackout sequencer when the diesel generators reenergize the shutdown board . 015AK1.05 001 Given the following plant conditions:

- Reactor power is stable at 30%

- Loop 1 RCP trips Assuming reactor power remains constant, core exit temperature will:

,/a. increase, then stabilize at a higher valu b. decrease, then stabilize at a lower valu c. increase, then return to the original steady-state valu d. decrease, then return to the original steady-state valu Page 2

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 4. 017AK3.03 001 Given the following conditions:

- Unit at 60% powe Confirmed Loop 1 RCP shaft vibration of 25 mil Which ONE of the following statements is correct per AO[-5, "Unscheduled Removal of One RCP", regarding the sequence of actions?

damag a. RCP should be tripped prior to the reactor trip to minimize pump pressurizer b. The reactor should be tripped prior to tripping the RCP to prevent level from dropping below 17%.

Coolant c. RCP should be tripped prior to the reactor trip to prevent Reactor Bus voltage from dropping and tripping additional RCP Yd. The reactor should be tripped prior to tripping the RCP to prevent an automatic trip and an unnecessary challenge to a safety syste . 017AA1.1 3 001 Given the following plant conditions:

- Unit was operating at 58% powe Problems with #4 RCP required the pump to be shut down in accordance with AO1-5, "Unscheduled Removal of One RCP".

restart AOl-5 requires the plant to be in which ONE of the following conditions for of #4 RCP?

Pa, < P-1 b. < P- c. < P- d. Mode Page 3

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 6. 024G2.4.16 001 Given the following plant conditions:

- Unit has experienced a Reactor tri The crew transitions to ES-0.1, Reactor Trip Repons RCS temperature has dropped to 5420 Step 2 RNO states:

- REFER to AOI-34, Immediate Boratio As the procedure reader, which ONE of the following is the proper method of applying this step?

a. Transition from ES-0.1 to AOI-34 and when AOI-34 is completed return to ES- b. Read steps from AOI-34 in conjunction with ES-0.1 on a not to interfere basi V Continue in ES-0.1 and assign AOI-34 to another control room team membe d. Assign ES-0.1 to another control room team member and transition to AOI-3 Page 4

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 7. 024AK1.02 001 Given the following plant conditions:

- Plant was operating at 100% power when a Main Feedwater pump trip resulted in a turbine runbac All systems in automatic and responded as expected to stabilize the plan Control rods inserted beyond the Lo-Lo Rod Insertion limit Operators implemented AO1-34, "Immediate Boration", in accordance with the AR Which ONE of the following indicates the final, stable plant conditions boration?

AFTER completion of the boration as compared to those PRIOR to the Reactor Power Rod Position Tavo Same Higher Higher v Same Higher Same Lower Lower Same Lower Lower Lower Page 5

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 8. 029EA1.02 001 Given the following plant conditions:

- ATWS without Safety Injection has occurre and

- Crew has implemented FR-S.1, "Nuclear Power Generation/ATWS",

currently performing step 4 to borate the RC must be Which ONE of the following identifies the correct Operator action that taken in order to align charging pump suction?

LCV-62-135 a. CLOSE LCV-62-132 and 133, VCT outlet isolation, then OPEN and 136, RWST supply to charging pump suctio suction, then vb. OPEN LCV-62-135 and 136, RWST supply to charging pump CLOSE LCV-62-132 and 133, VCT outlet isolatio AUTO c. Verify LCV-62-135 and 136, RWST supply to charging pump suction OPEN, then CLOSE LCV-62-132 and 133, VCT outlet isolatio and d. Verify LCV-62-135 and 136, RWST supply to charging pump suction LCV-62-132 and 133, VCT outlet isolation AUTO OPE . 055EA2.05 001 Given the following plant conditions:

- The reactor trips due to a loss of all AC power (Station Blackout)

- The crew is currently performing ECA-0.0, Loss of Shutdown Powe Non-essential 125V and 250V battery loads are being shed per AOI-40, Station Blackou The power loss occurred at 0938 hour0.0109 days 0.261 hours 0.00155 weeks 3.56909e-4 months restored to Which ONE of the following is the latest time that AC power must be ensure the station batteries are not fully discharged?

a. 1138

' c. 1538 d. 1738 Page 6

WATTS BAR NUCLEAR PLA NT SENIOR REACTOR OPERATOR NRC EXAMINATION 10. 055G2.4.45 001 Given the following plant conditions:

- Plant was operating at 100% power when a loss of offsite power occurre Emergency Diesel Generators (D/G) failed to start and tie on to their associated 6.9KV Shutdown Board The operating Crew implemented ECA-0.0, "Loss of Shutdown Power".

- The OAC has started 1A-A D/G and re-energized it's associated Shutdown Boar Annunciator, "LOGIC PNL 1A-A LOAD STRIP RELAYS OUT OF SYNC OR UV TEST" (BO-AN alarm), is still LI Which ONE of the following actions is required before this annunciator may be reset?

a. Reset D/G lA-A 86 LOR rela vb. Reset 1A-A Shutdown Board BOX and BOY relay c. Transfer 1A-A Shutdown Board to it's normal power suppl d. Shutdown all the D/Gs that aye not tied to associated Shutdown Boar Page 7

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 11. 057AA1.05 001 Given the following plant conditions:

- Plant is operating at 100% powe occurre A loss of 120V AC Vital Instrument Power Board 1-1 Instrument of 120V AC Vital

- The crew implements AO1-25.01, "Loss Power Board 1-l".

switches that must be Which ONE of the following identifies the train selector 1 feedwater/steam selected for automatic control of feedwater and which loop flow indications are available?

Feedwater/Steam Flow FeedwaterlSteam Flow Selector Switches Indications A train Channel I A train Channel II B train Channel I Bd.train 6 Channel II 12. 059AK1.01 001 Given the following plant conditions:

- Plant is operating a 100% powe Plant systems aligned and operating normall is in alar Annunciator, CCS HX A 1-RM-90-123 LIQ RAD HIGH, radiation sensed by the Which ONE of the following lists the type and source of radiation monitor that is in alarm?

, Gamma; Thermal Barrier leakag b. Beta; Thermal Barrier leakag c. Gamma; RCP motor cooler leakag d. Beta; RCP motor cooler leakag Page 8

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 13. 069AK2.03 001 Airlock would Which ONE of the following conditions concerning the Personnel an Action exceed a Limiting Condition for Operation and require entering Statement of Technical Specifications?

rod unlatching is in a. The lower containment airlock fails its LLRT while control progres airlock doors during b. Welding cables are laid through both lower containment RCS fill and vent at the end of an outag while reactor c. The lower containment airlock door interlocks are defeated vessel head is being tensione a normal Vd. The outer and inner doors are opened simultaneously during cooldown prior to aligning RHR to the RC . 074EA2.04 001 to atmospheric Which ONE of the following is the reason S/Gs are depressurized Core pressure during the performance of FR-C.1, "Response to Inadequate Cooling"?

head for natural a. Reduces RCS temperature to increase the thermal driving circulatio in the upper part of b. Reduces RCS temperature to collapse any steam voids the vesse superheated steam c. Reduces RCS pressure which prevents the formation of in the core as water exceeds the critical point RHR pumps to v' Reduces RCS pressure to allow the ECCS accumulators and inject water to the RC Page 9

WATTS BAR NUCLEAR PLANTr SENIOR REACTOR OPERATOR NRC EXAMINATION 15. 074EK1.03 001 Given the following plant conditions:

- Inadequate core cooling conditions exist

- Crew is performing FR-C.1, Inadequate Core Cooling Which ONE of the following sets of actions states the proper sequence of the major action categories to be performed for removing decay heat from the core?

a. Rapid secondary depressurization; reinitiation of high head safety injection; RCP restart

" Reinintiation of high head safety injection; rapid secondary depressurization; RCP restart c. Rapid secondary depressurization; RCP restart; reinitiation of high head safety injection RCP restart; rapid secondary depressurization; reinitiation of high head safety injection 16. 076AA1.04 001 Which ONE of the following correctly describes the indication on the main steam line radiation monitors when the MR/HR AUTO pushbutton is lit on the RM-23 readout module?

a. Indicates low range output onl v Indicates high range output onl c. Automatically switches between the low and high range outputs every 45 second d. Automatically switches between low and high range output based upon activity level in order to maintain accurate indicatio Page 10

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 17. EO1EK3.4 001 Once an operating crew has entered the EOP network, which ONE of the following is the earliest that a transition may be made to ES-0.0, "Rediagnosis"?

va. AFTER transition from E-0 and safety injection initiate b. AFTER transition from E-0 and NO safety injection initiate c. BEFORE transition from E-0 and safety injection initiate d. BEFORE transition from E-0 and NO safety injection initiate . E02EA2.2 001 Given the following conditions:

- Main steam line break has occurred outside containment, resulting in a reactor trip/safety injection (SI).

- MSIV closure stopped the steam releas Si termination criteria was met and the crew is currently terminating the SI per ES-1.1, "SI Termination."

Which ONE of the following combinations of parameters would require an immediate reinitiation of safety injection?

Maximum RCS RCS PZR CTMT Press SubcoolinQ Pressure Level psig 750 F Stable 18% psig 720F Decreasing 20% psig 870F Decreasing 34%

V psig 607F Stable 24%

Page 11

WATTS BAR NUCLEAR PLA.NT SENIOR REACTOR OPERATOR NRC EXAMINATION 19. E06EK2.1 001 Given the following plant conditions:

- Operators are responding to a large break LOCA and have determined that degraded core cooling conditions exis The crew has implemented FR-C.2, "Degraded Core Cooling".

- Preparations are in progress to depressurize all intact S/Gs to atmospheric pressure in accordance with FR- RCPs be Which ONE of the following is the reason the procedure directs all stopped prior to performing the depressurization?

to a. Reduces the core AP which will enhance the ability of the RHR pumps inject into the cor faste b. Minimizes heat input to the S/Gs allowing them to depressurize c. Limits heat removal requirements to the core decay heat onl "d. Anticipates a loss of RCP #1 seal AP requirement . E07EK2.1 001 Given the following plant conditions:

cooling

- A large break LOCA has occurred that resulted in saturated core condition RWST level is 28%

- Crew is performing step 4 of FR-C.3, Saturated Core Cooling to establish Si pump valve alignmen Which ONE of the following identifies valves that should be verified CLOSED during performance of this step?

RH a. FCV-63-6, 7 and 177, SI pump and Charging pump suction from b. FCV-63-47 and 48, SI pump suction valves c. FCV-63-152 and 153, Si pump cold leg injection cross-tie valves vd. FCV-63-3, 4 and 175 SI pump mini-flow valves Page 12

WATTQ BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 21. E09G2.1.34 001 Given the following plant conditions:

- Reactor trip has occurred in conjunction with a loss of offsite powe The operating crew is currently performing steps of ES-0.2, "Natural Circulation Cooldown".

- Boration to Cold Shutdown boron concentration of 870 ppm has been complete Chemistry reports the following boron concentrations:

850 ppm in the pressurize ppm in the RCS cold leg Which ONE of the following explains the difference in the boron concentration between the value calculated for Cold Shutdown and the values reported by Chemistry?

,/a. Mixing only occurs in the active portions of the RCS cold legs causing RCS boron concentration to be higher than calculate b. The cold legs remain subcooled during this event which causes boron to concentrate in these area PZR spray valves failed to automatically open on increasing pressure to ensure mixing between the cold legs and PZ d. Due to the loss of power the PZR heaters are unavailable to promote mixing between the loops and the PZ Page 13

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 22. E10EA2.1 001 Given the following plant conditions:

- Reactor trip occurred with subsequent loss of RCP Operators have implemented ES-0.2, "Natural Circulation Cooldown".

- A cooldown rate of 250 F/hour has been establishe RCS depressurization has been initiated while maintaining subcooling

> 1650 Operators are monitoring PZR level and RVLIS for void formatio The OAC observes that loss of inventory in the Condensate Storage Tank is imminen Which ONE of the following describes the appropriate procedural actions?

a. Stop the cooldown and remain in ES- b. Raise the cooldown rate and remain in ES- c. Transition to ES-0.3, "Natural Circulation Cooldown With Steam Voids in Vessel (With RVLIS) and lower the cooldown rat Ad. Transition to ES-0.3, "Natural Circulation Cooldown With Steam Voids in Vessel (With RVLIS) and raise the cooldown rat Page 14

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 23. E12EA2.2 001 Given the following plant conditions:

- Unit was at 100% powe A main steam line break occurred in the Turbine Buildin Operators were unable to close the MSIVs and transitioned to ECA-2.1, Uncontrolled Depressurization of All Steam Generator SI termination steps are in progres Loop 3 MSIV is closed locall The CRO observes the #3 SG pressure increasing slowl Which ONE of the following actions should be performed?

a. Transition to E-2, "Faulted SG Isolation".

b. Transition to ES-1.1, "SI Termination".

c. Remain in ECA-2.1 until RHR is in servic vd. Remain in ECA-2.1 until SI is terminate . E14EK3.2 001 Which ONE of the following describes the reason for tripping all RCPs during the performance of FR-Z.1, "High Containment Pressure"?

a. Removes heat transferred to the Containment atmosphere from the RCP motor b. Prevents depletion of primary inventory out of the break during a small LOC / Containment Isolation Phase B isolates cooling water to the RCPs and thermal barrier d. Removes additional energy to the RCS during a break and subsequent release to containmen Page 15

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 25. 007EA2.06 001 Given the following plant conditions:

- Reactor was at 100% powe A rod control system failure causes all shutdown rods to fall into the cor Power Range Indicators are at 6% and slowly decreasing (-0.1 DPM SUR).

- E-0, "Reactor Trip or Safety Injection" is implemente Operators actuate both manual Rx trip handswitche Both Rx trip breakers remain close Which ONE of the following identifies the correct procedural response?

a. Go to step 2 of E-0, "Reactor Trip or Safety Injection".

b. Hold at step 1 of E-0 until Rx trip breakers are open locall / Transition to and perform FR-S.1, "Nuclear Power Generation/ATWS", then transition back to E- d. Transition to FR-S.1, "Nuclear Power Generation/ATWS", and transition back to E-0 when control rods are fully inserted into the cor Page 16

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 26. 007EK2.02 001 Given the following plant conditions:

- Unit 1 operating at 22% powe Reactor Trip Breakers "A" & "B" close Bypass Breaker B is racked in and close "B" Train SSPS Input Error Inhibit Switch is in INHIBIT for surveillance testin Which ONE of the following describes the response of the Reactor Trip and Bypass Breakers if RCS pressure drops below the Low Pressure Reactor trip setpoint with no operator action?

a. Reactor Trip Breakers "A" & "B" open, Bypass Breaker "B" open b. Reactor Trip Breaker "A" opens and "B" remains closed, Bypass Breaker "B" remains close c. Reactor Trip Breaker "B" opens and "A" remains closed, Bypass Breaker "B" open v Reactor Trip Breaker "A" opens and "B" remains closed, Bypass Breaker "B" open Page 17

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 27. 008AK1.01 001 Given the following plant conditions:

- Unit was at 100% powe All systems operating in automatic and all plant parameters at their normal value PCV-68-340 failed partially ope Which ONE of the following identifies the approximate maximum expected temperature of the steam entering the PRT if the PRT pressure does not exceed 45 psig?

a. 228° b. 2500 c. 2750 F

'/d. 2900 F 28. 027AA2.02 001 Given the following plant conditions:

- The plant is at steady state 100% power equilibrium xenon with all control systems in automati Pressurizer level control is transferred to MANUAL and level is slowly increased to 75% and maintaine Which ONE of the following describes the PZR pressure response?

a. Pressure is essentially unaffecte b. Pressure will continuously cycle between 2235 and 2260 psi Pressure will increase until the spray valves open and control pressure at 2260 psi V Pressure will increase until the spray valves open and slowly return pressure to steady state 2235 psi Page 18

WATTS BAR NUCLEAR PLANIT SENIOR REACTOR OPERATOR NRC EXAMINATION 29. 027AK3.02 001 Given the following plant conditions:

- The Unit is at 100% loa Pressurizer pressure channel selector switch, 1-XS-68-340D, is in the PT-68-340 & 334 positio Instrument Maintenance has 1-PT-68-323 (CH 1II) OOS for a loop calibratio PZR Pressure transmitter, 1-PT-68-334 (CH II) has just failed AS I The operating crew implements AOI-18, "Malfunction of Pressurizer Pressure Control System".

