ML081200419

2008-03 - Final - Written Exam

ML081200419
Person / Time
Site:	Waterford
Issue date:	03/24/2008
From:	Gody A Division of Reactor Safety IV
To:	Walsh K Entergy Operations
References
50-382/08-301 50-382/08-301
Download: ML081200419 (108)

Text

1.

2.

3.

4.

5.

6.

7.

8.

9.

10.

11.

12.

13.

14.

15.

16.

17.

18.

19.

20.

21.

22.

23.

24.

25.

C D

D B

D D

D A

A B

C B

D D

C B

A C

B B

C C

C A

A

26.

27.

28.

29.

30.

31.

32.

33.

34.

35.

36.

37.

38.

39.

40.

41.

42.

43.

44.

45.

46.

47.

48.

49.

50.

Site-Specific Written Examination W3 2008 Senior Reactor Operator Answer Key A

D C

D A

C C

A D

D A

C B

A D

C B

D C

B B

D D

C A

51.

B

52. A

53. c

54.

D

55.

B

56.

B

57.

B

58.

B

59.

D

60.

C

61.

D

62. A

63.

D

64.

B

65.

D

66. A

67.

C

68.

B

69.

B

70. A

71.

B

72.

A

73. c

74.

D

75.

D

76.

D

77.

D

78.

C

79.

D

80.

D

81.

B

82.

A

83.

B

84.

B

85.

D

86.

C

87.

C

88.

C

89.

D

90.

A

91.

B

92.

C

93.

D

94.

A

95.

c

96.

B

97.

A

98.

C

99.

B 100. D Rev Post NRC Review BLI

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

4/03/2008 Region:

IV Start Time:

U.S. Nuclear Regulatory Commission FacilityTUnit:

Waterford 3 Reactor Type:

CE Finish Time:

Specific SRO Written Examination Amlicant Information Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets, To pass the examination you must achieve a final grade of at least 80.00 percent overall, with 70.00 percent or better on the SRO-only items if given in conjunction with the RO exam; SRO-only exams given alone require a final grade of 80.00 percent to pass.

You have 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to complete the combined examination, and 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> if you are only taking the SRO portion.

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

Awlicants Signature Results 75

/

25

/

100 Points ROISRO-OnlyITotal Examination Values Applicants Scores

- f - f -

Points AppIicant9s Grade NUREG-I 021, Revision 9

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator A

B C

D A

B C

D A

B C

D A

B C

D A

B C

D A

B C

D A

B C

D A

B C

D A

B C

D A

B C

D A

B C

D A

B C

D A

B C

D A

B C

D A

B C

D A

B C

D A

B C

D A

B C

D A

B C

D A

B C

D A

B C

D A

B C

D A

B C

D A

B C

D A

B C

D A

B C

D A

B C

D A

B C

D A

B C

D A

B C

D A

B C

D A

B C

D A

B C

D A

B C

D A

B C

D A

B C

D A

B C

D A

B C

D A

B C

D A

B C

D A

B C

D A

B C

D A

B C

D A

B C

D A

B C

D A

B C

D A

B C

D A

B C

D A

B C

D Page 2 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator

51.

A B

C D

52.

A B

C D

53.

A B

C D

54.

A B

C D

55.

A B

C D

56.

A B

C D

57.

A B

C D

58.

A B

C D

59.

A B

C D

60.

A B

C D

61.

A B

C D

62.

A B

C D

63.

A B

C D

64.

A B

C D

65.

A B

C D

66.

A B

C D

67.

A B

C D

68.

A B

C D

69.

A B

C D

70.

A B

C D

71.

A B

C D

72.

A B

C D

73.

A B

C D

74.

A B

C D

75.

A B

C D

A B

C D

A B

C D

A B

C D

A B

C D

A B

C D

A B

C D

A B

C D

A B

C D

A B

C D

A B

C D

A B

C D

A B

C D

A B

C D

A B

C D

A B

C D

A B

C D

A B

C D

A B

C D

A B

C D

A B

C D

A B

C D

A B

C D

A B

C D

100.

A B

C D

Page 3 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 001 Given the following:

0 The reactor is tripped.

RCS pressure has lowered to 1650 PSIA.

0 Containment pressure is currently 17.2 PSIA.

0 The crew is performing OP-902-000, Standard Post Trip Actions.

Which ONE of the following describes the effect on the RCPs for this condition?

A. Controlled Bleedoff Isolation valves, (CVC 401 and RC 606) are OPEN; CCW supply & return isolation valves, (CC 641; CC 710 & CC 713) are OPEN.

B. Controlled Bleedoff Isolation valves, (CVC 401 and RC 606) are OPEN; CCW supply & return isolation valves, (CC 641 ; CC 71 0 & CC 71 3) are CLOSED.

C. Controlled Bleedoff Isolation valves, (CVC 401 and RC 606) are CLOSED; CCW supply & return isolation valves, (CC 641; CC 710 & CC 713) are OPEN.

D. Controlled Bleedoff Isolation valves (CVC 401 and RC 606) are CLOSED; CCW supply & return isolation valves, (CC 641; CC 710 & CC 713) are CLOSED.

Page 4 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 002 Given the following:

0 A plant startup is in progress.

0 The Pressurizer is solid in preparation for forming a bubble.

0 RCS temperature is 210°F and rising slowly.

0 RCS pressure is 250 PSIA and stable.

Which ONE of the following describes how RCS pressure is being maintained, and the pressure at which the LTOP relief valves will operate to maintain RCS pressure within limits?

Letdown Backpressure Control Valve is throttling A. Closed as RCS temperature rises; LTOP reliefs lift at 392 PSIA.

B. Closed as RCS temperature rises; LTOP reliefs lift at 430 PSIA.

C. Open as RCS temperature rises; LTOP reliefs lift at 392 PSIA.

D. Open as RCS temperature rises; LTOP reliefs lift at 430 PSIA.

Page 5 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 003 The plant is in MODE 1 Which ONE of the following describes the power supply AND breaker status for RCS Loop Shutdown Cooling System Isolation Valve SI-401 A?

A. Powered by non-safety-related 480 volt MCC; breaker is CLOSED.

B. Powered by non-safety-related 480 volt MCC; breaker is LOCKED OPEN.

C. Powered by safety-related 480 volt MCC; breaker is CLOSED.

D. Powered by safety-related 480 volt MCC; breaker is LOCKED OPEN.

Page 6 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 004 Given the following:

0 A small-break loss of coolant accident has occurred.

Current conditions:

0 Two charging pumps are running.

0 Pressurizer Pressure is 1300 PSIA.

0 HPSl Pumps AB and B have been stopped upon meeting SI Termination Criteria.

0 Pressurizer level is now 7% and slowly dropping.

Which ONE of the following describes the MINIMUM action required for the current conditions?

A. Start HPSl Pumps AB and B and fully open all cold leg flow control valves; verify Pressurizer level is rising.

B. Start HPSl Pump AB or B and throttle open enough cold leg flow control valves to raise Pressurizer level.

C. Reinitiate safety injection by depressing the manual Safety Injection pushbuttons on CP-7.

D. Start the third charging pump and monitor for Pressurizer level stabilization.

Page 7 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 005 Given the following:

0 A LOCA has occurred.

0 A RAS signal has been received.

Which ONE of the following valves automatically changes position due to the Recirculation Actuation Signa I?

A. LPSI Cold Leg injection Flow Control Valve, SI-l38A B. SI Pumps Recirc Isolation Valve SI-12OB C. ESF Pumps Suction RWSP Valve, SI-l06B D. ESF Pumps Suction SI Sump Valve, SI-602A Page 8 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 006 Which ONE of the following describes how the Containment Penetration (#7) for Primary Makeup (PMU) is protected from over-pressurization during a design basis accident?

A. Penetration has a Relief valve directed to the Quench Tank B. Penetration has a Relief Valve directed to the Reactor Drain Tank C. PMU Isolation to Quench Tank (PMU-153), is locked closed in MODEs 1-4 D. PMU Isolation to Quench Tank (PMU-153), is maintained open in MODEs 1-4 Page 9 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 007 Given the following:

0 CCW Pumps A and B are currently running.

0 AB Bus is aligned to Train B.

0 CCW AB Assignment Switch is in the B position.

0 CCW Pump AB has NOT been started.

If a Loss of Offsite Power occurs, which ONE of the following describes the operation of the CCW pumps for this event (Assume Both Sequencers have timed out)?

A. ALL CCW Pumps are running.

B. ONLY CCW Pump A is running.

C. ONLY CCW Pumps A and B are running.

D. ONLY CCW Pumps A and AB are running.

Page 10 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 008 The plant is at 5% power:

If the controlling Pressurizer pressure channel (RC-IPIC-0100) failed m, then the first reactor trip signal would be: (Assume no operator actions)

A. CPC RCS Pressure Aux Trip B. A calculated DNBR LO trip C. RPS Pressurizer Pressure HI trip D. RPS Pressurizer Pressure LO trip Page 11 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 009 Given the following:

0 MODE 1, 1OO0/o power.

Channel 8 Narrow Range Pressurizer Pressure indication has failed low.

A short time later the following occurs:

Channel C Narrow Range Pressurizer Pressure transmitter output fails m.

Which of the following describes the current reactor status the reason?

A.

The reactor is tripped due to 2 out of 4 CPC Aux Trips, B.

The reactor is tripped due to 2 out of 4 Narrow Range Pressurizer Pressure Trips.

C.

The reactor is NOT tripped based on 1 out of 4 CPC Aux Trips.

D.

The reactor is NOT tripped based on 1 out of 4 Narrow Range Pressurizer Pressure Trips.

