Text

Final - RO & SRO Written Exam
	ML011920060
Person / Time
Site:	Beaver Valley
Issue date:	06/14/2001
From:	Wooley T; FirstEnergy Nuclear Operating Co
To:	Caruso J; NRC/RGN-I/DRS/OSB
	Conte R
References
	-RFPFR, 05000412/01-301 IR-01-301
	Download: ML011920060 (140)
	v • d • e

Memorandum To:

John Caruso, USNRC From:

Thomas Wooley, FENOC Date:

5/23/01 Re:

BVPS Unit 2 NRC Initial License Written Exam Enclosed is the final version of the NRC Initial License written exam for Beaver Valley Power Station Unit 2. This submittal includes all of the comments that were incorporated following our discussion and from Steve Dennis.

We request these materials to be withheld from public disclosure until after completion of the exam. If you have any questions or require further information, please contact me at (724) 682-5723 or 5479.

2LOT3 NRC Initial License Exam References List Calculator Steam Tables Procedures:

"* 20M-2.4.H, Source Range High Flux At Shutdown Bistable Adjustment

"* 20M-6.4.AAK, PRZR Level High/Low

"* 20M-26.4.AAK, Condenser Vacuum Low/Low-Low

"* F-0.2, Core Cooling (With RVLIS) Critical Safety Function Status Tree

"* F-0.2, Core Cooling (Without RVLIS) Critical Safety Function Status Tree

"* ES-0.2, Natural Circulation, pg. 10-12

"* ES-1.3, Transfer To Cold Leg Recirculation, pg. 2

"* ECA-1. 1, Loss Of Emergency Coolant Recirculation, pg. 11-16

"* FR-C. 1, Response to Inadequate Core Cooling pg. 13-15

"* EOP Attachment A-1.3, Starting Reactor Coolant Pump

"* EOP Attachment A-4.7, Minimum SI Flow Versus Time After Trip

"* EOP Attachment A-5. 1, 0°F Plus Subcooling Based On Core Exit TCs

"* EOP Attachment A-5.5, 50'F Plus Subcooling Based On Core Exit TCs

"* AOP 2.6.4, Steam Generator Tube Leakage

"* AOP 2.10.1, Residual Heat Removal System Loss, Attachment 1 - RCS Heatup Rate With RCS Intact And Initial PRZR Level At 22%

"* AOP 2.10.1, Residual Heat Removal System Loss, Attachment 2 - - RCS Heatup Rate With RCS Level One Foot Below Flange And All Three Loops Isolated

"* AOP 2.10.1, Residual Heat Removal System Loss, Attachment 3 - Boil Off Rate

"* AOP 2.10.1, Residual Heat Removal System Loss, Attachment 4 - Worksheet To Estimate Time To Saturation Graphs and Figures:

"* 20M-10 RHS Figure 10 Required RCS Water Level For Reduced Inventory/Midloop

"* 20M-56C.5.A. 1, Figure 56C RCS Pressure Limits

"* Curve Book CB RCS Cold Overpressurization Protection System Setpoint Program

"* Tank Curve - RWST [2QSS*TK21] Wide Range Level

"* Tank Curve - RWST [2QSS*TK21] Narrow Range Level

2LOT3 NRC Initial License Exam References List Technical Specifications 0

4.0.1 through 4.0.3 - Surveillance Requirement4 3/4.1 through 3/4.10 LCO's Prints:

0 20M VOND Figure 6-1, PRZR Section only 0

20M Figure 38-1, Vital Bus System Sheet 1

UFSAR Logic Diagram Figure 7.3 Reactor Trip Signals

ES-401 BV 412001 SRO ONLY WRITTEN EXAM BV 4/2001 SRO ONLY Form ES-401-9

1.

2.

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

7.

(1-5)

Stem Cues T/F Cred. Partial Job-Minutia

/

0Back-Q=

SRO U/E/S Explanation Focus I Dist.

Link units ward K/A Ony 2

X 6

X 7

X 8

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X 10 X

11 X

12 X

13 X

14 X

17 X

18 X

19 X

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RTL #A5.620.H 1/2-ADM-1303.F08 Page 1 of I Revision 1 EXAMINATION COVER SHEET Training Program: License Operator Initial Training Examination Number:

2LOT3 NRC RO Initial License Exam (6/4/01)

EXAMINATION REVIEW AND APPROVAL Submitted by:

T. Wooley Date:

5 Lo !/0 print Training Systems Date:

Review:

-. /-/ 9 Approved by:

Date:

'/l___o_

I sig~nature EXAMINEE INFORMATION (Please print)

Name:

ANSWER KEY Date:

Employee SSN#

Company:

(Ifother than utility employee)

SCORE Total Possible Points:

100.0 Score:

Graded by:

Date:

name (please print) & initials EXAMINATION POLICY

1. A score of 80 percent or greater is required for successful completion of this examination.

2. Unless specified by the proctor, reference materials and personal notes are not to be used or be visible during the examination.

3. If you have any questions, or need clarification during the examination, remain seated and signal to the proctor.

4.

Unless asking for clarification from the proctor, conversation is prohibited.

5. Biological breaks are limited. Only one examinee at a time is permitted to leave the examination setting while the examination is in progress.

6.

Cheating on an examination will result in failure of the examination and may result in further disciplinary action.

7.

Once you have completed your examination, return your exam to the proctor and receive the correct answers to any missed questions prior to leaving the examination area.

(Please Sian in black Ink)

"By this signature I state that I have neither given nor received aid regarding this examination, prior to or during its administration. The work completed on this examination is my own."

I I., Q;.. +..

Date:

ýPlease Sign in black Ink)

I Exam. nee z 61A,& ulue

ANSWER KEY 2LOT3 RO EXAMINATION (Revised 6/14/01)

1. D

21. C

41. D

61. B

81. A

2. B

22. B

42. D 62 A

82. A

3. D

23. A

43. C

63. B

83. B

4. D

24. D

44. D

64. A

84. B

5. B

25. A

45. D

65. C

85. B

6. B

26. B

46. C

66. A

86. A

7. C

27. D

47. D

67. B

87. D

8. D

28. C

48. A

68. C

88. D

9. D

29. A

49. A

69. B

89. A

10. C

30. D

50. C

70. D

90. C

11. C

31. D

51. A

71. B

91. A

12. B

32. A

52. A

72. A or D

92. A

13. C

33. C

53. A

73. B

93. D

14. B

34. D

54. D

74. C

94. C

15. A

35. D

55. C

75. B

95. D

16. C

36. D

56. D

76. B

96. D

17. B

37. C

57. B

77. C

97. B

18. A

38. C

58. B

78. B

98. A

19. A

39. D

59. B

79. B

99. C

20. C

40. C

60. A

80. B 100. B

Question # I ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference: Level RO SRO Tier #

1 Group #

1 K/A #

026AA 1.05 Importance Rating 3.1 With the Unit at 100% power and all systems in their at-power, NSA configurations, a tube leak has developed in the Seal Water Heat Exchanger. With no operator action, this will result in a -(1)_ in CCP Surge Tank Level, and the CCP surge tank _(2).

(1)_

_(2)_

A. rise will overflow to the Auxiliary Building Sump.

B.

rise relief valve will lift and relieve to the Gaseous Waste Surge Tank.

C.

drop level control valve [2CCP*LCV100A] will open to provide makeup from the Primary Grade Water System.

D. drop level control valve [2CCP*LCV100A] will open to provide makeup from the Demineralized Water System.

Answer:

D Technical Reference(s): 20M Figure 15-1 References to be provided to applicants during examination:

None Learning Objective:

08-02-731, ELO 6.B Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFR Part 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 2 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

1 Group #

2 K/A #

059AA2.01 Importance Rating 3.2 If the Liquid Waste Process Effluent Radiation Monitor, [2SGC-RQI100] failed during a radioactive liquid release, the indicating light on the RM-1 1 console for [2SGC-RQI100]

will flash...

A. magenta, dark blue or light blue even after acknowledged by the operator.

B.

magenta, dark blue or light blue until acknowledged by the operator.

C.

red or amber even after acknowledged by the operator.

D. red or amber until acknowledged by the operator.

Answer:

B Technical Reference(s):

20M-43.4. AAC References to be provided to applicants during examination: None Learning Objective:

08-02-770, ELO 6 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge X

Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 X

Comments:

NUREG-1021, Revision 8

Question # 3 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

1 Group #

2 K/A #

E03EA2.1 Importance Rating 3.4 Note: This is an open reference question.

Given the following:

"* The operators are responding to a small break LOCA and are currently in ES-1.2 - Post LOCA Cooldown and Depressurization.

"* RCS pressure is 1780 psig.

"* CNMT pressure is 1.7 psig.

"* All RCP's are secured.

"* The three maximum core exit thermocouples are 6677F, 6690F, and 670TF.

"* RVLIS full range is 47%.

What color is the core cooling status tree and what is the requirement for the applicable FR procedure usage?

A. Red, applicable FR procedure must be entered.

B.

Orange, applicable FR procedure may be entered at ANSS discretion.

C. Yellow, applicable FR procedure must be entered.

D. Yellow, applicable FR procedure may be entered at ANSS discretion.

Answer:

D Technical Reference(s):

F-0.2 and Att. A-5.1 References to be provided to applicants during examination: Steam Tables, F-0.2, and Att. A-5.1 Learning Objective:

2LP-SQS-53.3, ELO 6 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFR Part 55 Content: 55.41 55.43 X

Comments:

NUREG-1021, Revision 8

Question # 4 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

2 Group #

2 K/A #

002 2.4.20 Importance Rating 3.3 In what sequence should the RCP's be restarted when directed in ES-1.2 - Post LOCA Cooldown and Depressurization?

A. C,B,A B.

A,B,C C. B,A,C D. C,A,B Answer:

D Technical Reference(s):

ES -1.2 References to be provided to applicants during examination:

None Learning Objective:

08-02-714, ELO 4.a Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge X

Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 5 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

I Group #

I K/A #

076AK3.05 Importance Rating 2.9 With the unit at 100% power with all systems in their full power, NSA configurations, which of the following actions should be performed following notification that an RCS crud burst has occurred?

A. Secure RCS letdown flow.

B.

Maximize RCS letdown flow.

C. Place a deborating bed in service.

D. Bypass the CVCS demineralizers.

Answer:

B Technical Reference(s):

20M-43.4 AAF References to be provided to applicants during examination: None Learning Objective:

08-02-770, ELO 6 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge X

Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 6 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

Group #

1 K/A #

027AA2.01 Importance Rating 3.4 Given the following:

"* RCS pressure is 1600 psig and decreasing.

"* SI has actuated.

"* PRZR level is 25% and rising.

Which of the following can be ruled out as the location of the leak?

A. A leaking PRZR PORV.

B.

A break in the PRZR surge line.

C.

A break in the PRZR steam space sample line.

D. A break in the PRZR spray line down stream of the spray valves.

Answer:

B Technical Reference(s):

20M Figure 6.1 References to be provided to applicants during examination: None Learning Objective:

08-02-715, ELO 3 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFR Part 55 Content: 55.41 55.43 X

Comments:

NUREG-1021, Revision 8

Question # 7 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level Tier #

Group #

K/A #

Importance Rating Which of the following is the bases for the SG to RCS D/P, RCP trip criteria?

A. Ensures that the SG's remain a heat sink rather than becoming a heat source as the RCS saturation temperature approaches that of the SG's.

B. Requires the RCP's to be tripped prior to losing adequate #1 seal D/P, thus maintaining RCP seal integrity.

C. Minimizes the liquid mass inventory loss from the RCS during a small break LOCA.

D. Ensures that a minimum net positive suction head is maintained to a running RCP.

Answer:

C Technical Reference(s):

RCP Trip Criteria References to be provided to applicants during examination:

None Learning Objective:

2LP-SQS-53.2, ELO 1 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 10 CFRPart 55 Content: 55.41 X

55.43 Comments:

X NUREG-1021, Revision 8 SRO RO 1

2 009EK3.23 4.2

Question # 8 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

1 Group #

2 K/A #

025AKI.01 Importance Rating 3.9 Note: This is an open reference question.

Given the following:

"* The reactor was shutdown from an extended full power run at 1200 hours0.0139 days 0.333 hours 0.00198 weeks 4.566e-4 months , two days ago.

"* It is currently 1300 hours0.015 days 0.361 hours 0.00215 weeks 4.9465e-4 months .

"* RCS temperature is 190FT.

"* RCS pressure is 235 psig.

"* PRZR level is 22%.

"* A total loss of RHS has occurred.

Using the attachments provided from AOP-2. 10.1, calculate the estimated time to core boiling.

The estimated time to core boiling is A. < 5 minutes.

B.

> 5 minutes and < 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

C.

> 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months but < 2hours.

D. >2 hours.

Answer:

D (132 minutes)

Technical Reference(s):

AOP-2. 10.1, Att. 1, 2, 3 and 4 References to be provided to applicants during examination:

AOP-2. 10. 1, Att. 1, 2, 3 and 4; Steam Tables Learning Objective:

2LP-SQS-53. 1, ELO 8 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFR Part 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 9 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

1 Group #

2 K!A #

038 EKI.02 Importance Rating 3.2 Given the following:

A steam generator tube has ruptured in the 21C SG.

The operators are performing E Steam Generator Tube Rupture.

The cooldown of the RCS has been completed and the RCS has been depressurized to match steam generator pressure.

Which of the following must be done to prevent a restart of the tube leakage from the RCS into the ruptured SG?

A. Steam the intact SG's as necessary to maintain ruptured SG pressure within + 25 psig of the intact SG's.

B. Feed the ruptured SG with AFW as necessary to maintain ruptured SG NR water level > 5% [33% Adverse].

C.

Spray the PRZR as necessary to minimize RCS subcooling and hold the RCS pressure equal to or greater than the ruptured SG pressure.

D. Terminate safety injection, restore normal charging and letdown, and balance RCS pressure to match the ruptured SG pressure.

Answer:

D Technical Reference(s):

E-3 References to be provided to applicants during examination: None Learning Objective:

2LP-SQS-53.3, ELO 6 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFR Part 55 Content:

55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 10 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

I Group #

2 K/A #

E05EKI.3 Importance Rating 3.9 Given the following:

"* The operators are responding to an event and are currently in FR-H. 1, "Response to Loss of Secondary Heat Sink."

"* Attempts to restore feed flow have failed.

"* RCS bleed-and-feed has been established with only one PRZR PORV open.

"* The other two PORVs will not open.

Which of the following actions are required to be taken?

A. Terminate attempts to establish a SG heat sink because one PRZR PORV will provide sufficient bleed flow to permit adequate RCS heat removal.

B.

Continue attempts to open the failed PRZR PORVs and reduce SI flow as necessary to prevent rapid overpressurization of the RCS.

C. Establish alternate RCS bleed paths because one PRZR PORV may not depressurize the RCS sufficiently to permit adequate cooling from the SI flow.

D. Terminate RCS bleed-and-feed because with only one PRZR PORV open, RCS pressure will rise causing SI flow and RCS inventory to drop.

Answer:

C Technical Reference(s):

FR-H. 1 Issue 1B, Rev. 6, Step 17 Basis References to be provided to applicants during examination:

None Learning Objective:

2LP-SQS-53.3, ELO 6 Question Source:

Bank #

LRT NRC Bank # 530Q Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFRPart 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 11 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

1 Group #

2 K/A #

060AA1.02 Importance Rating 2.9 With the Unit at 100% power with all systems in their at-power, NSA configurations, a CREBAPS actuation has automatically shifted the control room ventilation to the recirculation mode of operation. If this was caused by a high _(1)_ signal, _(2)__

minutes later [2HVC-FN241A], Control Room Emergency Supply Fan will _(3).

(1)0

_(2)_

_(3)_

A. radiation 30 start B.

chlorine 30 stop C.

radiation 60 start D. chlorine 60 stop Answer:

C Techmical Reference(s):

20M-44A.1.D References to be provided to applicants during examination: None Learning Objective:

08-02-770, ELO 2 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge X

Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 12 ES-401 Sample Written Examination Form ES-40 1-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

I Group #

2 K/A #

ElIEK2.2 Importance Rating 3.9 Note: This is an open reference question.

Given the following:

"* A Rx trip and SI occurred at 0100.

"* At 1540, a transition was made to ECA-1.1 - Loss of Emergency Coolant Recirculation.

"* It is currently 1600 hours0.0185 days 0.444 hours 0.00265 weeks 6.088e-4 months .

"* The crew is performing step 15 - Check If SI Flow Can Be Terminated.

"* CNMT pressure peaked at 1.1 psig and is currently 11.5 psia.

"* CNMT radiation levels are 600 mr/hr.

"* Total SI flow is 400 gpm.

"* PSMS subcooling is 65'F.

"* RCS pressure is 1500 psig.

All RCP's are secured.

"* RVLIS Full Range is 75%.

Which of the following actions are required to be taken?

A. Maintain 400 gpm SI flow and reset CIA and CIB.

B. Maintain SI flow but reduce it to 140 gpm.

C.

Maintain SI flow but reduce it to 175 gpm.

D. Establish normal charging flow and reduce total charging flow to 90 gpm.

Answer:

B Technical Reference(s):

20M-53A.1.ECA-1.1, Issue LB, Rev. 6, 20M-53A.1.A-4.7, Issue 1B, Rev. 2 References to be provided to applicants during examination: 20M-53A.1.ECA-1.1 pages 11-16, 0M-53A. 1.A-4.7, Issue 1B, Rev. 2, Attachment 20M-53A. I.A-5.5, Issue IB, Rev. 2 Learning Objective:

2LP-SQS-53.3, ELO 6 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFRPart 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 13 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level Tier #

Group #

K/A #

Importance Rating Regarding the RM-1 1 console, a monitor that is backlit _(1)_ indicates the monitor is offline, backlit _(2)_ indicates the monitor has a system failure and backlit _(3)_

indicates an ALERT status.

