Text

Forwards Exam Matl & Associated QA Checklist for Written Exam to Support Plant RO Retake Exam Scheduled for 990423. Exam Matls Requested to Be Withheld from Public Disclosure Until After Exam Completion
	ML20207C363
Person / Time
Site:	Callaway
Issue date:	03/12/1999
From:	Neil R; UNION ELECTRIC CO.
To:	Bundy H; NRC
Shared Package
ML20207C344	List: ML20207C339; ML20207C346; ML20207C363;
References
	NUDOCS 9906030008
	Download: ML20207C363 (218)
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Union Electric Po Box G20 Caiwayttant '

. Fulton, M0 05251 March 12,1999 Mr. Howard Bundy, Lead Examiner U.S. Nuclear Regulatory Commission Harris Tower 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 Howard:

SUBJECT:

RO RETAKE EXAMINATION MATERIAL Please find enclosed the Examination Material and associated Quality Assurance Checklist for the Written Examination to support the Callaway Plant RO Retake Exam scheduled for April 23,1999. !

This material was prepared based on guidelines in NUREG-1021, Interim Rev. 8, Operator Licensing Examination Standards for Power Reactors and NUREG-1122, Rev. 2, Knowledge and Abilities Catalog for Nuclear Power Plant Operators.

Please withhold the examination materials from public disclosure until aRer exam completion.

Should you need any additional infonnation or have any questions concerning the material, please contact Dave Lantz at (573) 676-8512 or me at (573) 676-8739.

Respectfully, 9906030008 990526 7Y PDR ADOCK 05000483 Richard J. Neil y PDR '

Shin Supervisor, Operations Training RJN/DGUdkb

Attachment:

Written Exam QA Checklist: Form ES-401-6

Enclosures:

Book 1 of 3: Exam Cross Reference RO Written Exam RO Written Exam Key Book 2 of 3: RO Written Outline: Forms ES-401-4 and ES-401-5 Reference Material for R001 through R050 Book 3 of 3: Reference Material for ROSI through R100 h a subsidiary of Amorea Corporation

l

- ES-401 Written Examination Cover Sheet Form ES-401-7 U. S. NUCLEAR REGULATORY COMMISSION WRITTEN EXAMINATION APPLICANT INFORMATION Name: Region: IV j Date: April 23,1999 Facility / Unit: CallawayPlant/ Unit 1 License Level: RO Reactor Type: Westinghouse Start Time: Finish Time: l l Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top j of the answer sheets. The passing grade requires a final grade of at least 80.00 percent.

I Examination papers will be collected four hours after the examination starts.

1 l

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

l Applicant's Signature RESULTS 1

l Examination Value 100 Points l

Applicant's Score Points Applicant's Grade Percent NUREG-1021 Interim Rev. 8, January 1997 i

CALLAWAy PLANT -

EXAMINATION COVER SHEET TRAINING DEPARTMENT COURSE TITLE: RO INITIAL LICENSE RETAKE EXAMINATION DATE: 4/23/1999 NAME (Print): SCORING:

SIGNATURE: Points Possible: 100 Points Missed:

Grade:

DIRE CTIONS. BLACK OUT CORRLCT ANSWERS 1.lAllBl E lDl 26. l A l l B l E l D l 51. l A l l B l l C l E 76. l A l l B l E l D l

2. l A l l B l E y 27. l A l l B l l C l E 52. l A l E l C l l D l 77. l A l E l C l l D l

3. l A l E l C l l D l 28. l A l l B l l C l E $3. l A l l B l l C l E 78. l A l l B l E l D l

4. l A l l B l l C l E 29. IAl l B l E l D l 54. l A l l B l l C l E 79. E l B l l C l l D l 5.lAllBl E lDl 30. l A l E l C l l D l 55. E l B l l C l l D l 80. l A l E l C l l D l

6. l A l l B l l C l E 31. E l B l l C l l D l 56. l A l l B l l C l E 81. I l l B l E l D l

7. E l B l l C l l D l 32. E l B l IM l D l 57. l A l l B l E l D l 82. E l B l l C l l D l 8.lAl E lCllDl 33. l A l l B l E l D l 58. l A l l B l l C l E 83. l A l E l C l l D l