Page 12 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 010 Which ONE of the following describes the operation of the RPS/ESFAS PZR PRESS BYPASS?

A.

B.

C.

D.

Manually initiated using a keyswitch when Pressurizer pressure decreases below 500 PSIA. Automatically removed when Pressurizer pressure increases above 500 PSIA.

Manually initiated using a keyswitch when Pressurizer pressure decreases below 400 PSIA. Automatically removed when Pressurizer pressure increases above 500 PSIA.

Automatically initiated when Pressurizer pressure decreases below 500 PSIA.

Manually removed using a keyswitch.

Automatically initiated when Pressurizer pressure decreases below 400 PSIA.

Manually removed using a keyswitch.

Page 13 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 011 Given the following:

0 The plant is at 100% power.

0 Containment Cooling is in a normal alignment.

0 The following alarm is received:

o Cabinet C, E-I, TRN B CNTMT COOLER POWER LOST 0

CNTNT Fan Cooler D was running but is now stopped.

0 Containment temperature begins to rise slowly.

0 Investigation reveals that the fan supply breaker is in the ON position, and the control power fuses are intact.

Which ONE of the following describes the failure mechanism and impact of the failure?

A. Fan motor overcurrent; Containment temperature will FIRST exceed Technical Specification limits at 1 10°F.

B. Fan motor overcurrent; Containment temperature will FIRST exceed Technical Specification limits at 120°F.

C. Fan motor thermal overload; Containment temperature will FIRST exceed Technical Specification limits at 120°F.

D. Fan motor thermal overload; Containment temperature will FIRST exceed Technical Specification limits at 11 0°F.

Page 14 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 012 Given the following:

0 The plant is operating in MODE 1.

0 A LOCA has occurred.

0 The following conditions are noted:

o RCS pressure = 1750 PSIA.

o Containment Pressure = 17.3 PSIA.

o All Containment Fan Coolers (CFCs) are OPERABLE.

o The ring header is severely damaged Which ONE of the following describes the status of the Containment Cooling System?

A. All CFCs running in slow speed and system capability is degraded.

B. All CFCs running in slow speed and system capabiiity is not degraded.

C. All CFCs running in fast speed and system capability is degraded.

D. All CFCs running in fast speed and system capability is not degraded.

Page 15 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 013 Given the following:

0 The plant is operating in MODE 1.

0 A LOCA has occurred.

0 Containment pressure is 17.9 PSIA.

0 4.16KV Bus 63-S is de-energized.

The CRS directs closing Containment Spray Discharge Header Isolation Valve CS-125B.

Which ONE of the following describes the MINIMUM action required to close the valve?

A. Place the CP-8 control switch for CS-125B in CLOSE.

B. Place the CP-8 control switch for CS-125B in OPEN, then place in CLOSE.

C. Place the override key switch in the +35 Relay Room in OVERRIDE, then place the CP-8 control switch for CS-125B in CLOSE.

D. Place the override key switch in the +35 Relay Room in OVERRIDE, then place the CP-8 control switch for CS-1256 in OPEN, then place in CLOSE.

Page 16 of 103

U. S. N. R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 014 Given the following:

0 The plant is in MODE 1.

0 A LOCA has occurred.

0 CSAS has actuated.

0 RWSP level is 55% and lowering.

Assuming no action by the crew, which ONE of the following describes the effect on the Containment Spray System in order to perform its design function?

A. CCW flow is required through the Shutdown Cooling Heat Exchangers; CC-963A, SHDN HX A OUTLET remains closed.

B. CCW flow is required through the Shutdown Cooling Heat Exchangers; CC-963A, SHDN HX A OUTLET automatically opened.

C. CCW flow is NOT required through the Shutdown Cooling Heat Exchangers; CC-963Al SHDN HX A OUTLET remains closed.

D. CCW flow is NOT required through the Shutdown Cooling Heat Exchangers; CC-963A, SHDN HX A OUTLET automatically opened.

Page 17 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 015 Given the following:

0 A reactor startup is in progress following a reactor trip from 100% power that occurred 4 days ago.

0 250EFPD SBCS valves are maintaining no-load Tave.

0 SBCS Permissive setpoint is at 910 PSIA.

Which ONE of the following will cause actual critical rod position to be LOWER than estimated critical rod position?

A. Raise SBCS modulation setpoint 50 PSI.

B. Raise SBCS permissive setpoint 50 PSI.

C. Lower SBCS modulation setpoint 50 PSI.

D. Lower SBCS permissive setpoint 50 PSI.

Page 18 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 016 Given the following:

0 The plant is at 100% power.

0 The output of Master Controller # I for FWCS # I became erratic.

0 The crew has entered OP-901-201, Steam Generator Level Control System Malfunction.

0 The # I Master Controller both Main Feedwater Pump controllers are in Manual.

0 The output of the # I Master Controller is at 60%.

0 Subsequently, a reactor trip occurs.

Assuming no operator action occurs, what is the INITIAL post-trip response of SG # I level and FWCS #I?

A. Level in SG # I rises to the level setpoint; RTO resets; FWCS # I components go to program condition for 60% Master Controller output.

B. Level in SG # I rises to HLO setpoint of 81% NR; SUFRV # I cycles between the HLO and HLO reset setpoints at RTO flowrate.

C. Level in SG # I rises, RTO does not reset, and MFlV # I goes closed when SG 1 level reaches 96% WR.

D. Level in SG # I rises to HLO setpoint of 81% NR; SUFRV # I & MFRV # I cycle between the HLO and HLO reset setpoints at 60% demand flowrate.

Page 19 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 013 Given the following:

0 The plant is at 40% power.

0 The Feedwater Flow signal to FWCS #I fails low.

Which ONE of the following describes the FWCS #I response?

A.

B.

C.

D.

SG #I level will increase, but will be offset by a level error signal. SG #I level will stabilize at the program setpoint.

SG #I level will increase, but will be offset by a level error signal. SG #I level will stabilize above the program setpoint.

SG #I level will decrease, but will be offset by a level error signal. SG #I level will stabilize at the program setpoint.

SG #I level will decrease, but will be offset by a level error signal. SG #I level will stabilize below the program setpoint.

Page 20 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 018 The plant is at 100% power.

Which ONE of the following describes the direct power supply and design flow capacity of EFW Pump B?

A. 4.16KV Bus B2; 350 GPM.

B. 4.16KV Bus B2; 700 GPM.

C. 4.16KV Bus B3; 350 GPM.

D. 4.16KV Bus B3; 700 GPM.

Page 21 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 019 Given the following:

0 The crew is performing a post-maintenance 24-hour EDG B run in accordance with OP-903-116, Train B Integrated Emergency Diesel GeneratodEngineering Safety Features Test 15 minutes ago, the crew loaded EDG B to 4840 kW.

0 Which ONE of the following describes the time limit for EDG B operation at this load and the reason for that limit?

A. EDG B can remain at this load indefinitely without consequence.

B. EDG B can remain at this load for 1.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br />, then load must be reduced to 4400 kW or less to prevent generator winding damage.

C. EDG B can remain at this load for 23.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> without consequence.

D. EDG B is operating above its maximum design limit. Load must be immediately reduced to 4400 kW or less to prevent generator winding damage.

Page 22 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 020 Given the following:

0 The plant is at 100% power.

EDG A is synchronized to the grid for a post-maintenance test.

0 EDG A output is 2.2 MW.

Which ONE of the following completes the statement regarding the impact on EDG A if a loss of the A-DC-S Bus occurs?

EDG A will A.

B.

C.

D.

trip and the output breaker will trip open immediately.

trip and the output breaker will remain closed.

remain running but the output breaker will trip open immediately remain running and the output breaker will remain closed.

Page 23 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 021 Given the following:

0 The plant is in MODE 1.

0 All safety-related station batteries and battery chargers are Operable.

Which of the following describes the status of the DC electrical system?

Batterv chargers Station Batteries A.

In FLOAT mode Supplying DC loads B.

In EQUALIZE mode NOT supplying DC loads C.

In FLOAT mode NOT supplying DC loads D.

In EQUALIZE mode Supplying DC loads Page 24 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 022 Given the following:

0 EDG B is being synchronized to the grid for a retest following maintenance.

0 The synchroscope is slowly rotating in the counter-clockwise direction.

0 EDG voltage is approximately 10 volts lower than Bus voltage.

IF the EDG output breaker is closed under these conditions, which ONE of the following describes the effect on the EDG and the action required PRIOR to closing the breaker to prevent the effect?

A. Potential EDG output breaker overcurrent condition; raise EDG frequency.

B. Potential EDG output breaker overcurrent condition; raise EDG voltage.

C. Potential reverse power trip of EDG output breaker; raise EDG frequency.

D. Potential reverse power trip of EDG output breaker; raise EDG voltage.

Page 25 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 023 Given the following:

0 0

0 Controller output is 20%.

0 The plant is at 100% power.

The Pressurizer Pressure Controller is in MANUAL.

RCS pressure is 2220 PSIA.

Which ONE of the following actions will raise Pressurizer pressure?

A. Lower the controller setpoint.

B. Raise the controller setpoint.

C. Lower the controller output.

D. Raise the controller output.

Page 26 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 024 Given the following:

0 The plant is at 100% power.

0 The following alarm is received on Cabinet L:

o A-9, RAD MONITORING SYS ACTIVITY HI-HI.

0 ARM-IRE-5021, Letdown HWBlowdown Pump Hallway, is in alarm.

0 Chemistry sample of the RCS indicates elevated Iodine-I 31 activity levels.

Which ONE of the following describes the reason for notification of Radiation Protection to initiate surveys in the Reactor Auxiliary Building?