Which ONE of the following channels will be selected on 1-XS-68-340D and position of the master controller following completion of AO1-1 8, Malfunction of Pressurizer Pressure Control System?

a. Channel I and ll selected with 1-PIC-68-340A in AUT b. Channel I and IlIl selected with 1-PIC-68-340A in MANUA / Channel I and IV selected with 1-PIC-68-340A in AUT d. Channel I and IV selected with l-PIC-68-340A in MANUA Page 19

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 30. 032AK3.02 001 Given the following plant conditions:

- The Unit is in MODE Source Range Monitor (SRM) NI-132 has failed LOW resulting in a loss of the audio count rate signa WHICH ONE of the following describes the actions necessary to restore the audio count rate signal to the control roo ,/a. Place the audio count rate CHANNEL SELECTOR switch on the front of the Audio Count Rate Drawer to the SR N31 positio b. Place the audio count rate CHANNEL SELECTOR switch on the front of the Audio Count Rate Drawer to the SR N32 positio c. Place the AMPLIFIER SELECT switch on the rear of the audio count rate drawer assembly to the Al positio d. Place the AMPLIFIER SELECT switch on the rear of the audio count rate drawer assembly to the A2 positio Page 20

WATTS BAR NUCLEAR PL? iT SENIOR REACTOR OPERATOR NRC EXAMINATION 31. 033AA1.01 001 Given the following plant conditions:

- A Reactor startup in progres Reactor power is stable at 2 x 10-2% power on the Intermediate Range

- Intermediate Range channel N-135 was declared inoperable and removed from service per AOI-4, "Nuclear instrumentation Malfunction".

Which ONE of the following describes the plant response if an l&C Technician mistakenly removes the control power fuses for N-1 35 during troubleshooting activities?

, The trip bistable deenergizes and a reactor trip occurs because power is below P-1 b. The trip bistable deenergizes, however NO trip occurs because N-1 35 is bypasse c. The trip bistable energizes, however NO trip occurs because N-135 is bypasse d. The trip bistable energizes and a reactor trip occurs because power is below P-1 Page 21

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 32. 038EK1.01 001 Given the following plant conditions:

- Steam Generator Tube Rupture has occurre Crew has implemented E-3, "Steam Generator Tube Rupture".

- The operators have completed cooldown to target incore temperature of 480 0 Which ONE of the following identifies the pressure that steam dumps will be set to control RCS temperature at 4800 F? psi ' psi psi psia.

33. 058AK3.01 001-Given the following plant conditions:

- AUO reports Emergency Diesel Generator (D/G) 1A-A has lost 125V DC control power from it's associated Diesel Battery Distribution Panel

- D/G 1A-A is NOT runnin Which ONE of the following describes how this loss of DC control power would affect D/G operation?

a. D/G would start in response to an automatic or manual start signa Yb. D/G cannot be started by automatic or manual start signa c. D/G can only be started manually from local control pane d. D/G can only be started manually from the MCR pane Page 22

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 34. 060AA2.05 001 Given the following conditions:

- Unit at 100% powe The Control Room Air Intake radiation monitor, 1-RM-90-125, alarm Which ONE of the following describes the response of the Control Building Ventilation System?

, Pressurization fans inlet dampers CLOSE Emergency Pressurization fans inlet dampers OPEN Air cleanup fans inlet dampers OPEN b. Pressurization fans inlet dampers OPEN Emergency Pressurization fans inlet dampers CLOSE Air cleanup fans inlet dampers OPEN c. Pressurization fans inlet dampers CLOSE Emergency Pressurization fans inlet dampers OPEN Air cleanup fans inlet dampers CLOSE d. Pressurization fans inlet dampers OPEN Emergency Pressurization fans inlet dampers CLOSE Air cleanup fans inlet dampers CLOSE Page 23

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 35. 060AA2.04 001 Given the following plant conditions:

- A Gas Decay Tank release in progress with ABGTS running for dilution air flo A leak occurs on the waste gas compressor which results in a gas release to the Auxiliary Buildin RE-90-101, Auxiliary Building Vent Monitor, is in alar Which ONE of the following indicates the effect this leak will have on the plant?

a. Gas Decay Tank release will be terminated; ABGTS will be stoppe b. Gas Decay Tank release will be terminated; ABGTS will continue to ru c. Gas Decay Tank release will continue; ABGTS will be stoppe Ad. Gas Decay Tank release will continue; ABGTS will continue to run.

36. 065AA1.04 001 Following an automatic start due to low instrument air pressure, which ONE of the following describes what will cause Aux Air Compressors to shutdown?

, Running unloaded for 5 min b. Running unloaded for 10 min c. Low crankcase oil pressur d. High discharge air temperatur Page 24

.- 11-11 ...-

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 37. E03EK1.3 001 Given the following plant conditions:

- A small break LOCA has occurred

- 1B-B CCP and SIP failed to start and could not be started manuall E-1 is completed and transition to ES-1.2, "Post LOCA Cooldown and Depressurization", mad .9kV Shutdown Board 1A-A is de-energized due to a fault

- The following conditions are noted by the OAC

- RCS pressure is 1600 psig

- Containment pressure is 6 psig Which ONE of the following describes the action that should be taken and the basis for that action?

a. All RCPs should be stopped to limit heat input during the RCS cooldow "b. All RCPs should be stopped because Phase B isolation has occurre c. All RCPs should NOT be stopped because no CCP or SIP is injecting into the RC d. All RCPs should NOT be stopped because the RCS pressure is above 1500 psi . E03EK2.2 001 Which ONE of the following is the significance of draining the SG U-tubes and blowing the inverted "loop seal" during a cold leg small break LOCA?

Va. A steam vent path is established from the core to the break location and mass loss from the system is decrease b. Core cooling will be lost after the loop seal is blown due to increased injection flow being diverted to the break locatio c. RCS pressure control will be lost resulting in a challenge to Pressurized Thermal Shock limit d. The heat sink effect of the water in the "crossover" leg is lost when the loop seal is lost resulting in a degraded core coolin Page 25

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 39. E05EK2.1 001 Given the following plant conditions:

- Reactor trip and safety injection occurre The crew implemented FR-H.1, "Loss of Secondary Heat Sink" due to heat sink red pat Operators are preparing for main feedwater startu Which ONE of the following lists the minimum actions required to reset Main Feedwater Pump 1A?

a. Reset safety injection and cycle reactor trip breaker b. Reset safety injection and reset feedwater isolation signa c. Cycle the reactor trip breakers and reset feedwater isolation signa >/ Reset safety injection, cycle reactor trip breakers, and reset feedwater isolation signal.

40. E11 EA1.2 001 Given the following plant conditions:

- Reactor trip and SI occurred at 0200 due to a small LOC At 0300 the crew transitioned to ECA-1.1, "Loss of RHR Sump Recirculation", due to the failure of both RHR pump Crew has reduced ECCS flow to 1 SIP and 1 CCP per ECA- At 0500 the crew is performing step 17 RNO to establish the minimum required ECCS flow to remove decay hea Using Figure 1 from ECA-1 .1, which ONE of the following flow rates would satisfy the intent of the RNO?

a. 180 gpm vb. 210 gpm c. 240 gpm d. 280 gpm Page 26

WBN LOSS OF RHR SUMP RECIRCULATION ECA- Rev 6 ECAll 03/05/99 27 of 30

.. .- .

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 41. 028G2.2.9 001 Given the following plant conditions:

- The Unit is at 100% powe PZR level channel 1-LT-68-335 has failed HIGH

- Operating crew has addressed the failure per AOI-20, Malfunction of Pressurizer Level Control In response to the failure, which ONE of the following will most likely require a safety evaluation?

a. A non-intent procedure change to AOI-20 is submitted to clarify a ste v/b. A special test is performed on PZR level channel 1-LT-68-335 to determine automatic action c. A surveillance is required to be performed on channel 1-LT-68-339 while 1-LT-68-335 is out of servic d. Post maintenance test is required to be performed on 1-LT-68-335 prior to returning channel to servic Page 27

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 42. 036AA2.01 001 Given the following plant conditions:

- Plant is in Mode 6 with core offload in progres The fuel assembly being withdrawn into the refueling mast is dropped onto the lower core plat The refuel crew observes bubbles coming from the dropped fuel assembl Which ONE of the following identifies the most likely indications/actions as a result of this incident?

, Upper Cntmt area radiation monitor, 1-RM-90-59, alarms onl b. Spent Fuel Pit area radiation monitor, 1-RM-90-102, alarms onl c. Shield Bldg vent monitor, 1-RM-90-400, initiates Containment Vent Isolatio d. Spent Fuel Pit area radiation monitor, 1-RM-90-1, initiates Auxiliary Bldg Isolation.

43. 036AK1.03 001 Which ONE of the following describes why the baseline count rate used for developing the 1/M plot must be re-calculated following movement of any source bearing fuel assembly ?

a. Re-verify the operability of the source range instrument vb. Ensures an accurate 1/M plot to monitor subcriticalit c. Determine adequate shutdown margin during refuelin d. Readjust the setpoint for the High Flux at Shutdown alar Page 28

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 44. 001 K5.28 001 Given the following plant conditions:

- The Unit is at 1% power after an extended shutdow Core burnup is 2000 MWD/MT RCS boron concentration is 1000 pp Control rods at 175 steps

- The STA has determined that 236 pcm of reactivity must be added to increase power to 10%.

Using the attached NUPOP curve and assuming no control rod movement, which ONE of the following identifies the final boron concentration of the RCS after the reactivity change has been made?

, ppm b. 969 ppm c. 1031 ppm d. 1034 ppm 45. 001K6.02 001 Unit is operating at 100% power with all systems in their normal configuration, when Auctioneered High Tavg fails LO Which ONE of the following describes the plant response?

a. Control rods will step in; Charging Flow Control valve, 1-FCV-62-93, open At Control rods will step out; Charging Flow Control valve, 1-FCV-62-93, close c. Control rods will not move; Charging Flow Control valve, 1-FCV-62-93, open d. Control rods will not move; Charging Flow Control valve, 1-FCV-62-93, close Page 29

WESTINGHOUSE PROPRIETARY CLASS 2C-6. 0

.IT I I I II

- )

E4 -7 .0 z0

-7. 5

,_ __ C__111 H

40~

200 60~ 80 10120 14001601800200 trBOO CNETRAIO (PPM..I)T 1

[:4 H

a-8 BORO CONENTRTION(PPM

_9.1 Figure 6-22 Differential Boron Worth Versus Boron Concentration at BOL, MOL, and EOL, HZP, With No Xenon Burnup Dependent Parameters 6 - 27 WCAP-15562 (Rev. 0)

- ~~~ ~..~~a:~ ".11

~~~~~~~ - .. - 1 .. . ..... . . i. .. ::. . - .

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 46. 003G2.4.48 001 Given the following plant conditions:

- Unit is operating at 20% power with a startup in progres A problem develops which requires removal of Loop 1 RCP

- At 1101, using ICS, you determine the following conditions exist:

- Motor Bearing Temperature is 180 0 F and increasing at 1 F/mi Motor Winding Temperature is 315'F and stabl Pump Bearing Temperature is 220 0 F and increasing at 1F/mi Which ONE of the following correctly describes when loop 1 RCP must be removed from service and the effects on loop 1 steam flow when the RCP is stopped?

,/a. 1101; RCS loop 1 hot leg temperature decreases; Steam flow decrease b. 1101; RCS loop 1 hot leg temperature increases; Steam flow decrease c. 1106; RCS loop 1 hot leg temperature decreases; Steam flow increase d. 1106; RCS loop 1 hot leg temperature increases; Steam flow increase Page 30

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 47. 003A1.08 001 Given the following plant conditions:

- The Unit is operating at 100% powe All systems are operating norma Annunciatior "RCP #1 Seal Outlet Temp Hi" alarm actuates. 0

- The operator verifies that ALL RCP seal temperatures are 180 F risin Which ONE of the following is the most probable cause of this alarm?

a. The Charging Pump suction has swapped to the RWS b. The operator has just placed Excess Letdown in service at maximum flow rat V/c. The Letdown Heat Exchanger temperature control valve 1-TCV-70-192 has failed close d. A loss of control air to charging flow control valve 1-FCV-62-9 . 004K3.01 001 Given the following conditions:

- Reactor power 35%.

- Turbine load 32%

- Control Rods are in AUTOMATI CVCS Mixed Bed A was placed in service resulting in a T-avg increase to 571' Which ONE of the following describes the response of the rod control system?

(assume no operator action)

a. Rods will step in at 8 steps per minut v Rods will step in at 40 steps per minut Rods will step in at 64 steps per minut Rods will step in at 72 steps per minut Page 31

.- ....... .1 _!;_-- .4 WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 49. 004K2.03 001 Given the following plant conditions:

- The unit is at 100% power with 1A-A CCP is in operatio A loss of offsite power occurs

- All appropriate loads sequence onto the Shutdown Boards

- The crew has implemented E-0, "Reactor Trip or Safety Injection"

- While the immediate actions are being completed, a safety injection signal (SI) is receive Which ONE of the following describes the response of the Centrifugal Charging Pumps (CCPs)?

a. 1A-A CCP load sheds on the SI signal, and both CCPs auto sequence on the shutdown board b. iA-A CCP load sheds on the SI signal, and must be restarted manually by the operato c. 1A-A CCP does not load shed on the SI signal, and 1B-B CCP auto sequences on the shutdown board s/d. Both CCPs remain energized and running following the SI signa Page 32

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 50. 013K2.01 001 Given the following:

- 1A-A and 1B-B SI Pump breakers are "Racked In".

- A fuse blows in the NORMAL DC Trip circuit for the 1A-A SI pum A safety injection (SI) actuation occur Which ONE of the following describes the response of the SI Pumps to the SI signal?

a. 1B-B SI Pump will auto start, but lA-A SI Pump will not auto start until the control power supply is transferre b. 1B-B SI Pump will auto start, but 1A-A SI Pump will not auto start and must be started from the MCR handswitc V Both SI Pumps will auto start, but the 1A-A SI Pump cannot be stopped from the MC d. Both SI Pumps will auto start, but the 1A-A SI Pump cannot be stopped mechanically at the breake . 013K4.08 001 Which ONE of the following describes the logic for Safety Injection (SI) actuation handswitches and reset pushbuttons?

a. Each actuation handswitch initiates both trains of S Each reset pushbutton resets both trains of S 'b Each actuation handswitch initiates both trains of S Each reset pushbutton resets only it's associated train of S c. Each actuation handswitch initiates only it's associated train of S Each reset pushbutton resets only it's associated train of S d. Each actuation handswitch initiates only it's associated train of S Each reset pushbutton resets both trains of S Page 33

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 52. 015A2.03 001 Given the following plant conditions:

- Unit is operating at 75% power

- A plant transient has resulted in a xenon oscillation

- Control rods are currently at 216 steps on D bank Which ONE of the following is the effect of the xenon oscillation on NIS and the action required to dampen the oscillation?