9. l A l l B l l C l E 34. l A l E l C l l D l 59. l A l W l C l E 84. l A l l B l E l D l

10. l A l l B l E l D l 35. E l B l [Cl l D l 60. l A l E l C l l D l 85. l A l E l C l l D l

11. l A l l B l E l D l 36. E l B l l C l l D l 61. l A l l B l l C l E 86. l A l l B l E l D l

12. l A l l B l ICl E 37. l A l l B l E l D l 62. E l B l l C l l D l 87. l A l E l C l l D l

13. l A l E l C l l D l 38. l A l l B l l l D l 63. l A l l B l l l D l 88. l A l l B l l C l E

14. I A l l B i l C I E 39. E l B l l C l l D l 64. E l B l l C l l D l 89. l A l E l C l l D l

15. l A l l B l l C l E 40. E l B l l C l l D l 65. l A l l B l E l D l 90. l A l E l C l l D l

16. l A l E l C l l D l 41. l A l l B l E l D l 66. l A l l B l E l D l 91. E l B l l C l l D l

17. [A] l B l l C l E 42. l A l l B l E l D l 67. E l B l l C l l D l 92. E l B l l C l l D l

18. E l B l l C l l D l 43. E l B l l C l l D l 68. l A l l B l l C l E 93. l A l E l C l l D l

19. l A l E l C l l D l 44. E l B l l C l l D l 69. l A j l B l l C l E 94. E l B l l C l l D l 20.

lAllBl E lDl 45. l A l E l C l l D l 70. E l B l l C l l D l 95. l A l E l C l l D l

21. l A l E l C l l D l 46. l A l l B l l C l E 71. E l B l l C l l D l 96. E l B l l C l l D l

22. E l B l l C l l D l 47. l A l l B l l C l E 72. l A l E l C l l D l 97. l A l l B l l C l E

23. l A l l B l E l D l 48. l A l E l C l @j 73. l A l l B l E l D l 98. l A l E l C l l D l 24, l A l E l C l l D l 49. l A l l B l l C l E 74. l A l l B l l C l E 99. E l B l l C l l D l

25. l A l l B l E l D l 50. l A l l B l E l D l 75. l A l l B l l C l E 100. l A l l B l E l D l

[:

l QUESTION # 001 1

The following plant conditions exist:

'. A power reduction from 80% to 60% has just been completed.

. Control Bank 'D' rods are at 83 steps with the exception of rod M-4.

I Which ONE of the following M-4 rod positions meets the MINIMUM difference in position that l would require the rods to be considered misaligned per Technical Specifications?

A. 90 steps B. 91 steps C. 96 steps l- D. 97 steps ANSWER:

1 C. 96 steps K/A #: 005AA1.05 RO IMPORTANCE: 3.4 KA DESCRIPTION: Misaligned Control Rod OBJECTIVE #: A

REFERENCES:

.T61.003B.6 LP B-55, Page 1 l OTO-SF-00004, Page 1 Technical Specification 3.1.3.1 AUTHOR: DGL SOURCE: New - H DISTRACTER EXPLANATION:

l Technical Specification 3.1.3.1 requires rods to be within i12 steps of their group to be operable, therefore the minimum difference to be inoperable would be 13 steps (83 steps + 13 steps = 96 steps).

RO Outline #R001 1

1 1

l l-

QUESTION # 002 -

The following plant conditions exist:

. Reactor TRIPPED from 100% power

.- Pressurizer levelis 0%

. Containment pressure is 16 psig

. . Teoid is 420 F for all four loops Which ONE of the following events is in progress?

A. RCS leak on Loop 1 Cold Leg.

B. S/G Tube leak in the 'C' S/G.

C. Main Steam Line leak from the 'B' S/G 2 feet downstream of the S/G.

D. Main Feedwater Line leak between the 'D' MFRV and the 'D' MFIV.

ANSWER:

C. Main Steam Line leak from the 'B' S/G 2 feet downstream of the S/G.

KIA #: 040AK1.06 RO IMPORTANCE: 3.7 KA DESCRIPTION: Identification of Steam Line Break OBJECTIVE #: H (LP SD-4)

REFERENCES:

T61.003D.6 LP SD-4, Page 6 T61.003D.6 LP 15, Pages 6 & 7 AUTHOR: DGL SOURCE: New - H DISTRACTER EXPLANATION:

A. _ Would NOT cause cold leg temperature to decrease to 420 F.

B. & D. Would NOT cause cold leg temperature decrease or containment pressure increase.

RO Out'line #R007 L _

. i f

i QUESTION # 003 Which ONE of the following best describes the organization of the Fire Brigade?

l

- A'. Fire Brigade personnel are under the control of the Safety Supervisor.