A. Area radiation levels may require additional controls.

B. Surveys are required for confirmation of ARM-IRE-5023 detector response.

C. ARM-IRE-5021 reads in CPM and therefore has no correlation to area radiation levels.

D. Area radiation levels are used to determine the need for additional letdown flow.

Page 27 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 025 Given the following:

0 The plant is operating at 100% power.

0 A, B, and D Containment Fan Coolers are operating in Fast Speed.

0 A LOCA occurs.

0 Containment Pressure is 19.5 PSIA.

Which ONE of the following describes the CCW flow configuration to the Containment Fan Coolers?

A. CCW flow of 2700 GPM on each header.

B. CCW flow of 1400 GPM on each header.

C. CCW flow of 2700 GPM to each header that was in service prior to SIAS. 1400 GPM to the header that was not in service prior to SiAS.

D. CCW flow of 1400 GPM to each header that was in service prior to SIAS. 2700 GPM to the header that was not in service prior to SIAS.

Page 28 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 026 Given the following:

0 100 percent power.

0 Instrument Air Header pressure is 115 PSIG.

An air leak occurs, causing Instrument Air Header pressure to drop to 90 PSIG.

Which ONE of the following describes the status of the instrument air system?

A. SA-125 Station Air Backup is OPEN, IA-I23 Air Dryer Bypass is OPEN B. SA-I 25 Station Air Backup is CLOSED, IA-I 23 Air Dryer Bypass is OPEN C. SA-I 25 Station Air Backup is OPEN, IA-I 23 Air Dryer Bypass is CLOSED D. SA-125 Station Air Backup is CLOSED, IA-I23 Air Dryer Bypass is CLOSED Page 29 of 103

U.S. N, R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 027 Given the following:

0 Containment Pressure = 16.9 PSIA.

0 RCS Pressure = 1450 PSIA.

0 CC-641, CCW RCP Inlet Outside lsol Valve is OPEN.

0 BAM-133, Emergency Boration Valve is OPEN.

0 SI-343, SI Tanks Drain to RWSP Valve is CLOSED.

0 MS 120A, Main Steam Line 1 Normal Drain Valve is OPEN.

Which ONE of the following valves requires operator action for the current plant co nd it ions?

A. CC-641 B. BAM-133 C. SI-343 D. MS-120A Page 30 of 103

U.S. N. R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 028 Which ONE of the following describes the operation of the Containment Vacuum Relief System to maintain Containment pressure within design limits?

If Containment to Annulus Differential Pressure reaches...

A. 8.5 INWD, verify Containment Vacuum Relief Valves CVR-101 and CVR-201 OPEN; Valves must be manually realigned when DP rises to the specified value.

B. 5.5 INWD, verify Containment Vacuum Relief Valves CVR-101 and CVR-201 OPEN; Valves must be manually realigned when DP rises to the specified value.

C. 8.5 INWD, verify Containment Vacuum Relief Valves CVR-IO1 and CVR-201 OPEN; Verify valves automatically close when DP drops to the specified value.

D. 5.5 INWD, verify Containment Vacuum elief Valves CVR-I 01 and CVR-201 OPEN; Verify valves automatically close when DP drops to the specified value.

Page 31 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 029 Given the following:

The plant is operating at 100% power.

0 A transient occurs, resulting in reactor power rising slightly.

Channel A LPD pre-trip alarm is received in the control room.

Which ONE of the following describes the effect on CEA motion?

A. CEA withdrawal is prohibited in Manual Individual ONLY.

B. CEA withdrawal is permitted in all Modes, but if one more LPD pre-trip is received, CEA withdrawal will be prohibited in Manual Individual ONLY.

C. CEA Withdrawal is permitted in Manual Individual ONLY.

D. CEA withdrawal is permitted in all Modes, but if one more LPD pre-trip is received, CEA withdrawal will be permitted in Manual Individual ONLY.

Page 32 of 103

U.S. N. R. C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 030 Given the following condition:

The in-service Pressurizer pressure control channel has just failed &.

Which ONE of the following prevents a simultaneous Reactor Protection System (RPS)

Trip bistable actuation?

A.

Separate circuits are used for protection channel and control channel functions.

B.

Each circuit is provided with two separate outputs; one for control channel, one for protection channel.

C.

Isolation amplifiers from the output of each circuit ensure that feedback from the control signal will not affect the protection channel.

D.

Circuit outputs are multiplexed to be processed separately by the control channel and protection channel circuitry.

Page 33 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 031 Given the following:

0 A loss of off-site power has occurred.

0 RCS Thot is 585°F and stable.

0 RCS Tcold is 555°F and stable.

0 The ATC Operator is currently verifying Natural Circulation.

Which ONE of the following values is the MAXIMUM Representative CET temperature that ensures single phase natural circulation has been established?

A. 589°F B. 592°F C. 594°F D. 597°F Page 34 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 032 Given the following:

0 A LOCA has occurred.

0 The crew is performing OP-902-002, Loss of Coolant Accident Recovery.

Which ONE of the following describes the sequence of actions required to place a Hydrogen Analyzer in service, and the hydrogen concentration indicated when the containment atmosphere reaches a flammable limit?

A. Open the H2 Analyzer containment isolation valve, then turn the power switch ON; 2%.

B. Place the power switch ON, then open the H2 Analyzer containment isolation valve; 2%.

C. Open the H2 Analyzer containment isolation valve, then turn the power switch ON; 4%.

D. Place the power switch ON, then open the H2 Analyzer containment isolation valve; 4%.

Page 35 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 033 Given the following:

0 A plant startup is in progress.

0 Condensate Pump A was started from a cold condition, run for 30 seconds, and manually tripped 3 minutes ago.

0 Investigation revealed an erroneous indication, and the pump may be run as required.

In accordance with OP-003-003, Condensate System, which ONE of the following describes the time requirement for restart of Condensate Pump A?

A. The pump may be started ONE time immediately.

B. An additional 2 minutes must pass prior to attempting restart.

C. An additional 27 minutes must pass prior to attempting restart.

D. An additional 57 minutes must pass prior to attempting restart.

Page 36 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 034 Given the following:

0 A discharge of Boric Acid Condensate Tank (BACT) A is in progress.

0 The following alarm is received:

o Cabinet G, A-IO, BAC CONDENSATE RAD MONITOR TROUBLE 0

Boron Management Discharge Rad Monitor recorder on CP-4, PRM-IRE-0627 (Green Pen) indicates off-scale low.

NOTE:

0 0

BM-547, Boron Management Discharge to Circulating Water Auto Isolation Valve BM-549, Boron Management Discharge to Circulating Water Flow Control Valve Which ONE of the following describes the status of the BACT release path?

A. BOTH BM-547 AND BM-549 remain open.

B. ONLY BM-547 closes.

C. ONLY BM-549 closes.

D. BOTH BM-547 AND BM-549 close.

Page 37 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 035 Given the following:

0 The plant is at 100% power.

0 A Gaseous Waste Discharge is in progress when the Waste Gas Flow and Radiation Recorder, GWM-IFRR-0648, fails.

0 The recorder cannot be immediately repaired.

Which ONE of the following describes the impact of the failure, and the action required?

A. Waste Gas Discharge automatic isolation is inoperable; stop the release until the recorder is returned to operable status. The release may resume ONLY when a new release permit is issued.

B. Waste Gas Discharge automatic isolation is inoperable; stop the release until the recorder is returned to operable status. The release may resume under the existing release permit after verifying NO new additions to the WGD Tank(s) being released.

C. Waste Gas Discharge automatic isolation remains operable but flow indication is lost; verify the flow setpoint on GWM-309 remains below the limit specified on the release permit, and continue the release.

D. Waste Gas Discharge automatic isolation remains operable but flow indication is lost; estimate discharge flow rate by determining the change in GDT pressure over time to ensure flow rate remains within limits.

Page 38 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 036 For the Containment Purge Isolation Monitors, (RE-5024 - RE-5027) (1) which ONE of the following describes the type of radiation monitoring provided, and (2) the Containment Purge System components operated directly by a Containment Purge Isolation Signal (CPIS)?

A. (1 ) Area Radiation Monitors; (2) Supply and Exhaust Valves ONLY.

B. (1 ) Area Radiation Monitors; (2) Supply and Exhaust Valves, and RAB Normal Exhaust Fans.

C. (1 ) Process Radiation Monitors; (2) Supply and Exhaust Valves ONLY.

D. (1 ) Process Radiation Monitors; (2) Supply and Exhaust Valves, and RAB Normal Exhaust Fans.

Page 39 of 103

U.S. N. R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 037 Given the following:

0 The plant is at 50% power.

0 Three Circ Water Pumps are running.

Circ Water Pump B trips.

0 The crew is performing actions of OP-901-220, Loss of Condenser Vacuum.

0 Condenser vacuum is 21 inches Hg and lowering slowly in all condenser sections.

Which ONE of the following describes the status of Steam Bypass Control System, (SBCS) and the action required at this moment?

A. All SBCS valves are NOT available due to low vacuum; trip the reactor.

B. All SBCS valves are NOT available due to low vacuum; trip the turbine.

C. All SBCS valves remain available; trip the reactor D. All SBCS valves remain available; trip the turbine.

Page 40 of 103

U.S. N. R. C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 038 Given the following:

0 The plant is at 100% power.

0 A report from the RAB is received that a broken latch is discovered on a Fire Door in a safety related area.

0 The door is closed but will not stay latched closed.

0 Fire detection is operable on BOTH sides of the broken door.

Which ONE of the following describes the action required?