-(1)

A. white B.

cyan C.

white D. cyan Answer:

C

_(2)_

magenta magenta dark blue dark blue red red yellow yellow Technical Reference(s):

20M Table 43-3 References to be provided to applicants during examination: None Learning Objective:

08-02-770, ELO 1 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 Comments:

X X

NUREG-1021, Revision 8 SRO RO 1

2 061AK2.01 2.5

Question # 14 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

1 Group #

2 K/A #

058AA1.03 Importance Rating 3.1 Note: This is an open reference question.

Given the following lineup for the Vital Bus #2-1 Uninterruptable Power Supply (UPS),

and that there are no equipment failures, which of the following is providing power to Vital Bus #2-1?

"* All associated breakers external to the UPS are CLOSED.

"* UPS Status:

CB#1 - Manual Bypass Input - CLOSED

CB#2 - Static Switch Bypass Input - CLOSED CB #131 - DC Input - Tripped OPEN CB #132 - AC Input - CLOSED

CB #133 - Static Switch AC Output - CLOSED S S5 - Manual Bypass Switch - BYPASS Static Switch DS 117 Yellow Indicating light (upper) - LIT Static Switch DS 118 Red Indicating light (lower) - OFF A. The Static Line Voltage Regulator via the Static Switch.

B.

The Static Line Voltage Regulator bypassing the Static Switch.

C.

480V MCC*2-E13.

D.

125VDC Bus #2-1.

Answer:

B Technical Reference(s):

20M Fig 38-1 Rev. 18, 20M-38.4.A Issue 4, Rev. 1 References to be provided to applicants during examination: 20M Fig 38-1, Rev. 18 Learning Objective:

08-02-732, ELO 7 Question Source:

Bank #

Modified Bank # LRT NRC Bank # 0696J Question History:

New Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFR Part 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 15 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

1 Group #

2 K/A #

022AK3.06 Importance Rating 3.2 While operating at 100% power with all systems in their at-power, NSA configurations, the running charging pump trips and the standby charging pump cannot be started. Which of the following describes the adverse consequences of continued operation under these conditions?

1. RCS activity levels will rise due to the inability to maintain letdown flow.

2. The RCP seals will begin to degrade due to the loss of filtered seal injection water.

3.

The RCP seals will overheat and fail due to the loss of cool seal injection water.

4. The RCP lower radial bearings will overheat due to the loss of cool seal injection water.

A.

1 and 2 only.

B.

3 and4 only.

C.

2, 3 and 4 only.

D.

1, 2, 3 and 4.

Answer:

A Technical Reference(s):

20M-6.1 References to be provided to applicants during examination: None Learning Objective:

08-02-720, ELO I Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFR Part 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 16 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level Tier #

Group #

K/A #

Importance Rating RO 2

1 059K 1.04 3.4 SRO The unit is operating at 50% power. A steam dump valve has failed causing SG water level to go to 55% in 3 seconds. No protective system actuations have occurred. In response to the steam dump failure and with no operator actions, the FRV's will A. immediately close to return level to 44%.

B.

after a 30 second delay, open to return level to 44%.

C. immediately open to match feed flow to steam flow.

D. after a 30 second delay, close to match feed flow to steam flow.

Answer:

C Technical Reference(s):

Simulator Response References to be provided to applicants during examination: None Learning Objective:

08-02-741, ELO 14 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 Comments:

X X

NUREG-1021, Revision 8

Question # 17 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

2 Group f 1

K/A #

061A3.01 Importance Rating 4.2 With the Unit in Mode 1 and all systems in their NSA configurations, which of the following signals will cause the turbine driven auxiliary feed pump to start, but will not cause the motor driven auxiliary feed pumps to start?

A. An AMSAC actuation.

B.

2/3 RCP bus undervoltage signals.

C.

A Low-Low SG water level signal from 2/3 channels in 2/3 SG's.

D. The trip of both main feed pumps with their control switches in "After-Start".

Answer:

B Teclmical Reference(s):

20M -24. 1.D Issue 4, Rev. 2, pg. 16-18 References to be provided to applicants during examination:

None Learning Objective:

08-02-741, ELO 6 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge X

Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 18 ES-401 Sample Written Examination Form ES401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

2 Group #

3 K/A #

008A3.05 Importance Rating 3.0 With the Unit at full power and all systems in their NSA configurations, which of the following will result in automatically isolating cooling water to the CRDM cooling fans?

1. A Large Break LOCA inside CNMT.

2. A 500 gpm Steam Generator Tube Rupture.

3. A double ended shear of a Main Steam Line outside of CNMT.

A.

1 only.

B.

1 and 2 only.

C.

2 and 3 only.

D. 1,2and3.

Answer:

A Technical Reference(s):

EOP Att. A-0.5 (chilled water isolation valves are CIB valves)

References to be provided to applicants during examination: None Learning Objective:

2LP-SQS-53.3, ELO 6 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFR Part 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 19 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

2 Group II K/A #

015K2.01 Importance Rating 3.3 With the Unit at 100% power with all systems in their at-power, NSA configurations, the loss of which of the following Motor Control Centers will result in the loss of the "A" train of the Gammametrics (Neutron Flux Monitoring System)?

A.

[MCC*2-E13]

B.

[MCC*2-E14]

C.

[MCC-2-08]

D. [MCC-2-09]

Answer:

A Technical Reference(s): 20M Figure 5D-34 References to be provided to applicants during examination: None Learning Objective:

08-02-763, ELO 5 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge X

Comprehension or Analysis 10 CFRPart 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 20 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

2 Group #

2 K/A #

039K5.08 Importance Rating 3.6 With the Unit at 100% power with all systems in their at-power, NSA configurations, which of the following describes the effect of an atmospheric steam dump valve failing full open?

Actual Tavg will go _(1)_ Tref and reactor power will _(2).

_(1)_

_(2)_

A. above remain constant.

B.

above rise.

C. below rise.

D. below remain constant.

Answer:

C Technical Reference(s): Simulator Response References to be provided to applicants during examination: None Learning Objective:

08-08-737, ELO 5 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFR Part 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 21 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

2 Group #

2 K/A #

014A2.04 Importance Rating 3.4 Given the following:

"* The Unit is operating at 60% power with all systems in their at-power, NSA configurations.

"* A load reduction is being performed.

"* Rod Control is in AUTO with Control Bank D Group Step Counter at 170 steps.

ONLY the following Annunciators are received:

[A4-4F] NIS POWER RANGE COMPARATOR DEVIATION

[A4-5H] NIS POWER RANGE HIGH/LOW SP FLUX DEVIATION/AUTO DEFEAT

[A4-8G] ROD POSITION DEVIATION Which of the following events would cause the plant conditions listed above?

A. Rod control urgent failure on the Control Bank D Group 2 power cabinet.

B. A single Digital Rod Position Indicator in Control Bank D has failed at 157 steps.

C.

One control rod is misaligned from its group step counter by greater than 12 steps.

D.

A single control rod in close proximity to a power range neutron detector has dropped to the bottom of the core.

Answer:

C Technical Reference(s):

20M-2.4.AAD & AAK References to be provided to applicants during examination: None Learning Objective:

2LP-SQS-1.4, ELO 7.A; 08-02-703, ELO 21 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFR Part 55 Content: 55.41 X

55.43 X

Comments:

NUJREG-1021, Revision 8

Question # 22 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

2 Group #

2 K/A #

014A2.03 Importance Rating 3.6 Under which of the following conditions would the reactor need to be tripped if a single control rod dropped when the reactor was at 20% power with all systems in their at power, NSA configurations?

1. Tavg drops to a minimum of 544TF.

2. Tavg is 10TF below Tref and dropping.

3.

Tavg cannot be maintained within + 40F of Tref A.

I only.

B.

2 only.

C.

1 or 2 only.

D.

1, 2 or3.

Answer:

B Technical Reference(s):

AOP-2.1.8 References to be provided to applicants during examination: None Learning Objective:

2LP-SQS-53 C. 1, ELO 8 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge X

Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X

55.43 X

Comments:

NUREG-1021, Revision 8

Question # 23 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

2 Group #

2 K/A #

062A4.03 Importance Rating 2.8 Under which of the following conditions is it permissible to close the 2-1 EDG output breaker [2ACB*2E9] when paralleling the EDG to the emergency 4KV bus?

2AE 2-1 EDG Voltage Output Voltage (Volts)

(Volts)

Synchroscope Rotation A. 122 123 slow in the fast direction B.

122 123 fast in the slow direction C.

123 122 fast in the slow direction D.

123 122 slow in the fast direction Answer:

A Technical Reference(s):

2OST-36. 1 References to be provided to applicants during examination: None Learning Objective:

08-02-762, ELO 12 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFR Part 55 Content: 55.41 X

55.43 Comments:

NIJREG-1021, Revision 8

Question # 24 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

3 Group #

K/A #

2.1.28 Importance Rating 3.2 In addition to CNMT general area radiation levels, which of the following CNMT parameters, if any, can be determined from [2RMR-RQ201 1, Reactor Containment Area, Low Range Monitor?

A. Particulate activity.

B.

Dose Equivalent Iodine and Gaseous activity.

C.

Dose Equivalent Iodine, Gaseous and Particulate activity.

D. No additional information can be obtained from [2RMIR-RQ201].

Answer:

D Technical Reference(s):

20M-43. 1.C Issue 4, Rev. 3, pg. 37 References to be provided to applicants during examination: None Learning Objective:

08-02-770, ELO 1 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge X

Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X

55.43 Comments:

NIUREG-1021, Revision 8

Question # 25 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

1 Group E I

K/A #

026AK3.02 Importance Rating 3.6 Which of the following statements is correct if component cooling pumps 2CCP*P21A and 2CCP*P21C are both racked onto bus 2AE during normal plant operation?

A.

To ensure that an "A" Train CCP pump is started in the event of a loss of offsite power, 2CCP*P21A must be operable with its control switch in the auto position.

B.

To ensure that an "A" Train CCP pump is started in the event of a loss of offsite power, 2CCP*P21C must be operable with its control switch in the auto position.

C.

When the second CCP pump is racked onto the 2AE bus, the CCP pump that was already racked onto the bus, will receive a trip signal.

D. Both 2CCP*P21A and 2CCP*P21C will start in the event of a loss of offsite power.

Answer:

A Teclmical Reference(s):

20M-15.4. A References to be provided to applicants during examination: None Learning Objective 08-02-731, ELO 5 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFRPart 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 26 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

1 Group #

I K/A #

005AA1.01 Importance Rating 3.6 Given the following:

"* The Unit is operating at 32% power with all systems in their NSA configurations for the current power level.

"* Power Range channel N-44 then fails high.

For the above listed conditions, with the Rod Control Selector Switch in...

1. MANUAL, outward rod motion is prevented, but inward rod motion is possible.

2. MANUAL, both outward and inward rod motion is prevented.

3. AUTOMATIC, both outward and inward rod motion is prevented.

4. AUTOMATIC, outward rod motion is prevented, but inward rod motion is possible.

A.

1 and 3 only.

B.

1 and 4 only.

C.

2 and 3 only.

D. 2 and 4 only.

Answer:

B Technical Reference(s): 20M-1.2.B Issue 4, Rev. 6, pg. 9 References to be provided to applicants during examination: None Learning Objective:

2LOT-V-4, ELO 1-12; 2LOT-V-7, ELO 1-5 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFR Part 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 27 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

2 Group #

I K/A #

004K6.13 Importance Rating 3.1 The Unit is operating at 100% power with all systems in their at-power, NSA configurations. Alternate Dilute is selected on the Makeup Mode Selector Switch. Which of the following valve positions would indicate a failure of a valve to be in its required position after the Boric Acid Makeup Control Switch is taken to the START position?

1. [2CHS*FCV113A] - "Boric Acid to Boric Acid Blender" - Closed

2. [2CHS*FCV1 13B] - "Boric Acid Blender Discharge to Charging Pumps" - Open

3. [2CHS*FCV1 14A] - "Primary Grade Water to Boric Acid Blender" - Open

4. [2CHS*FCV1 14B] - "Boric Acid Dilute Injection to Volume Control Tank" - Closed A. 1 and 3 only.

B.

2 only.

C.

2 and 4 only.

D.

4 only.

Answer:

D Technical Reference(s):

20M-7.4.M References to be provided to applicants during examination: None Learning Objective:

08-02-720, ELO 37 & 43.t Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFR Part 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 28 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

2 Group #

3 K/A #

007A2.01 Importance Rating 3.9 Note: This is an open reference question.

Given the following:

"* A plant heatup is in progress with the RCS at 3660F and 1900 psig.

"* Due to an equipment failure, a PRZR PORV failed open.

"* The PRT Rupture Disc has ruptured.

"* The associated PORV Block Valve has been closed.

"* After closing the PORV Block Valve, the PRZR is saturated at 1600 psig.

"* Containment pressure is 10 psia.

What will be the PORV tailpipe temperature if the block valve is leaking?

A.

193T B.

212TF C. 233TF D. 2460F Answer:

C Techmical Reference(s):

Steam Tables References to be provided to applicants during examination: Steam Tables Learning Objective:

08-02-715, ELO 11 Question Source:

Bank #

Unit 1 - 1LOT2 #21 (1997)

Modified Bank #

Question History:

New Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFR Part 55 Content: 55.41 X

55.43 X

Comments:

NUREG-1021, Revision 8

Question # 29 ES-401 Sample Written Examination Form ES-401-6 Examination Outline Cross-reference:

Level Tier #

Group #

K/A #

Importance Rating Question Worksheet RO 2

1 061K1.01 4.1 SRO When operating in Mode 1, the NSA configuration for the turbine driven AFW pump

[2FWE*P22] is to be aligned to discharge to the _(1)_ AFW injection header(s) with

_(2)- SG manual steam supply isolation valves [2MS S

15(16)(17)] open.

-(1)

A. A B.

A and B C. B D. A

_(2)_

A, B and C A, B and C only B and C only A and B Answer:

A Technical Reference(s):

20M Figure 24-3 References to be provided to applicants during examination:

None Learning Objective:

08-02-741, ELO 3; 08-02-737, ELO 2 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 Comments:

X NUREG-1021, Revision 8 X

Question # 30 ES-401 Sample Written Examination Form ES-40 1-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

1 Group #

1 K/A #

005AA1.02 Importance Rating 3.7 During the recovery of a dropped control rod, the lift coil disconnect switches are required to be operated. If the rod being recovered is rod F-2, a Group 1, Control Bank C (CBC) rod, which of the following lift coil disconnect switches need to be repositioned to allow the withdrawal of only rod F-2?

1. Only rod F-2 switch.

2. All CBC Group 1 switches.

3.

All CBC Group 1 switches except F-2.

4. All CBC Group 2 switches.

A.

1 only.

B.

3 only.

C.

2 and 4 only.

D.

3 and 4 only.

Answer:

D Technical Reference(s):

20M-1.4.P Issue 4, Rev. 4, pg. 7 References to be provided to applicants during examination: None Learning Objective:

08-02-703, ELO 18 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge X

Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 31 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

Group #

K/A#

2.1.11 Importance Rating 3.0 Which of the following Tech Specs does NOT require action in less than 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ?

A.

3.6.1.2 - Containment Leakage.

B.

3.6.1.3 - Containment Air Locks.

C.

3.6.1.4 - Containment Internal Air Partial Pressure.

D. 3.6.1.5 - Containment Air Temperature.

Answer:

D Technical Reference(s):

TS 3.6.1.2 thru 3.6.1.5 References to be provided to applicants during examination:

None Learning Objective:

l/2LP-SQS-TS. 1, ELO 5 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge X

Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 X

Comments:

NUREG-1021, Revision 8

Question # 32 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

2 Group #

3 KIA #

005A2.04 Importance Rating 2.9 The Unit is in Mode 4 with the "A" Train of RHS in service and all systems in their NSA configurations for the current Mode of operation. A loss of instrument air to

[2RHS*HCV758A] RHS Train A HX Outlet Flow Control Valve will cause the valve to go _(1)___, and, [2RHS*FCV605A] RHS Train A HX Bypass Flow Control Valve will automatically _(2).

-(1)-

_(2)_

A. open close.

B. open open.

C. closed close.

D. closed open.

Answer:

A Technical Reference(s):

20M10.5, Figurel0.1 References to be provided to applicants during examination: None Learning Objective:

2LP-SQS-10.1, ELO 8 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFR Part 55 Content: 55.41 X

55.43 X

Comments:

NUREG-1021, Revision 8

RTL #A5.620.H 1/2-ADM-1303.F08 Page 1 of 1 Revision 1 EXAMINATION COVER SHEET Training Program: License Operator Initial Training Examination Number:

2LOT3 NRC SRO Initial License Exam (6/4/01)

EXAMINATION REVIEW AND APPROVAL Submitted by:

T. Wooley Date:

- /[t/0i print Training Systems Date:

Review:

_________Date:

Approved by:

s__.

__ure Date:

__/I__/

signature EXAMINEE INFORMATION (Please print)

Name:

ANSWER KEY Date:

Employee SSN#

Company:

(If other than utility employee)

SCORE Total Possible Points:

100.0 Score:

Graded by:

Date:

name (please print) & initials EXAMINATION POLICY I. A score of 80 percent or greater is required for successful completion of this examination.