, The oscillation affects AFD and is dampened by inserting control rods at its most positive pea b. The oscillation affects AFD and is dampened by inserting control rods at its most negative pea c. The oscillation affects, QPTR and is dampened by dropping turbine load at its highest valu d. The oscillation affects QPTR and is dampened by dropping turbine load at its lowest valu Page 34

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 53. 017A3.01 001 Given the following plant conditions:

- A small break LOCA has occurre The crew responded lAW EOPs and tripped the RCPs when require The crew is currently in ES-1.2, "Post LOCA Cooldown And Depressurization".

- RCS pressure is 1490 psi Wide range Tc's are 505 0 F and decreasing slowl Wide range Th's are 515 0 F and decreasing slowl Core exit thermocouples (CETC) are 551 OF and stabl Containment pressure is 1.5 psi SG levels are being maintained at 38%.

- SG pressures are 715 psig and decreasing slowl Which ONE of the following describes the status of natural circulation for the existing plant conditions?.

Va. Cannot be assured, since there is inadequate sub-coolin b. Cannot be assured, since SG parameters are not satisfie c. Cannot be assured, since CETCs are not decreasin d. Exists since all natural circulation criteria are me Page 35

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 54. 022K4.03 001 Given the following plant conditions:

- Reactor trip & Safety Injection occurred due to Large Break LOC Containment 0B isolation has occurre All systems responded normall Which ONE of the following describes the response of the Lower Compartment Coolers when 0B is reset?

a. Fans in A-P-AUTO star Cooler ERCW isolation valves ope yb. Fans in A-P-AUTO star Cooler ERCW isolation valves remain close Fans in A-P-AUTO remain of Cooler ERCW isolation valves ope d. Fans in A-P-AUTO remain of Cooler ERCW isolation valves remain close . 022A4.02 001 Given the following plant conditions:

- Main Steam Line Break occurred inside containment causing a reactor trip and safety injectio Operators have implemented the EOP Containment pressure is 3.2 psig and droppin OAC observes the "INSTR ROOM COOLER A/B FLOW LOW" alarm LI Which ONE of the following ESFAS signals caused the Incore Instrument Room Cooling fans, circ pump, and chiller to shut down?

a. Containment vent isolation (CVI).

b. 0A containment isolatio c. 0B containment isolatio d. Aux. Building Isolation (ABI)

Page 36

- - - .

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 56. 025A3.02 001 Given the following plant conditions:

- Large break LOCA has occurred causing a reactor trip and safety injectio OAC observes annunciator "Glycol Exp Tank Level Hi/Hi-Hi is LI Which ONE of the following describes the most likely reason the annunciator is LIT?

a. 0A closes the glycol containment isolation valves; glycol inside containment heats up and relief valves on the containment side of the isolation valves relieve glycol into the glycol expansion tan v A closes the glycol containment isolation valves; glycol inside containment heats up and expands into the glycol expansion tan c. 0B closes the glycol containment isolation valves; glycol inside containment heats up and relief valves on the containment side of the isolation valves relieve glycol into the glycol expansion tan d. 0B closes the glycol containment isolation valves; glycol inside containment heats up and expands into the glycol expansion tan Page 37

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 57. 026A2.09 001 Given the following plant conditions:

- Large break LOCA has occurre Swapover to containment sump was unsuccessful and crew has implemented ECA-1.1, "Loss of RHR Sump Recirculation".

- Containment Spray has been aligned to the containment sum Unit Supervisor has directed the OAC to initiate makeup to the RWS Which ONE of the following lists the preferred makeup source to the RWST?

a. Transfer water from the Holdup Tan b. Transfer water from the Spent Fuel Pi /c. Align Containment Spray to the RWS d. Align CVCS blender to makeu . 059K3.04 001 Given the following conditions:

- Unit is operating at 100% powe FCV-2-35, Condensate Short Cycle valve fails OPEN Which ONE of the following describes the effect on reactor power and the correct operator response?

Reactor power will:

a. Increase; Boratethe RC vb. Increase; Reduce turbine loa c. Decrease; Dilute the RC d. Decrease; Raise turbine loa Page 38

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 59. 061K5.02 001 Which ONE of the following describes the decay heat sources and design basis for the Auxiliary Feedwater (AFW) System during a loss of offsite power?

onl a. Prevents relief through the PZR safety valves by removing core decay heat onl b. Prevents relief through the S/G safety valves by removing core decay heat

/ Prevents relief through the PZR safety valves by removing core decay heat and stored RCS heat .

d. Prevents relief through the S/G safety valves by removing core decay heat and RCP hea . 063K2.01 001 Given the following plant conditions:

- Reactor tripped on lo-lo SG leve All MSIVs are close All feedwater reg and bypass reg valves are close Turbine Driven AFW pump is the ONLY AFW pump runnin All DGs are running unloade that Which ONE of the following correctly lists the 125V DC Vital Battery Board(s)

is/are deenergized?

a. Only Board b. Only Board Il sac Board I and 1 d. Board I and 11 Page 39

- -:.. -

.... .........

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERAiOa NRC EXAMINATION 61. 071A1.06 001 Given the following plant conditions:

- Unit is at 100% powe "A" Waste Gas Compressor is in servic Pressure in the "in service" Waste Gas Decay Tank (WGDT) is 60 psi No WGDT release is in progress

- The relief valve on the "in service" WGDT begins to experience seat leakag Which ONE of the following will provide the best indication that the relief valve on the WGDT is leaking?

a. Increasing count rates on RM-90-101A, Auxiliary Building Vent Monito Yb. Increasing count rates on RM-90-400, Shield Building Vent Monito c. FCV 77-119, Plant Vent Flow Control valve, isolates due to high radiatio d. The Waste Gas Vent Header pressure increases causing the Waste Gas Compressor to run continuousl Page 40

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 62. 072K1.02 001 Given the following plant conditions:

- A source check is being performed on Spent Fuel Pool Monitor (RE-90-102).

- Auto Block handswitches are in the OFF positio Which ONE of the following will occur when the control switch is placed in

"SOURCE CHECK"?

a. The fuel handling area ventilation system is diverted to the suction of the EGTS syste b. The green light on the monitor goes out indicating that the monitor is being source checke Vc. Auxiliary Building Ventilation isolates, but no Auxiliary Building isolation signal is generate d. A Containment Ventilation Isolation signal is generate . 002K1.02 001 Given the following plant conditions:

- The reactor is at 100% power

- Rod control is in automati Power Range nuclear instrument N-42 fails HIG Which ONE of the following describes the rod control and plant response?

a. Rods move in until the power mismatch rate signal decays, then move out to the original position to correct the temperature erro vb. Rods move in until the power mismatch rate signal decays, then remain at the new position with a reduced T-av c. Rods move out until the power mismatch rate signal decays, then move in to the original position to correct the temperature erro Rods move out until the high power rod block is reached, then remain at the new position with a higher T-av Page 41

.. .. - r.v . ..... !; .... - I ...

. - .. . .. . ------- - . .1. I w. -1. 1-WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 64. 002K4.05 001 Given the following plant conditions:

- Unit was at 100% powe A spurious Safety Injection occur Operators are responding per the EOP network and have just transitioned to ES-1.1, "SI Termination".

- Annunciators "PRT LEVEL Hi/LO, PRESS HI, and TEMP HI" alar Assuming all systems function as designed, which ONE of the following describes the probable cause of this alarm?

a. Pressurizer PORVs, 1-PCV-68-340 and 334, have lifte b. CVCS Letdown Header Relief valve, 1-RLF-62-662 has lifte c. RHR Pump Discharge Relief valve, 1-RLF-63-620, has lifte Ad. RCP #1 Seal Leakoff Relief Valve, 1-RLF-62-636, has lifte . 010K6.04 001 Given the following plant conditions:

- Operating at 100% powe PZR PORV, PCV 68-340, is leaking throug PRT pressure increases resulting in rupture of the PRT diaphrag What effect will the rupture of the PRT diaphragm have on PRT temperature and leakage through the PORV?

PRT Temp PORV Leakage Rises Rises Rises Drops v Drops Rises Drops Drops Page 42

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 66. 010A3.01 001 Given the following plant conditions:

- Unit is operating at 100% powe PZR PORV testing is in progress

- While Operators are raising PRT level to reduce PRT Oxygen content the PRT PRESS HI alarm annunciate Which ONE of the following automatic actions will occur?

,va. The WDS vent header control valve PCV-68-301 will CLOS b. The primary water supply valve, FCV-68-303 will CLOS c. The PRT drain valve to RCDT FCV-68-310 will OPE d. The PRT nitrogen supply isolation valve FCV-68-305 will CLOS . 011 G2.4.45 001 Given the following plant conditions:

- Unit is operating at 100% powe Controlling PZR level transmitter,1-LT-68-339 failed LO The OAC observes annunciator, "PZR LEVEL HI/LO", LIT with PZR level at 72% and slowly risin Which ONE of the following lists the status of PZR heaters and charging after the failure? (assume NO operator action)

a. All back-up heaters energized; charging flow at minimum of 0 gp b. All back-up heaters energized; charging flow at minimum of 35 gp c. All back-up heaters deenergized; charging flow at minimum of 0 gp Vd. All back-up heaters deenergized; charging flow at minimum of 35 gp Page 43

.. .. .........-- .. -.11. --- I. .

111. ....I .

I . ..11 WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 68. 012K5.02 001 Which ONE of the following would result in the OPAT reactor protection trip setpoint being reduced? Consider each parameter independentl a. AT increasin ,/b. Tavg increasin c. PRZ pressure decreasin d. Reactor Power decreasing.

69. 012A2.04 001 Given the following plant conditions:

- The operating crew is responding to a reactor trip due to a loss of 120V AC Vital Instrument Power Bd PZR pressure transmitter 68-334 (Channel II) failed LO Which ONE of the following describes the plant response?

a. Both trains of SSPS SI master relays would actuate AND both trains of ECCS equipment auto star vb. Both trains of SSPS SI master relays would actuate BUT only "B" train ECCS equipment auto star c. Only the "B" train SSPS SI master relays would actuate BUT both trains of ECCS equipment auto star d. Only the "B" train SSPS SI master relays would actuate ANL only "B" train ECCS equipment auto star Page 44

WATTS BAR NUCLEAR PLAN E SENIOR REACTOR OPERATOR NRC EXAMINATION 70. 027K2.01 001 Given the following plant conditions

- Unit is at 100% powe A-A 6.9 KV Shutdown Board is out of service for maintenanc A reactor trip and safety injection (SI) is initiated due to a large break LOC Automatic and manual "B" train Safety Injection fails to actuat With no further operator action, which ONE of the following describes the status of the Emergency Gas Treatment System (EGTS)?

a. Both trains are running b. Only "A"train is running c. Only "B" train is running V Neither train is running Page 45

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 71. 028K6.01 001 Given the following plant conditions:

- A large break LOCA occurs from 100% powe "B" Hydrogen recombiner is tagged ou "A" Hydrogen Recombiner has been placed in servic Subsequently the "A"Hydrogen Recombiner trips on overcurren Which ONE of the following indicates how the concentration of hydrogen will be controlled inside containment if the "A" Hydrogen Recombiner trips?

a. Containment Purge Supply and Exhaust fans are placed in service to dilute the hydrogen concentration in containmen b. A continuous vent path is provided that allows hydrogen to vent to the annulus and then be removed by EGT " Air Return Fans create a mixing effect and the hydrogen igniters will burn hydrogen to maintain it below an explosive concentratio d. Emergency Gas Treatment System will remove hydrogen which collects in the containment dome and discharge to the shield building ven . 034K4.01 001 Which ONE of the following describes a feature of the Refueling Machine designed to prevent the accidental release of a fuel assembly?

a. Gripper is mechanically engaged and disengaged by remote operating handle on bridge and requires no power or air to operat vb. Gripper requires air to disengage however a mechanical latch prevents gripper release under load even if air is applie Gripper disengages upon loss of air, however a mechanical latch prevents griper release under load even if air is remove d. When gripper is engaged, operators mechanically lock gripper in place with extension shaft which must be unlocked before gripper can releas Page 46

. .1 ---. ...-...:,..

1;...m- -....-- --- _- ... 1-.: --.-

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 73. 034A1.02 001 Given the following plant conditions:

- Core load is in progres A failure of the Reactor Cavity Seal occurre Cavity level is currently el. 748' and dropping slowl Which ONE of the following actions is required per AOI-29, "Dropped or Damaged Fuel or Refueling Cavity Seal Failure"?

a. Align RHR suction to the RWST and discharge to the RCS through the hot leg . Align CCP suction to RWST and discharge to the RCS through normal chargin c. Start one SI pump in the cold leg injection flowpath for cavity makeu d. Align Refueling Water Purification pumps suction to RWST and discharge directly to refueling cavity.

74. 039A1.03 001 Given the following plant conditions:

- Startup in progres Operators are warming the main steam lines using the MSIV bypasse The OAC observes that the RCS has cooled down 108'F in the past hou The CRO observes that the main steam lines have heated up 102'F in the past hou Which ONE of the following indicates the actions that should be taken by the operators and why?

, Close the MSIV bypass valves; RCS cooldown limit was exceede b. Close the MSIV bypass valves; main steam line heat-up limit was exceede Close the MSIV bypass valves; both RCS and main steam line limits were exceede d. Leave MSIV bypass valves open; NO RCS or main steam line limits were exceede Page 47

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 75. 039A3.02 001 Given the following plant conditions:

- Reactor coolant system pressure has decreased to 1930 psig during a plant cooldow The operator has placed the Low Steam Line Pressure Block switches HS-63-135 A & B to BLOC Which ONE of the following describes the status of the Safety Injection and Main Steam Line isolation signals?

a. Only the low steamline pressure MSIV isolation is blocked; low steamline pressure Si is operationa b. Only the low steamline pressure Si signal is blocked; low steam line pressure MSIV isolation is operationa c. Both the high steamline pressure negative rate MSIV isolation and high steamline pressure negative rate SI signal are operationa Yd. Both the low steam line pressure MSIV isolation and low steam line pressure Si signal are blocke Page 48

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 76. 064G2.2.18 001 Given the following plant conditions:

- Plant is in Mode "A" train RHR is in operation controlling RCS temperature at 120' RCS level is at elevation 718'10"

- MEG requests that Emergency Diesel Generator (D/G) 1A-A be tagged out to replace the voltage regulator with a new mode Which ONE of the following describes how this request should be handled?