A. A Continuous Fire Watch MUST be posted until the latch is repaired.

B. An Hourly Fire Watch patrol MUST be initiated until the latch is repaired.

C. A Fire Watch is NOT required because all Fire Detection is operable.

D. A Fire Watch is NOT required because the door remains closed and the fire boundary is intact.

Page 41 of I03

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 039 Given the following:

0 A reactor trip has occurred.

0 Automatic AND Manual Main Turbine Trip has FAILED.

Which ONE of the following identifies the contingency action that will be performed in accordance with Standard Post Trip actions, and the reason for the action?

A. Close both MSIVs; prevent uncontrolled cooldown of the RCS.

B. Close both MSIVs; conserve secondary inventory.

C. Open the Main Generator Output Breakers; prevent uncontrolled cooldown of the RCS.

D. Open the Main Generator Output Breakers; conserve secondary inventory.

Page 42 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 040 Given the fo I lowing :

Initial Conditions:

0 A Pressurizer Safety Valve has stuck open after a load rejection.

RCS pressure is 1200 PSIA.

Containment pressure is 18 PSIA and rising.

SI flow is approximately 250 GPM.

Current Conditions:

The stuck open Safety Valve cannot be isolated.

RCS pressure continues to decrease and is currently 600 PSIA.

Containment pressure is 21 PSIA and rising.

Assuming no action by the crew, which ONE of the following correctly describes the current RCS leak rate and SI flow? [Use attached reference]

A. Leak rate is approximately 50% of the initial leak rate.

SI flow is less than 500 GPM.

B. Leak rate is approximately 50% of the initial leak rate.

SI flow is greater than 500 GPM.

C. Leak rate is approximately 70% of the initial leak rate.

SI flow is &than 500 GPM.

D. Leak rate is approximately 70% of the initial leak rate.

SI flow is greater than 500 GPM.

Page 43 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 041 Given the following:

A LOCA has occurred.

RCS pressure is 1600 PSIA.

Containment pressure is 18 PSIA.

The crew is performing OP-902-002, Loss of Coolant Accident Recovery.

All required actions have been taken.

\\

lic,i ONE of the following describes the method and rate that will be used to perform RCS cooldown in accordance with OP-902-0022 Cooldown using...

A. SBCS at no greater than 50" B. SBCS at no greater than 100°F per hour C. ADVs at no greater than 50°F per hour D. ADVs at no greater than 100°F per hour Page 44 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 042 Given the following:

0 A LOCA has occurred.

0 RCS pressure is 100 PSIA.

0 The crew is performing OP-902-002, Loss of Coolant Accident Recovery.

0 The following alarms are received on Control Room Cabinet K:

o o

K-19, RAS TRAIN A LOGIC INITIATED K-20, RAS TRAIN B LOGIC INITIATED Which ONE of the following describes the plant status, and the action required?

A. LPSl Pumps are off; SI Pumps Recirc Isolation Valves, SI-l20A and B, must be opened.

B. LPSl Pumps are off; SI Pumps Recirc Isolation Valves, SI-l20A and B, must be closed.

C. HPSl Pumps are off; SI Pumps Recirc Isolation Valves, SI-l20A and B, must be opened.

D. HPSl Pumps are off; SI Pumps Recirc Isolation Valves, SI-l20A and B, must be closed.

Page 45 of 103

U.S. N. R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 043 Given the following:

0 The reactor was manually tripped.

0 2A RCP was secured due to 2A RCP ARRD High Temperature.

0 Reverse rotation was indicated on 2A RCP and all RCPs were secured.

0 OP-902-003, Loss of Offsite Power/Loss of Forced Circulation Recovery has been implemented.

After 30 minutes, which ONE of the following would indicate adequate single phase natural circulation flow?

A. Thot is 538°F and rising; Tcold is 529°F and constant.

9. RCS Subcooling is 26°F and constant.

C. Thot is 480°F with Representative CET temperature 492°F.

D. Steam Generator pressures are 450 PSlA with RCS Tcold 450°F.

Page 46 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 044 Given the following:

0 The plant is at 100% power.

0 Charging Pump B is tagged out of service.

0 The following alarm is received:

o Cabinet GI B-4, CHARGING PUMP A TRIPFROUBLE 0

The RO determines that Charging Pump A has tripped with no indications of the cause.

0 Charging Pump AB trips upon starting on overcurrent.

0 Regenerative Heat Exchanger Outlet temperature is 440°F and rising at 5°F every 30 seconds.

0 NO action has been taken by the crew.

0 Tave is 572°F.

0 Pressurizer level is 54% and lowering at 1 YO every 2 minutes.

Assuming the following trends continue, which ONE of the following describes Pressurizer level indication for this event? (Use included Reference.)

Pressurizer level will continue to lower...

A. At a constant rate for the duration of this event because letdown has isolated.

B. At a constant rate until reactor trip is required in approximately 15 minutes.

C. At a constant or decreasing rate until letdown isolates in approximately 3 minutes.

D. At a constant or decreasing rate until letdown isolates in approximately 15 minutes.

Page 47 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 045 Given the following:

The plant is in MODE 5.

The RCS was drained to 14.5 ft. MSL.

LPSl pumps have been secured due to RCS leakage.

HPSl Pump B has been started in accordance with OP-901-131, Shutdown Cooling Malfunction.

RCS level has been raised to and is being maintained at 16 ft MSL.

Which ONE of the following describes the process for restoring a LPSl pump in accordance with OP-901-131?

Vent and start LPSl Pump...

A. A because HPSl Pump B is injecting to Hot Leg 1 B. A because HPSl Pump B is injecting to Hot Leg 2.

C. B because HPSl Pump B is injecting to Hot Leg 1.

D. B because HPSl Pump B is injecting to Hot Leg 2.

Page 48 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 046 Given the following:

The plant is at 50% power.

A CCW System leak is in progress.

The crew is performing actions of OP-901-510, Component Cooling Water System Malfunction.

Makeup from the Condensate Storage Pool (CSP) has just been initiated.

CCW Surge Tank level is 28% and lowering at 1% per minute.

CSP level is currently 97%.

Which ONE of the following parameters will be the FIRST to require entry into a Technical Specification LCO?

A. CCW Surge Tank level is reduced below 24%

B. CCW Surge Tank level is reduced below 20%

C. CSP level is reduced below 92%

D. CSP ievei is reduced below 11 YO Page 49 of 103

U.S. N. R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 047 Given the following:

0 The crew has evacuated the Control Room due to a fire in CP-8.

0 The crew has entered OP-901-502, Evacuation of the Control Room and Subsequent Plant Shutdown.

0 The SM has directed restoring Pressurizer Proportional Heaters.

To complete this action, the operator will: [Assume each is the only action taken.]

A. At LCP-80 SB place key-operated Isolation Switch SS/1055 to ISOLATE and close the 32A Feeder Breaker locally using the Permissive button.

B. At LCP-80 SB place key-operated Isolation Switch SSI1055 to ISOLATE and close the 32B Feeder Breaker locally using the Permissive button.

C. Place the SST 32A FDR PERMISSIVE TO CLOSE Key switch to SWGR and close the 32A Feeder Breaker locally using the Permissive button and breaker hand switch D. Place the SST 328 FDR PERMISSIVE TO CLOSE Key switch to SWGR and close the 32B Feeder Breaker locally using the Permissive button and breaker hand switch Page 50 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 048 Given the following:

0 The plant was at 100°/~ power.

0 A load rejection occurred.

0 Reactor Trip on High Pressure was generated, but the reactor did not trip.

Which ONE of the following describes the additional automatic action that takes place to shut down the reactor?

Diverse Reactor Trip System actuates at A. 2350 PSlA to open CEDM MG Set feeder breakers.

5. 2350 PSIA to open CEDM MG Set load contactors.

C. 2435 PSlA to open CEDM MG Set feeder breakers.

D. 2435 PSlA to open CEDM MG Set load contactors.

Page 51 of 103

Question 049 U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Initial Conditions:

0 A SGTR has occurred in SG #I.

0 RCS Cooldown and Depressuriz ti are in rog r in dance with OP-902-007, Steam Generator Tube Rupture Recovery.

Current Conditions:

RCS pressure 1050 PSlA 0

RCS temperature (REP CET) 51 0°F SG pressures 900 PSlA (#I )

800 PSlA (#2)

Which ONE of the following describes the value of RCS subcooling, and whether the MINIMUM RCS subcooling requirement is met for OP-902-0072 A. 33°F; met B. 19°F; NOT met C. 41°F; met D. 14°F; NOT met Page 52 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 050 Given the following:

The plant trips from 100% power.

0 An ESD has occurred downstream of the MSlV on SG #I.

Steam Generator pressures are as follows:

o #I SG 660 PSIA.

o #2 SG 680 PSIA.

Which ONE of the following describes the valve alignment associated with the SGs for this condition?

A. MSlVs on both SGs closed; EFW flow isolated to both SGs.

B. MSlVs on both SGs closed; EFW flow available to ONLY ONE SG.

C. MSlVs on both SGs open; EFW flow isolated to both SGs.

D. MSlVs on both SGs open; EFW flow available to ONLY ONE SG.

Page 53 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 051 Given the following:

0 A Loss of Main Feedwater has occurred.

The crew is performing OP-902-006, Loss of Main Feedwater Recovery.

EFW Pump A is tagged out.

EFW Pump B has tripped on overcurrent.

0 EFW Pump AB is feeding both SGs.

BOTH SG narrow ranges are off-scale low.

CSP level is 24% and lowering slowly.

Which ONE of the following describes the action required in accordance with OP-902-006?

A. Throttle EFW flow in accordance with Appendix 2-G, Condensate Inventory Curves, to ensure cooldown requirements may be met.