2. Unless specified by the proctor, reference materials and personal notes are not to be used or be visible during the examination.

3. If you have any questions, or need clarification during the examination, remain seated and signal to the proctor.

4. Unless asking for clarification from the proctor, conversation is prohibited.

5. Biological breaks are limited. Only one examinee at a time is permitted to leave the examination setting while the examination is in progress.

6. Cheating on an examination will result in failure of the examination and may result in further disciplinary action.

7.

Once you have completed your examination, return your exam to the proctor and receive the correct answers to any missed questions prior to leaving the examination area.

"By this signature I state that I have neither given nor received aid regarding this examination, prior to or during its administration. The work completed on this examination is my own."

Examinee's Signature:

Date:

(Please Sign in black Ink)

ANSWER KEY 2LOT3 SRO EXAMINATION (Revised 6114/01)

1. D

21. C

41. D

61. B

81. A

2. C

22. D

42. D 62 A

82. A

3. C

23. C

43. C

63. B

83. B

4. B

24. B

44. D

64. A

84. B

5. A

25. C

45. D

65. C

85. B

6. C

26. B

46. C

66. A

86. A

7. A

27. A

47. D

67. B

87. D

8. C

28. D

48. A

68. C

88. D

9. B

29. A

49. A

69. B

89. A

10. D

30. D

50. C

70. D

90. C

11. A

31. D

51. A

71. B

91. A

12. B

32. A

52. A

72. A or D

92. A

13. D

33. C

53. A

73. B

93. D

14. C

34. D

54. D

74. C

94. C

15. A

35. D

55. C

75. B

95. D

16. C

36. D

56. D

76. B

96. D

17. D

37. C

57. B

77. C

97. B

18. B

38. C

58. B

78. B

98. A

19. C

39. D

59. B

79. B

99. C

20. D

40. C

60. A

80. B 100. B

- .. *.'

C....... n.p.....

Question # 1 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

I Group #

1 K/A #

029EK3.06 Importance Rating 4.3 Procedure FR-S. 1 - Response to Nuclear Power Generation - ATWS, Step 3 states

'Verify Turbine Trip.' What is the bases for this step?

A. To maintain condenser vacuum which will be required for the subsequent RCS cooldown.

B.

To ensure continued operation of the RCP's by forcing the Normal 4KV buses to the SSST.

C.

To prevent damage to the main generator due to the loss of generator cooling systems.

D. To prevent an uncontrolled cooldown of the RCS and to maintain SG inventory.

Answer:

D Explanation (Optional):

Technical Reference(s):

20M-53B.4.FR-S.1, Step 3 References to be provided to applicants during examination: None Learning Objective 2LP-SQS-53.3, ELO 3

/

Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge X

Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 2 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

I Group #

I KIA #

E02EA1.2 Importance Rating 3.8 The operators are responding to an event and are currently in ECA-3.1 - SGTR With Loss Of Reactor Coolant - Subcooled Recovery Desired, and are about to perform Step 17

'Depressurize RCS To Refill PRZR'. Prior to performing this step the following conditions exist:

Both HHSI pumps are running.

PZR level is 7% and stable.

PZR pressure is 900 psig and stable.

Ruptured SG narrow range level is 73% and stable.

Ruptured SG pressure is 900 psig and stable.

Step 17 is then performed, PZR level rises as expected to > 14%, and the RCS depressurization is stopped with RCS pressure at 800 psig and ruptured SG pressure at 850 psig. What is the expected response of RCS and ruptured SG pressures when the RCS depressurization is stopped?

A. RCS pressure will remain at 800 psig with ruptured SG pressure dropping to match RCS pressure.

B. RCS pressure will rise and ruptured SG pressure will drop to a point of equilibrium somewhere between 800 and 850 psig.

C. RCS pressure and ruptured SG pressures will both rise to 900 psig.

D. RCS pressure and ruptured SG pressures will both rise to > 1000 psig.

Answer:

C Technical Reference(s):

ATA/MCD and Simulator Response References to be provided to applicants during examination: None Learning Objective 1I/2ATA-4.2, ELO 4 & 12; 2LOT-V, ELO 14 Question Source:

Bank #

LRT Bank NRC # 429J Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFR Part 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 3 ES-401 Sample Written Examination Form ES-401-6 Examination Outline Cross-reference:

Level Tier #

Group h!

K/A #

Importance Rating Question Worksheet RO SRO 1

E09EK3.3 3.6 The Unit was operating at 100% power with all systems in their at-power, NSA configurations when the Unit tripped and a loss of all offsite power occurred. The operators are in ES-0.2 - Natural Circulation Cooldown. One of the major concerns with the reactor vessel head is the possibility of_(1)_ which can be minimized by _(2).

-(1)

A. void formation, B. thermal shock, C. void formation, D. thermal shock,

_(2)_

maximizing charging flow.

securing the CRDM cooling fans.

running the CRDM cooling fans.

minimizing charging flow.

Answer:

C Technical Reference(s):

ES-0.2 References to be provided to applicants during examination: None Learning Objective:

2LP-SQS-53.3, ELO 6 Question Source:

Bank #

Modified Bank #

Question History:

New X

Question Cognitive Level:

10 CFR Part 55 Content:

Previous NRC Exam Previous Quiz / Test Memory or Fundamental Knowledge Comprehension or Analysis 55.41 X

55.43 Comments:

NUREG-1021, Revision 8 X

Question # 4 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

I Group #

1 K/A #

024AK2.01 Importance Rating 2.7 There is a plant fire that requires leaving the control room. "Alternate Safe Shutdown From Outside the Control Room" has been activated and the Alternate Shutdown Panel has been manned. It becomes necessary to emergency borate the reactor; however, the normal emergency boration valve, 2CHS*MOV350 will not open. Which of the following will provide emergency boration flow?

A. Isolate air to 2CHS*FCV1 13A Boric acid to Boric Acid Blender valve, then open 2CHS*SOV206 Alternate Emergency Boration Valve by energizing its power supply.

B. Isolate air to 2CHS*FCVl 13A Boric acid to Boric Acid Blender valve, then open 2CHS*SOV206 Alternate Emergency Boration Valve using its control switch at the ASP.

C. Locally open 2CHS*FCV1 13A Boric acid to Boric Acid Blender valve by applying full air pressure to its actuator with a hand regulator, then open 2CHS*SOV206 Alternate Emergency Boration Valve by de-energizing its power supply.

D. Locally open 2CHS*FCV1 13A Boric acid to Boric Acid Blender valve by applying full air pressure to its actuator with a hand regulator, then open 2CHS*SOV206 Alternate Emergency Boration Valve using its control switch at the ASP.

Answer:

B Technical Reference(s):

20M-56.4.F-9 References to be provided to applicants during examination: None Learning Objective:

08-02-720, ELO 37 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFRPart 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 5 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

I Group #

I K/A #

011K3.01 Importance Rating 3.4 Note: This is an open reference question.

The unit is in Mode 4 with PRZR heater 2RCP*H2A out of service. All other PRZR heaters are energized. PRZR level is 15%. It is desired to raise PRZR level to 22%. This is accomplished by adjusting net charging flow to no more than _(I)_ gpm to ensure there is no _(2)_ the PRZR.

-(1)-

_(2)_

A. 25 insurge to B. 30 insurge to C. 25 outsurge from D. 30 outsurge from Answer:

A Technical Reference(s):

20M-6.4.AAK References to be provided to applicants during examination: 20M-6.4.AAK Learning Objective:

08-02-720, ELO 51 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFRPart 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 6 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level Tier #

Group #

K/A #

Importance Rating Which of the following is the correct sequence of steps that the operator needs to perform to recover a dropped control rod in Control Bank D (CBD), in accordance with 2OM-1.4.P - RCCA or RCCA Group Misalignment?

1. Withdraw the dropped rod to the height of the remainder of the CBD rods.

2. Place the Rod Group Selector Switch in MANUAL.

3. Place the Rod Group Selector Switch in the CBD position.

4. Reset the ROD CONTROL SYSTEM URGENT ALARM.

5. Align the CBD Lift Coil Disconnect Switches and reset the CBD Group Step Counter and the P/A Converter to zero.

A. 2,5, 1,4.

B. 2,5,4,1.

C. 3,5,1,4.

D. 3,5,4, 1.

Answer:

C Technical Reference(s): AOP-2.1.8 Issue IA, Rev. 0 References to be provided to applicants during examination:

None Learning Objective:

2LP-LOT-V-4, ELO 1-10 Question Source:

Bank #

Modified Bank #

2-LOT-1 #22 (1997)

Question History:

New Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 Comments:

X X

NUREG-102 1, Revision 8 SRO 1

I 003AA1.02 3.4 RO,

Question # 7 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

Group #

K/A #

Importance Rating 074EK3. 10 3.8 When responding to an inadequate core cooling event in FR-C. 1 - Response to Inadequate Core Cooling, the SG depressurization is stopped when SG pressures are 200 psig. What is the bases for stopping the SG depressurization at this point in the recovery actions?

A. To allow the SI accumulators to be isolated thus precluding an excessive nitrogen injection into the RCS.

B. At this SG pressure, the LHSI pumps should be injecting, therefore no further SG depressurization is required.

C. To minimize the adverse effects of Pressurized Thermal Shock.

D. To place the RHS in service to continue the RCS cooldown.

Answer:

A Technical Reference(s):

FR-C. 1 Background References to be provided to applicants during examination: None Learning Objective:

2LP-SQS-53.3, ELO 6 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X

55.43 Comments:

X NUREG-1021, Revision 8

Question # 8 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

1 Group#

I K/A #

024AK2.04 Importance Rating 2.5 Note: This is an open reference question.

Given the following:

"* The Unit is operating at 100% power with all systems in their at-power, NSA configurations.

"* An auto makeup occurs at 0245 on January 10, and the in service boric acid transfer pump immediately trips.

"* The standby boric acid transfer pump is on clearance.

What are the minimum required actions, if any, to avoid a plant shutdown?

A. Since there is still an available boration flow path from the RWST via the charging pump, no action is required.

B.

One boric acid transfer pump must be returned to operable status by 0345 on January 10.

C.

One boric acid transfer pump must be restored to operable status by 0245 on January 13.

D. One boric acid transfer pump must be restored to operable status by 0345 on January 10, and the other by 0245 on January 13.

Answer:

C Technical Reference(s):

TS 3.1.2.2 and 3.1.2.6 References to be provided to applicants during examination:

TS 3.1.2.2 and 3.1.2.6 Learning Objective:

08-02-720, ELO 37.A Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFRPart 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 9 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

1 Group #

2 K/A #

007 EK2.03 Importance Rating 3.6 Given the following:

"* The Unit is operating at 100% power with all systems in their at-power, NSA configurations.

"* Annunciator [A5-2A] - Reactor Protection System Train A Trouble and [A5-3A]

Reactor Protection System Train B Trouble are simultaneously received.

An operator sent to investigate reports that the SSPS Logic Cabinet General Warning Light is lit on both Train A and Train B.

Which of the following actions are required to be performed?

A. Immediately trip the reactor and perform the immediate manual actions of E-0, Reactor Trip or Safety Injection.

B.

Immediately commence a controlled reactor shutdown to a condition with the reactor trip breakers open.

C.

Enter TS 3.0.3, and commence a normal shutdown if at least one annunciator has not cleared within one hour.

D. Evaluate TS 3.3.2.1 - ESF Actuation System Instrumentation, contact I&C to investigate and restore at least one train to operable status within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Answer:

B Technical Reference(s):

20M-1.4.AAI & 1/20M-48. 1.B Issue 4, Rev. 1, pg. 10 References to be provided to applicants during examination:

None Learning Objective:

2LP-SQS-l.2, ELO 16; 3SQS-2389 ELO I & 5 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level:

Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFR Part 55 Content:

55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question A 10 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level Tier #

Group #

K/A #

Importance Rating Note: This is an open reference question.

The reactor is being cooled down at 50 degrees F per hour from the remote shutdown panel. Which of the following temperatures fall within the acceptable operating region of figure 56C. 1 - RCS Pressure Limits, for the following pressures?

875#

A.

135 0F B.

110OF C.

125TF D.

135 0F Answer:

D Technical Reference(s):

References to be provided Learning Objective:

Question Source:

Question History:

750#

95TF 1 00°F 115TF 1250F Figure 56C-1 to applicants during examination:

2LP-SQS-56C. 1, ELO 7 Bank #

Modified Bank #

New X

600#

85 0F 85OF 70T 70OF Fi*

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X

55.43 Comments:

iure 56C-1 X

NUREG-1021, Revision 8 RO SRO SRO 1

068AK2.01 4.0

Question # 11 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

1 Group I

K/A #

069AK2.03 Importance Rating 2.9 Note: This is an open reference question.

While operating in Mode 1, in order to maintain CNMT airlock operability, which of the following is required to be operable on each CNMT airlock?

A. Both doors.

B.

Only the inner door.

C.

Only the outer door.

D. Only one door, either the inner or outer door.

Answer:

A Technical Reference(s):

T.S. 3.6.1.3 Bases References to be provided to applicants during examination: T.S. 3.6.1.3 Learning Objective:

2LP-SQS-47. 1, ELO 8; 1/2LP-SQS-TS. 1, ELO 5 Question Source:

Bank #

Modified Bank# #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFRPart 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 12 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level Tier #

Group #

K/A#

Importance Rating Note: This is an open reference question.

Given the following:

A rapid (5%/min) power reduction from 100% to 75% was performed due to grid instabilities.

Power has been stable at 75% for 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months .

The results from the RCS chemistry samples taken four hours after power was stabilized at 75%, reveal the following; Dose Equivalent 1-131 (DEI) is 27 uCi/gm.

SGross coolant activity is 18 uCi/gm.

The 100/E-Bar limit is 250 uCi/gm. (E-Bar itself is 0.4 uCi/gm)

What is the status of the RCS activity levels and what actions are required to comply with Technical Specifications?

A. RCS activity levels are within the LCO limits and no actions are necessary to comply with the Technical Specifications. /

B.

The DEI limit has been exceeded, power operation may continue provided an isotopic analysis for iodine is performed every four hours.

C. The DEI limit has been exceeded, be in Hot Standby with Tae < 5000F within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

D. The 100/E-Bar limit has been exceeded, be in Hot Standby with T,,, < 5000F within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Answer:

B Technical Reference(s):

TS 3.4.8 References to be provided to applicants during examination:

TE Learning Objective:

1/2LP-SQS-TS. 1, ELO 5 Question Source:

Bank #

Modified Bank #

Question History:

New X

Question Cognitive Level:

Memory or Fundamental Knowledge X

Comprehension or Analysis 10 CFR Part 55 Content:

Comments:

i3.4.8 X

55.41 55.43 NUREG-1021, Revision 8 SRO 1

076AK2.01 3.0 RO

Question # 13 ES-401 Sample Written Examination Form ES-40 1-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

Group #

K/A #

E04EK 1.2 Importance Rating 4.2 Note: This is an open reference question.

Which of the following is considered a red path while in ECA-1.2 - LOCA Outside Containment?

5 Highest Core Exit RVLIS Full Thermocouples RCP Status Range Level A. 825°F All Running 100%

B.

825TF None Running 90%

C.

750OF None Running 85%

D. 750°F None Running 30%

Answer:

D Technical Reference(s):

ECA 1.2 References to be provided to applicants during examination: F-0.2 Status tree Learning Objective:

2LP-SQS-53.3, ELO 6 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X

55.43 X

Comments:

NUREG-1021, Revision 8

Question # 14 ES-401 Sample Written Examination Form ES-40 1-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier#

1 Group#

I K/A #

E09EA2.1 Importance Rating 3.8 Note: This is an open reference question.

Given the following:

The Unit was operating at 100% power with all systems in their at-power, NSA configurations when a SG safety valve opened and would not reseat.

Subsequently, a total loss of offsite power occurred at 1300 hours0.015 days 0.361 hours 0.00215 weeks 4.9465e-4 months .

All emergency buses have been energized by their respective EDG's.

The operators are currently in 20M-53A. 1.ES-0.2 - Natural Circulation Cooldown, Step 11 - Maintain Following RCS Conditions.

All attempts to limit the RCS cooldown have been completed.

RVLIS Full range is 100%.

PRZR level is being maintained at 22%.

RCS pressure is 2000 psig and slowly dropping due to the RCS cooldown.

RCS cold leg temperatures since the reactor trip are:

1300-547OF; 1330-537OF; 1400-526OF; 1430-510'F; 1500-4830F Which of the following actions are required to be performed next?

A. Initiate an RCS depressurization per ES-0.2 - Natural Circulation Cooldown.

B. Energize all PRZR heaters to collapse the bubble that is forming in the reactor vessel head.

C.

Transition to ES-0.3 - Natural Circulation Cooldown With Steam Voids In Vessel (With RVLIS).

D.

Transition to ES-0.4 - Natural Circulation Cooldown With Steam Voids In Vessel (Without RVLIS).

Answer:

C Technical Reference(s):

20M-53A.1.ES-0.2 Issue 1B, Rev. 4, pg. 10 References to be provided to applicants during examination:

20M-53A. L.ES-0.2, pg. 10 - 12, EOP Attachments A-4.1, 4.2 and 4.3 Learning Objective:

2LP-SQS-53.3, ELO 6 Question Source:

Bank #

Modified Bank #

Question History:

New X

Question Cognitive Level:

Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFR Part 55 Content:

55.41 55.43 X

Comments:

NUREG-1021, Revision 8

Question # 15 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

1 Group#

2 K/A #

008AA2.06 Importance Rating 3.6 Note: This is an open reference question.

Given the following:

RCS Temperature is 190TF.