, D/G 1A-A may NOT be removed from service at this time to protect RHR train "A".

b. D/G 1A-A may NOT be removed from service at this time since both the 1A-A and 1B-B D/G are required to be operable by Tech Spec c. D/G 1A-A may be removed from service at this time as long as one offsite circuit is operabl d. D/G 1A-A may be removed from service at this time as long as risk guidance was obtained from the PSA engineering grou . 073K1.01 001 Given the following plant conditions:

- Unit is at 100% power

- High radiation alarms are in on Steam Generator Blowdown (SGBD)

radiation monitors 1-RM-90-120 and 12 Which ONE of the following describes the SGBD System response?

a. The SGBD Containment isolation valves, FCV-15-181 through 184, clos ' The SGBD Cooling Tower blowdown isolation valve, FCV-1 5-44, close c. The SGBD to Condensate Header isolation Valve, FCV-15-6, close d. The SGBD flow control valve, FCV-15-43, close Page 49

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 78. 075K3.07 001 Given the following conditions:

- A loss of offsite power has occurre Tavg is 557° Steam Dump controls are in the Steam Pressure mod Steam dump demand is manually increased to begin cooldow Steam Dump valves will NOT ope Which ONE of the following explains why the Steam Dump valves will NOT open?

a. P-4, Reactor Trip, has not been actuate vb. C-9, Condenser Available, interlock is not me c. P-12, Lo-Lo Tavg, has disarmed the Steam Dump syste d. C-7, Load Rejection controller, has not been actuated.

79. 075A4.01 001 Given the following plant conditions:

- Reactor trip and safety injection occurred while the plant was operating at 100% powe Four ERCW pumps were running in their normal alignment before the SI occurre Which ONE of the following identifies ERCW pump status after the SI and the effect it has on the Condenser Circulating Water (CCW) system make-up?

a. Four ERCW pumps runr. ,g; CCW make-up is provided only, -m ERCW since RCW bypass strainer is isolate b. Eight ERCW pumps running; CCW make-up is provided only from RCW since ERCW is routed through the overflow structur / Four ERCW pumps running; CCW make-up provided from both RCW and ERC d. Eight ERCW pumps running; CCW make-up is not required since the unit is trippe Page 50

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 80. 005K4.07 001 Given the following plant conditions:

- Unit was operating at 100% powe A large break LOCA resulted in a reactor trip and safety injectio Alignment to Cold Leg Recirculation is in progres FCV-63-8, 1A-A RHR Pump to CCP suction, will NOT open from the Control Roo Assuming all other equipment functions as expected, which ONE of the following would prevent the valve from opening?

a. SI pump minimum flow valve 1-FCV-63-175 ope b. RHR pump suction from RWST 1-FCV-63-1 ope /c. Containment sump suction valve 1-FCV-63-72 close d. The A train safety injection signal has been rese . 041G2.4.21 001 A reactor trip and turbine trip occurs while at 25% powe Which ONE of the following describes the response of the Steam Dump system?

a. Load rejection arms Steam Dump valves; Tavg will be reduced to no-load Tav b. Load rejection arms Steam Dump valves; Tavg will be reduced to within 50F of Tre V/ Reactor trip arms Steam Dump valves; Tavg will be reduced to no-load Tav d. Reactor trip arms Steam Dump valves; Tavg will be reduced to within 50F of Tre Page 51

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 82. 045A1.05 001 Given the following plant conditions:

- Unit 1 at 20% RTP

- Turbine trip occurs without a Reactor tri The Steam Dump System is in T-avg Mod Rod Control is in Automatic Which ONE of the following describes the effect of the Turbine trip on the Steam Dump and the Rod Control Systems? Assume no operator action ,/ The Steam Dump System will maintain T-avg at 5620 F with all Control Rods fully inserte b. The Steam Dump System will maintain T-avg at 5570 F with all Control .Rods fully inserte c. The Steam Dump System will maintain T-avg at 5620 F with Control Rods maintaining ;15% Reactor power due to C- The Steam Dump System will maintain T-avg at 5570 F with Control Rods maintaining z1 5% Reactor power due to C-5.

83. 078K1.05 001 Which ONE of the following describes the source of instrument air and the effect of a loss of instrument air on the Main Steam Isolation Valves (MSIVs)?

va. Non-essential air; MSIVs fail CLOSE b. Non-essential air; MSIVs fail OPE c. Essential air; MSIVs fail CLOSE d. Essential air; MSIVs fail OPE Page 52

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 84. G2.1.6 001 Given the following plant conditions:

- A large break LOCA has occurre The operating crew has entered the EOPs and is currently implementing E-0, "Reactor Trip or Safety Injection".

Which ONE of the following describes when a crew brief should be held?

a. After step 4 of E-0 is complet b. After step 11 of E-0 is complet vc. Upon transitioning from E- d. Upon making the Emergency Classification 85. G2.1.7 001 Given the following plant conditions:

- Unit at 100% RTP

- A S/G #1 safety valve begins leaking and power increases to 105% RT The crew enters AOI-38 and reduces turbine load to 90% with the valve position limite This load reduction caused reactor power to decrease to 95% RT Which ONE of the following would be the correct crew response per AOI-38 if the flow increased through the leaking safety valve causing the reactor power to return to 101%?

a. Decrease turbine load at 5%/min to reduce reactor power to <100% and continue AOI-3 b. Use the valve position limiter to maintain power <100% and continue AO1-3 / Trip the reactor, close the MSIVs and bypasses, and go to E- d. Trip the reactor, initiate SI, close the MSIVs and bypasses and go to E- Page 53

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 86. G2.1.11 001 Given the following conditions:

- Plant was operating at 100% power when a Main Feedwater pump tripped causing a plant runbac The OAC observes AFD to be outside the "doghouse" on PRM channels N41, and N4 Which ONE of the following identifies the action required to comply with Technical Specifications?

a. Restore AFD to within limits AND Reduce power to < 50% within 30 minute b. Restore AFD to within limits AND Reduce power to < 50% within 15 minute / Restore AFD to within limits OR Reduce power to < 50% within 30 minute d. Restore AFD to within limits OR Reduce power to < 50% within 15 minutes.

87. G2.1.12 001 Given the following conditions:

- Plant is at 100% powe RCS pressure is 2235 psig and T-avg is 5880 RHR discharge relief valve 1-63-637 is leaking to the PRT at a rate of 2.5 gp Which ONE of the following describes the type of leakage and the action required by Technical Specifications? (Assume all other systems are operating normally and no other RCS leakage)

a. Unidentified leakage that requires shutdow b. Pressure boundary leakage that requires shutdow ,/c. Identified leakage, but does not require shutdow d. Controlled leakage, but does not require shutdow Page 54

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 88. G2.1.33 001 Given the following plant conditions:

- Plant is in Mode 3

- During performance of Control Building routine rounds the AUO discovers the 125V DC supply breaker to 120V AC Vital Inverter 1-Il in the TRIPPED positio Which ONE of the following describes the correct action which must be taken with regard to Tech Specs?

a. Attempt to close the supply breaker one time, if the breaker can be closed, Tech Spec LCO action entry is NOT require vb. The Tech Spec LCO action for the inverter must be entered until the breaker can be close If the inverter is aligned to it's AC supply and the voltage is normal, Tech Spec LCO action entry is NOT require d. If the inverter is aligned to it's AC supply and the voltage is normal, enter the appropriate Tech Spec LCO action for the inverter for tracking only until the breaker can be close Page 55

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 89. G2.2.20 001 Given the following plant conditions:

- Plant is in Mode 3 with startup in progres The breaker for "C" hotwell pump will not clos The Shift Manager and Work Week Manager determined that trouble shooting could be conducted as "minor work" if the pump is tagged ou Which ONE of the following describes how this trouble shooting activity should be documented?

a. WO is NOT required since only trouble shooting is planned and will have no operational impact, no detailed planning or documentation is require b. WO is NOT required since a PER will be written to address the condition adverse to quality and trouble shooting may be documented in the PE vc. WO is required, the WO may be sent directly to the craft after OPS approval and the work may be documented on the WO for d. WO is required, the WO must be routed to planning after OPS approval and the work will be conducted and documented in the work package developed by the planne . G2.2.22 001 Given the following plant conditions:

- Unit is in Mode 3 with cooldown to Cold Shutdown in progres A transient occurred resulted in the pressurizer going solid and RCS pressure increasing to 2835 psi Which ONE of the following actions is required?

a. Be in hot shutdown with RCS pressure within its limit in 1 hou b. Be in hot shutdown with RCS pressure within its limit in 30 minute c. Reduce RCS pressure to within its limit within 15 minute Pd. Reduce RCS pressure to within its limit within 5 minute Page 56

- ...... -

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 91. G2.2.24 001 Given the following plant conditions:

- Unit is operating at 100% powe Pressure Pressure channel 11, 1-PT-68-335, has failed HIG All required actions for this instrument failure have been complete The surveillance for Pressurizer pressure channel IV, 1-PT-68-322, will become late at the end of this shif Which ONE of the following actions should be taken?

a. Apply Tech Spec SR 3.0.3 to extend the surveillance for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to allow completion of maintenance on 1-PT-68-33 b. Bypass the bistables on 1-PT-68-322, enter LCO 3.0.3 and then perform surveillance on 1-PT-68-32 ,/c. Bypass the bistables on 1-PT-68-335 and then allow surveillance to be performed on 1-PT-68-32 d. Do not allow surveillance to be performed and enter Tech Spec 3.0.3 when the surveillance period expire Page 57

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 92. G2.2.28 001 Given the following plant conditions:

- Unit is in Mode Refueling operations are in progres An irradiated fuel assembly cannot be placed in its specified core locatio Which ONE of the following describes an approved location for the fuel assembly per FHI-7, Fuel Handling and Movement?

a. Fuel assembly can be placed in the New Fuel Elevator, but the elevator must be full down with power remove b. Fuel assembly may be placed in a free-standing core location as long as no other fuel assembly is free-standin c. Fuel assembly must be returned to the SFP until an alternate core location is determine P Fuel assembly may be temporarily stored in the RCCA change fixtur Page 58

I - ,; ! .I; .. : i i- , .;-. - -

-i.1--- .. .. ...I .

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 93. G2.3.1 001 The following conditions are encountered after a surveyof a pump room in the Auxiliary building:

- General area radiation level in the room 70 mrem/hr Radiation level 30 cm from the pump casing 350 mrem/hr

- Contamination levels 800 dpm/1 00cm 2 beta 0 dpm/1 00cm 2 alpha Which ONE of the following identifies the correct radiological postings required to reflect current radiological conditions for this room?

a. Radiation Are v High Radiation Are Radiation Area;. Contamination Are d. High Radiation Area; Contamination Are . G2.3.4 001 Given the following plant conditions:

- A LOCA has occurred and a SAE has been declare The TSC and OSC have been activate To prevent core damage it is recommended that entry be made into Safety Injection Pump Room 1 Projected dose rate in the pump room is 1.16x10 mr/h Duration of the exposure is expected to be 3 minute Which ONE of the following must authorize this exposure?

a. Radcon Manager vb. Site Emergency Director c. Plant Manager d. Site Vice President Page 59

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 95. G2.3.6 001 Given the following plant conditions:

- Unit is operating at 100% powe A release of the Monitor Tank to Cooling Tower Blowdown is planne RM-90-122, Liquid Radwaste Effluent Monitor is inoperabl Which ONE of the following identifies the requirements to make the planned release under these conditions?

a. No release can be made until 1-RM-90-122 is returned to servic b. Sample results must show that activity of the release liquid is <2x1 0-4 microcuries per millilite v Two separate samples must be analyzed and two independent qualifie members of facility staff verify release rate and discharge valve lineu d. The tank must be recirculated for two volumes and a licensed Senior Reactor Operator must confirm release rate and discharge valve lineup.

96. G2.3.11 001 Which ONE of the following identifies the first radiation monitor that should respond to a SGTR and the effect on the monitor?

a. Condenser Vacuum Exhaust Monitor RM-90-119 and the monitor will be automatically isolate v Condenser Vacuum Exhaust Monitor RM-90-119 and the monitor will NOT be automatically isolate c. Steam Generator Blowdown Sample Monitor RM-90-120/121 and the monitor will be automatically isolate d. Steam Generator Blowdown Sample Monitor RM-90-120/121 and the monitor will NOT be automatically isolate Page 60

1- I.........- ......1_11-- .

. ...,.......-.11.-

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 97. G2.4.1 001 Given the following conditions:

- Unit 1 in MODE 1 at 10% RT Turbine at 1800 rpm at no load (generator PCB open).

- Loss of offsite power occur Emergency Diesels fails to re-energize Shutdown Board Which ONE of the following describes the correct usage of the Emergency Instructions?

va. Go directly to ECA-0.0 without entering E- b. Implement ECA-0.0 in conjunction with E- c. Go to ECA-0.0 from E-0 after verifying reactor and turbine tri d. Complete E-0 IMMEDIATE ACTIONS then go immediately to ECA-0.0.

98. G2.4.7 002 Given the following plant conditions:

- Reactor trip and SI have occurre Operators are using E-3, "Steam Generator Tube Rupture", to mitigate the even Which ONE of the following correctly describes the applicability of the low RCS pressure RCP trip criteria on the Foldout Page while performing steps of E-3?

a. RCPs should be tripped during the performance of E-3 ANY TIMF the foldout page low pressure RCP trip criteria are me b. Low RCS pressure RCP trip criteria is not applicable in E-3 EXCEPT as an RNO if excessive RCS inventory loss is also experience v' RCPs should be tripped during E-3 ONLY if the low RCS pressure RCP trip criteria is met before beginning the cooldown and depressurizatio d. RCPs should be tripped during E-3 ONLY if the low RCS pressure RCP trip criteria is met during the performance of step 1 when the operator is specifically required to check the criteri Page 61

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 99. G2.4.19 001 A step in ES-1.3, "Transfer to RHR Containment Sump", reads as follows:

ISOLATE SI pump miniflow:

CLOSE FCV-63- * CLOSE FCV-63-17 * CLOSE FCV-63- The bullets ("-") indicate that:

a. The actions must be performed in the specified sequence, but once a step is in progress, the next step may be starte b. The actions must be performed and completed in the specified sequenc c. These actions should have been completed, so only verification may be require / These actions must all be completed, but any sequence of completion is allowe Page 62

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 100. G2.4.48 001 Following Safety Injection reset during ES-1.1 the following conditions exist:

- Tavg is 560T PRZ level is 45%.

- PRZ pressure is 2230 psi Which ONE of the following describes the PZR heater status the OAC would observe?

a. Control group 1D OF Backup group 1C OF Backup group 1A-A OF Backup group 1B-B OF b. Control group 1D O Backup group 1C OF Backup group 1A-A OF Backup group 1B-B OF Vc. Control group 1D OF Backup group 1C O Backup group 1A A OF Backup group 1B-B OF d. Control group 1D OF Backup group 1C OF Backup group 1A-A O Backup group 1B-B O Page 63

U.S. Nuclear Regulatory Commission Site-Specific Written Examination Applicant Information Name: Region: /il/ Il I IV Date: 01/26/2001 Facility/Unit: Watts Bar Unit 1 License Level: RO / (SRO Reactor Type: W / CE / BW / GE lStartTime: IFinish Time:

Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. The passing grade requires a final grade of at least 80.00 percent. Examination papers will be collected five hours after the examination start Applicant Certification All work done on this examination is my own. I have neither given nor received ai Applicant's Signature Results

_

l VwIo ExLrni,;cV Evam ,i,-~II Points Applicant's Score Grade Percent Applicant's

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION NAME SSN _ _

1. 0000 1 (0(00 ( 35. (0(000 19. 0000 3 (0000 3.(i)(i)(i)(i)

20. 0000@ 3 . 0000 38. 0(00 4.(D(D(DQ 7. 0000 22. 0000 39 (0000 2 . 0000

. e(D()(DO 2 (i)00@

250000@ 4 .0000 26. (000 4 . 0000 2 . 0000D@

11.0000e 2 . 0000 12. Q (0 (00( 2 (000 46. 0000 1300 (0(0(i) 3 (00(0)N 47 @(i)(i)0 1 . 0000@ 48 0000 15. 0 (000 32. 0000 49. (0000@

16. 0 000 3 . 0000 17. 0000 34. 0000D@ 5 Page 1

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATORt NRC EXAMINATION NAME SSN

.