B. Transfer EFW Pump suction to ONE operating train of ACCW.

C. Transfer EFW Pump suction to BOTH operating trains of ACCW.

D. Locally throttle open CMU-141, Condensate Storage Pool LCV Bypass, and throttle EFW flow to minimum allowable.

Page 54 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 052 Given the following:

0 A loss of off-site power has occurred.

0 Both EDGs start automatically.

0 The following parameters were obtaineG upon comp,&ion of EDG start:

0 EDG A voltage 4000 volts 0

EDG A frequency 59.8 Hz 0

EDG B voltage 4400 volts 0

EDG B frequency 60.9 Hz Which ONE of the following describes the operation of the EDG output breakers for this event, and the indication that will be seen on the EDG MW output?

A. BOTH EDG output breakers will automatically close; MW output will immediately rise upon breaker closure.

B. Both EDG output breakers will automatically close; MW output will not rise until load sequencing is initiated after a time delay.

C. ONLY ONE EDG output breaker will close; MW output will immediately rise upon breaker closure.

D. ONLY ONE EDG output breaker will close; MW output will not rise until load sequencing is initiated after a time delay.

Page 55 of 103

U.S. N. R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 053 Given the following:

The plant is at 70% power.

Auxiliary Component Cooling Water Pump A is running 0

A loss of SUPS MA has occurred.

NOTE:

ACC-l26A, CC HX A ACC OUTLET TCV CMU-407A, WET COOLING TOWER A LEVEL CONTROL VALVE CMU-4lOA, WET COOLING TOWER A LCV BYPASS Which ONE of the following action(s) will be required to control Component Cooling Water temperature, and reason for the action(s)?

A. ACC-I 26A fails closed; manually control Dry Cooling Tower (DCT) and Wet Cooling Tower (WCT) Train A fans based on a loss of temperature control.

B. CMU-407A fails open; close CMU-41 OA to prevent a high WCT Basin level.

C. ACC-126A fails open; manually control DCT and WCT Train A fans because power is lost to the DCT A Sequencer and WCT A Fan logic.

D. CMU-407A fails closed; manually throttle CMU-407A to maintain WCT Basin level.

Page 56 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 054 Given the following:

At 1800, a reactor trip occurred due to a station blackout.

At 1810, the crew entered OP-902-005, Station Blackout Recovery At 181 5, the CRS directs the ATC operator to reduce battery loads.

Which ONE of the following describes the clock time limit to accomplish these actions and the reason for those actions?

A. 1845; meet two hour coping time for restoration of AC power.

B. 1830; meet two hour coping time for restoration of AC power.

C. 1845; meet four hour coping time for 125 VDC buses to carry vital loads.

D. 1830; meet four hour coping time for 125 VDC buses to carry vital loads.

Page 57 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 055 Given the following:

0 The plant is on Shutdown Cooling.

0 RCS Temperature is 280' F.

0 RCS pressure is 325 PSIA.

0 CCW Surge Tank Level has lowered from 40% to 30% in 20 minutes.

CCW Makeup is initiated.

0 Pressurizer Level is 60% and stable.

0 VCT level is 73% and stable.

Which ONE of the following is causing the drop in CCW Surge Tank Level?

A.

Letdown Heat Exchanger tube leak.

B.

Spent Fuel Pool heat exchanger tube leak.

C.

Shutdown Cooling heat exchanger tube leak.

D.

RCP Seal Cooler tube leak.

Page 58 of 103

U.S. N. R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 056 Given the following:

0 The plant is at 100% power.

0 A leak on the Instrument Air system has occurred.

0 The crew is performing actions of OP-901-51 I, Instrument Air Malfunction.

0 Instrument Air header pressure is 90 PSlG and slowly lowering.

In accordance with OP-901-511, which ONE of the following conditions requires the crew to consider initiation of a plant shutdown in accordance with OP-010-005, Plant Shutdown?

A. Immediately based on current Instrument Air header pressure.

B. If

c. If nstrument Air pressure cannot be maintained above 80 PSIG.

nstrument Air pressure cannot maintain Pressurizer Normal Spray valves operable.

D. If Instrument Air pressure drops below 65 PSlG at ANY time.

Page 59 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 057 Given the following:

0 Plant startup to 100% is in progress.

Reactor power is at 70%.

0 The following conditions are observed:

o Reg Group 6 CEAs indicate 100 inches.

o Loop 2 Tave has lowered by 15°F since the last CEA withdrawal.

o Core Exit thermocouple indication has lowered by IO-13°F near Loop 2.

o CPC B power indication is 76%.

o CPC A, C and D indication is 82%.

Which ONE of the following describes the cause of these indications?

A. Xenon oscillation.

B. Dropped CEA C. RCP degraded flow D. Inadvertent SG safety valve lift Page 60 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 058 The plant is at 100% power Which ONE of the following plant conditions requires verification of Shutdown Margin within one hour, and the reason why Shutdown Margin must be verified?

A. One CEA is determined to be immovable; Shutdown Margin calculations do not account for immovable CEAs.

B. One CEA is determined to be immovable; Shutdown Margin calculations account for only ONE immovable CEA.

C. One CEA is misaligned from its group by 6 inches; Shutdown Margin calculations do not account for misaligned CEAs.

D. One CEA is misaligned from its group by 6 inches; Shutdown Margin calculations account for only ONE misaligned CEA.

Page 61 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 059 Given the following:

0 The plant is operating at 100% power.

0 Pressurizer Level control is selected to Channel X.

0 Pressurizer Level Channel X indicates 0 %.

0 Pressurizer Level Channel Y indicates 55 %.

Which ONE of the following describes the status of Charging and Letdown?

A. Backup charging pumps stop if running, letdown flow drops to minimum.

B. Backup charging pumps stop if running, letdown flow rises to maximum.

C. Backup charging pumps start, letdown rises to maximum.

D. Backup charging pumps start, letdown flow drops to minimum.

Page 62 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 060 Given the following:

0 The plant is at 100% power.

o The following annunciators are received:

o RAD MONITORING SYS ACTIVITY HI-HI on CP-36 o CLASS 1 E RAD MONITORING SYS ACTIVITY HI-Hi on CP-18 0

CROAI A NORTH (0200.1) rad monitor indicates red with a rising trend 0

CROAI B NORTH (0200.2) rad monitor indicates red and off-scale high Which of the following actions will occur as a result of this condition?

A. Control Room Toilet Exhaust Fans start. BOTH Control Room Emergency Filtration Units A and B start.

B. Control Room Toilet Exhaust Fans start. ONLY ONE Control Room Emergency Filtration Unit starts.

C. Control Room Toilet Exhaust Fans stop. BOTH Control Room Emergency Filtration Units A and B start.

D. Control Room Toilet Exhaust Fans stop. ONLY ONE Control Room Emergency Filtration Unit starts.

Page 63 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 061 Given the following:

0 A LOCA has occurred.

0 The following alarm reflashes on Control Room Panel SA:

o K-4, CLASS 1E RAD MONITORING SYS ACTIVITY HI-HI 0

The RO verifies Containment Radiation on ARM-IRE-5400ASI Cntmt Rad Monitor Hi Range A, has spiked to approximately 3500 RemlHr.

0 Approximately 1 minute later, Containment Radiation indication is 300 Rem/Hr and lowering.

Which ONE of the following describes the reason for the radiation monitor indication?

A. Initiation of Containment Spray has reduced iodine levels.

B. Blowdown phase of the LOCA resulted in high radiation indication. Refill and reflood phases are reducing radiation levels in Containment.

C. Failure of the radiation monitor, as it is not qualified for harsh Containment environment, and not required for safety related use.

D. Thermally induced currents due to harsh Containment environment, location of detector, and length of cabling.

Page 64 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 062 With SG pressure at 1060 PSIA, which ONE of the following conditions indicate core uncovery during a SBLOCA?

A. Representative CET temperature 570°F; RCS pressure 1020 PSlA B. Representative CET temperature 580°F; RCS pressure 1375 PSIA C. Representative CET temperature 590°F; RCS pressure 1550 PSlA D. Representative CET temperature 600°F; RCS pressure 1720 PSlA Page 65 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 063 Given the following:

0 Off-Site power was lost 20 rr,,,wtes ago.

The crew is performing OP-902-003, Loss of Offsite Power/Loss of Forced Circulation Recovery.

Which ONE of the following describes a MINIMUM criterion for verifying single phase natural circulation, and the action required if it CANNOT be verified?

A. Loop AT less than 58°F on BOTH loops; adjust feeding and steaming of SGs.

B. Loop AT less than 58°F on at least ONE loop; ensure all available Charging pumps are operating.

C. Loop AT less than 58°F on BOTH loops; ensure all available Charging pumps are operating.

D. Loop AT less than 58°F on at least ONE loop; adjust feeding and steaming of SGs.

Page 66 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 064 Given the following:

0 0

0 0

e 0

0 0

0 0

0 0

An RCS leak is in progress.

Reactor Drain Tank level has been rising steadily.

Reactor Drain Tank temperature is rising.

ONE Charging Pump is operating.

Letdown flow is 28 GPM.

RCP Controlled Bleedoff Flow is 5.5 GPM.

Pressurizer Level is stable.

RCS temperature is stable.

Containment PIG radiation monitor indication is stable.

Containment Sump level is stable.

A plant shutdown has been commenced.

Power has been lowered by 10% in the past 30 minutes.

Which ONE of the following describes the Technical Specification leakage limit being exceeded, and the notification required?

A. Identified leakage exceeds the limit; notify Chemistry to sample iodine due to power change.

B. Identified leakage exceeds the limit; notify Radiation Protection for radiological support as required.

C. Unidentified leakage exceeds the limit; notify Chemistry to sample iodine due to power change.

D. Unidentified leakage exceeds the limit; notify Radiation Protection for radiological support as required.

Page 67 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 065 Given the following:

A reactor trip has occurred.