RCS pressure is 425 psig.

RCS Cold Overpressure Protection System is armed.

If"A" loop WR Tcold instrument T1413 fails low, _(1)_PRZR PORV(s) will open.

To close any open PORV with the Cold Overpressure Protection System armed, the respective PORV control switch must be placed in the CLOSE position _(2) the associated Cold Overpressure Protection arm switch must be placed in the BLOCK position.

_(1)_

_(2)_

A.

0 or B.

1 or C.

1 and D. 2 and Answer:

A Technical Reference(s):

UFSAR Figure 7.3-22, Plant Curve CB-25 References to be provided to applicants during examination: Plant Curve CB-25 Learning Objective:

08-02-715, ELO 14; 08-02-723, ELO 12 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFR Part 55 Content: 55.41 55.43 X

Comments:

NUREG-1021, Revision 8

Question # 16 ES-401 Sample Written Examination Form ES-40 1-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tie Tier #

Group #

K/A #

importance Rating 2

E03 EK3.02 3.9 Given the following:

The operators are responding to an event and are currently in ES-1.2 - Post LOCA Cooldown and Depressurization at Step 27 - 'Check If SI Accumulators Should Be Isolated.'

RCS subcooling is 18'F.

PRZR level is 10%.

All hot leg temperatures are less than 380TF.

CNMT conditions are not adverse.

If the SI Accumulators are not isolated or vented at this point, the accumulator (1)0 volume injected into the RCS could _(2).

_(1)_

_(2)_

A. water cause the PRZL to go watersuou B. water lead to a CNMT Orange Path condition C.

gas lead to gas binding of the SG U-tubes D. gas vent to CNMT atmosphere causing an.

Answer:

C Technical Reference(s):

20M-53.B.4.ES-1.2 Issue 1B, Rev. 6, Step 27 References to be provided to applicants during examination:

None Learning Objective:

2LP-SQS-53.3, ELO 3 Question Source:

Bank #

LRT NRC Bank # 402Q Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 10 CFRPart 55 Content: 55.41 X

55.43 Comments:

on high sump level inacceptable pressure rise X

NUREG-1021, Revision 8

Question # 17 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

1 Group #

2 K/A #

025AAI.02 Importance Rating 3.9 Note: This is an open reference question.

Given the following:

"* The reactor is de-fueled.

"* Reactor vessel level on RCS-LI104 (LGI01) is 16 inches.

"* The running RHS pumps have just been swapped with "B" pump now in service.

Which of the following is the maximum RHS flow rate that should be directed to be established?

A. 2500 gpm.

B. 2000 gpm.

C.

1800 gpm.

D.

1700 gpm.

Answer:

D Technical Reference(s):

20M-10 Figure 10-10 (RHR)

References to be provided to applicants during examination: 20M-10 Figure 10-10 (RHR)

Learning Objective:

08-02-723, ELO 15 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFR Part 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 18 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

1 Group #

2 K/A #

027AK2.02 Importance Rating 2.6 Note: This is an open reference question.

With the Unit in Mode 3 returning from a refueling outage, it has been reported that two PRZR instrument root isolation valves have been found out of position. 2RCS*271 and 2RCS*272 are closed. All other systems are in their NSA configurations. Under these conditions a maximum of (1)__ PRZR PORV's, _(2)_ PRZR Pressure protection instruments and -(3)_ PRZR Level protection instruments may be considered operable?

0

2)

(3)

A. 3 1

1 B. 3 2

2 C.

1 2

3 D. 2 3

2 Answer:

B Technical Reference(s):

2OM Fig 6-1, TS 3.3.1, 3.4.11 References to be provided to applicants during examination: 20M Figure 6-1 PRZR Section Only Learning Objective:

08-02-715, ELO 18 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFR Part 55 Content: 55.41 55.43 X

Comments:

NUREG-1021, Revision 8

Question # 19 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

I Group#

2 K/A #

038 EK3.08 Importance Rating 4.2 A cooldown is being conducted in accordance with ES-3.1 - RCS Cooldown Using Backfill. The depressurization of the RCS must be stopped just before going less than 360 psig. Which of the following is the reason for stopping the depressurization at this point?

A. The vessel must be soaked for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to remove thermal stresses from the cooldown.

B. The ruptured steam generator must be soaked above Nil Ductility Transition Temperature.

C. To maintain the differential pressure across the number 1 RCP seals above 215 psid.

D. To stop the backfill from the ruptured steam generator prior to establishing RHS cooling.

Answer:

C Technical Reference(s):

ES-3.1 References to be provided to applicants during examination: None Learning Objective:

2LP-SQS-53.3, ELO 3 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge X

Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 20 ES-401 Sample Written Examination Form ES-40 1-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

I Group #

2 KIA #

E05 EK2.1 Importance Rating 3.9 Given the following:

The Unit was operating at 100% power with all systems in their at-power, NSA configurations when a tornado passing through the site causes the following damage:

A loss of offsite power with all diesel generators, including the ERF "Black" diesel generator, starting and loading as required.

A rupture of the PDWST [2FWE*TK210] resulting in it being totally unavailable.

All NR SG water levels are offscale low.

All SG pressures are 900 psig and rising slowly.

Which of the following, if any, are currently capable of providing feed flow to the SG's without performing any field operations?

1. Motor Driven AFP's.

2. Turbine Driven AFP.

3. Condensate Pump.

4. S/U Feed pump.

A. 1 and 2 only.

B. 3 or 4 only.

C.

4 only.

D. No feed flow capability currently exists.

Answer:

D Technical Reference(s):

FR-H. I Executive Volume References to be provided to applicants during examination: None Learning Objective:

2LP-SQS-53.3, ELO 6; 08-08-741, ELO 3, 5 and 7 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFRPart 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 21 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

1 Group#

2 K/A #

EliEKI.I Importance Rating 4.0 After an automatic initiation of cold leg recirculation it is noted that 2RSS*MOV 156D, 2 ID Recirc Spray Pump Discharge Isolation Valve is open. The 'C' and 'D' Recirc Spray pumps are running. Which of the following actions are required in accordance with EOP Attachment A-0.7, Cold Leg Recirculation Actuation?

A. Continue with the procedure and step in effect. All conditions are as required.

B. Place 2RSS*P2lD Recirc Spray Pump in Pull-To-Lock, reset both trains of SI and CIA, close 2RSS*MOV156D and start 2RSS*P21D.

C. Place 2RSS*P21D Recirc Spray Pump in Pull-To-Lock, reset both trains of CIB, close 2RSS*MOV156D and start 2RSS*P21D.

D. Place 2RS S*P21 C and 2RS S*P21D Recirc Spray Pumps in Pull-To-Lock, reset train A of CIB, close 2RS S *MOV 156D and start 2RS S*P21D and 2RS S *P2LC.

Answer:

C Technical Reference(s):

EOP Attachment A-0.7 References to be provided to applicants during examination: None Learning Objective:

2LP-SQS-53.3, ELO 6; 08-02-727, ELO 6, 7 and 15 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFR Part 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 22 ES-401 Sample Written Examination Form ES-401-6 Examination Outline Cross-reference:

Level Tier #

Group #

K/A #

Importance Rating Note: This is an open reference question.

Given the following:

Question Worksheet RO SRO SRO 1

2 037 2.1.7 4.4 The Unit is operating at 100% power with all systems in their at power, NSA configurations.

At 0600 hours0.00694 days 0.167 hours 9.920635e-4 weeks 2.283e-4 months the "A" SG developed a 35 gpd leak.

All required actions have been completed for the 35 gpd SG tube leak.

The following SG tube leak rates are then reported and qualitatively confirmed; S1000 hours - 35 gpd S1100 hours - 85 gpd S1115 hours - 101 gpd S1130 hours - 150 gpd S1145 hours - 162 gpd 1200 hours0.0139 days 0.333 hours 0.00198 weeks 4.566e-4 months - 162 gpd S1215 hours - 162 gpd Assuming that PRZR level has remained on program for the entire event, which of the following actions are required to be directed?

A. At 1100 hours0.0127 days 0.306 hours 0.00182 weeks 4.1855e-4 months , reduce letdown flow to 45 gpm and evaluate the need for a manual Safety Injection.

B.

At 1130 hours0.0131 days 0.314 hours 0.00187 weeks 4.29965e-4 months , commence a unit shutdown and be in Mode 3 by 1830 hours0.0212 days 0.508 hours 0.00303 weeks 6.96315e-4 months .

C.

At 1130 hours0.0131 days 0.314 hours 0.00187 weeks 4.29965e-4 months , manually initiate a reactor trip and enter E Reactor Trip Or Safety Injection.

D. At 1215 hours0.0141 days 0.338 hours 0.00201 weeks 4.623075e-4 months , reduce power to < 50% by 1315 hours0.0152 days 0.365 hours 0.00217 weeks 5.003575e-4 months and be in Mode 3 by 1515 hours0.0175 days 0.421 hours 0.0025 weeks 5.764575e-4 months .

Answer:

D Technical Reference(s):

AOP 2.6.4, Rev. 11 References to be provided to applicants during examination: AOP 2.6.4, Rev. 11 Learning Objective:

2LP-SQS-53C. 1 ELO 8 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFR Part 55 Content: 55.41 55.43 X

Comments:

NUREG-1021, Revision 8

Question # 23 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

2 Group #

2 K/A #

103G2.1.33 Importance Rating 4.0 Note: This is an open reference question.

With the Unit at full power and all systems in their NSA configurations, a condition report is brought to the control room that states that the NaOH storage tank has not been sampled for a period of exactly 8 months. No additions have been made to the tank since the last sample was taken. What actions, if any, are required to satisfy Tech Specs?

A. Be in Hot Standby within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , verify the NaOH concentration of the Chemical Addition storage tank within the next 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

B. Rely upon the provisions of T.S. 4.0.3 and delay entry of T.S. 3.6.2.3. Verify the NaOH concentration of the Chemical Addition storage tank within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

C. Enter T.S. 3.6.2.3. Verify the NaOH concentration of the Chemical Addition storage tank within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , then exit T.S. 3.6.2.3.

D. No action is required, the tank is only required to be sampled if there was a makeup made to the tank since the last sample.

Answer:

C Technical Reference(s):

TS 4.3.6.2.3.c.2 & TS 4.0.3 References to be provided to applicants during examination: TS 4.3.6.2.3 and TS 4.0.3 Learning Objective:

08-04-007, ELO 8 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFR Part 55 Content: 55.41 55.43 X

Comments:

NUREG-1021, Revision 8

Question # 24 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level Tier #

Group #

K/A #

Importance Rating What is the minimum Emergency Action Level that would require activation of the Technical Support Center?

A. Unusual Event.

B.

Alert.

C.

Site Area Emergency.

D. General Emergency.

Answer:

B Technical Reference(s):

EPP, Vol.1, Rev. 9, Sec.6.2.4 References to be provided to applicants during examination: None Learning Objective:

Question Source:

Question History:

EPP-9250 ELO 9 Bank #

Modified Bank #

New Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 10 CFRPart 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8 RO SRO 2.4.29 4.0 X

X

Question # 25 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

Group #

K/A #

2.1.4 Importance Rating 3.4 Given the following:

"* Unit 1 is in Mode 1 and Unit 2 in Mode 4 with the normal shift complement.

"* At 0400 hours0.00463 days 0.111 hours 6.613757e-4 weeks 1.522e-4 months , the Unit 2 ANSS is injured and is transported to a local emergency center for treatment.

"* The injured Unit 2 ANSS will not return to work this shift.

Which of the following describes the shift manning requirements?

A. The Unit 2 NSS may not leave the control room unless the Unit 1 NSS assumes command and control for Unit 2.

B.

One additional SRO, Unit 1 or Unit 2, must be added to the shift complement by 0500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months .

C. One additional Unit 2 SRO must be added to the shift complement by 0600 hours0.00694 days 0.167 hours 9.920635e-4 weeks 2.283e-4 months .

D. Since the next shift will be relieving within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , no additional shift manning is required.

Answer:

C Technical Reference(s):

TS 6.2.2 and 1/2 OM-48.1.B References to be provided to applicants during examination: None Learning Objective:

I/2LP-SQS-TS.1, ELO 5; 3SQS-2389 ELO 2 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge X

Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 26 ES-401 Sample Written Examination Form ES-40 1-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

I Group#

2 K/A #

009 EK3.21 Importance Rating 4.5 Procedure ES-1.2 - Post LOCA Cooldown and Depressurization requires PRZR level to be greater than 14% prior to starting a RCP if no RCP is running. The bases for this requirement is to ensure that...

A. the PRZR heaters are available to maintain RCS pressure.

B.

SI flow will not need to be re-initiated when an RCP is restarted.

C. an adequate volume is available in the PRZR to accommodate a steam bubble formation in the reactor vessel head.

D. a steam bubble of adequate size exists in the PRZR to dampen the rise in RCS pressure when the RCP is started and the RCS subsequently heats up.

Answer:

B Technical Reference(s):

20M-53B.4.ES-1.2 Issue 1B, Rev. 6 References to be provided to applicants during examination: None Learning Objective:

2LP-SQS-53.2, ELO 4; 2LP-SQS-53.3, ELO 3 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge X

Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 27 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

1 Group #

2 K/A #

033 AA2.1l Importance Rating 3.4 With the Unit operating at 100% power with all systems in their at-power, NSA configurations, N3 5, Intermediate Range Nuclear Instrument Channel I, compensating voltage is lost. If the reactor would trip, N35 will indicate...

A. high, preventing the source range from automatically energizing when required.

B.

high, and the source range will be energized when N35 is > P-6.

C. low, and the source range will be energized when N35 is < P-6.

D. low, and the source range will be energized when N36 is < P-6.

Answer:

A Technical Reference(s):

20M-2.1.B Issue 4, Rev. 1, pg. 17 References to be provided to applicants during examination: None Learning Objective:

2LP-SQS-2. 1, ELO 2 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFR Part 55 Content: 55.41 55.43 X

Comments:

NUREG-1021, Revision 8

Question # 28 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

Group #

K/A #

2.3.6 Importance Rating 3.1 Which of the following signatures are required on the RWDA-L prior to the release of radioactive liquid to the environment from the Unit 2 Liquid Waste System?

1. Unit I NSS.

2. Unit 2 NSS.

3. Health Physics.

4. Chemistry.

A.

1, 3 and 4 only.

B.

3 and4 only.

C.

1 and 3 only.

D.

1, 2, 3 and 4.

Answer:

D Technical Reference(s):

1/20M-17.4A.D References to be provided to applicants during examination: None Learning Objective:

2LP-SQS-WD, ELO 2 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge X

Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 X

Comments:

NUREG-1021, Revision 8

Question # 29 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

Group #

K/A #

2.2.26 Importance Rating 3.7 Which of the following describes the administrative requirements for the movement of nuclear fuel?

A record of each fuel movement is maintained in the CNMT, Spent Fool Pool area and the Control Room. The _(1) copy is the official copy and is updated by (2).

The Refueling _(3)_ is ultimately responsible for conducting any core alterations.

-(1)-

_(2)_

_(3)_

A. Control Room a refueling team member SRO B. Control Room the Refueling SRO Supervisor C.

CNMT the Refueling SRO SRO D. CNMT a refueling team member Supervisor Answer:

A Technical Reference(s):

Refueling Manual References to be provided to applicants during examination: None Learning Objective:

2LP-SQS-6.13, ELO 2 and 4 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge X

Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 X

Comments:

NUREG-1021, Revision 8

Question # 30 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

Group #

K/A #

2.2.23 Importance Rating 3.8 While in Mode 5, which of the following, if any, is required to be performed if a piece of equipment that is required to be operable in Mode 4 is made inoperable by the performance of an operating procedure?

A. Enter it in the Tech Spec LCO Log.

B. Enter it in the Operations Night Order Book.

C. Enter it in the Mode 1-4 section of the L5 Log.

D. No action is required, this information is not tracked.

Answer:

D Technical Reference(s):

1/20M-48. 1.1, Rev. 8 References to be provided to applicants during examination: None Learning Objective:

3SQS-2389 ELO 10 & 26 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge X

Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 X

Comments:

NUREG-1021, Revision 8

Question # 31 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

Group #

K/A #

2.1.33 Importance Rating 4.0 Note: This is an open reference question.

Given the following:

"* The unit is in Mode 5.

"* The "A" loop isolation valves [2RCS-MOV590 and 591] were closed for maintenance at 1600.

"* At 2005 the same day, it was realized that both hot and cold leg loop isolation valves are still energized.

Which of the following actions, if any, are required to be taken?

A. Do not enter a Tech Spec but verify [2RCS-MOV590 and 591] are still closed.

B. Do not enter a Tech Spec but de-energize [2RCS-MOV590 and 591].

C. Enter a Tech Spec and verify [2RCS-MOV590 and 591] are still closed.

D. Enter a Tech Spec and de-energize [2RCS-MOV590 and 591].

Answer:

D Technical Reference(s):

TS 3.4.1.4.2 References to be provided to applicants during examination: TS 3.4.1.4.1, 3.4.1.4.2 Learning Objective:

1/2LP-SQS-TS. 1, ELO 5 Question Source:

Bank #

Modified Bank # LRT 1416 Question History: New Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 X

Comments:

X NUREG-1021, Revision 8

Question # 32 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

2 Group #

3 K/A #

005 A2.03 Importance Rating 3.1 Note: This is an open reference question.

Given the following:

RCS temperature is 180TF.

RCS pressure is 25 psig.

No RCP's are running.

Two trains of RHS are operable with the "A" train in operation.

Without warning, the "A" RHS pump trips and cannot be restarted.