52. (0(0(i0 6 . 0000 5 . 0000 87. (0000 54. (00(00(D() 71. 0000 88. 0000 5 . 0000 89. 0000 5 . 0000 90. 0000 57. 0D00 74. 0000 91. 0000 5 (0(00 7 . (0(000@

5 @ 76. 0000 93. 0000 60. 0000 07 A000 94. (0000 61. 0000 780 (0(00@ 95 (i)(i)(i)(i)

62. 0000 79. 0000@ 9 . 0000 80. 0000 97 (0000 64000D 810000 @ 98. 0000 6 . 0000 99. 0000 66. 0000 8 (0000 67. 0000 84. 0000 6 . 0000 Page 2

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 1. Given the following plant conditions:

- Reactor is at 75% with a power increase in progress using control rod The OAC determines that Control Bank D rod H-12 is not moving and is 14 steps below the other rods in D ban Crew is performing AOI-2, "Malfunction of Reactor Control System" to realign control rod H-12 with the ban Which ONE of the following describes how control rod H-12 will be realigned to control bank D and how control bank insertion limit will change following the realignment?

a. Control Bank D will be realigned to control rod H-12 and control bank D insertion limit will be highe b. Control Bank D will be realigned to control rod H-12 and control bank D insertion limit will be lower c. Control rod H-12 will be realigned to Control Bank D and control bank D insertion limit will be lowe d. Control rod H-12 will be realigned to Control Bank D and control bank D insertion limit will be highe Page 1

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 2. Given the following conditions:

- A large break LOCA occurred

- Operators have just completed swapover to Containment Sump

- A loss of offsite power occurs Which ONE of the following describes the actions required for this condition?

a. Pull to lock Si pumps and CCPs until the RHR pumps have been restarted after the shutdown boards are reenergize b. Pull to lock the CCPs until the RHR pumps are restarted after the shutdown boards are reenergize c. Ensure both RHR pumps are started by the blackout sequencer after the diesel generators reenergize the shutdown boards then restart the Si pump d. Ensure all ECCS pumps are started by the blackout sequencer when the diesel generators reenergize the shutdown boards.

3. Given the following plant conditions:

- Reactor power is stable at 30%

- Loop 1 RCP trips Assuming reactor power remains constant, core exit temperature will:

a. increase, then stabilize at a higher valu b. decrease, then stabilize at a lower valu c, increase, then reoturi to the origirnal steady-state valu d. decrease, then return to the original steady-state valu Page 2

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 4. Given the following conditions:

- Unit at 60% powe Confirmed Loop 1 RCP shaft vibration of 25 mil Which ONE of the following statements is correct per AOI-5, "Unscheduled Removal of One RCP", regarding the sequence of actions?

a. RCP should be tripped prior to the reactor trip to minimize pump damag b. The reactor should be tripped prior to tripping the RCP to prevent pressurizer level from dropping below 17%.

c. RCP should be tripped prior to the reactor trip to prevent Reactor Coolant Bus voltage from dropping and tripping additional RCP d. The reactor should be tripped prior to tripping the RCP to prevent an automatic trip and an unnecessary challenge to a safety syste . Given the following plant conditions:

- Unit was operating at 58% powe Problems with #4 RCP required the pump to be shut down in accordance with AOI-5, "Unscheduled Removal of One RCP".

AOl-5 requires the plant to be in which ONE of the following conditions for restart of #4 RCP?

a. <P-1 b < P-9 < P- d. Mode Page 3

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 6. Given the following plant conditions:

- Unit has experienced a Reactor tri The crew transitions to ES-0.1, Reactor Trip Repons RCS temperature has dropped to 5420 Step 2 RNO states:

- REFER to AOI-34, Immediate Boratio As the procedure reader, which ONE of the following is the proper method of applying this step?

a. Transition from ES-0.1 to AOI-34 and when AOI-34 is completed return to ES-0. b. Read steps from AOI-34 in conjunction with ES-0.1 on a not to interfere basi c. Continue in ES-0.1 and assign AOI-34 to another control room team membe d. Assign ES-0.1 to another control room team member and transition to AOI-3 Page 4

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 7. Given the following plant conditions:

- Plant was operating at 100% power when a Main Feedwater pump trip resulted in a turbine runbac All systems in automatic and responded as expected to stabilize the plan Control rods inserted beyond the Lo-Lo Rod Insertion limit Operators implemented A01-34, "Immediate Boration", in accordance with the AR Which ONE of the following indicates the final, stable plant conditions AFTER completion of the boration as compared to those PRIOR to the boration?

Reactor Power Rod Position Tavq Same Higher Higher Same Higher Same Lower Lower Same Lower Lower Lower Page 5

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 8. Given the following plant conditions:

- ATWS without Safety Injection has occurre Crew has implemented FR-S.1, "Nuclear Power Generation/ATWS", and currently performing step 4 to borate the RC Which ONE of the following identifies the correct Operator action that must be taken in order to align charging pump suction?

a. CLOSE LCV-62-132 and 133, VCT outlet isolation, then OPEN LCV-62-135 and 136, RWST supply to charging pump suctio b. OPEN LCV-62-135 and 136, RWST supply to charging pump suction, then CLOSE LCV-62-132 and 133, VCT outlet isolatio c. Verify LCV-62-135 and 136, RWST supply to charging pump suction AUTO OPEN, then CLOSE LCV-62-132 and 133, VCT outlet isolatio d. Verify LCV-62-135 and 136, RWST supply to charging pump suction and LCV-62-132 and 133, VCT outlet isolation AUTO OPE . Given the following plant conditions:

- The reactor trips due to a loss of all AC power (Station Blackout)

- The crew is currently performing ECA-0.0, Loss of Shutdown Powe Non-essential 125V and 250V battery loads are being shed per AOI-40, Station Blackou The power loss occurred at 0938 hour0.0109 days 0.261 hours 0.00155 weeks 3.56909e-4 months Which ONE of the following is the latest time that AC. power must be restored to ensure the station batteries are not fully discharged?

a. 1138 b. 1338 c. 1538 d. 1738 Page 6

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 10. Given the following plant conditions:

- Plant was operating at 100% power when a loss of offsite power occurre Emergency Diesel Generators (D/G) failed to start and tie on to their associated 6.9KV Shutdown Board The operating Crew implemented ECA-0.0, "Loss of Shutdown Power".

- The OAC has started 1A-A D/G and re-energized it's associated Shutdown Boar Annunciator, "LOGIC PNL 1A-A LOAD STRIP RELAYS OUT OF SYNC OR UV TEST" (BO-AN alarm), is still LI Which ONE of the following actions is required before this annunciator may be reset?

a. Reset D/G 1A-A 86 LOR rela b. Reset 1A-A Shutdown, Board BOX and BOY relay c. Transfer 1A-A Shutdown Board to it's normal power suppl d. Shutdown all the D/Gs that are not tied to associated Shutdown Boar Page 7

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 11. Given the following plant conditions:

- Plant is operating at 100% powe A loss of 120V AC Vital Instrument Power Board 1-l occurre The crew implements AOI-25.01, "Loss of 120V AC Vital Instrument Power Board 1-l".

Which ONE of the following identifies the train selector switches that must be selected for automatic control of feedwater and which loop 1 feedwater/steam flow indications are available?

Feedwater/Steam Flow Feedwater/Steam Flow Selector Switches Indications A train Channel I A train Channel II B train Channel I B train Channel II 12. Given the following plant conditions:

- Plant is operating a 100% powe Plant systems aligned and operating normall Annunciator, CCS HX A 1-RM-90-123 LIQ RAD HIGH, is in alar Which ONE of the following lists the type and source of radiation sensed by the radiation monitor that is in alarm?

a. Gamma; Thermal Barrier leakag b. Beta; Thermal Barrier leakag c. Gamma; RCP motor cooler leakag d. Beta; RCP motor cooler leakag Page 8

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 13. Which ONE of the following conditions concerning the Personnel Airlock would exceed a Limiting Condition for Operation and require entering an Action Statement of Technical Specifications?

a. The lower containment airlock fails its LLRT while control rod unlatching is in progres b. Welding cables are laid through both lower containment airlock doors during RCS fill and vent at the end of an outag c. The lower containment airlock door interlocks are defeated while reactor vessel head is being tensione d. The outer and inner doors are opened simultaneously during a normal cooldown prior to aligning RHR to the RC . Which ONE of the following is the reason S/Gs are depressurized to atmospheric pressure during the performance of FR-C.1, "Response to Inadequate Core Cooling"?

a. Reduces RCS temperature to increase the thermal driving head for natural circulatio b. Reduces RCS temperature to collapse any steam voids in the upper part of the vesse c. Reduces RCS pressure which prevents the formation of superheated steam in the core as water exceeds the critical poin d. Reduces RCS pressure to allow the ECCS accumulators and RHR pumps to inject water to the RCS, Page 9

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 15. Given the following plant conditions:

- Inadequate core cooling conditions exist

- Crew is performing FR-C.1, Inadequate Core Cooling Which ONE of the following sets of actions states the proper sequence of the major action categories to be performed for removing decay heat from the core?

a. Rapid secondary depressurization; reinitiation of high head safety injection; RCP restart b. Reinintiation of high head safety injection; rapid secondary depressurization; RCP restart c. Rapid secondary depressurization; RCP restart; reinitiation of high head safety injection d. RCP restart; rapid secondary depressurization; reinitiation of high head safety injection

.16. Which ONE of the following correctly describes the indication on the main steam line radiation monitors when the MR/HR AUTO pushbutton is lit on the RM-23 readout module?

a. Indicates low range output onl b. Indicates high range output onl c. Automatically switches between the low and high range outputs every 45 seconds d. Automatically switches between low and high range output based upon activity level in order to maintain accurate indicatio Page 10

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 17. Once an operating crew has entered the EOP network, which ONE of the following is the earliest that a transition may be made to ES-0.0, "Rediagnosis"?

a. AFTER transition from E-0 and safety injection initiate b. AFTER transition from E-0 and NO safety injection initiate c. BEFORE transition from E-0 and safety injection initiate d. BEFORE transition from E-0 and NO safety injection initiate . Given the following conditions:

- Main steam line break has occurred outside containment, resulting in a reactor trip/safety injection (SI).

- MSIV closure stopped the steam releas SI termination criteria was met and the crew is currently terminating the SI per ES-1.1, "SI Termination."

Which ONE of the following combinations of parameters would require an immediate reinitiation of safety injection?

Maximum RCS RCS PZR CTMT Press Subcooling Pressure Level psig 750 F Stable 18% psig 720F Decreasing 20% psig 87 0 F Deccreasing 34% psig 600F Stable 24%

Page 11

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 19. Given the following plant conditions:

- Operators are responding to a large break LOCA and have determined that degraded core cooling conditions exis The crew has implemented FR-C.2, "Degraded Core Cooling".

- Preparations are in progress to depressurize all intact S/Gs to atmospheric pressure in accordance with FR- Which ONE of the following is the reason the procedure directs all RCPs be stopped prior to performing the depressurization?

a. Reduces the core AP which will enhance the ability of the RHR pumps to inject into the cor b. Minimizes heat input to the S/Gs allowing them to depressurize faste c. Limits heat removal requirements to the core decay heat onl d. Anticipates a loss of RCP #1 seal AP requirement . Given the following plant conditions:

- A large break LOCA has occurred that resulted in saturated core cooling condition RWST level is 28%

- Crew is performing step 4 of FR-C.3, Saturated Core Cooling to establish Si pump valve alignmen Which ONE of the following identifies valves that should be verified CLOSED during performance of this step?

a. FCV-63-6, 7 and 177, St pump and Charging pump suction from RH b. FCV-63-47 and 48, Si pump suction valves c. FCV-63-152 and 153, SI pump cold leg injection cross-tie valves d. FCV-63-3, 4 and 175 Si pump mini-flow valves Page 12

I --

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 21. Given the following plant conditions:

- Reactor trip has occurred in conjunction with a loss of offsite powe The operating crew is currently performing steps of ES-0.2, "Natural Circulation Cooldown".

- Boration to Cold Shutdown boron concentration of 870 ppm has been complete Chemistry reports the following boron concentrations:

850 ppm in the pressurize ppm in the RCS cold leg Which ONE of the following explains the difference in the boron concentration between the value calculated for Cold Shutdown and the values reported by Chemistry?

a. Mixing only occurs in the active portions of the RCS cold legs causing RCS boron concentration to be higher than calculate b. The cold legs remain subcooled during this event which causes boron to concentrate in these area PZR spray valves failed to automatically open on increasing pressure to ensure mixing between the cold legs and PZ d. Due to the loss of power the PZR heaters are unavailable to promote mixing between the loops and the PZ Page 13

WATTS BAR NUCLEAR PLAN T SENIOR REACTOR OPERATOR NRC EXAMINATION 22. Given the following plant conditions:

- Reactor trip occurred with subsequent loss of RCP Operators have implemented ES-0.2, "Natural Circulation Cooldown".

- A cooldown rate of 250F/hour has been establishe RCS depressurization has been initiated while maintaining subcooling

> 165 0 Operators are monitoring PZR level and RVLIS for void formatio The OAC observes that loss of inventory in the Condensate Storage Tank is imminen Which ONE of the following describes the appropriate procedural actions?

a. Stop the cooldown and remain in ES- b. Raise the cooldown rate and remain in ES- c. Transition to ES-0.3, "'Natural Circulation Cooldown With Steam Voids in Vessel (With RVLIS) and lower the cooldown rat d. Transition to ES-0.3, "Natural Circulation Cooldown With Steam Voids in Vessel (With RVLIS) and raise the cooldown rat Page 14

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 23. Given the following plant conditions:

- Unit was at 100% powe A main steam line break occurred in the Turbine Buildin Operators were unable to close the MSIVs and transitioned to ECA-2.1, Uncontrolled Depressurization of All Steam Generator Si termination steps are in progres Loop 3 MSIV is closed locall The CRO observes the #3 SG pressure increasing slowl Which ONE of the following actions should be performed?

a. Transition to E-2, "Faulted SG Isolation".

b. Transition to ES-1.1, "SI Termination".

c. Remain in ECA-2.1 until RHR is in servic d. Remain in ECA-2.1 until SI is terminate . Which ONE of the following describes the reason for tripping all RCPs during the performance of FR-Z.1, "High Containment Pressure"?

a. Removes heat transferred to the Containment atmosphere from the RCP motor b. Prevents depletion of primary inventory out of the break during a small LOC Containment Isolation Phase B isolates cooling water to the RCPs and thermal barrier d. Removes additional energy to the RCS during a break and subsequent release to containmen Page 15

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 25. Given the following plant conditions:

- Reactor was at 100% powe A rod control system failure causes all shutdown rods to fall into the cor Power Range Indicators are at 6% and slowly decreasing (-0.1 DPM SUR).