0 Two CEAs failed to insert on the reactor trip.

0 Emergency Boration is not in progress.

RCS pressure is 1690 PSIA.

0 Containment pressure is 15.2 PSIA.

0 RCS temperature is 380" F and lowering slowly.

0 The crew has diagnosed and entered OP-902-008, Functional Recovery.

Which ONE of the following describes the operation of RCPs for these conditions and the basis?

A. ALL RCPs must be stopped; loss of cooling water.

B. No more than TWO RCPs operating; loss of cooling water C. ALL RCPs must be stopped; low RCS temperature causing core uplift problems.

D. No more than TWO RCPs operating; low RCS temperature causing core uplift problems.

Page 68 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator BDELT PMC PID C24104 MSBSRAW PMC PID C24631 Question 066 28.9%

29.3%

Given the following:

FWBSRAW PMC PID C24630 USBSRAW PMC PID C24629 0

Plant Startup in progress.

0 Power is at 30% and holding.

The ATC is taking Tech Spec Logs when the UFM fails.

0 The following data is available:

31 2%

28.8%

o Plant power change was 3% over the last hour.

o Indicated PMC Power is:

/ Sec Calorimetric PMC PID C24230 I 29.9% I Which ONE of the following power indications will be logged in Attachment 11.I of OP-903-001, Technical Specification Surveillance Logs?

A. 28.9%

B. 29.3%

C. 29.9%

D. 31.2%

Page 69 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 067 Given the following:

The plant is in MODE 5.

Which ONE of the following identifies the RCS Pressure Safety Limit, and the MAXIMUM time allowed to reduce RCS pressure below the safety limit in accordance with Technical Specifications?

A. 2735 PSIA; 5 minutes B. 2735 PSIA; 15 minutes C. 2750 PSIA; 5 minutes D. 2750 PSIA; 15 minutes Page 70 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 068 Given the following :

0 The plant is in MODE 6.

Which ONE of the following describes the MINIMUM required Source Range Neutron Flux Monitors prior to commencing core off-load?

A.

C.

D.

Visual in CR 1

2 1

2 Audible in CR 0

1 1

2 Audible in CTMT 1

1 1

2 Page 71 of 103

U.S. N. R. C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 069 Which ONE of the following describes the personnel required to grant permission to commence Core Alterations?

A. Containment Coordinator and Shift Manager

6. Refueling SRO and Shift Manager C. Shift Manager and Refuel Director

0.

Refuel Director and Refueling SRO Page 72 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 070 Given the following:

0 The plant is in MODE 5.

Emergency Feedwater Pump A is out of service.

Which ONE of the following describes the HIGHEST OPERATIONAL MODE that may be entered with the pump out of service?

A. MODE4 B. MODE3 C. MODE2 D. MODE1 Page 73 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 071 Given the following:

A LOCA has occurred.

A General Emergency has been declared.

The Emergency Response Organization is fully staffed.

An operator has suffered life-threatening injuries in the RAB.

Which ONE of the following describes the MAXIMUM TEDE dose allowed to attempt a rescue of the individual, in accordance with EP-002-030, Emergency Radiation Exposure Guidelines and Controls, and whether the limits may be exceeded?

A. 25 Rem; may NOT be exceeded under any circumstances.

B. 25 Rem; may ONLY be exceeded by volunteers fully aware of the risks involved.

C. 75 Rem; may NOT be exceeded under any circumstances.

D. 75 Rem; may ONLY be exceeded by volunteers fully aware of the risks involved.

Page 74 of 103

U.S. N. R. C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 072 Given the following:

0 Containment Purge is in progress on a Continuous Release Permit.

0 A Gas Decay Tank release is planned.

Which ONE of the following describes the restriction, if any, associated with the Gas Decay Tank release with Containment Purge in progress?

A. The release may proceed because Containment Purge is on a Continuous release.

B. The release must be postponed until the Containment Purge is complete.

C. The release may NOT be performed because Containment Purge is on a Continuous release.

D. The release may be performed ONLY if Plant Stack flow is raised AND ambient barometric pressure is within limits.

Page 75 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 073 An accessible area with a dose rate of 96 mRem per hour and contamination level of 132,550 dpm/lOO cm2 beta-gamma will be posted as a...

A.

B.

C.

D.

Contamination Area and Radiation Area Contamination Area and High Radiation Area High Contamination Area and Radiation Area High Contamination Area and High Radiation Area Page 76 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 074 Given the following:

0 A LOCA has occurred.

The crew is performing EOP actions related to the event.

The Emergency Response Organization has been staffed.

Which ONE of the following describes the radio frequency that will be used for emergency activities, and who has the PRIMARY responsibility for completion of the Notification Message Forms (NMF)?

A. Operations Channel; Emergency Communicator.

B. Maintenance C han ne1 ; Emergency Communicator.

C. Operations Channel; Shift ManagedEmergency Coordinator D. Maintenance Channel; Shift ManagedEmergency Coordinator.

Page 77 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 075 What is the basis for the step in OP 902-006, Loss of Main Feedwater Recovery, that requires the operators to ensure RCPs are stopped?

A. Prevent overpressurization of the RCS.

6. Prevent excessive loss of RCS inventory.

C. Prevent operating RCPs without adequate NPSH.

D. Eliminate RCP heat input into the RCS.

Page 78 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 076 Given the following:

A failure of SBCS resulted in an automatic LPD trip.

0 Reactor Trip Circuit Breakers remained closed.

0 The crew attempted to trip the reactor manually.

0 The RO performed ALL contingency actions for Reactivity Control.

4 CEAs remained stuck fully out.

0 The crew is unable to establish Emergency Boration due to Volume Control Tank Discharge Valve (CVC-183) failed open.

0 Reactor power is stable at 8%.

What are the proper actions by the operating crew in response to this event?

A.

Refer to OP-901-103, Emergency Boration, while continuing in OP-902-000.

B.

Immediately transition to OP-902-008, Safety Function Recovery Procedure.

C.

Complete the Standard Post Trip Actions, then diagnose a Reactor Trip Recovery event in accordance with OP-902-001.

D.

Complete the Standard Post Trip Actions, then diagnose a Functional Recovery entry in accordance with OP-902-008.

Page 79 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 077 Given the following:

Initial Conditions 0

The plant is in MODE 6.

0 Refueling Cavity level is 24 feet above the Reactor Vessel Flange.

The plant has been shutdown for 244 hours0.00282 days <br />0.0678 hours <br />4.034392e-4 weeks <br />9.2842e-5 months <br />.

RCS temperature is 109°F.

0 Shutdown Cooling Train B is in service.

Current Conditions 0

LPSl Pump B trips and cannot be restarted.

0 RCS temperature has risen to 118°F.

Which ONE of the following describes the MINIMUM Shutdown Cooling flow, and the MAXIMUM RCS cooldown rate allowed by Technical Specifications when flow is restored?

A. 4000 GPM; 50"FIHr B. 4000 GPM; 100"F/Hr.

C. 3000 GPM; 50"F/Hr.

D. 3000 GPM; IOO"F/Hr.

Page 80 of 103

U. S. N. R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 078 Given the following:

The plant is at 100% power.

An inadvertent CSAS occurs.

0 The crew entered OP-901-504, inadvertent ESFAS Actuation.

0 CC-710, RCP Outlet Inside Isolation Valve cannot be opened.

0 The crew trips the reactor and secures ALL Reactor Coolant Pumps.

Which ONE of the following describes: (1) the time limit for securing RCPs with no CCW flow, (2) the time limit for restoration of CCW flow, and (3) the reason for these time limits.

(1)

(2)

(3)

A.

10 minutes 3 minutes Seal failure and potential RCS to CCW leak.

B.

10 minutes 10 minutes Waterhammer and potential SBLOCA.

C.

3 minutes 10 minutes Seal failure and potential RCS to CCW leak.

D.

3 minutes 3 minutes Waterhammer and potential SBLOCA.

Page 81 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 079 Which ONE of the following events requires notification to the NRC within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />?

A.

Initiation of a plant shutdown in accordance with T.S. 3.0.3 E.

Vehicle crash in the Owner Controlled Area C.

D.

Confirmed violation of Fitness for Duty requirements Pressurizer Safety Valve failure resulting in SlAS actuation and SI flow to the core Page 82 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 080 Given the following:

0 The reactor has tripped.

0 A Steam Generator Tube Rupture is in progress.

0 The crew is performing OP-902-007, Steam Generator TLde Rupture Recovery.

0 SG # I has been diagnosed as the ruptured SG and has been isolated.

0 Containment pressure is 16.6 PSIA and rising slowly.

0 Containment temperature is 118°F and rising slowly.

0 Containment Area Radiation Monitors are rising.

Which ONE of the following describes the status of Containment Safety Functions, and the action required?

A. ONLY Containment Temperature and Pressure Control is NOT satisfied; remain in OP-902-007 while restoring Containment parameters to normal.

B. ONLY Containment Temperature and Pressure Control is NOT satisfied; go to OP-902-008, Functional Recovery to mitigate the symptoms of multiple events.

C. Containment Isolation AND Containment Temperature and Pressure Control are NOT satisfied; remain in OP-902-007 while restoring Containment parameters to normal.

D. Containment Isolation AND Containment Temperature and Pressure Control are NOT satisfied; go to OP-902-008, Functional Recovery to mitigate the symptoms of multiple events.

Page 83 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 081 Given the following:

Initial conditions 0

The plant is at 50% power.

0 Main Feedwater Pump B is out of service.

0 EDG B is out of service.

Main Feedwater Pump A trips.