The operators start the "B" RHS pump and stabilize RCS temperature at 185TF.

What actions, if any, are required to satisfy Technical Specifications?

A. Raise RCS pressure to establish support conditions for RCP operation.

B.

Open all control rod lift coil disconnect switches to prevent rod withdrawal.

C.

Suspend all operations involving a reduction in boron concentration of the RCS.

D. No action is required, all applicable Technical Specification are satisfied.

Answer:

A Technical Reference(s):

TS 3.4.1.3, Action a, TS 1.0 Definitions (OPERABILITY)

References to be provided to applicants during examination: TS 3.4.1.3 Learning Objective:

08-04-007, ELO 8 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFRPart 55 Content: 55.41 X

55.43 X

Comments:

NUREG-1021, Revision 8

Question # 33 U_.J-U Jail'jJs. V Oust Worksheet Ouestion Worksheet Examination Outline Cross-reference:

Level Tier #

Group #

K/A #

Importance Rating RO SRO 1

1 1

1 051 AK3.01 051 AK3.01 2.8 3.1 Which of the following will prevent the opening of two banks of the condenser steam dumps?

A. RCS Temperature > P-12.

B. Actuation of load rejection bistables C-7A and C-7B.

C. Steam dump controller in the steam pressure mode.

D. Condenser vacuum > 20" with one cooling tower pump running.

Answer:

C Technical Reference(s): Steam dump controller handout References to be provided to applicants during examination: None Learning Objective:

08-02-737, ELO 5 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 Comments:

X X

NUREG-1021, Revision 8

Question # 34 1AA1 V,nar&1p U7Attn vmmn2tinn Porni ES-401-6

dLTV

.I LIuALLIJi'

VT & &&&

Question Worksheet Examination Outline Cross-reference:

Level Tier #

Group #

K/A #

Importance Rating RO 1

1 055 EKI.02 3.3 SRO 1

1 055 EKI.02 3.7 Note: This is an open reference question.

With the RCS at 2000 psig and stable, under which of the following conditions is natural circulation established? Assume all loops have the same parameters.

SG pressures A. 1000 - stable B.

900 - stable C.

800 - rising D.

700 - stable Core Exit TC's

&M~

565 - stable 545 - rising 525 - stable 545 - stable Thot (0-F) 565 - stable 540 - stable 525 - stable 540 - stable Tcold (OF) 555 - stable 532 - stable 517 - dropping 503 - stable Answer:

D Technical Reference(s):

EOP attachment A-1.7, A-5.1 References to be provided to applicants during examination:

EOP Attachment A-5.1 Learning Objective:

2LP-SQS-53.2, ELO I1 and 12; 2LP-SQS-53.3, ELO 3 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz I Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X

55.43 Comments:

X NUREG-1021, Revision 8 2ýALL V Ouestion Worksheet VC AM Q I Ufr;ffýn Pýnm;m nn Form ES401-6 L120 r5i

Question # 3 5 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

Group #

K/A #

E08 EA2.02 E08 EA2.02 Importance Rating 3.5 4.1 Note: This is an open reference question.

Given the following:

"* The unit is at 300OF following a refueling outage.

"* RCS pressure is 300 psig.

"* At 1400 hours0.0162 days 0.389 hours 0.00231 weeks 5.327e-4 months on April 1, a PRZR code safety valve sporadically opens and subsequently re-seats.

"* PRT level has risen 2%.

For the above listed conditions, the RCS is required to be borated to _(1)_ % AK/K at

_(2)_ F by _(3)

(D)

(2)

)

A.

1.77 100 1500, April I B.

1.77 200 1500, April I C.

1 100 2200, April 1 D. 1 200 1400, April 2 Answer:

D Technical Reference(s):

Technical Specifications 3/4.4.2 References to be provided to applicants during examination: TS 3.4.2 Learning Objective:

1/2LP-SQS-TS. 1, ELO 5 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz I Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFR Part 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 36 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

1 I

Group #

1 1

K/A #

040 AA2.01 040 AA2.01 Importance Rating 4.2 4.7 Given the following:

The Unit was operating at 100% power with all systems in their at-power, NSA configurations when an automatic reactor trip, MSLI and SI occurred.

RCS temperature is 525TF and rising.

RCS pressure is 1975 psig and rising.

PRZR level is 4% and rising.

All SG pressures are 850 psig and rising.

All SG levels are off scale low.

CNMT pressure is 9.8 psia and stable.

Which of the events has occurred?

A. Steam generator tube rupture.

B.

Small break LOCA inside CNMT.

C.

Main Steam Line break inside CNMT.

D. Main Steam Line break outside CNMT.

Answer:

D Technical Reference(s):

Simulator Response References to be provided to applicants during examination: None Learning Objective:

2LOT-V-9, ELO 2-3, 1/2LP-ATA-4.1, ELO 4D Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFR Part 55 Content: 55.41 55.43 X

Comments:

NUIREG-1021, Revision 8

Question # 37 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

1 I

Group #

1 1

K/A #

057 AA2.19 057 AA2.19 Importance Rating 4.0 4.3 Which of the following signals will cause the 2-5 Essential Bus Inverter Static Switch to automatically switch from the Inverter output to the Static Line Voltage Regulator output?

A. A 2-5 Battery Undervoltage.

B.

An Essential Bus Underfrequency.

C.

An Essential Bus Inverter Output Overvoltage.

D. An Overcurrent through the Essential Bus Static Switch.

Answer:

C Teclnical Reference(s):

20M - 38.1.B References to be provided to applicants during examination: None Learning Objective:

08-02-765, ELO 14 Question Source:

Bank #

Modified Bank #

Question History:

New X

/

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge X

Comprehension or Analysis 10 CFRPart 55 Content: 55.41 55.43 X

Comments:

NUREG-1021, Revision 8

Question # 38 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

1 1

Group #

1 1

K/A #

015 A1.03 015 A1.03 Importance Rating 3.7 3.7 Given the following:

"* The Unit is at 100% power with all systems in their at-power, NSA configurations.

"* Power Range channel N42 then fails high and is removed from service in accordance with the respective instrument failure procedure.

"* A reactor trip due to a turbine trip then occurs.

What is the earliest time, if at all, that the source range nuclear instruments will automatically energize following a reactor trip?

A. The Source Range NI's will not automatically energize under these conditions.

B.

0 - 10 minutes.

C.

11 - 25 minutes.

D. 26 - 40 minutes.

Answer:

C Technical Reference(s):

Fundamentals - Simulator Response References to be provided to applicants during examination: None Learning Objective:

2LP-SQS-2.1. ELO 11 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFR Part 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 39 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

1 I

Group #

1 1

K/A #

062 2.2.13 062 2.2.13 Importance Rating 3.6 3.8 When preparing a clearance for a Service Water System component, it is desired to use a check valve as a clearance point because the manual isolation valve is known to leak by.

Which of the following describes the use of a check valve as a clearance boundary in this case?

A. It cannot be used because this is a safety related system.

B. It cannot be used because check valves can never be used as clearance boundaries.

C. It can be used because this system is not a potentially contaminated system.

D. It can be used provided a drain or flange is continuously open to determine if the check valve is leaking.

Answer:

D Technical Reference(s):

NPDAP 3.4, Rev. 9, pg. 19 References to be provided to applicants during examination: None Learning Objective:

1/2LP-SQS-AP.2, ELO 5 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge X

Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 40 Oiie~tinn Worksheet Examination Outline Cross-reference:

Level Tier #

Group #

K/A #

Importance Rating RO 1

1 067 AK 1.02 3.1 SRO 1

067 AK1.02 3.9 Which of the following is the preferred extinguishing agent for a small fire located inside the 2-1 Battery Charger?

A. Manually actuate the normal switchgear CO2 discharge system.

B. Dry chemical portable fire extinguisher.

C.

CO 2 portable fire extinguisher.

D. Foam with high velocity fog.

Answer:

C Technical Reference(s):

20M-56B.3.B.2 Issue 1, Rev. 7, pg. 3 References to be provided to applicants during examination:

None Learning Objective:

FB-9340, ELO 4 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X

55.43 Comments:

x NUREG-1021, Revision 8

'PQA01 Q.

1ý XViff,,ý P^rm IPQ-Af) 1 -6 E

Ouestion Worksheet

Question A 41 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

1 1

Group #

I I

K/A #

017 AK3.03 017 AK3.03 Importance Rating 3.7 4.0 If the number 1 seal of a RCP fails, the operator is directed to trip the reactor, trip the affected RCP, wait 3 minutes after tripping the RCP, then shut the respective seal leakoff isolation valve [2CHS*MOV303A(B)(C)]. Which of the following is the bases for waiting 3 minutes after the affected RCP has been stopped to close the seal leakoff isolation valve?

A. To ensure that adequate lower radial bearing cooling exists during pump coastdown.

B. To minimize crud deposits and post S/D radiation levels by providing a 3 minute flush of the seal leakoff line.

C.

To provide the operator adequate time to perform the immediate manual actions of E Reactor Trip or Safety Injection.

D. To ensure that an excessive amount of water is not forced through the number 2 seal until after the RCP has stopped rotating.

Answer:

D Technical Reference(s):

20M-7.4 AAH References to be provided to applicants during examination: None Learning Objective:

08-02-714, ELO 1O.L, 2LOT-V-1, 2 & 3, ELO 1-11 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge X

Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 42 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

I I

Group 2

2 K/A #

033 AA1.02 032 AA1.02 Importance Rating 3.0 3.1 Given the following:

"* A Unit startup is in progress with reactor power at 17% on the steam dumps.

"* All systems are in their required status for the current power level.

"* When placing the Main Generator on line, a malfunction in the steam dumps caused reactor power to drop to 9%.

"* The operators turned the steam dumps off and raised Main Generator load to stabilize reactor power at 15%.

"* No other operator actions were performed during the transient.

"* The Main Generator loading is then recommenced.

Which of the following applies to this situation?

A. Reactor power should be limited to 49% due to the inoperability of the steam dumps.

B.

Automatic rod control cannot be enabled until 20% power.

C. Reactor power cannot be raised above 20% power.

D. The reactor will trip at 25% power.

Answer:

D Technical Reference(s):

TS 3.1.1 References to be provided to applicants during examination: None Learning Objective:

2LP-SQS-2. 1, ELO 6 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFR Part 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 43 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

I I

Group #

2 2

K/A #

E03 EA2.1 E03 EA2.1 Importance Rating 3.4 4.2 Note: This is an open reference question.

Given the following:

"* The operators are responding to an event and are currently in ES-1.2 - Post LOCA Cooldown And Depressurization, Step 16 - Depressurize RCS To Minimize Break Flow.

"* The STA then reports that all RWST levels are 455 inches and that a valid red path exits on the Pressurized Thermal Shock status tree.

Which of the following actions are required to be performed?

A. Complete Step 16 of ES-1.2 - Post LOCA Cooldown And Depressurization, then transition to ES-1.3 - Transfer To Cold Leg Recirculation.

B.

Immediately transition to FR-P. 1 Response to Imminent Pressurized Thermal Shock, complete the first 6 steps of FR-P.1, then transition to ES-1.3 Transfer To Cold Leg Recirculation.

C. Immediately transition to ES-1.3 Transfer To Cold Leg Recirculation, complete the first 6 steps of ES-1.3, then transition to FR-P. 1 - Response to Imminent Pressurized Thermal Shock.

D. Immediately transition to ES-1.3 Transfer To Cold Leg Recirculation, complete it in its entirety, then, if the red path still exists, transition to FR-P. 1 - Response to Imminent Pressurized Thermal Shock.

Answer:

C Technical Reference(s):

ES-1.2 LHP and ES-1.3, Step 1 Note References to be provided to applicants during examination: ES-1.3, pg. 2 Learning Objective:

2LP-SQS-53.3, ELO 3 & 4 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFR Part 55 Content: 55.41 55.43 X

Comments:

NUREG-1021, Revision 8

Question # 44 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

I I

Group 2

2 K/A #

038 EK3.06 038 EK3.06 Importance Rating 4.2 4.5 During performance of E Steam Generator Tube Rupture, Step 13 - Initiate RCS Cooldown, the operator is directed to determine the "Target" core exit temperature for which the RCS cooldown is to be terminated. Which of the following is the bases for this "Target" temperature?

A. To allow a rapid cooldown without exceeding a maximum cooldown rate of 100TF in one hour.

B. To ensure that the limits which would require tripping the RCPs will not be exceeded.

C. To maintain RCS pressure/temperature points within the limits of the PTS Plant Operational Limits curve.

D. To maintain adequate RCS subcooling following the subsequent RCS depressurization.

Answer:

D Technical Reference(s):

20M-53B.4.E-3 Issue lB, Rev. 6, Step 13 References to be provided to applicants during examination: None Learning Objective:

2LP-SQS-53.3, ELO 3 Question Source:

Bank #

LRT NRC bank #607Q Modified Bank #

.Question History:

New Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFR Part 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 45 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

3 3

Group #

K/A #

2.1.7 2.1.7 Importance Rating 3.7 4.4 Given the following:

"* The Unit is operating at 100% power with all systems in their at-power, NSA configurations.

"* [2FWS-LT474] 21A SG Level Channel fails low.

Which of the following actions are required to be performed?

A. Initiate a turbine runback to 80% power at 5%/minute in accordance with AOP-2.5 1.1 - Emergency Shutdown.

B.

Take manual control of[2FWS*FCV478] 21A Main Feed Regulating Valve and maintain 21A SG water level at 44%.

C. Take manual control of[2FWS*FCV478] 21A Main Feed Regulating Valve, place the 21A SG level signal selector switch to an operable channel, then return the FRV to Auto.

D. Leave all SG water level controls in auto and remove the failed channel from service in accordance with 20M-24.4.1F - Instrument Failure Procedure.

Answer:

D Technical Reference(s):

20M-24.4. AAK References to be provided to applicants during examination: None Learning Objective:

08-02-741, ELO 14; 03-10-706, ELO 21 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFR Part 55 Content: 55.41 55.43 X

Comments:

NUREG-1021, Revision 8

Question # 46 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

1 1

Group #

2 2

K/A #

E 16 EA2.1 E16 EA2.1 Importance Rating 2.9 3.3 Given the following:

"* A large break LOCA has occurred.

"* All ESF equipment responded as required.

"* The operators are in E Loss Of Reactor Or Secondary Coolant, Step 20 Obtain Samples.

"* CNMT radiation levels have peaked at 5E+5 R/Hr and are now 2. 1E+3 RJHr.

"* CNMT pressure peaked at 8 psig and is now 2 psig.

"* All SG's are intact with the following narrow range water levels:

21A-3%

21B - 30%

21C-55%

Which of the following shall be done with regard to SG water levels?

A. Feed 21A to at least 5%, maintain 21B at 30% and isolate feed to 21C.

B.

Feed 21A to at least 5%, maintain 21B and 21C at their current levels.

C.

Feed 21A and 21B to at least 33%, isolate feed to 21C.

D. Feed 21A and 21B to at least 50%, isolate feed to 21C.

Answer:

C Technical Reference(s):

E-1 Step 6 (Adverse CNMT due to radiation levels)

References to be pro*ided to applicants during examination: None Learning Objective:

2LP-SQS-53.2, ELO 15 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFR Part 55 Content: 55.41 55.43 X

Comments:

NUREG-1021, Revision 8

Question # 47 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

I 1

Group#

2 2

K/A #

054 AKI.02 054 AK1.02 Importance Rating 3.6 4.2 While in FR-H. 1 - Response to Loss of Secondary Heat Sink, which of the following are the adverse effects of initiating feed flow from the Auxiliary Feedwater System too quickly to a SG that has been determined to be "Hot and Dry"?

A. A thermal shock to the reactor internals could occur resulting in a possible catastrophic fuel element failure.

B.

Gas binding of the auxiliary feed pump discharge piping could occur resulting in a total loss of feed flow capability.

C. Excessive cooldown of the RCS could occur resulting in meeting RCS Bleed and Feed criteria thus compounding the recovery.

D. A thermal shock to the SG U-tubes could occur resulting in a possible SG tube rupture and subsequent radioactive release to the atmosphere.

Answer:

D Technical Reference(s):

FR-H. 1 Issue IB, Rev. 6 Background References to be provided to applicants during examination: None Learning Objective:

2LP-SQS-53.3, ELO 3

/

Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge X

Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 48 ES-40.1 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

I I

Group#

2 1

K/A#

011EAI.03 011 EAI.03 Importance Rating 4.0 4.0 Given the following:

"* The operators are responding to an event and are currently at Step 24 of E Reactor Trip or Safety Injection.

"* All RCP's are running.

"* The "B" RCP [2RCS*P21B] has no CCP flow indicated.

"* HHS1 flow as indicated on [2SIS*FI943] is 600 gpm.

"* "A" and "C" S/G pressures are 1000 psig and stable.

"* "B" S/G pressure is 1010 psig and stable.

"* RCS pressure is 1150 psig.

"* CNMT pressure is 5.0 psig.

Which of the following actions are required be taken?

A. Stop all RCP's.

B.

Stop only the "B" RCP.

C. Stop "A" and "C" RCP's.

D. Maintain all RCP's running.

Answer:

A Technical Reference(s):

20M-53A. 1.E-0 Issue LB, Rev. 5, Step 24 & Fold Out page References to be provided to applicants during examination: None Learning Objective:

2LP-SQS-53.3, ELO 1; 2LP-SQS-53.3, ELO 3 Question Source:

Bank #

LRT NRC Bank # 352Q Modified Bank #

Question History:

New Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFR Part 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 49 CC Afll

Uh4*t,,

1in,t;rn Ff,1¶j 1.4fl1-V Oii~tion Worksheet F,.ýO

'JIt cu~iii V11

-L..'1I W

(hsto Worksheet=

.~

Examination Outline Cross-reference:

Level Tier #

Group #

K/A #

Importance Rating RO 1

3 028 AA2.09 2.9 SRO 1

3 028 AA2.09 3.2 The definition of "Net Charging" flow is:

Charging _(1)_ Total Seal Injection _(2)_ Letdown _(3)_ Total Seal Leakoff.