- E-0, "Reactor Trip or Safety Injection" is implemente Operators actuate both manual Rx trip handswitche Both Rx trip breakers remain close Which ONE of the following identifies the correct procedural response?

a. Go to step 2 of E-0, "Reactor Trip or Safety Injection".

b. Hold at step 1 of E-0 until Rx trip breakers are open locall c. Transition to and perform FR-S.1, "Nuclear Power Generation/ATWS", then transition back to E- d. Transition to FR-S.1, "Nuclear Power Generation/ATWS", and transition back to E-0 when control rods are fully inserted into the cor Page 16

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 26. Given the following plant conditions:

- Unit 1 operating at 22% powe Reactor Trip Breakers "A" & "B" close Bypass Breaker B is racked in and close "B" Train SSPS Input Error Inhibit Switch is in INHIBIT for surveillance testin Which ONE of the following describes the response of the Reactor Trip and Bypass Breakers if RCS pressure drops below the Low Pressure Reactor trip setpoint with no operator action?

a. Reactor Trip Breakers "A" & "B" open, Bypass Breaker "B" open b. Reactor Trip Breaker "A"opens and "B" remains closed, Bypass Breaker "B" remains close c. Reactor Trip Breaker "B" opens and "A" remains closed, Bypass Breaker "B" open d. Reactor Trip Breaker "A" opens and "B" remains closed, Bypass Breaker "B" open . Given the following plant conditions:

- Unitwas at 100% powe All systems operating in automatic and all plant parameters at their normal value PCV-68-340 failed partially ope Which ONF of the following identifies the approximate maximum expected temperature of the steam entering the PRT if the PRT pressure does not exceed 45 psig?

a. 2280 b. 250 0 c. 2750 F d. 2900 F Page 17

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 28. Given the following plant conditions:

- The plant is at steady state 100% power equilibrium xenon with all control systems in automati Pressurizer level control is transferred to MANUAL and level is slowly increased to 75% and maintaine Which ONE of the following describes the PZR pressure response?

a. Pressure is essentially unaffecte b. Pressure will continuously cycle between 2235 and 2260 psi c. Pressure will increase until the spray valves open and control pressure at 2260 psi Pressure will increase until the spray valves open and slowly return pressure to steady state 2235 psi . Given the following plant conditions:

- The Unit is at 100% load,

- Pressurizer pressure channel selector switch, 1-XS-68-340D, is in the PT-68-340 & 334 positio Instrument Maintenance has 1-PT-68-323 (CH ll) OOS for a loop calibratio PZR Pressure transmitter, 1-PT-68-334 (CH II) has just failed AS I The operating crew implements AOI-18, "Malfunction of Pressurizer Pressure Control System".

Which ONE of the following channels will be selected or.n -XS-68-340D and position of the master controller following completion of AOI-1 8, Malfunction of Pressurizer Pressure Control System?

a. Channel I and Ill selected with 1-PIC-68-340A in AUT b. Channel I and III selected with 1-PIC-68-340A in MANUA c. Channel I and IV selected with 1-PIC-68-340A in AUT d. Channel I and IV selected with 1-PIC-68-340A in MANUA Page 18

- ;I I - WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 30. Given the following plant conditions:

- The Unit is in MODE Source Range Monitor (SRM) NI-132 has failed LOW resulting in a loss of the audio count rate signa WHICH ONE of the following describes the actions necessary to restore the audio count rate signal to the control roo a. Place the audio count rate CHANNEL SELECTOR switch on the front of the Audio Count Rate Drawer to the SR N31 positio b. Place the audio count rate CHANNEL SELECTOR switch on the front of the Audio Count Rate Drawer to the SR N32 positio c. Place the AMPLIFIER SELECT switch on the rear of the audio count rate drawer assembly to the Al positio d. Place the AMPLIFIER SELECT switch on the rear of the audio count rate drawer assembly to the A2 positio Page 19

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 31. Given the following plant conditions:

- A Reactor startup in progres Reactor power is stable at 2 x 10-2% power on the Intermediate Range

- Intermediate Range channel N-135 was declared inoperable and removed from service per AOI-4, "Nuclear instrumentation Malfunction".

Which ONE of the following describes the plant response if an l&C Technician mistakenly removes the control power fuses for N-1 35 during troubleshooting activities?

a. The trip bistable deenergizes and a reactor trip occurs because power is below P-1 b. The trip bistable deenergizes, however NO trip occurs because N-135 is bypasse c. The trip bistable energizes, however NO trip occurs because N-135 is bypasse d. The trip bistable energizes and a reactor trip occurs because power is below P-1 . Given the following plant conditions:

- Steam Generator Tube Rupture has occurre Crew has implemented E-3, "Steam Generator Tube Rupture".

- The operators have completed cooldown to target incore temperature of 480° Which ONE of the following identifies the pressure that steam dumps will be set to control RCS temperature at 4800F? psi b. 550 - 555 psi psi psi Page 20

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 33. Given the following plant conditions:

- AUO reports Emergency Diesel Generator (D/G) 1A-A has lost 125V DC control power from it's associated Diesel Battery Distribution Panel

- D/G 1A-A is NOT runnin Which ONE of the following describes how this loss of DC control power would affect D/G operation?

a. D/G would start in response to an automatic or manual start signa b. D/G cannot be started by automatic or manual start signa c. D/G can only be started manually from local control pane d. D/G can only be started manually from the MCR panel.

34. Given the following conditions:

- Unit at 100% powe The Control Room Air Intake radiation monitor, 1-RM-90-125, alarm Which ONE of the following describes the response of the Control Building Ventilation System?

a. Pressurization fans inlet dampers CLOSE Emergency Pressurization fans inlet dampers OPEN Air cleanup fans inlet dampers OPEN b. Pressurization fans inlet dampers OPEN Emergency Pressurization faris inlet dampers CLOSE Air cleanup fans inlet dampers OPEN c. Pressurization fans inlet dampers CLOSE Emergency Pressurization fans inlet dampers OPEN Air cleanup fans inlet dampers CLOSE d. Pressurization fans inlet dampers OPEN Emergency Pressurization fans inlet dampers CLOSE Air cleanup fans inlet dampers CLOSE Page 21

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 35. Given the following plant conditions:

- A Gas Decay Tank release in progress with ABGTS running for dilution air flo A leak occurs on the waste gas compressor which results in a gas release to the Auxiliary Buildin RE-90-1 01, Auxiliary Building Vent Monitor, is in alar Which ONE of the following indicates the effect this leak will have on the plant?

a. Gas Decay Tank release will be terminated; ABGTS will be stoppe b. Gas Decay Tank release will be terminated; ABGTS will continue to ru c. Gas Decay Tank release will continue; ABGTS will be stoppe d. Gas Decay Tank release will continue; ABGTS will continue to ru . Following an automatic start due to low instrument air pressure, which ONE of the following describes what will cause Aux Air Compressors to shutdown?

a. Running unloaded for 5 min b. Running unloaded for 10 min c. Low crankcase oil pressur d. High discharge air temperatur Page 22

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 37. Given the following plant conditions:

- A small break LOCA has occurred

- 1B-B CCP and SIP failed to start and could not be started manuall E-1 is completed and transition to ES-1.2, "Post LOCA Cooldown and Depressurization", mad .9kV Shutdown Board 1A-A is de-energized due to a fault

- The following conditions are noted by the OAC

- RCS pressure is 1600 psig

- Containment pressure is 6 psig Which ONE of the following describes the action that should be taken and the basis for that action?

a. All RCPs should be stopped to limit heat input during the RCS cooldow b. All RCPs should be stopped because Phase B isolation has occurre c. All RCPs should NOT be stopped because no CCP or SIP is injecting into the RC d. All RCPs should NOT be stopped because the RCS pressure is above 1500 psi . Which ONE of the following is the significance of draining the SG U-tubes and blowing the inverted "loop seal" during a cold leg small break LOCA?

a. A steam vent path is established from the core to the break location and mass loss from the system is decrease b. Core cooling will be lost after the loop seal is blown due to increased injection flow being diverted to the break locatio c. RCS pressure control will be lost resulting in a challenge to Pressurized Thermal Shock limit d. The heat sink effect of the water in the "crossover" leg is lost when the loop seal is lost resulting in a degraded core coolin Page 23

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 39. Given the following plant conditions:

- Reactor trip and safety injection occurre The crew implemented FR-H.1, "Loss of Secondary Heat Sink" due to heat sink red pat Operators are preparing for main feedwater startu Which ONE of the following lists the minimum actions required to reset Main Feedwater Pump 1A?

a. Reset safety injection and cycle reactor trip breaker b. Reset safety injection and reset feedwater isolation signa c. Cycle the reactor trip breakers and reset feedwater isolation signa d. Reset safety injection, cycle reactor trip breakers, and reset feedwater isolation signal.

40. Given the following plant conditions:

- Reactor trip and Si occurred at 0200 due to a small LOC At 0300 the crew transitioned to ECA-1.1, "Loss of RHR Sump Recirculation", due to the failure of both RHR pump Crew has reduced ECCS flow to 1 SIP and 1 CCP per ECA- At 0500 the crew is performing step 17 RNO to establish the minimum required ECCS flow to remove decay hea Using Figure 1 from ECA-1.1, which ONE of the following flow rates would satisfy the intent of the RNO?

a. 180 gpri b. 210 gpm c. 240 gpm d. 280 gpm Page 24

A - I;~: ;: - - i ~-- " r- ~ ; .. . -' *'. 1 V FIGURE 1 8 8 0 8 8 I I N 1* O T= -"

_ I I I I I I III I I

_ I _- _ I I I I I I I l E

I-w __ _ _ _ P 4 1 og A-44 _ _- a ci) I I I I V- I

/

. o 2 0 t--I-It-1I- -

'IF I 0 = -'.

1'.4 .

a a

._

V

- .L - -- 4 - 4---4-4 t-

.E E 7 r - I I ?I

8 8 8 8 8 8cm 8_-

wdS - ae-j molj ECA111 ECAll 03/05/99 27 of 30

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 41. Given the following plant conditions:

- The Unit is at 100% powe PZR level channel 1-LT-68-335 has failed HIGH

- Operating crew has addressed the failure per AOI-20, Malfunction of Pressurizer Level Control In response to the failure, which ONE of the following will most likely require a safety evaluation?

a. A non-intent procedure change to AOI-20 is submitted to clarify a ste b. A special test is performed on PZR level channel 1-LT-68-335 to determine automatic action c. A surveillance is required to be performed on channel 1-LT-68-339 while 1-LT-68-335 is out of servic d. Post maintenance test is required to be performed on 1-LT-68-335 prior to returning channel to service.

42. Given the following plant conditions:

- Plant is in Mode 6 with core offload in progres The fuel assembly being withdrawn into the refueling mast is dropped onto the lower core plat The refuel crew observes bubbles coming from the dropped fuel assembl Which ONE of the following identifies the most likely indications/actions as a result of this incident?

a. Upper Cntmt area radiation monitor, 1-RM-90-59, alarms onl b. Spent Fuel Pit area radiation monitor, 1-RM-90-102, alarms onl c. Shield Bldg vent monitor, 1-RM-90-400, initiates Containment Vent Isolatio Spent Fuel Pit area radiation monitor, 1-RM-90-1, initiates Auxiliary Bldg Isolatio Page 25

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION for 43. Which ONE of the following describes why the baseline count rate used developing the 1/M plot must be re-calculated following movement of any source bearing fuel assembly ?

a. Re-verify the operability of the source range instrument b. Ensures an accurate 1/M plot to monitor subcriticalit c. Determine adequate shutdown margin during refuelin d. Readjust the setpoint for the High Flux at Shutdown alar . Given the following plant conditions:

- The Unit is at 1% power after an extended shutdow Core burnup is 2000 MWDIMT RCS boron concentration is 1000 pp Control rods at 175 steps

- The STA has determined that 236 pcm of reactivity must be added to increase power to 10%.

which Using the attached NUPOP curve and assuming no control rod movement, the ONE of the following identifies the final boron concentration of the RCS after reactivity change has been made?

a. 966 ppm b. 969 ppm ppm d. 1034 ppm Page 26

WESTINGHOUSE PROPRIETARY CLASS 2C

- .

U

5-71 I I I Es4 - .

H E

- .0i II i 1111111 I

- ~ .. ~ ~ 4~I~ 4Afl'¶ i~lflBOL l ~l

~U

~uu .LUU .~UU L MOL

_91 'A U 0uu 40U ouu 800 1QUU .lAVU 14UU Lwww our WVUW 100 BORON CONCENTRATION (PPM)

Figure 6-22 Differential Boron Worth Versus Boron Concentration at BOL, MOL, and EOL, HZP, With No Xenon WCAP-15562 (Rev. 0) Bumup Dependent Parameters 6 - 27

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 45. Unit is operating at 100% power with all systems in their normal configuration, when Auctioneered High Tavg fails LO Which ONE of the following describes the plant response?

a. Control rods will step in; Charging Flow Control valve, 1-FCV-62-93, open b. Control rods will step out; Charging Flow Control valve, 1-FCV-62-93, close c. Control rods will not move; Charging Flow Control valve, 1-FCV-62-93, open d. Control rods will not move; Charging Flow Control valve, 1-FCV-62-93, closes.

46. Given the following plant conditions:

- Unit is operating at 20% power with a startup in progres A problem develops which requires removal of Loop 1 RCP

- At 1101, using ICS, you determine the following conditions exist:

- Motor Bearing Temperature is 180'F and increasing at 1 F/mi *Motor Winding Temperature is 315'F and stabl Pump Bearing Temperature is 220 0 F and increasing at 1 F/mi Which ONE of the following correctly describes when loop 1 RCP must be removed from service and the effects on loop 1 steam flow when the RCP is stopped?

a. 1101; RCS loop 1 hot leg temperature decreases; Steam flow decrease b. 1101; RCS loop 1 hot leg temperature increases; Steam flow decrease c. i 106; RCS loop 1 1lot leg temperature decreases; Sttarn flow increase d. 1106; RCS loop 1 hot leg temperature increases; Steam flow increase Page 27

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERA`OR NRC EXAMINATION 47. Given the following plant conditions:

- The Unit is operating at 100% powe All systems are operating norma Annunciatior "RCP #1 Seal Outlet Temp Hi" alarm actuate The operator verifies that ALL RCP seal temperatures are 180'F risin Which ONE of the following is the most probable cause of this alarm?

a. The Charging Pump suction has swapped to the RWS b. The operator has just placed Excess Letdown in service at maximum flow rat c. The Letdown Heat Exchanger temperature control valve 1-TCV-70-192 has failed close d. A loss of control air to charging flow control valve 1-FCV-62-93.

48. Given the following conditions:

- Reactor power 35%.

- Turbine load 32%

- Control Rods are in AUTOMATI CVCS Mixed Bed A was placed in service resulting in a T-avg increase to 571O Which ONE of the following describes the response of the rod control system?