EFAS-1 and EFAS-2 actuate.

0 EFW Pump AB trips.

20 minutes later Off-site power is lost.

3 minutes later 0

EDG A trips.

Which ONE of the following describes the sequence of EOP entry for these events following completion of Standard Post Trip Actions?

A. OP-902-006, Loss of Main Feedwater Recovery; OP-902-008, Functional Recovery, when off-site power is lost.

B. OP-902-006, Loss of Main Feedwater Recovery; OP-902-008, Functional Recovery, when EDG A is lost.

C. OP-902-001, Reactor Trip Recovery; OP-902-008, Functional Recovery, when off-site power is lost.

D. OP-902-001, Reactor Trip Recovery; OP-902-008, Functional Recovery, when EDG A is lost.

Page 84 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 082 Given the following:

0 The plant is at 100% power.

0 The following indications are observed for ONE of the Regulating Group 5 CEAs:

o Amber light on the CEA Mimic is lit.

o Pulse Counter indication is zero.

o RSPT 1 and 2 indicate zero.

Which ONE of the following describes the status of the affected Core Protection Calculator (CPC) position indication, and an action required related to the condition?

A. Operable; immediately declare COLSS inoperable.

B. Operable; declare COLSS inoperable if the CEA cannot be realigned within the required ti me requirement.

C. Inoperable; immediately declare COLSS inoperable.

D. Inoperable; declare COLSS inoperable if the CEA cannot be realigned within the required time requirement.

Page 85 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 083 Given the following:

A LOCA occurred.

All Emergency Planning facilities have been staffed.

0 The TSC reports that Containment Penetration #54 has been breached.

Which ONE of the following describes the (1) actions required, (2) time limit for the actions, and (3) the Technical Specification bases?

(1)

(2)

(3)

A. Isolate the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Ensure dose at the EAB is limited to 25 affected penetration during the release.

mRem TEDE for any 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> period B. Pressurize 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Ensure Control Room dose does not exceed 5 Rem TEDE for the duration the Control Room of the accident.

C. Isolate the 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Ensure dose at the EAB is limited to 25 affected penetration during the release.

mRem TEDE for any 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> period D. Pressurize 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Ensure Control Room dose does not exceed 5 Rem TEDE for the duration the Control Room of the accident.

Page 86 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 084 Given the following:

The plant is at 60% power.

The following alarms are received on Cabinet H:

o o A-I, PRESSURIZER LEVEL HI-HI B-I, PRESSURIZER LEVEL HVLO Letdown flow is rising.

PZR level indicator RC-ILI-11 OX indicates 75% and rising.

PZR level indicator RC-ILI-1 1OY indicates 40% and lowering.

NOTE:

OP-901-1 10, Pressurizer Level Control Malfunction OP-901-112, Charging and Letdown Malfunction Which ONE of the following describes the appropriate procedure and associated subsection for the failure, and the action req A.

B.

C.

D.

OP-901-1 I O, Subsection E2;start or stop Charging Pumps as necessary.

OP-901-110, Subsecti OP-901-110, Subsecti Valves controller (RC-IHIC OP-901-112; Subsection Valves controller (RC-IHIC-01 IO).

t the non-faulted control channel.

i. J l l e c tiri... i [* I i-b anual control of Letdown Flow Control manual control of Letdown Flow Control Page 87 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 085 Given the following:

0 The control room has been evacuated due to a fire in the Cable Spreading Room.

0 The crew has established controi at LCP-43 in accordance with OP-901-502, Evacuation of Control Room and Subsequent Plant Shutdown.

0 RCS cooldown and depressurization is in progress.

0 The ATC reports indications of RCS voiding.

Which ONE of the following describes the expected indications and the required operator action?

Pressurizer Pressurizer Level Pressure Action A.

Rising Dropping Match Charging and Letdown flow; stop depressurization; slowly raise Pressurizer Pressure.

B.

Dropping Rising Stop depressurization; raise Pressurizer Level to 50%; slowly raise Hot Leg I Pressure.

C.

Dropping Rising Match Charging and Letdown flow; stop depressurization; slowly raise Pressurizer Pressure.

D.

Rising D ro p p i ng Stop depressurization; raise Pressurizer Level to 50%; slowly raise Hot Leg 1 Pressure.

Page 88 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator D.

Question 086 NOT MET Given the following:

0 A reactor trip has occurred.

0 The crew is performing OP-902-000, Standard Post Trip Actions.

0 Pressurizer pressure indicates 1900 PSlA and lowering slowly.

0 Pressurizer level indicates 22% and stable.

0 All available Charging Pumps are running.

0 Containment temperature is 1 15°F and rising slowly.

0 Containment pressure is 16.0 PSlA and rising slowly.

Which ONE of the following describes the status of the RCS Pressure Control (PC) and Containment Temperature and Pressure Control (CTPC) safety functions, and the required mitigation strategy?

1 MET None None Restore and maintain Pressurizer Pressure 21 25 PSlA to 2275 PSIA by operating heaters.

Verify no more than two RCPs running.

MET NOT MET MET NOT MET None Verify ALL available Containment Fan Coolers are operating in emergency mode.

None Verify at least three Containment Fan Coolers are operating.

Page 89 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 087 Given the following:

The plant is at 100% power.

0 PPS Channel A is in BYPASS for RPS trip testing.

0 A loss of SUPS MB occurs.

NOTE:

OP-902-000, Standard Post Trip Actions OP-901-312, Loss of Vital Instrument Bus Which ONE of the following describes the impact on the plant, and the action required?

A. The reactor will trip; perform actions of OP-902-000; TS LCO 3.8.3.1 for On-Site electrical distribution may be exited when SUPS MB is restored.

B. The reactor will trip; perform actions of OP-902-000; TS LCO 3.8.3.1 for On-Site electrical distribution remains applicable after the reactor is tripped and the plant is stabilized in MODE 3.

C, The reactor will NOT trip; perform actions of OP-901-312; TS LCO 3.3.1 for RPS Instrumentation may be exited when both PPS channels are restored.

D. The reactor will NOT trip; perform actions of OP-901-312; TS LCO 3.3.1 for RPS Instrumentation may be exited when either PPS Channel A is removed from BYPASS SUPS MB is restored.

Page 90 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 088 Given the following:

0 The plant is at 60% power.

0 A large feedwater line break occurs at the feedwater inlet piping weld connection to SG #I.

0 A reactor trip occurs.

0 Containment pressure is rising.

Which ONE of the following describes the impact on the plant, and the procedure diagnosis upon transition from OP-902-000, Standard Post Trip Actions?

A. SG #I pressure will lower until stabilized by the MSIS signal; OP-902-004, Excess Steam Demand Recovery.

B. SG #I pressure will lower until stabilized by the MSlS signal; OP-902-006, Loss of Main Feedwater Recovery.

C. SG #I pressure will lower and will continue to lower after the MSIS signal is generated; OP-902-004, Excess Steam Demand Recovery.

D. SG #I pressure will lower and will continue to lower after the MSIS signal is generated; OP-902-006, Loss of Main Feedwater Recovery.

Page 91 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 089 Given the following:

0 The plant is at 100% power.

0 DC Bus A voltage indicates 75 VDC and lowering.

Which ONE of the following describes the procedure entry requirements for these co nd it ions?

A. OP-901-313, Loss of a 125 Volt DC Bus ONLY.

B. OP-902-000, Standard Post Trip Actions ONLY.

C. OP-902-000 is performed to completion, and then actions of OP-901-313 are performed to restore DC Bus A.

D. OP-902-000 and OP-901-313 are performed concurrently to stabilize the plant.

Page 92 of 103

U.S.N.R,C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 090 Given the following:

The plant is at 100% power.

0 TCW Pump B is in service.

0 TCW Pump A is tagged for repair.

The following alarms are received on Cabinet E:

o o

F-IO, TURB CLNG WTR PUMP B TRIP/TROUBLE E-9, TURB CLNG WATER DISCH HDR PRESS LO 0

Operator actions fail to restore TCW flow.

NOTE:

0 OP-901-512, Loss of Turbine Cooling Water OP-901-212, Rapid Plant Power Reduction Which ONE of the following describes the impact of this event, and the procedural actions required for these conditions?

A. Generator Winding damage; enter OP-901-512; trip the reactor based on loss of all turbine cooling water.

B. Loss of Main Turbine Lube Oil; enter OP-901-512; trip the reactor based on inability to maintain Main Turbine lube oil cooling.

C. Generator Winding damage; refer to alarm response procedures and initiate a plant shutdown in accordance with OP-901-212; remove the main generator from service.

D. Loss of Main Turbine Lube Oil; refer to alarm response procedures and initiate a plant shutdown in accordance with OP-901-212; remove the main turbine from service based on inability to maintain Main Turbine lube oil cooling.

Page 93 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 091 Given the following:

0 The plant has shut down for refueling.

0 The following timeline of events is available:

o 1330, 3/18/2008, Reactor Trip Breakers are open.

o 1830, 3/18/2008, MODE 4 conditions reached.

o 0015, 3/19/2008, MODE 5 conditions reached.

o 1000, 3/20/2008, MODE 6 conditions reached.

o 1200, 3/21/2008, Refueling Cavity is filled to greater than the TS limit.

Which ONE of the following describes the EARLIEST time that fuel may be removed from the reactor vessel in accordance with RF-005-001, Fuel Movement?

A. 1200, 3/21 /2008 B. 1330, 3/21/2008 C. 0015, 3/22/2008 D. 1000, 3/23/2008 Page 94 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 092 Given the following:

0 The plant is at 100% power.

0 SG #2 level transmitter SG-ILT-1121 is rising and currently indicates 88% NR.

All other SG #2 NR level indications are stable.