A.

plus minus minus B.

plus C.

plus D.

minus plus minus plus minus plus plus Answer:

A Technical Reference(s):

20M-6.4.AAK References to be provided to applicants during examination:

None Learning Objective:

08-02-720, ELO 18.a, 24.a & 30.a; 03-10-706, ELO 7 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge X

Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 X

Comments:

NUREG-1021, Revision 8

Question # 50 ES-401 Sample Written Examination Form ES-401-6 Ouestion Worksheet Examination Outline Cross-reference:

Level Tier #

Group #

K/A#

Importance Rating RO SRO 1

1 3

3 056 AK3.02 056 AK3.02 4.4 4.7 Step 17 of ECA-0.0 - Loss Of All AC Power directs the isolation of the RCP seal injection lines. This is performed (1) and is done to prevent _(2).

A. in the field B. from the control room C.

in the field D. from the control room

_(2)_

excessive leakage from the number 1 seal.

thermal shock to the RCP seal package.

Answer:

C Teclmical Reference(s):

ECA-0.0 and ECA-0.0 Executive Volume References to be provided to applicants during examination: None Learning Objective:

2LP-SQS-53.3, ELO 3 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 Comments:

X X

NUREG-1021, Revision 8

Question # 51 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

2 2

Group h I

I K/A #

061 KI.01 061 K1.01 Importance Rating 4.1 4.4 Which of the following are the adverse consequences of being unable to isolate AFW flow to a SG that is faulted inside CNMT?

1. An excessive RCS cooldown could occur resulting in a potential PTS concern.

2. The peak design CNMT pressure could be challenged resulting in a failure of the CNMT structure.

3. The PRZR will refill much quicker resulting in an increased overpressure challenge to the RCS.

4. The thermal blanket on the affected SG U-tubes will be cooled resulting in the inability to cooldown to the "Target" temperature during subsequent recovery actions.

A.

1 and 2 only.

B.

1 and 3 only.

C. 2, 3 and 4 only.

D.

1, 2, 3 and 4.

Answer:

A Technical Reference(s):

E-2 Issue 1B, Rev. 4 Background References to be provided to applicants during examination: None Learning Objective:

2LP-SQS-53.3, ELO 3 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFR Part 55 Content: 55.41 X

55.43 Comments:

NUR.EG-1021, Revision 8

Question # 52 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier h 2

2 Group #

1 1

K/A #

072 K1.04 072 K1.04 Importance Rating 3.3 3.5 Which of the following, if any, will occur if both [2RMC*RQ201 and 202] Control Room Area Radiation Monitors go into the ALERT status?

A. No automatic actions will occur.

B.

A full CREBAPS actuation will occur.

C.

One Control Building Emergency Supply Fan will start.

D. The Control Building Normal Supply and Exhaust Fans will trip.

Answer:

A Technical Reference(s):

20M-43.4.AAU References to be provided to applicants during examination:

None Learning Objective:

08-02-770, ELO 7.b Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge X

Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 53 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

1 1

Group#

3 3

K/A #

E13 EKI.3 El3 EKI.3 Importance Rating 3.0 3.2 During the recovery from a ruptured 21C SG, which of the following is an indication that the ruptured SG atmospheric relief valve [2SVS*PCV101C] has lifted and subsequently reseated?

Annunciator [A6-7A] Steamline Pressure High activates, when acknowledged, changes to

_(1)_ and [2SVS*PCV101C] demand indicator is at _(2)_ with the valve _(3)_

indicating light lit.

-(1)-

_(2)_

_(3)_

A. white 0%

green B. red 0%

red C.

white 0%

red D. white 100%

green Answer:

A Technical Reference(s):

20M-21.4 AAK References to be provided to applicants during examination: None Learning Objective:

08-02-737, ELO 9 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge X

Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 54 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level Tier #

Group #

K/A#

Importance Rating Given the following:

"* The Unit is operating at 100% power with all systems in their at-power, NSA configurations.

"* A feed flow instrument on the 21B SG causes [2FWS*FCV488] Main Feed Regulating Valve to go full open.

"* A reactor/turbine trip occurs on the resultant 21B SG high water level.

"* All equipment operates as designed on the trip with the exception of the "B" Reactor Trip Breaker which is still shut.

"* RCS temperature is 547TF.

For the above listed conditions, what should be the positions of the following feedwater components for the 21B SG?

[2FWS*FCV488]

(Main FRV)

A. Open B.

Open C.

Closed D. Closed

[2FWS*FCV489]

(Main FRV Bypass)

Closed Closed Open Closed

[2FWS*HYV157B]

(Feed Line Isolation)

Closed Open Open Closed Answer:

D Technical Reference(s):

UFSAR logic 7.3-18 (Sheet 13)

References to be provided to applicants during examination: None Learning Objective:

08-02-741, ELO 7.b Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8 RO 2 1 059 A3.06 3.2 SRO 2

1 059 A3.06 3.3 X

Question # 55 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level Tier #

Group #

K/A #

Importance Rating Note: This is an open reference question.

The Unit is operating at 100% power with all systems in their at-power, NSA configurations with the following exceptions:

"* Testing is in progress on Train "B" of the Solid State Protection System (SSPS).

"* The "B" Reactor Trip Breaker (RTB) is OPEN.

For the above listed conditions, which of the following will result in a Reactor Trip?

1. Racking in but not closing the "A" Train Reactor Trip Bypass breaker.

2. Racking in and closing the "A" Train Reactor Trip Bypass breaker.

3.

Closing the "A" Train Reactor Trip Bypass breaker in the racked out position.

A.

1 and 2 only.

B.

2 and 3 only.

C. 2 only.

D. 1, 2, and 3.

Answer:

C Technical Reference(s)

FSAR Logic Diagram - Sheet 2, Figure 7.3-7, Rev. 9 References to be provided to applicants during examination:

FSAR Logic Diagram - Sheet 2, Figure 7.3 7, Rev. 9 Learning Objective:

08-02-703, ELO 14 Question Source:

Bank #

2LOT1 #27 (1997)

Question History:

Question Cognitive Level:

10 CFR Part 55 Content:

Modified Bank #

New Previous NRC Exam Previous Quiz / Test Memory or Fundamental Knowledge Comprehension or Analysis 55.41 X

55.43 Comments:

NUREG-1021, Revision 8 RO 2

1 001 K2.02 3.6 SRO 2

1 001 K2.02 3.7 X

Question # 56 ES-401 Sample Written Examination Form ES-40 1-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

2 2

Group #

1 I

K/A#

001K6.11 001 K6.11 Importance Rating 2.9 3.2 Which of the following Rod Control System failures will still permit control rod motion?

A. Logic Cabinet Oscillator failure.

B.

Logic Cabinet Slave Cycler failure.

C. Power Cabinet Regulation failure.

D. Power Cabinet Redundant +24 vdc Power Supply failure.

Answer:

D Technical Reference(s):

20M-1.4.D, pg. 16-18, 2OM-I.4-AAB References to be provided to applicants during examination: None Learning Objective:

08-02-703, ELO 7 & 17 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test

/

Question Cognitive Level: Memory or Fundamental Knowledge X

Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 57 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

2 2

Group 1

I K/A #

003 K5.02 003 K5.02 Importance Rating 2.8 3.2 Which of the following is the bases for the underfrequency trip of the RCP's?

A. Ensures that the RCP motor windings will not overheat due to the increased 12R losses at reduced operating frequencies.

B.

Ensures that the inertia of the RCP flywheel will aid in maintaining loop flow thus maintaining DNBR within acceptable limits.

C.

Aids in maintaining grid stability by reducing grid loading demands after the Normal 4KV buses have transferred to the SSST's.

D. Ensures that the RCP's are not operated at "critical" speeds which could result in severe vibrations and catastrophic failure of the RCP or an RCS LOCA.

Answer:

B Teclimical Reference(s):

20M-1.1.B Issue 4, Rev. 2, pg. 7, 8 References to be provided to applicants during examination: None Learning Objective:

08-02-714, ELO 6 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge X

Comprehension or Analysis 10 CFRPart 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 58 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

2 2

Group #

1 1

K/A #

003 A4.06 003 A4.06 Importance Rating 2.9 2.9 Given the following:

"* The Unit is operating at 100% power with all systems in their at-power, NSA configurations.

"* Annunciator [A2-5D] RCP SEAL VENT POT LEVEL HIGH/LOW has just illuminated with the computer point indicating a high seal vent pot level on the "A" RCP.

"* "A" RCP number 1 seal leakoff flow on [2CHS-FR154A] has dropped from 2.5 gpm to 0.75 gpm.

"* "A" RCP seal injection flow has risen from 7 gpm to 7.5 gpm.

"* "B" and "C" seal injection flows have remained at 7 gpm.

"* No other alarms have been received.

Which of the following could be the cause of these conditions?

A. There is a leak in the "A" RCP seal injection line.

B.

The number 2 seal on the "A" RCP has excessive leakage.

C. The RCP seal leakoff bypass valve [2CHS*MOV307] is leaking by.

D. The "A" RCP seal leakoff isolation valve [2CHS*MOV303A] has gone shut.

Answer:

B Technical Reference(s):

20M-6.4.AAB References to be provided to applicants during examination: None Learning Objective:

08-02-714, ELO 10.d & 12 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFR Part 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 59 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

2 2

Group#

1 1

K/A#

013 AI.06 013 AI.06 Importance Rating 3.6 3.9 Note: This is an open reference question.

Given the following:

"* The Unit is operating at 100% power with all systems in their at-power, NSA configurations.

"* RWST level is at the minimum required Tech Spec level.

"* A large break LOCA has occurred and RCS pressure drops to 0 psig instantaneously.

"* All ESF equipment functions as designed.

"* HIHSI flow as indicated on [2SIS*FI943] is 600 gpm.

"* LHSI flow as indicated on [2SIS*FI945] and [2SIS*FI946] is 3750 gpm.

"* Quench spray flow as indicated on [2QSS*FIIO1A] and [2QSS*FIIO1B] is 2900 gpm.

"* The design flowrate of a Recirculation Spray pump is 3500 gpm.

Assuming no operator actions are taken, how long should it take for the RWST level to reach the transfer to cold leg recirculation setpoint required by the EOP's?

A.

10 - 20 minutes.

B.

21 - 30 minutes.

C.

31 - 40 minutes.

D. 41 - 50 minutes.

Answer:

B - RWST level change = 316,072 gal, total flow rate = 13,900 gpm, total time = 22.7 minutes Technical Reference(s):

20M-7.1, 11.1, 13. 1, ES-1.3, RWST Tank Curves References to be provided to applicants during examination:

RWST Tank Curves - NR and WR Learning Objective:

08-02-727, ELO 11; 08-02-725, ELO 2 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level:

Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFR Part 55 Content:

55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 60 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

2 2

Group #

1 I

K/A #

013 K6.01 013 K6.01 Importance Rating 2.7 3.1 The Unit is operating at 100% power with all systems in their at-power, NSA configurations when the following occurs:

"* Annunciator [A1-2F] CONTAINMENT PRESSURE HIGH/HIGH-HIGH actuates.

"* CNMT pressure indicator [2LMS*PI950] is off scale high.

"* All other CNMT indications are normal.

Which of the following actions are required to be taken for [2LMS*PI950]?

1. Trip the HI CNTMT Press SI bistable.

2. Bypass the HI-HI CNMT PRESS CIB bistable.

3. Trip the Intermediate HI-HI CNMT Press SLI bistable.

A. 2 only.

B.

I and3 only.

C.

2 and 3 only.

D. 1,2and3.

Answer:

A Technical Reference(s):

20M-1.4.IF References to be provided to applicants during examination: None Learning Objective:

2LP-SQS-47. 1, ELO 5 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFRPart 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 61 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

2 2

Group #

1 I

K/A #

004 K3.06 004 K3.06 Importance Rating 3.4 3.6 The Unit is operating at 75% power with all systems in their at-power, NSA configurations when [2CCP*TCV 144] Non-Regenerative Heat Exchanger Discharge Temperature Control Valve fails open. With no operator action, which of the following describes the response to this malfunction?

A. Equilibrium xenon level will drop.

B.

Main steam pressure will increase.

C.

PRZR spray valves will initially throttle closed.

D. PRZR level will initially drop and then return to program level.

Answer:

B Technical Reference(s):

Demineralizer Fundamental References to be provided to applicants during examination: None Learning Objective:

08-02-720, ELO 54.c Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFR Part 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 62 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

2 2

Group #

I K/A #

015 K4.07 015 K4.07 Importance Rating 3.7 3.8 When power is being reduced, Permissive P-8 changes the coincidence for the trip signal(s) from 1/3 loops to 2/3 loops.

1. RCS Loop Low Flow

2. RCP Breaker Position

3.

RCP Bus Undervoltage

4. RCP Bus Underfrequency A.

1 only.

B.

1 and2 only.

C.

2, 3 and 4 only.

D.

1, 2, 3 and 4.

Answer:

A Technical Reference(s):

UFSAR Figure 7.3-10 References to be provided to applicants during examination: None Learning Objective:

08-02-019, ELO 10 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFR Part 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 63 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

2 2

Group #

1 1

K/A #

017 K5.03 017 K5.03 Importance Rating 3.7 4.1 Note: This is an open reference question.

Under which of the following conditions would the RCS be 50O superheated?

5 Hottest Core RCS Pressure Exit TC's (0F)

(psig)

A.

658 2000 B.

667 1735 C.

522 1250 D.

533 750 Answer:

B Technical Reference(s): Steam Tables References to be provided to applicants during examination:

Steam Tables Learning Objective:

GFES Question Source:

Bank #

Modified Bank #

/

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFR Part 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 64 rc Afl1 C,,..,n1 IMffn 1niinitnn Fnrm Pg-401-6 L,3-tU

1..JalLLjJ*.s V. £LtflI Ouestion Worksheet TRISECTOR 1 MAX 1202°F AVG 11850F MIN 1172*F TRISECTOR 3 MAX 1205°F AVG 11920F MIN 11820F TRISECTOR 2 MAX 1192 0F AVG 1187 0F MIN 1171F Which of the following actions are required to be performed?

A. Depressurize all SG's to atmospheric pressure.

B.

Attempt to start an RCP regardless of support system status.

C. Attempt to start an RCP after verifying all support systems are functional.

D. Enter SACRG I - Severe Accident Control Room Guideline Initial Response Answer:

A Technical Reference(s):

20M-FR-C. I Step 22 References to be provided to applicants during examination: 20M-FR-C.1 pg. 13-15, EOP Attachment A-1.3 Learning Objective:

2LP-SQS-53.3, ELO 6 Question Source:

Bank #

Modified Bank #

Question History:

New X

Question Cognitive Level:

Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFR Part 55 Content:

55.41 X

55.43 Comments:

NUREG-1021, Revision 8

.1210-aille %.'

AA1 0

1 UATý;4+ý Vnrm ES-401-6 Examination Outline Cross-reference:

Level R,

5Uu Tier #

2 2

Group #

I I

K/A #

017 A4.01 017 A4.01 Importance Rating 3.8 4.1 Note: This is an open reference question.

Given the following:

The operators are responding to an event and are currently in FR-C. 1 Response to Inadequate Core Cooling, Step 22 - Check if RCPs Should Be Started.

"* All RCP's are stopped and available; however, support systems have not been verified.

"* All SG NR water levels are 33%.

"* The following Core Exit TC indications are displayed on the PSMS Core Temp Display:

Question # 65 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

2 2

Groupf#

1 I

K/A #

056 A2.04 056 A2.04 Importance Rating 2.6 2.8 With the Unit operating at 100% power with all systems in their at-power, NSA configurations, a main condensate pump trips. Which of the following describes the plant response to this pump trip?

A. The reactor will trip on low SG water levels unless reactor power is reduced to 80% power.

B. The reactor will trip on low SG water levels unless the standby condensate pump is manually started.

C. The standby condensate pump will automatically start and have little effect on the feedwater system.

D. The standby condensate pump will automatically start, however, the operator must manually control feedwater flow until steam generator level is stabilized.

Answer:

C Technical Reference(s):

20M - 22A.4.AAC References to be provided to applicants during examination: None Learning Objective:

08-02-738, ELO 4&7 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFR Part 55 Content: 55.41 X

55.43 X

Comments:

NUREG-1021, Revision 8

Question # 66 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

2 2

Group#

1 I

K/A #

056 KI.03 056 K1.03 Importance Rating 2.6 2.6 With the Unit operating at 100% power with all systems in their at-power, NSA configurations, which of the following malfunctions will cause annunciator [A6-1OB]

STM GEN FEED PUMP 21A/B SUCTION PRESS LOW to illuminate?

A. [2CNM-FCV101] Condensate Pump to Hotwell Recirc Valve fails open.

B.

[2CNM-DCV100] Condensate Polishing Bypass Differential Control Valve fails open.

C.

[2CNM-AOV 100] Condensate Feedwater Heater Bypass Valve fails closed.