(assume no operator action)

a Rods will step in at 8 steps per minut b. Rods will step in at 40 steps per minut c. Rods will step in at 64 steps per minut d. Rods will step in at 72 steps per minut Page 28

---

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 49. Given the following plant conditions:

- The unit is at 100% power with 1A-A CCP is in operatio A loss of offsite power occurs

- All appropriate loads sequence onto the Shutdown Boards

- The crew has implemented E-0, "Reactor Trip or Safety Injection"

- While the immediate actions are being completed, a safety injection signal (SI) is receive Which ONE of the following describes the response of the Centrifugal Charging Pumps (CCPs)?

a. 1A-A CCP load sheds on the Si signal, and both CCPs auto sequence on the shutdown board b. 1A-A CCP load sheds on the Si signal, and must be restarted manually by the operato A-A CCP does not load shed on the SI signal, and 1B-B CCP auto sequences on the shutdown board d. Both CCPs remain energized and running following the SI signa Page 29

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 50. Given the following:

- 1A-A and 1B-B SI Pump breakers are "Racked In".

- A fuse blows in the NORMAL DC Trip circuit for the 1A-A SI pum A safety injection (SI) actuation occur Which ONE of the following describes the response of the SI Pumps to the SI signal?

a. 1B-B SI Pump will auto start, but 1A-A SI Pump will not auto start until the control power supply is transferre b. 1B-B SI Pump will auto start, but 1A-A SI Pump will not auto start and must be started from the MCR handswitc c. Both SI Pumps will auto start, but the lA-A SI Pump cannot be stopped from the MC d. Both SI Pumps will auto start, but the 1A-A SI Pump cannot be stopped mechanically at the breake . Which ONE of the following describes the logic for Safety Injection (SI) actuation handswitches and reset pushbuttons?

a. Each actuation handswitch initiates both trains of S Each reset pushbutton resets both trains of S b. Each actuation handswitch initiates both trains of S Each reset pushbutton resets only it's associated train of S c. Each actuation handswitch initiates only it's associated train of S Each reset pushbutton resets only it's associated train of S d. Each actuation handswitch initiates only it's associated train of S Each reset pushbutton resets both trains of S Page 30

q 1, i r, WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 52. Given the following plant conditions:

- Unit is operating at 75% power

- A plant transient has resulted in a xenon oscillation

- Control rods are currently at 216 steps on D bank Which ONE of the following is the effect of the xenon oscillation on NIS and the action required to dampen the oscillation?

a. The oscillation affects AFD and is dampened by inserting control rods at its most positive pea b. The oscillation affects AFD and is dampened by inserting control rods at its most negative pea c. The oscillation affects QPTR and is dampened by dropping turbine load at its highest valu d. The oscillation affects QPTR and is dampened by dropping turbine load at its lowest valu Page 31

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 53. Given the following plant conditions:

- A small break LOCA has occurre The crew responded lAW EOPs and tripped the RCPs when require The crew is currently in ES-1.2, "Post LOCA Cooldown And Depressurization".

- RCS pressure is 1490 psi Wide range Tc's are 5050 F and decreasing slowl Wide range Th's are 5150 F and decreasing slowl Core exit thermocouples (CETC) are 551OF and stabl Containment pressure is 1.5 psi SG levels are being maintained at 38%.

- SG pressures are 715 psig and decreasing slowl Which ONE of the following describes the status of natural circulation for the existing plant conditions?

a. Cannot be assured, since there is inadequate sub-coolin b. Cannot be assured, since SG parameters are not satisfie c. Cannot be assured, since CETCs are not decreasin d. Exists since all natural circulation criteria are me Page 32

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 54. Given the following plant conditions:

- Reactor trip & Safety Injection occurred due to Large Break LOC Containment 0B isolation has occurre All systems responded normall Which ONE of the following describes the response of the Lower Compartment Coolers when 0B is reset?

a. Fans in A-P-AUTO star Cooler ERCW isolation valves ope b. Fans in A-P-AUTO star Cooler ERCW isolation valves remain close Fans in A-P-AUTO remain of Cooler ERCW isolation valves ope d. Fans in A-P-AUTO remain of Cooler ERCW isolation valves remain closed.

55. Given the following plant conditions:

- Main Steam Line Break occurred inside containment causing a reactor trip and safety injectio Operators have implemented the EOP Containment pressure is 3.2 psig and droppin OAC observes the "INSTR ROOM COOLER A/B FLOW LOW" alarm LI Which ONE of the following ESFAS signals caused the Incore Instrument Room Cooling fans, circ pump, and chiller to shut down?

a. Containment vent isolation (CVI).

b. 0A containment isolatio c. 0B containment isolatio d. Aux. Building Isolation (ABI)

Page 33

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 56. Given the following plant conditions:

- Large break LOCA has occurred causing a reactor trip and safety injectio OAC observes annunciator "Glycol Exp Tank Level Hi/Hi-Hi is LI Which ONE of the following describes the most likely reason the annunciator is LIT?

a. 0A closes the glycol containment isolation valves; glycol inside containment heats up and relief valves on the containment side of the isolation valves relieve glycol into the glycol expansion tan b. 0A closes the glycol containment isolation valves; glycol inside containment heats up and expands into the glycol expansion tan B closes the glycol containment isolation valves; glycol inside containment heats up and relief valves on the containment side of the isolation valves relieve glycol into the glycol expansion tan B closes the glycol containment isolation valves; glycol inside containment heats up and expands into the glycol expansion tank.

57. Given the following plant conditions:

- Large break LOCA has occurre Swapover to containment sump was unsuccessful and crew has implemented ECA-1.1, "Loss of RHR Sump Recirculation".

- Containment Spray has been aligned to the containment sum Unit Supervisor has directed the OAC to initiate makeup to the RWS Which ONE of the following lists the preferred makeup source to the RWST?

a. Transfer water from the Holdup Tan b. Transfer water from the Spent Fuel Pi c. Align Containment Spray to the RWS d. Align CVCS blender to makeu Page 34

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 58. Given the following conditions:

- Unit is operating at 100% powe FCV-2-35, Condensate Short Cycle valve fails OPEN Which ONE of the following describes the effect on reactor power and the correct operator response?

Reactor power will:

a. Increase; Borate the RC b. Increase; Reduce turbine loa c. Decrease; Dilute the RC d. Decrease; Raise turbine load.

59. Which ONE of the following describes the decay heat sources and design basis for the Auxiliary Feedwater (AFW) System during a loss of offsite power?

a. Prevents relief through the. PZR safety valves by removing core decay heat only. f b. Prevents relief through the S/G safety valves by removing core decay heat onl c. Prevents relief through the PZR safety valves by removing core decay heat and stored RCS hea d. Prevents relief through the S/G safety valves by removing core decay heat and RCP hea Page 35

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 60. Given the following plant conditions:

- Reactor tripped on lo-lo SG leve All MSIVs are close All feedwater reg and bypass reg valves are close Turbine Driven AFW pump is the ONLY AFW pump runnin All DGs are running unloade Which ONE of the following correctly lists the 125V DC Vital Battery Board(s) that is/are deenergized?

a. Only Board b. Only Board l c. Board I and 1 d. Board I and ll.

61. Given the following plant conditions:

- Unit is at 100% powe "A" Waste Gas Compressor is in servic Pressure in the "in service" Waste Gas Decay Tank (WGDT) is 60 psi No WGDT release is in progress

- The relief valve on the "in service" WGDT begins to experience seat leakag Which ONE of the following will provide the best indication that the relief valve on the WGDT is leaking?

a. Increasing count rates on RM-90-101A, Auxiliary Building Vent Monito b. Increasing count rates on RM-90-400, Shield Building Vent Monito c. FCV 77-119, Plant Vent Flow Control valve, isolates due to high radiatio d. The Waste Gas Vent Header pressure increases causing the Waste Gas Compressor to run continuousl Page 36

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 62. Given the following plant conditions:

- A source check is being performed on Spent Fuel Pool Monitor (RE-90-102).

- Auto Block handswitches are in the OFF positio Which ONE of the following will occur when the control switch is placed in

"SOURCE CHECK"?

a. The fuel handling area ventilation system is diverted to the suction of the EGTS syste b. The green light on the monitor goes out indicating that the monitor is being source checke c. Auxiliary Building Ventilation isolates, but no Auxiliary Building isolation signal is generate d. A Containment Ventilation Isolation signal is generated.

63. Given the following plant conditions:

- The reactor is at 100%. power

- Rod control is in automati Power Range nuclear instrument N-42 fails HIG Which ONE of the following describes the rod control and plant response?

a. Rods move in until the power mismatch rate signal decays, then move out to the original position to correct the temperature erro Rods move in until the power mismatch rate signal decays, then remain at the new position with a reduced T-av Rods move out until the power mismatch rate signal decays, then move in to the original position to correct the temperature erro d. Rods move out until the high power rod block is reached, then remain at the new position with a higher T-av Page 37

WATTS BAN NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 64. Given the following plant conditions:

- Unit was at 100% powe A spurious Safety Injection occur Operators are responding per the EOP network and have just transitioned to ES-1.1, "SI Termination".

- Annunciators "PRT LEVEL HI/LO, PRESS Hi, and TEMP HI" alar Assuming all systems function as designed, which ONE of the following describes the probable cause of this alarm?

a. Pressurizer PORVs, 1-PCV-68-340 and 334, have lifte b. CVCS Letdown Header Relief valve, 1-RLF-62-662 has lifte c. RHR Pump Discharge Relief valve, 1-RLF-63-620, has lifte d. RCP #1 Seal Leakoff Relief Valve, 1-RLF-62-636, has lifted.

65. Given the following plant conditions:

- Operating at 100% powe PZR PORV, PCV 68-340, is leaking throug PRT pressure increases resulting in rupture of the PRT diaphrag What effect will the rupture of the PRT diaphragm have on PRT temperature and leakage through the PORV?

PRT Temp PORV Leakage a Rises Rises Rises Drops Drops Rises Drops Drops Page 38

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 66. Given the following plant conditions:

- Unit is operating at 100% powe PZR PORV testing is in progress

- While Operators are raising PRT level to reduce PRT Oxygen content the PRT PRESS HI alarm annunciate Which ONE of the following automatic actions will occur?

a. The WDS vent header control valve PCV-68-301 will CLOS b. The primary water supply valve, FCV-68-303 will CLOS c. The PRT drain valve to RCDT FCV-68-310 will OPE d. The PRT nitrogen supply isolation valve FCV-68-305 will CLOS . Given the following plant conditions:

- Unit is operating at 100% powe Controlling PZR level transmitter, 1-LT-68-339 failed LO The OAC observes annunciator, "PZR LEVEL HI/LO", LIT with PZR level at 72% and slowly risin Which ONE of the following lists the status of PZR heaters and charging after the failure? (assume NO operator action)

a. All back-up heaters energized; charging flow at minimum of 0 gp b. All back-up heaters energized, charging flow at minimrnu of 35 gp c. All back-up heaters deenergized; charging flow at minimum of 0 gp d. All back-up heaters deenergized; charging flow at minimum of 35 gp Page 39

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 68. Which ONE of the following would result in the OPAT reactor protection trip setpoint being reduced? Consider each parameter independentl a. AT increasin b. Tavg increasin c. PRZ pressure decreasin d. Reactor Power decreasing.

69. Given the following plant conditions:

- The operating crew is responding to a reactor trip due to a loss of 120V AC Vital Instrument Power Bd PZR pressure transmitter 68-334 (Channel 11) failed LO Which ONE of the following describes the plant response?

a. Both trains of SSPS Si master relays would actuate AND both trains of ECCS equipment auto star b. Both trains of SSPS SI master relays would actuate BUT only "B" train ECCS equipment auto star c. Only the "B" train SSPS Si master relays would actuate BUT both trains of ECCS equipment auto star d. Only the "B" train SSPS SI master relays would actuate AND only "B" train ECCS equipment auto star Page 40

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 70. Given the following plant conditions

- Unit is at 100% powe A-A 6.9 KV Shutdown Board is out of service for maintenanc A reactor trip and safety injection (SI) is initiated due to a large break LOC Automatic and manual "B" train Safety Injection fails to actuat With no further operator action, which ONE of the following describes the status of the Emergency Gas Treatment System (EGTS)?

a. Both trains are running b. Only "A" train is running c. Only "B" train is running d. Neither train is running 71. Given the following plant conditions:

- A large break LOCA occurs from 100% powe "B" Hydrogen recombiner is tagged ou "A" Hydrogen Recombiner has been placed in servic Subsequently the "A" Hydrogen Recombiner trips on overcurren Which ONE of the following indicates how the concentration of hydrogen will be controlled inside containment if the "A" Hydrogen Recombiner trips?

a. Containment Purge Supply and Exhaust fans are placed in service to dilute the hydrogen concentration in containment'

b. A continuous vent path is provided that allows hydrogen to vent to the annulus and then be removed by EGT c. Air Return Fans create a mixing effect and the hydrogen igniters will burn hydrogen to maintain it below an explosive concentratio d. Emergency Gas Treatment System will remove hydrogen which collects in the containment dome and discharge to the shield building ven Page 41

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 72. Which ONE of the following describes a feature of the Refueling Machine designed to prevent the accidental release of a fuel assembly?

a. Gripper is mechanically engaged and disengaged by remote operating handle on bridge and requires no power or air to operat b. Gripper requires air to disengage, however a mechanical latch prevents gripper release under load even if air is applie c. Gripper disengages upon loss of air, however a mechanical latch prevents griper release under load even if air is remove d. When gripper is engaged, operators mechanically lock gripper in place with extension shaft which must be unlocked before gripper can release.

73. Given the following plant conditions:

- Core load is in progres A failure of the Reactor Cavity Seal occurre Cavity level is currently el. 748' and dropping slowl Which ONE of the following actions is required per AOI-29, "Dropped or Damaged Fuel or Refueling Cavity Seal Failure"?

a. Align RHR suction to the RWST and discharge to the RCS through the hot leg b. Align CCP suction to RWST and discharge to the RCS through normal chargin c. Start one SI pump in the cold leg injection flowpath for cavity makeu d. Aligrt Refueling Water Purification pumps suction to RWST and discharge directly torefueling cavit Page 42

WATTS BAR NUCLEAR PLANT SED.!IOR REACTOR OPERATOR NRC EXAMINATION 74. Given the following plant conditions:

- Startup in progres Operators are warming the main steam lines using the MSIV bypasse The OAC observes that the RCS has cooled down 108'F in the past hou The CRO observes that the main steam lines have heated up 102 F in the past hou Which ONE of the following indicates the actions that should be taken by the operators and why?

a. Close the MSIV bypass valves; RCS cooldown limit was exceede b. Close the MSIV bypass valves; main steam line heat-up limit was exceede c. Close the MSIV bypass valves; both RCS and main steam line limits were exceede d. Leave MSIV bypass valves open; NO RCS or main steam line limits were exceede Page 43

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATC!-,

NRC EXAMINATION 75. Given the following plant conditions:

- Reactor coolant system pressure has decreased to 1930 psig during a plant cooldow The operator has placed the Low Steam Line Pressure Block switches HS-63-135 A & B to BLOC Which ONE of the following describes the status of the Safety Injection and Main Steam Line isolation signals?

a. Only the low steamline pressure MSIV isolation is blocked; low steamline pressure SI is operationa b. Only the low steamline pressure SI signal is blocked; low steam line pressure MSIV isolation is operationa c. Both the high steamline pressure negative rate MSIV isolation and high steamline pressure negative rate SI signal are operationa d. Both the low steam line pressure MSIV isolation and low steam line pressure SI signal are blocke Page 44

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 76. Given the following plant conditions:

- Plant is in Mode "A" train RHR is in operation controlling RCS temperature at 120' RCS level is at elevation 718'10"

- MEG requests that Emergency Diesel Generator (D/G) 1A-A be tagged out to replace the voltage regulator with a new mode Which ONE of the following describes how this request should be handled?

a. D/G 1A-A may NOT be removed from service at this time to protect RHR train "A".

b. D/G 1A-A may NOT be removed from service at this time since both the 1A-A and 1B-B D/G are required to be operable by Tech Spec c. D/G 1A-A may be removed from service at this time as long as one offsite circuit is operabl d. D/G 1A-A may be removed from service at this time as long as risk guidance was obtained from the PSA engineering group.