NOTE:

0 OP-901-201, Steam Generator Level Control Malfunction 0

OP-902-000, Standard Post Trip Actions 0

OP-902-001, Reactor Trip Recovery Which ONE of the following describes the impact on the plant and the action required?

A. SG #2 High Level Override will actuate; enter OP-901-201 and place all FWCS

1. 2 controllers in MANUAL.

B. SG #2 High Level Override will actuate; perform OP-902-000. SG level control will be restored in OP-902-001.

C. FWCS #2 controilers shift to MANUAL; enter OP-901-201 and stabilize SG ievei in accordance with the General Actions flow chart.

D. FWCS #2 controllers shift to MANUAL; perform OP-902-000 while restoring Feedwater control to SG #2 in accordance with OP-901-201.

Page 95 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 093 Given the following:

0 The plant is at 100% power.

0 The following alarm is received on Cabinet E:

O B-I 1, CW PUMP A TRIPTTROUBLE 0

Circ Water Pump A control switch amber light is illuminated.

Condenser Vacuum indicates 25 INHG and slowly lowering.

NOTE:

0 OP-500-005, Annunciator Response For Control Room Cabinet E 0

OP-901-212, Rapid Plant Power Reduction 0

OP-901-220, Loss of Condenser Vacuum 0

OP-901-313, Loss of a 125 Volt DC Bus Which ONE of the following describes the procedure and action required?

A. Enter OP-500-005; dispatch an operator to determine and correct the cause of the pump trip, and attempt to restart the pump.

B. Enter OP-901-220; ensure all Condenser Vacuum Pumps are operating and Air Separator sight glasses are less than half full of water.

C. Enter OP-500-005; dispatch an operator to check Control Power for Load Breakers 1A Switchgear (DC) Closed. Refer to OP-901-313.

D. Enter OP-901-220; ensure all Condenser Vacuum Pumps are operating, and commence a rapid power reduction in accordance with OP-901-212.

Page 96 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 094 What ONE of the following is the MOST RESTRICTIVE event associated with Technical Specification require men ts for Shutdown Margin?

A.

Excessive cooldown resulting from a Main Steam Break at end of core life from 0% power conditions.

B.

Positive reactivity addition resulting from a Rod Ejection event at end of core life from 100% power conditions.

C.

Positive reactivity addition resulting from a Rod Ejection event beginning of core life from 0% power conditions.

D.

Excessive cooldown resulting from a Main Steam Break at beginning of core life from 100% power conditions.

Page 97 of 103

U.S.N.R.C. Site-Specific Written Examination Watetford 3 Senior Reactor Operator Question 095 Given the following:

0 0

0 0

The plant is in MODE 3.

RCS heatup is in progress.

All RCPs are in operation.

RCS Tcold indication over the last 60 minutes is as follows:

o T= (-) 60 minutes Loop 1A Tcold 385°F Loop 1B Tcold 385°F Loop 2A Tcold 388°F

. Loop 2B Tcold 387°F Loop 1A Tcold 446 O F Loop 1B Tcold 446°F Loop 2A Tcold 449" F

. Loop 2B Tcold 448" F o T= 0 minutes (current time)

Which ONE of the following describes the Technical Specification implications of the RCS heatup rate, and the basis for the heatup rate limit?

A. Within Technical Specification limits; pressure-induced and temperature-induced stresses being additive at the Reactor Vessel outer wall.

B. Within Technical Specification limits; pressure-induced and temperature-induced stresses providing off-setting forces at the Reactor Vessel outer wall.

C. Exceeds Technical Specification limits; pressure-induced and temperature-induced stresses being additive at the Reactor Vessel outer wall.

D. Exceeds Technical Specification limits; pressure-induced and temperature-induced stresses providing off-setting forces at the Reactor Vessel outer wall.

Page 98 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 096 Which ONE of the following describes the (1) Technical Specification basis for the setpoint of the Local Power Density High reactor trip, and (2) the ONLY parameters that are measured or calculated to provide a direct input to the trip?

The limiting fuel rod does not exceed the fuel design limit for anticipated operational occurrences; RCS Tcold, Excore NI Power, RCS pressure.

The limiting fuel rod does not exceed the fuel design limit for anticipated operational occurrences; Axial Power Distribution, Delta T Power, CEA position.

Ensures actual heat flux does not exceed critical heat flux at a particular core location; RCS Tcold, Excore NI Power, RCS pressure.

Ensures actual heat flux does not exceed critical heat flux at a particular core location; Axial Power Distribution, Delta T Power, CEA position.

Page 99 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 097 Given the following:

The plant is in MODE 5.

Maintenance requests to remove Battery Charger A I from service for scheduled work.

Shutdown EOOS assigned an ORANGE risk level to the configuration resulting from removal of the Charger.

Which ONE of the following describes who can authorize the request to remove the charger from service and the requirement for a qualitative assessment?

A. Duty Plant Manager; qualitative assessment required B. Duty Plant Manager; qualitative assessment NOT required.

C. Shift Manager; qualitative assessment required.

D. Shift Manager; qualitative assessment NOT required.

Page 100 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 098 Given the following:

0 The plant is in MODE 4.

0 The crew is preparing to initiate Containment Purge, OP-002-010, Reactor Auxiliary Building HVAC and Containment Purge.

0 Annual accumulated Containment Purge time for Containment Purge Isolation Valves is as follows:

o CAP-I 03 and CAP-I 04 58 hours6.712963e-4 days <br />0.0161 hours <br />9.589947e-5 weeks <br />2.2069e-5 months <br /> o CAP-203 and CAP-204 57.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> NOTE:

0 CAP-I 03, Containment Purge Inlet Inside Annulus 0

CAP-I 04, Containment Purge Inlet Inside Containment 0

CAP-203, Containment Purge Exhaust Inside Containment 0

CAP-204, Containment Purge Exhaust Inside Annulus Assuming ALL four CAP valves are opened at the same time, which ONE of the following describes the MAXIMUM time the valves may be open prior to entering a Technical Specification LCO, and the release permit requirement?

A. 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br />; a batch release permit is required after 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> of purge operation.

B. 32.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />; a batch release permit is required for the duration of the release.

C. 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br />; a continuous release permit is required after 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> of purge operation.

D. 32.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />; a continuous release permit is required for the duration of the release.

Page 101 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 099 Initial conditions:

0 Steam Generator Tube Rupture has occurred on #I.

0 A manual reactor trip was performed.

On the trip off-site power was lost.

EDG A tripped upon starting and CANNOT be restarted.

Current conditions:

RCS pressure is 1550 PSlA and stable.

1. I SG pressure is 950 PSlA and rising. NR level indicates 90%.

1. 2 SG pressure is 900 PSlA and stable. NR level indicates 45%.

0 Standard Post Trip Actions are complete.

NOTE:

0 OP-902-007, Steam Generator Tube Rupture Recovery OP-902-008, Functional Recovery Which ONE of the following describes the procedure required for this event, and the SG isolation strategy required for the affected SG?

A. OP-902-007; isolate the ADV.

B. 012-902-007; place the ADV in AUTO, controlling at 980 PSIA.

C. OP-902-008: isolate the ADV.

D. OP-902-008; place the ADV in AUTO, controlling at 980 PSIA.

Page 102 of 103

U.S.N.R.C. Site-Specific Written Examination Waterford 3 Senior Reactor Operator Question 100 Given the following:

The plant tripped due to a 300 GPM Loss of Coolant Accident.

OP-902-002, Loss of Coolant Accident Recovery has been entered.

RCS pressure is 1550 PSIA and lowering slowly.

0 Representative CET temperature is 51 5 degrees F and stable.

Five minutes later, the following conditions are observed:

o SG # I level is 20% NR and lowering rapidly.

o Representative CET temperature is 440 degrees F and lowering.

o RCS pressure is 1350 PSIA and lowering.

Which ONE of the following describes the strategy for the current plant conditions?

A. Remain in OP-902-002. Refer to Appendix 13, Stabilize RCS Temperature, and stabilize RCS temperature.

B. Go to the OP-902-004, Excess Steam Demand Recovery, to isolate the SG #I and stabilize RCS temperature.

C. Go to OP-902-008, Functional Recovery, and isolate the SG # I by use of the appropriate RCS Inventory Control Success Path.

D. Go to OP-902-008, Functional Recovery, and isolate the SG #I by use of the appropriate RCS Heat Removal Success Path.

Page 103 of 103

Waterford 3 2008 NRC SRO Written Exam Reference Handout Index Exam Submittal Rev 1 L

I :

Reference:

OP-902-009, STANDARD APPENDICES Appendix 2: -E: HPSl Flow Curve, -F: LPSl Flow Curve OP-901-112, Charging or Letdown Malfunction e : Pressurizer Level Versus Tave Curve Steam Tables

WATERFORD 3 SES STANDARD APPENDICES OP-902-009 Revision 301 Page 10 of 195

~-

1 Appendix2 Page 5 of 40 Figures -E: HPSI Flow Curve RCS Pressure, PSIA 1600 1400 1 200 2-5 I000 E!

2

p.

v 800 u) n-oc O3 0 600 400 200 I

I I

I I

I I

I I \\,

I I

I I

I 1

O I " " !

I I

I I

I " ' " " ' '

0 50 I00 I50 200 250 individual Injection Line Flow Rate (GPM)

End of Attachment 2-E

WATERFORD 3 SES OP-902-009 Revision 301 STANDARD APPENDICES Figures -F: LPSl Flow Curve RCS Pressure, PSlA 0

500 t 000 1500 2000 2500 3000 3500 4000 4500 Train A or B Flow Rate {gpm)

End of Attachment 2-F

,