D. [2FWR-FCV150A] SG Feed Pump 21A Recirc Valve fails closed.

Answer:

A Technical Reference(s):

20M-24.4-AAF References to be provided to applicants during examination: None Learning Objective:

2-LOT-V-5, ELO 1-8; 08-02-738, ELO 9 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFRPart 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 67 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

2 2

Group #

2 1

K/A #

063 K3.02 063 K3.02 Importance Rating 3.5 3.7 With the Unit operating at 100% power with all systems in their at-power, NSA configurations, which of the following Tech Specs, if any, must be entered if

[PNL*DC2-11] Breaker 8-16, [2FWS*HYV157A] 21A SG FW Isol Vlv trips open and cannot be reclosed?

A. 3.3.1.1 Reactor Trip System Instrumentation.

B. 3.6.3.1 Containment Isolation Valves.

C.

3.3.1.1 Reactor Trip System Instrumentation and 3.6.3.1 Containment Isolation Valves.

D. Tech Specs 3.3.1.1 and 3.6.3.1 are not applicable for this problem.

Answer:

B Technical Reference(s):

20M-39.5.B4 Load List References to be provided to applicants during examination: None Learning Objective:

08-02-741, ELO 20 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFR Part 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 68 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

2 2

Group#

I K/A #

071 A2.03 071 A2.03 Importance Rating 2.7 3.3 A malfunction in the Unit 2 Waste Gas System is causing [2GWS-TK21] Waste Gas Surge Tank pressure to steadily rise. Which of the following shall occur?

A. The surge tank relief valve [2GWS-RV101] will open before the rupture disc blowout pressure is reached. If pressure continues to rise, the rupture disc will fail to further protect the surge tank.

B.

The rupture disc will fail first, relieving to the inlet of the surge tank relief valve

[2GWS-RV101] which will lift and discharge the entire contents of the surge tank.

C. The rupture disc will fail first, relieving to the inlet of the surge tank relief valve

[2GWS-RV101] which will lift and discharge until the relief valve reseats at - 90 psig.

D. The surge tank relief valve [2GWS-RV101] will open first, relieving to the inlet of rupture disc which will fail and discharge until the relief valve reseats at - 90 psig.

Answer:

C Technical Reference(s):

20M-19.4.AAB, 20M Figure 19-1 References to be provided to applicants during examination:

None Learning Objective:

2LP-SQS-WD, ELO 8.f& 8.g; 08-02-735, ELO 3 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFR Part 55 Content: 55.41 X

55.43 X

Comments:

NUREG-1021, Revision 8

Question # 69 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

3 3

Group #

K/A #

2.1.7 2.1.7 Importance Rating 3.7 4.4 The unit was operating at full power with all systems in NSA when a loss of offsite power and Reactor Trip occurred. Service water cooling flow cannot be established to the 2-1 EDG which is carrying the 2AE 4KV bus. Which of the following are required to be performed?

A. Stop the 2-1 EDG engine and prevent it from automatically restarting by depressing the 2-1 EDG Local Stop pushbutton.

B.

Stop the 2-1 EDG engine and prevent it from automatically restarting by simultaneously depressing both 2-1 EDG BB-C Stop pushbuttons.

C.

Stop the 2-1 EDG engine and prevent it from automatically restarting by placing the BB-C Auto/Exercise control switch in Exercise and depress either of the 2-1 EDG BB-C Stop pushbuttons.

D. Shift loads from the 2-1 EDG to the 2-2 EDG by starting redundant equipment.

If required, the 2-1 EDG will automatically shutdown on high jacket water temperature.

Answer:

B Technical Reference(s):

E-12F, 20M Figure 36-19, 20M Figure 36-24A (12241-LSK-22-6A)

References to be provided to applicants during examination: None Learning Objective:

08-02-762, ELO 7.c, 7.d, 14.b Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFR Part 55 Content: 55.41 55.43 X

Comments:

NUREG-1021, Revision 8

Question # 70 Iz'.*_4fl 1,qmnle~ Written Examination Form ES-40 1-6 Ouestion Worksheet Examination Outline Cross-reference:

Level Tier #

Group #

K/A #

Importance Rating RO 2

1 068 A3.02 3.6 SRO 2

1 068 A3.02 3.6 For an automatic isolation of a radioactive liquid waste discharge from the SG Blowdown Test Tanks to occur, [2SGC-HCV100] Liquid Waste Effluent High Radiation Isolation Valve _(1)_ be in manual control and a _(2)_ High alarm condition must be present.

-(1) -

_(2)_

A. can B.

cannot C. can D. cannot Answer:

D Techmical Reference(s):

References to be provided Learning Objective:

Question Source:

Question History:

[2SGC-RQI100] Liquid Waste Process Effluent

[2SSR-RQI100] Steam Generator Blowdown

[2SGC-RQII00] Liquid Waste Process Effluent 20M-43.4.AEE to applicants during examination: None 08-02-770, ELO 2 & 7.b Bank #

Modified Bank #

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X

55.43 Cormnents:

NUREG-1021, Revision 8 X

'POZ-401 S le Written Examination Form ES-401-6

Question # 71 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

2 2

Group #

1 1

K/A #

072 K1.01 072 K1.01 Importance Rating 3.1 3.5 Which of the following, if any, should occur if [2RMR-RQI3 01 ] Leak Collection Ventilation Radiation Monitor goes into High alarm?

A. Ventilation dampers reposition to isolate the contiguous area ventilation exhaust.

B. Ventilation dampers reposition to align the contiguous area ventilation exhaust to the Auxiliary Building filtered exhaust plenum.

C. No automatic actions will occur, the operator is required to manually reposition dampers to align the contiguous area ventilation exhaust to the Auxiliary Building filtered exhaust plenum.

D. No automatic actions will occur because the contiguous area ventilation exhaust is normally aligned to the Auxiliary Building filtered exhaust plenum.

Answer:

B Technical Reference(s):

20M-43.4.AEB References to be provided to applicants during examination: None Learning Objective:

08-02-770, ELO 2 & 7 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge X

Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 72 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

2 2

Group#

2 2

K/A #

006 K5.02 006 K5.02 Importance Rating 2.8 2.9 Given the following:

"* The Unit is operating at 100% power with all systems in their at-power, NSA configurations.

"* The 21A SI accumulator Level/Pressure High/Low annunciator is lit.

"* 21A SI accumulator parameters are:

Level - 35%

Pressure - 643 psig Which of the following should be done to the 21A SI accumulator to clear the annunciator without causing any SI accumulator parameter to exceed its Tech Spec required value during the process?

A. Vent to maintain 630 psig while simultaneously filling to 50%.

B. Pressurize to 665 psig while simultaneously filling to 50%.

C. Fill to 50% then pressurize to 665 psig.

/

D. Fill to 50% then vent to 630 psig.

Answer:

A Technical Reference(s):

20M-11.4-AAC,20M-11.4.D References to be provided to applicants during examination: None Learning Objective:

08-02-725, ELO 13.b Question Source:

Bank #

Modified Bank #

Question Hlistory:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFR Part 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 73 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

2 2

Group 2

2 K/A #

002 A1.06 002 A1.06 Importance Rating 4.0 4.0 Given the following:

"* All systems are in their NSA configurations for the current power level.

"* The operators are performing 20M-52.4.C - Decreasing Load From 40% To Turbine Shutdown And Reactor At Approximately 5% Power.

"* The main generator output breakers [PCB-352 and 362] have just been opened.

"* The steam dumps are in auto and have reached an equilibrium condition.

"* Control rods are withdrawn 5 steps at this time.

Assuming no operator action is taken, and no protective actions are warranted, when conditions stabilize, the final values as compared to the initial values of reactor power, Tavg, and steam pressure will be which of the following?

Reactor Power Tavg Steam Pressure A. Unchanged Higher Higher B. Higher Higher Unchanged C. Higher Higher Higher D. Unchanged Unchanged Unchanged Answer:

B Technical Reference(s):

Simulator Response References to be provided to applicants during examination: None Learning Objective:

03-10-705, ELO 2 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFR Part 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 74 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

2 2

Group 2

2 K/A#

011 KI.04 011 K1.04 Importance Rating 3.8 3.9 The unit is operating at 5% power in preparation for a turbine startup. Due to a failure of the charging flow control valve, PRZR level is rising. All other plant parameters are at the normal operating band for 5% power. Which of the following is the expected plant response?

A. A Rx trip will occur when 2/3 PRZR level detectors reach 92%.

B.

A Rx trip will occur when 3/3 PRZR level detectors reach 92%.

C. No PRZR level trip will occur because power is less than P-7.

D. No PRZR level trip will occur because RCS pressure is greater than P-11.

Answer:

C Technical Reference(s): 20M-1.1B Issue 4, Rev. 1, pg. 7, 20M-1.2.B Issue 4, Rev. 3, pg. 7 & 8 References to be provided to applicants during examination: None Learning Objective:

08-02-720, ELO 47.a; 2LP-SQS-1.1, ELO 5.a Question Source:

Bank #

LRT NRC Bank # 634J Modified Bank #

Question History:

New Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFR Part 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 75 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

2 2

Group #

2 2

K/A #

010 A3.02 010 A3.02 Importance Rating 3.6 3.5 Given the following:

The Unit is operating at 100% power with all systems in their at-power, NSA configurations except for PRZR pressure channel [2RCS*PT455] which has been declared inoperable and taken out of service in accordance with the respective instrument failure procedure.

"* A second PRZR pressure channel, [2RCS*PT444], subsequently fails high.

Assuming no operator action, which of the following describes the plant response to this subsequent instrument failure?

A. All PRZR heaters will turn off, all PRZR PORV's and spray valves will remain closed.

B.

All PRZR heaters will turn off, one PRZR PORV and both spray valves will open.

C.

All PRZR PORV's and spray valves will open resulting in a Low PRZR Pressure Rx Trip and SI.

D. The Rx will trip immediately on High PRZR Pressure and a subsequent SI will actuate on Low PRZR Pressure.

Answer:

B Technical Reference(s):

20M-6.4.1F References to be provided to applicants during examination: None Learning Objective:

08-02-715, ELO 5 & 13.h Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFR Part 55 Content: 55.41 X

55.43 Conunents:

NUREG-1021, Revision 8

Question # 76 FPg-401 Samnie Written Examination Form ES-401-6 Ouestion Worksheet Examination Outline Cross-reference:

Level Tier #

Group #

K/A #

Importance Rating Which of the following will generate an EDG Emergency A. 480V Bus 2N feeder breaker 2N3B tripping open B. 4KV Emergency Bus feeder breaker 2E7 tripping C.

1/3 4KV Emergency Bus 75% relays actuated for D.

1/2 4KV Emergency Bus 90% relays actuated for Answer:

B Technical Reference(s):

20M Figure 36-24A, 10080-E-5DU Sh. I References to be provided to applicants during examination: None Learning Objective:

08-02-762, ELO 7 Question Source:

Bank #

LRT NRC Bank # 0711 Modified Bank #

Question History:

New Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X

55.43 Comments:

Start signal?

open.

0.1 seconds.

90.0 seconds.

J X

NUREG-1021, Revision 8 RO 2

2 062 K4.07 2.7 SRO 2

2 062 K4.07 3.1 ES401 Sample Written Examination Form ES401-6

Question # 77 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level Tier #

Group #

K/A #

Importance Rating Which of the following describes the signal that is used as the input for the listed process program generators?

PRZR Program Level A.

Selected 1st Stage Pressure B.

Auctioneered High Tave C.

Median Tave D.

Median Tave Answer:

C SG Program Water Level 1st Stage Pressure

[2MSS*PT446]

Auctioneered High Tave Selected 1st Stage Pressure Median Tave Tave Program Selected Ist Stage Pressure 1st Stage Pressure

[2MSS*PT447]

Selected 1st Stage Pressure 1st Stage Pressure

[2MSS*PT446]

Steam Dump Load Rejection Program Tave 1st Stage Pressure

[2MSS*PT447]

Selected 1 st Stage Pressure 1st Stage Pressure

[2MSS*PT446]

1st Stage Pressure

[2MSS*PT446]

Technical Reference(s):

20M-1.1, 6.1, 21.1, 24.1 References to be provided to applicants during examination:

None Learning Objective:

1/2LP-ATA-5, ELO 11, 17 & 20 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 Comments:

X X

NUREG-1021, Revision 8 RO 2

2 016 K4.03 2.8 SRO 2

2 016 K4.03 2.9

Question # 78 ES-401 Sample Written Examination Form ES-401-6 FormES-41-6 Ouestion Worksheet Examination Outline Cross-reference:

Level Tier #

Group #

K/A#

Importance Rating Given the following:

"* The unit is in Mode 5 with all systems in their NSA configurations for the current mode of operation.

"* A CNMT purge is in progress.

"* Personnel are attempting to open both doors on the normal CNMT airlock to allow unrestricted access to CNMT. They have the interlock defeated and the outer door open.

"* Personnel then report that when attempting to open the inner airlock door, it will not open.

Which of the following could be the cause of not being able to open the airlock door?

1.

2.

3.

4.

CNMT purge exhaust damper [2HVR*MOD23B] is throttled too far closed.

CNMT purge exhaust damper [2HVR*MOD23B] is throttled too far open.

CNMT purge supply damper [2HVR*MOD25B] is throttled too far closed.

CNMT purge supply damper [2HVR*MOD25B] is throttled too far open.

A. Only I or 3.

B.

C.

Only 1 or 4.

Only 2 or 3.

D. Only 2 or 4.

Answer:

B Technical Reference(s):

Fundamentals References to be provided to applicants during examination:

Learning Objective:

2LP-SQS-47. 1, ELO 4 & 7 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level:

Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content:

X 55.41 55.43 None x

Comments:

NUJREG-1021, Revision 8 RO 2

2 029K4.02 2.9 SRO 2

2 029K4.02 3.1

Question # 79 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

2 2

Group #

2 2

K/A l 033 K4.01 033 K4.01 Importance Rating 2.9 3.2 Which of the following design features ensures Keff remains less than or equal to 0.95 in the Spent Fuel Pool with irradiated fuel in the pool?

1. A minimum of 2000 ppm boron concentration in the pool.

2. The minimum center-to-center distance between fuel assemblies.

3. Boron coated poison rods inserted into every other spent fuel assembly.

A. 1 and 2 only.

B.

2 only.

C.

I and3 only.

D. 1,2and3.

Answer:

B Technical Reference(s):

20M-20.1.B Issue 4, Rev. 1, pg. 3 References to be provided to applicants during examination: None Learning Objective:

2LP-SQS-20. 1, ELO 2 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge X

Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 80 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

2 2

Group#

2 2

K/A#

035 K6.01 035 K6.01 Importance Rating 3.2 3.6 Given the following:

"* The operators are responding to an event and are currently in ECA-2.1 Uncontrolled Depressurization of All SG's.

"* All MSIV's have initially failed to close.

"* An operator was then able to shut the "A" and "B" SG MSIV's.

"* The following indications were then observed:

"* "A" SG Pressure - 150 psig and stable.

"* "B" SG Pressure - 145 psig and dropping.

' "C" SGPressure - 150 psig and stable.

CNMT Pressure is 10.2 psia.

Which of the following describes the status of the SG's at this point?

A. "A" and "B" are intact, "C" is faulted outside CNMT.

B. "A" and "C" are intact, "B" is faulted outside CNMT.

C. "B" is intact, "A" and "C" are faulted inside CNMT.

D. "A" and "C" are intact, "B" is faulted inside CNMT.

Answer:

B Technical Reference(s):

E-0 Criteria for faulted SG References to be provided to applicants during examination: None Learning Objective:

2LP-SQS-53.3, ELO 6 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFR Part 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 81 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

2 2

Group #

3 2

K/A #

028 K2.01 028 K2.01 Importance Rating 2.5 2.8 Where is the electrical supply breaker for the "A" Hydrogen Recombiner and where is this breaker controlled from?

A. 480V Substation 2-8, controlled locally at the 480V Substation 2-8.

B.

480V Substation 2-8, controlled from the "A" Post Accident H2 Control Panel.

C.

2AE Emergency 4KV bus, controlled locally at the 2AE Emergency 4KV bus.

D. 2AE Emergency 4KV bus, controlled from the "A" Post Accident H2 Control Panel.

Answer:

A Technical Reference(s):

20M-46.4.A References to be provided to applicants during examination: None Learning Objective:

08-02-763, ELO 5 Question Source:

Bank #

Modified Bank #)

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge X

Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 82 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

2 2

Group#

2 2

K/A #

055 KI.06 055 KI.06 Importance Rating 2.6 2.6 Which of the following is performed to ensure that the minimum amount of radioactive gases are released offsite from the Unit 2 condenser air ejector off gas?

The air ejector off gas is...

A. manually aligned to the charcoal delay beds if [2ARC-RQI 100] Air Ejector Discharge radiation monitor indicates high radiation.

B.

automatically aligned to the charcoal delay beds on a High alarm from

[2ARC-RQI100] Air Ejector Discharge radiation monitor.

C.

manually aligned to the Unit 2 CNMVfT if[2ARC-RQI100] Air Ejector Discharge radiation monitor, indicates high radiation.

D. automatically aligned to the Unit 2 CNMT on a High alarm from

[2ARC-RQI100] Air Ejector Discharge radiation monitor.

Answer:

A Technical Reference(s):

20M-19.1.B, 20M-19.4.H References to be provided to applicants during examination: None Learning Objective:

08-02-770, ELO 2 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge X

Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 83 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

2 2

Group#

2 2

KIA #

064 K2.02 064 K2.02 Importance Rating 2.8 3.1 Where is the electrical supply breaker for the 2-1 EDG fuel oil transfer pump

[2EGF*P21A] located?