77. Given the following plant conditions:

- Unit is at 100% power

- High radiation alarms are in on Steam Generator Blowdown (SGBD)

radiation monitors 1-RM-90-120 and 12 Which ONE of the following describes the SGBD System response?

a. The SGBD Containment isolation valves,.FCV-15-181 through 184, clos b. The SGBD Cooling Tower blowdown isolation valve, FCV-15-44, close c. The SGBD to Condensate Header isolation Valve, FCV-15-6, close d. The SGBD flow control valve, FCV-1 5-43, close Page 45

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 78. Given the following conditions:

- A loss of offsite power has occurre Tavg is 5570 Steam Dump controls are in the Steam Pressure mod Steam dump demand is manually increased to begin cooldow Steam Dump valves will NOT ope Which ONE of the following explains why the Steam Dump valves will NOT open?

a. P-4, Reactor Trip, has not been actuate b. C-9, Condenser Available, interlock is not me c. P-12, Lo-Lo Tavg, has disarmed the Steam Dump syste d. C-7, Load Rejection controller, has not been actuate . Given the following plant conditions:

- Reactor trip and safety injection occurred while the plant was operating at 100% powe Four ERCW pumps were running in their normal alignment before the Si occurre Which ONE of the following identifies ERCW pump status after the SI and the effect it has on the Condenser Circulating Water (CCW) system make-up?

a. Four ERCW pumps running; CCW make-up is provided only from ERCW since RCW bypass strainer is isolate b. Eight ERCW pumps running; CCW make-up is provided only from RCW since ERCW is routed through the overflow structur Four ERCW pumps running; CCW make-up provided from both RCW and ERC Eight ERCW pumps running; CCW make-up is not required since the unit is trippe Page 46

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 80. Given the following plant conditions:

- Unit was operating at 100% powe A large break LOCA resulted in a reactor trip and safety injectio Alignment to Cold Leg Recirculation is in progres FCV-63-8, 1A-A RHR Pump to CCP suction, will NOT open from the Control Roo Assuming all other equipment functions as expected, which ONE of the following would prevent the valve from opening?

a. Sl pump minimum flow valve 1-FCV-63-175 ope b. RHR pump suction from RWST 1-FCV-63-1 ope c. Containment sump suction valve 1-FCV-63-72 close d. The A train safety injection signal has been reset.

81. A reactor trip and turbine trip occurs while at 25% powe Which ONE of the following describes the response of the Steam Dump system?

a. Load rejection arms Steam Dump valves; Tavg will be reduced to no-load Tav b. Load rejection arms Steam Dump valves; Tavg will be reduced to within 50F of Tre c. Reactor trip arms Steam Dump valves:

Tavg will be reduced to no-load Tav d. Reactor trip arms Steam Dump valves; Tavg will be reduced to within 5YF of Tre Page 47

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 82. Given the following plant conditions:

- Unit 1 at 20% RTP

- Turbine trip occurs without a Reactor tri The Steam Dump System is in T-avg Mod Rod Control is in Automatic Which ONE of the following describes the effect of the Turbine trip on the Steam Dump and the Rod Control Systems? Assume no operator action a. The Steam Dump System will maintain T-avg at 5620 F with all Control Rods fully inserte b. The Steam Dump System will maintain T-avg at 5570 F with all Control Rods fully inserte c. The Steam Dump System will maintain T-avg at 5620 F with Control Rods maintaining ;1 5% Reactor power due to C- d. The Steam Dump System will maintain T-avg at 5570 F with Control Rods maintaining &15% Reactor power due to C- . Which ONE of the following describes the source of instrument air and the effect of a loss of instrument air on the Main Steam Isolation Valves (MSIVs)?

a. Non-essential air; MSIVs fail CLOSE b. Non-essential air; MSIVs fail OPE c. Essential air; MSIVs fail CLOSE d. Essential air; MSIVs fail OPE Page 48

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 84. Given the following plant conditions:

- A large break LOCA has occurre The operating crew has entered the EOPs and is currently implementing E-0, "Reactor Trip or Safety Injection".

Which ONE of the following describes when a crew brief should be held?

a. After step 4 of E-0 is complet b. After step 11 of E-0 is complet c. Upon transitioning from E- d. Upon making the Emergency Classification 85. Given the following plant conditions:

- Unit at 100% RTP

- A S/G #1 safety valve begins leaking and power increases to 105% RT The crew enters AOI-38 and reduces turbine load to 90% with the valve position limite This load reduction caused reactor power to decrease to 95% RT Which ONE of the following would be the correct crew response per AOI-38 if the flow increased through the leaking safety valve causing the reactor power to return to 101%?

a. Decrease turbine load at 5%/min to reduce reactor power to <100% and cor+inue AOI 3 b. Use the valve position limiter to maintain power <100% and continue AOI-3 c. Trip the reactor, close the MSIVs and bypasses, and go to E- d. Trip the reactor, initiate SI, close the MSIVs and bypasses and go to E- Page 49

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 86. Given the following conditions:

- Plant was operating at 100% power when a Main Feedwater pump tripped causing a plant runbac The OAC observes AFD to be outside the "doghouse" on PRM channels N41, and N4 Which ONE of the following identifies the action required to comply with Technical Specifications?

a. Restore AFD to within limits AND Reduce power to < 50% within 30 minute b. Restore AFD to within limits AND Reduce power to <50% within 15 minute Restore AFD to within limits OR Reduce power to < 50% within 30 minute Restore AFD to within-limits OR Reduce power to < 50% within 15 minutes.

87. Given the following conditions:

- Plant is at 100% powe RCS pressure is 2235 psig and T-avg is 5880 RHR discharge relief valve 1-63-637 is leaking to the PRT at a rate of 2.5 gp Which ONE of the following describes the type of leakage and the action required by Technical Specifications? (Assume all other systems are operating normally and no other RCS leakage)

a. Unidentified leakage that requires shutdow b. Pressure boundary leakage that requires shutdow Identified leakage, but does not require shutdow d. Controlled leakage, but does not require shutdow Page 50

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 88. Given the following plant conditions:

- Plant is in Mode 3

- During performance of Control Building routine rounds the AUO discovers the 125V DC supply breaker to 120V AC Vital Inverter 1-Il in the TRIPPED positio Which ONE of the following describes the correct action which must be taken with regard to Tech Specs?

a. Attempt to close the supply breaker one time, if the breaker can be closed, Tech Spec LCO action entry is NOT require b. The Tech Spec LCO action for the inverter must be entered until the breaker can be close c. If the inverter is aligned to it's AC supply and the voltage is normal, Tech Spec LCO action entry is NOT require d. If the inverter is aligned to it's AC supply and the voltage is normal, enter the appropriate Tech Spec LCO action for the inverter for tracking only until the breaker can be close Page 51

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 89. Given the following plant conditions:

- Plant is in Mode 3 with startup in progres The breaker for "C" hotwell pump will not clos The Shift Manager and Work Week Manager determined that trouble shooting could be conducted as "minor work" if the pump is tagged ou Which ONE of the following describes how this trouble shooting activity should be documented?

a. WO is NOT required since only trouble shooting is planned and will have no operational impact, no detailed planning or documentation is require b. WO is NOT required since a PER will be written to address the condition adverse to quality and trouble shooting may be documented in the PE c. WO is required, the WO may be sent directly to the craft after OPS approval and the work may be documented on the WO for d. WO is required, the WO must be routed to planning after OPS approval and the work will be conducted and documented in the work package developed by the planne . Given the following plant conditions:

- Unit is in Mode 3 with cooldown to Cold Shutdown in progres A transient occurred resulted in the pressurizer going solid and RCS pressure increasing to 2835 psi Which ONE of the following actions is required?

a. Be in hot shutdown with RCS pressure within its limit in 1 hou b. Be in hot shutdown with RCS pressure within its limit in 30 minute c. Reduce RCS pressure to within its limit within 15 minute d. Reduce RCS pressure to within its limit within 5 minute Page 52

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 91. Given the following plant conditions:

- Unit is operating at 100% powe Pressure Pressure channel 11, 1-PT-68-335, has failed HIG All required actions for this instrument failure have been complete The surveillance for Pressurizer pressure channel IV, 1-PT-68-322, will become late at the end of this shif Which ONE of the following actions should be taken?

a. Apply Tech Spec SR 3.0.3 to extend the surveillance for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to allow completion of maintenance on 1-PT-68-33 b. Bypass the bistables on 1-PT-68-322, enter LCO 3.0.3 and then perform surveillance on 1-PT-68-32 c. Bypass the bistables on 1-PT-68-335 and then allow surveillance to be performed on 1-PT-68-32 d. Do not allow surveillance to be performed and enter Tech Spec 3.0.3 when the surveillance period expire Page 53

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 92. Given the following plant conditions:

- Unit is in Mode Refueling operations are in progres An irradiated fuel assembly cannot be placed in its specified core locatio Which ONE of the following describes an approved location for the fuel assembly per FHI-7, Fuel Handling and Movement?

a. Fuel assembly can be placed in the New Fuel Elevator, but the elevator must be full down with power remove b. Fuel assembly may be placed in a free-standing core location as long as no other fuel assembly is free-standin c. Fuel assembly must be returned to the SFP until an alternate core location is determine d. Fuel assembly may be temporarily stored in the RCCA change fixtur . The following conditions are encountered after a survey of a pump room in the Auxiliary building:

- General area radiation level in the room 70 mrem/hr

- Radiation level 30 cm from the pump casing 350 mrem/hr

- Contamination levels 800 dpm/1 00cm 2 beta 0 dpm/100cm2 alpha Which ONE of the following identifies the correct radiological postings required to reflect current radiological conditions for this room?

a. Radiation Are b. High Radiation Are c. Radiation Area; Contamination Are d. High Radiation Area; Contamination Are Page 54

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 94. Given the following plant conditions:

- A LOCA has occurred and a SAE has been declare The TSC and OSC have been activate To prevent core damage it is recommended that entry be made into Safety Injection Pump Room 1 Projected dose rate in the pump room is 1.16x10 mr/h Duration of the exposure is expected to be 3 minute Which ONE of the following must authorize this exposure?

a. Radcon Manager b. Site Emergency Director c. Plant Manager d. Site Vice President 95. Given the following plant conditions:

- Unit is operating at 100% powe A release of the Monitor Tank to Cooling Tower Blowdown is planne RM-90-122, Liquid Radwaste Effluent Monitor is inoperabl Which ONE of the following identifies the requirements to make the planned release under these conditions?

a. No release can be made until 1-RM-90-122 is returned to servic b. Sample results must show that activity of the release liquid is <2x10-4 microcuries per millilite c. Two separate samples must be analyzed and two independent qualified members of facility staff verify release rate and discharge valve lineu Reactor d. The tank must be recirculated for two volumes and a licensed Senior Operator must confirm release rate and discharge valve lineu Page 55

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION radiation monitor that should 96. Which ONE of the following identifies the first respond to a SGTR and the effect on the monitor?

and the monitor will be a. Condenser Vacuum Exhaust Monitor RM-90-119 automatically isolate and the monitor will NOT be b. Condenser Vacuum Exhaust Monitor RM-90-1 automatically isolate RM-90-120/121 and the monitor c. Steam Generator Blowdown Sample Monitor will be automatically isolate RM-90-120/121 and the monitor d. Steam Generator Blowdown Sample Monitor will NOT be automatically isolate . Given the following conditions:

- Unit I in MODE 1 at 10% RT Turbine at 1800 rpm at no load (generator PCB open).

- Loss of offsite power occur Board Emergency Diesels fails to re-energize Shutdown of the Emergency Which ONE of the following describes the correct usage Instructions?

a. Go directly to ECA-0.0 without entering E- b. Implement ECA-0.0 in conjunction with E- and turbine tri c. Go to ECA-0.0 from E-0 after verifying reactor immediately to ECA- d. Cornplete E-0 IMMEDIATE ACTIONS then go Page 56

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 98. Given the following plant conditions:

- Reactor trip and SI have occurre mitigate

- Operators are using E-3, "Steam Generator Tube Rupture", to the even of the low RCS Which ONE of the following correctly describes the applicability steps of E-3?

pressure RCP trip criteria on the Foldout Page while performing TIME the a. RCPs should be tripped during the performance of E-3 ANY foldout page low pressure RCP trip criteria are me as an Low RCS pressure RCP trip criteria is not applicable in E-3 EXCEPT RNO if excessive RCS inventory loss is also experience RCP trip RCPs should be tripped during E-3 ONLY if the low RCS pressure criteria is met before beginning the cooldown and depressurizatio RCP trip d. RCPs should be tripped during E-3 ONLY if the low RCS pressure is criteria is met during the performance of step 1 when the operator specifically required to check the criteri Page 57

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION 99. A step in ES-1.3, "Transfer to RHR Containment Sump", reads as follows:

ISOLATE SI pump miniflow:

CLOSE FCV-63- * CLOSE FCV-63-17 * CLOSE FCV-63- The bullets ("*") indicate that:

a. The actions must be performed in the specified sequence, but once a step is in progress, the next step may be starte b. The actions must be performed and completed in the specified sequenc c. These actions should have been completed, so only verification may be require d. These actions must all be completed, but any sequence of completion is allowe Page 58

WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION conditions exist:

100. Following Safety Injection reset during ES-1.1 the following

- Tavg is 560T PRZ level is 45%.

- PRZ pressure is 2230 psi OAC would Which ONE of the following describes the PZR heater status the observe?

a. Control group 1D OF Backup group 1C OF Backup group 1A-A OF Backup group IB-B OF b. Control group 1D O Backup group 1C OF Backup group 1A-A OF Backup group 1B-B OF c. Control group 1D OF Backup group 1C O Backup group 1A-A OF Backup group 1B-B OF d. Control group 1D OF Backup group 1C OF Backup group 1A-A O Backup group 1B-B O Page 59

IR 05000390/2001301

Text

Navigation menu

v t e Inspection Report - Watts Bar - 2001301 (Operator Exams)
80 \| 81 \| 82 \| 83 \| 84 \| 85 \| 86 \| 87 \| 88 \| 89 \| 90 \| 91 \| 92 \| 93 \| 94 \| 95 \| 96 \| 97 \| 98 \| 99 00 \| 01 \| 02 \| 03 \| 04 \| 05 \| 06 \| 07 \| 08 \| 09 \| 10 \| 11 \| 12 \| 13 \| 14 \| 15 \| 16 \| 17 \| 18 \| 19 \| 20 \| 21 \| 22 \| 23 \| 24 \|
2001 Quarterly Integrated 1Q (1) 2Q (0) 3Q (0) 4Q (0) Assessments Mid Cycle End of Cycle 7(0) Security Operator Exams 301(0) Emergency Planning Other

IR 05000390/2001301

Text

Navigation menu

Search