A. 2AE 4KV Bus B.

[MCC*2-EO7]

C. [PNL*VITBS2-1D]

D. [PNL-DC2-07]

Answer:

B Technical Reference(s):

20M-36.2.C.8, pg. 2 References to be provided to applicants during examination: None Learning Objective:

08-02-762, ELO 6 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge X

Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 84 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

2 2

Group#

2 2

K/A #

073A2.02 073A2.02 Importance Rating 2.7 3.2 The unit is in Mode 3 with all systems in NSA. [2CCP-RQI100] Component Cooling Water radiation monitor has just gone into High alarm. To verify the High alarm, which of the following is required to be checked for leakage?

1. CVCS Non-Regenerative Heat Exchanger

2. RCP Seal Water Heat Exchanger

3. RCP Thermal Barrier Heat Exchangers A. 1 and 2 only.

B.

1 and 3 only.

C.

2 and3 only.

D. 1,2and3.

Answer:

B Technical Reference(s):

20M-43.4.ACO References to be provided to applicants during examination: None Learning Objective:

08-02-770, ELO 6 & 7 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFR Part 55 Content: 55.41 X

55.43 X

Comments:

NUREG-1021, Revision 8

Question # 85 ES-401 Samnle Written Examination Form ES-401-6 Ouestion Worksheet Examination Outline Cross-reference:

Level Tier #

Group #

K/A #

Importance Rating Note: This is an open reference question.

With all systems in their NSA configurations, all but one of the cooling tower pumps trip.

Assuming all turbine vibration readings are normal, which of the following sustained conditions would require a manual Turbine and/or Reactor Trip?

Main Generator Output (MW) 230 700 800 210 Condenser Backpressure (In. Hg Abs.)

4.0 4.5 6.5 2.5 A. 1, 2 and 4 only.

B.

1 and 3 only.

C. 3 only.

D. 2 and 4 only.

Answer:

B Technical Reference(s):

20M-26.4.AAK References to be provided to applicants during examination: 20M-26.4.AAK Learning Objective:

08-02-743, ELO 4 Question Source:

Bank #

Modified Bank # Unit I - 1LOT2, (1997) - Modified Question History:

New Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 Comments:

X X

X NUREG-1021, Revision 8 RO 2

2 075 A2.02 2.5 SRO 2

2 075 A2.02 2.7

1.

2.

3.

4.

Question # 86 ES-401 Sample Written Examination Form ES-40 1-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

2 2

Group 3

2 K/A#

041 K4.14 039 K1.06 Importance Rating 2.5 3.0 Which of the following describes the C-7A condenser steam dump load rejection bistable?

A _

(1)_

pressure transmitter supplies the rate of change signal and the bistable will reset when _(2).

(1)

(2)

A. turbine 1st stage manually reset by the operator.

B.

main steam header manually reset by the operator.

C. turbine 1st stage the rate of change drops below the setpoint.

D. main steam header the rate of change drops below the setpoint.

Answer:

A Technical Reference(s):

20M-21.1.C References to be provided to applicants during examination:

None Learning Objective:

08-02-737, ELO 5 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz I Test Question Cognitive Level: Memory or Fundamental Knowledge X

Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 87 ES-401 Sample Written Examination Form ES-40 1-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

2 2

Group#

2 2

K/A #

079 A4.01 079 A4.01 Importance Rating 2.7 2.7 Given the following:

"* The Unit was operating at 100% power with all systems in their at-power, NSA configurations except for the "A" CNMT Instrument Air Compressor which is on clearance.

"* An electrical fault on the 2DF bus caused the loss and lockout of the 2DF bus and an inadvertent Safety Injection.

"* All ESF equipment operated as designed.

Which of the following is the minimum required to restore instrument air pressure to CNMT?

1. Reset SI and CIA.

2. Open [2IAC*MOV130] CNMT Instrument Air Isolation valve.

3.

Open [2IAC*MOV13 1] CNMT Instrument Air Backup Supply valve.

A.

1 and 2 only.

B.

2 and 3 only.

C.

3 only.

D. 1,2and3.

Answer:

D Technical Reference(s):

20M-34.4.D Issue 4, Rev. 1, pg. 6 and Figure 34-3 References to be provided to applicants during examination: None Learning Objective:

2LP-SQS-34. 1, ELO 5 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFRPart 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 88 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

2 2

Group#

3 3

K/A #

008 Al.03 008 A1.03 Importance Rating 2.7 2.9 When swapping CCP pumps, the operator is directed to adjust [2CCP*DCV100-I] Pri Comp Clg Wtr Pump Diff Control Vlv in manual to raise CCP pump discharge pressure to 120 - 125 psig. If indicated CCP pump discharge pressure is 110 psig and

[2CCP*DCV100-1] controller is in manual, which of the following describes how this is to be accomplished?

A.

Adjust [2CCP*DCV1001-(2)] controller setpoint to a higher value to cause the valve to throttle open.

B.

Adjust [2CCP*DCV10O-1(2)] controller setpoint to a lower value to cause the valve to throttle closed.

C. Depress [2CCP*DCV100-1 (2)] controller output up button to cause the valve to throttle open.

D. Depress [2CCP*DCV100-1(2)] controller output down button to cause the valve to throttle closed.

Answer:

D Technical Reference(s):

20M Figure 15-1 References to be provided to applicants during examination: None Learning Objective:

08-02-73 1, ELO 7 & 8 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFR Part 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 89 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

2 2

Group#

3 3

K/A #

045 K4.11 045 K4.11 Importance Rating 3.6 3.9 Under which of the following conditions will a Reactor Trip occur?

1. N 48.5%, N 49.5%, N 48.5%, N 50.0%

2. N 48.3%, N 50.0%, N 48.4%, N 48.6%

3. Emergency Trip Header Pressures:

63-4/AST - 1050 psig, 63-5/AST - 1025 psig, 63-6/AST - 975 psig

4. Emergency Trip Header Pressures:

63-4/AST - 1025 psig, 63-5/AST - 985 psig, 63-6/AST - 990 psig

5. Main Turbine Throttle Valves:

TV Open, TV Closed, TV Open, TV Open A.

1 and 4 only.

B.

2 and 3 only.

C.

1 and either (4 or 5).

D. Either (1 or 2) and either (4 or 5).

Answer:

A Technical Reference(s):

UFSAR Figure 7.3-20 References to be provided to applicants during examination:

None Learning Objective:

2LP-SQS-1. 1, ELO 5 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFR Part 55 Content: 55.41 X

.55.43 Comments:

NUREG-1021, Revision 8

Question # 90 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

2 2

Group#

3 3

K/A #

076 A4.01 076 A4.01 Importance Rating 2.9 2.9 Given the following:

"* The Unit is operating at 100% power with all systems in their at-power, NSA configurations.

"* ACB-2A10 is inadvertently opened and the 2-1 EDG starts.

"* All required loads start except for [2SWS*P21A] Service Water Pump which has a bright white indication.

Which of the following actions, if any, is the minimum required to place [2SWE*P21A]

Standby Service Water Pump in service?

A. No actions are required, [2SWE*P21A] will auto start on low SWS header pressure once the 2-1 EDG sequencer completes its sequence.

B.

Place the control switch for [2SWE*P21 A] to START.

C. Place the control switch for [2SWE*P21 A] to STOP, then to START.

D. Open [2SWE*MOV1 16A] Standby Service Water Pump Discharge Valve, place the control switch for [2SWE*P21A] to STOP, then to START.

Answer:

C Technical Reference(s):

20M Figure 30-14 References to be provided to applicants during examination: None Learning Objective:

08-02-750, ELO 7.a Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFR Part 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 91 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level Tier #

Group #

K/A #

Importance Rating Which of the following describes the Operations Expectation with regard to reactivity control during Mode I operations?

A.

All operator initiated reactivity manipulations are to be announced to the control room crew and acknowledged by an SRO.

B.

SRO acknowledgment need not be received for normal reactivity manipulations but must be received to initiate a Rx Trip.

C. SRO acknowledgment for reactivity manipulations is only required for turbine load adjustments; normal rod and boron concentration adjustments may be made without SRO acknowledgment.

D. SRO acknowledgment for reactivity manipulations is only required for rod and boron concentration adjustments; turbine load adjustments may be made without SRO acknowledgment.

Answer:

A Tecimical Reference(s):

Operations Expectations Handbook, pg. 18 References to be provided to applicants during examination:

None Learning Objective:

Question Source:

Question History:

Question Cognitive Level 10 CFR Part 55 Content:

2LP-SQS-48.1, ELO 39 Bank #

Modified Bank #

New X

Previous NRC Exam Previous Quiz / Test Memory or Fundamental Knowledge Comprehension or Analysis 55.41 X

55.43 Comnnents:

NUREG-1021, Revision 8 RO 2.1.2 3.0 SRO 2.1.2 4.0 X

Question # 92 ES-401 Sample Written Examination Form ES-401-6 Examination Outline Cross-reference: Level Question Worksheet RO SRO Tier #

Group #

K/A#

2.1.31 2.1.31 Importance Rating 4.2 3.9 Note: This is an open reference question.

The Unit is in Mode 5 with a stable Source Range count rate of 16 cps. Which of the following is pointing to the value that should be set for the High Flux at Shutdown Alarm?

A. 1 B.

C.

2 3

D.

4

=_102

©0

_101

-1 4

Answer:

A Technical Reference(s):

References to be provided to Learning Objective:

Question Source:

Question History:

Question Cognitive Level:

10 CFR Part 55 Content:

20M-2.4.H applicants during examination:

20M-2.4.H 2LP-SQS-2.1, ELO 4.b Bank #

LTR NRC Bank # 625J Modified Bank 4 New Memory or Fundamental Knowledge Comprehension or Analysis X

55.41 55.43 Conmnents:

NUREG-1021, Revision 8

Question # 93 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

Group #

K/A #

2.2.12 2.2.12 Importance Rating 3.0 3.4 Which of the following includes ALL of the factors that must be considered to verify Shutdown Margin when the Unit is in Mode 4?

1. RCS pressure

2. RCS temperature

3.

RCS boron concentration

4. Control rod position

5. Xenon concentration

6. Samarium concentration

7. Core age A. Only 3.

B.

Only 1, 3 thru 7.

C.

Only 2 thru 6.

D. Only 2 thru 7.

Answer:

D Technical Reference(s):

TS 4.1.1.1.1.e References to be provided to applicants during examination: None Learning Objective:

1/2LP-SQS-TS. 1, ELO 3 and GFES Question Source:

Bank #

Modified Bank #

LRT NRC# 0739J - Modified Question History:

New Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge X

Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 94 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

Group #

K/A #

2.4.4 2.4.4 Importance Rating 4.0 4.3 With the Unit at 80% power and all systems in their at-power, NSA configurations, which of the following, if any, taken alone, would require entry into an Abnormal Operating Procedure (AOP)?

1. A Shutdown Bank "A" DRPI indicates 222 steps and its Group Step Counter indicates 230 steps.

2. Heater Drain Pump [2HDH-P21A] trips.

3. [2CHS*LCV460A] Regen HX Ltdn Inlet Vlv goes closed.

A.

1 only.

B. 2 only.

C. 3 only.

D. None.

Answer:

C Technical Reference(s):

AOP-2.7.1 References to be provided to applicants during examination: None Learning Objective:

2LP-SQS-53C. 1, ELO 2 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFR Part 55 Content: 55.41 X

55.43 X

Comments:

NUREG-1021, Revision 8

Question # 95 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level Tier #

Group #

K/A #

Importance Rating Given the following:

Planned maintenance on a system requires a portion of the system to be taken out of service for one week.

A fire hose is to be installed to bypass the affected portion of the system.

This evolution is determined to be complex in nature.

This evolution is required to be performed only once.

To control this evolution, should be generated.

A. OMCN's B.

C.

D.

OMCR' s TCN's TOP's Answer:

D Technical Reference(s):

1/20M-48.2.B, Rev. 22, pg. 8 References to be provided to applicants during examination: None Learning Objective:

I/2LP-SQS-48.1, ELO 3 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X

55.43 X

Comments:

X NUREG-1021, Revision 8 RO 2.2.11 2.5 SRO 2.2.11 3.4

Question # 96 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO S RO Tier #

Group #

K/A #

2.3.1 2.3.1 Importance Rating 2.6 3.0 Which of the following is the minimum required for an Operator who is meter qualified to enter a high radiation area to complete a non-emergency clearance?

1. Have a portable radiation meter.

2. Be signed onto a High Radiation Area RWP.

3. Perform a self brief, or receive a briefing by an HP Technician for entering a high radiation area.

A.

1 only.

B.

1 and 2 only.

C. 2 and 3 only.

D. 1,2and3.

Answer:

D Technical Reference(s):

Health Physics Manual, Chapter 1 References to be provided to applicants during examination: None Learning Objective:

08-01-801, ELO 33 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge X

Comprehension or Analysis 10 CFRPart 55 Content: 55.41 X

55.43 X

Comments:

NUREG-1021, Revision 8

Question # 97 ES-401 Sample Written Examination Form ES-40 1-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

Group #

K/A 4 2.3.11 2.3.11 Importance Rating 2.7 3.2 All of the following are applicable to a radioactive gaseous waste discharge to the environment EXCEPT:

A. The RWDA-G will provide the maximum allowable discharge rate.

B. No more than two gaseous waste storage tanks may be released at one time.

C. A radiation technician must adjust Hi and Hi-Hi alarm setpoints on the applicable radiation monitor.

D. The meteorological monitoring instrumentation required by the Unit 2 Licensing Requirements Manual must be operable.

Answer:

B Technical Reference(s):

1/20M-19.4A.B References to be provided to applicants during examination: None Learning Objective:

08-02-735, ELO 2 & 7 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge X

Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 Comments:

NUREG-1021, Revision 8

Question # 98 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

Group #

K/A #

2.4.10 2.4.10 Importance Rating 3.0 3.1 The operators are searching for a ground in the Annunciator System in accordance with 20M-5B.4.AAA - Annunciator Trouble. The procedure directs the operation of the sectionalization switches to isolate different field contacts, in an attempt to locate the ground. If there is an annunciator that is in alarm and has been acknowledged by the operator, and the sectionalization switch for that alarm is placed in the "Dedicated" position, that annunciator will _(1)_ and when the switch is returned to the "Normal" position, it will _(2).

-(1)-

_(2)_

A. clear re-alarm B.

clear remain clear C. remain in alarm clear D. remain in alarm re-alarm Answer:

A Technical Reference(s):

20M-5B.4.AAA References to be provided to applicants during examination:' None Learning Objective:

2LP-SQS-5B. 1, ELO 2 & 3 Question Source:

Bank #

Modified Bank #

Question History:

New X

Previous NRC Exam Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge X

Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X

55.43 X

Comments:

NUIREG-1021, Revision 8

Question # 99 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

Group #

K/A #

2.4.18 2.4.18 Importance Rating 2.7 3.6 Given the following:

"* The reactor has failed to trip automatically when required and cannot be manually tripped.

"* The main turbine is tripped.

"* All AFW pumps are running.

"* Emergency boration is in progress.

"* PRZR pressure is 2335 psig.

"* The PRZR PORV's do not automatically open.

"* The operators manually open one PRZR PORV and reduce RCS pressure to 2135.

Which of the following is the reason for reducing RCS pressure at this point in the transient?

A. To prevent the rapid RCS overpressurization transient expected with most ATWS events.

B.

To minimize primary-to-secondary leakage until further recovery actions can be taken, in the case of the most limiting ATWS event, a SGTR.

C.

To allow enough borated flow into the RCS to ensure the addition of negative reactivity to the core.

D. To add negative reactivity from the RCS pressure coefficient of reactivity as the RCS is depressurized.

Answer:

C Technical Reference(s):

20M-53B.4.FR-S. I Issue 4, Rev. 5, pg. 67 References to be provided to applicants during examination:

None Learning Objective:

2LP-SQS-53.3, ELO 6 Question Source:

Bank #

LRT NRC # 429Q Modified Bank #

Question History:

New Previous NRC Exam Previous Quiz / Test Question Cognitive Level:

Memory or Fundamental Knowledge Comprehension or Analysis X

10 CFR Part 55 Content:

55.41 X

55.43 Comments:

NUREG-1021, Revision 8

Question # 100 ES-401 Sample Written Examination Form ES-401-6 Question Worksheet Examination Outline Cross-reference:

Level RO SRO Tier #

I I

Group#

1 1

K/A #

067 AK3.02 067 AK3.02 Importance Rating 2.5 3.3 Given the following:

"* A fire has started in the [CB-2] Cable Spreading Room.

"* The fire is now out of control and the Fire Brigade has not been able to enter the area.

"* Smoke is entering the control room and the NSS has implemented 20M-56C Alternate Safe Shutdown From Outside Control Room.

Which of the methods is to be used bring the unit to Cold Shutdown?

A. Transfer all Train B (Purple) equipment to the Emergency Shutdown Panel and conduct a natural circulation cooldown.

B. Transfer all Train A (Orange) equipment to the Alternate Shutdown Panel and conduct a natural circulation cooldown.

C. Conduct a natural circulation cooldown using only the Train B (Purple) equipment from the control room.

D. Conduct a forced circulation cooldown using only Train A (Orange) equipment from the Alternate Shutdown Panel.

Answer:

B Technical Reference(s):

20M-53B.4. 20M-56C.4.B, Issue 1, Rev. 14 References to be provided to applicants during examination: None Learning Objective:

2LP-SQS-56C. 1 Question Source:

Bank #

Modified Bank #

Question History:

New Previous NRC Exam X

Previous Quiz / Test Question Cognitive Level: Memory or Fundamental Knowledge X

Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X

55.43 Comments:

NUREG-1021, Revision 8

ML011920060

Text

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