B. The Fire Brigade Leaderis one of the On-Shift Operating Supervisors.

C. The Fire Brigade team consists of at least six members from the operating shift who can respond to an emergency.

D. The Shift Supervisor assumes the role of Fire Brigade Leader if the Leader fails to report to the fire or is incapacitated.

ANSWER:

B. The Fire Brigade Leader is one of the On-Shift Operating Supervisors.

i K/A #: 067G2.4.26 RO IMPORTANCE: 2.9 i KA DESCRIPTION: Fire Brigade Organization !

OBJECTIVE #: E.1

{

REFERENCES:

T61.003A.6 LP A-30, Page 3 APA-ZZ-00743 AUTHOR: DGL SOURCE: Bank (Modified)- L DISTRACTER EXPLANATION:

A. They are under control of the Fire Brigade Leader.

C. Only five members are required.

D. The Assistant Fire Brigade Leader would assume command.

RO Outline #R013

QUESTION # 004

,Which ONE of the following conditions will result in an automatic reactor trip while operating at 100% power?

A. 'B' S/G NR Level (%): 22(LT-527), 23(LT-528), 23(LT-529), 24(LT-552)

B. Power Range Nls (%): 107(N41 ), 108(N42), 108(N43), 109(N44)

C. Pressurizer Pressure (psig): 2375(PT-455), 2380(PT-456), 2385(PT-457), 2380(PT-458)

D. RCP Bus Frequency (Hz): 56.9( 'A'), 57.1('B'), 57.0 ('C'), 57.4('D')

ANSWER:

D. RCP Bus Frequency (Hz): 56.9( 'A'), 57.1('B'), 57.0 ('C'), 57.4('D')

K/A #: 007EK2.03 RO IMPORTANCE: 3.5 KA DESCRIPTION: Reactor Trip Signals OBJECTIVE #: D

REFERENCES:

T61.0110.6 LP 27, Pages 24 & 25 l

E-0, Attachment 1 AUTHOR: DGL SOURCE: New - L DISTRACTER EXPLANATION:

A. Requires 2 of 4 less than 14.8 (Normal) or 20.2 (EAM).

B. Requires 2 of 4 greater than 109.

C. Requires 2 of 4 greater than 2385.

RO Outline #R019

m QUESTION # 005 The following plant conditions exist:

. Reactor Power is 90%.

. . ALL controls are in AUTOMATIC.

VCT Level Transmitter BGLT0149 fails HIGH causing a letdown diversion.

. At the time of the VCT Level Channel failure, actual VCT level was 50%. l 1

Which ONE of the following describes the correct plant response? (Assume NO Operator Actions are taken.) 3 VCT level decreases:

A. until Auto makeup starts and maintains VCT level.

B. until charging pumps lose suction and start to cavitate.

C. with NO Auto makeup capability and charging suctions swap to the RWST.

D. faster than~ Auto makeup input and charging suctions swap to the RWST.

B ANSWER:

C, with NO Auto makeup capability and charging suctions swap to the RWST.

K/A #: 022AA1.08 RO IMPORTANCE: 3.4 KA DESCRIPTION: VCT Level Channel Failure OBJECTIVE #: F

REFERENCES:

.T61.0110.6 LP 11, Page 22 ),

AUTHOR: .DGL SOURCE: New - H DISTRACTER EXPLANATION-A. Auto makeup is fed from channel BGLT0149 (failed high). I B. . Suetions will swap to RWST at 5% level. l D. Auto makeup is fed from channel BGLT0149 (failed high).

. RO Outline #R025 l

YW l

QUESTION # 006 FR-H.1, Response to Loss of Secondary Heat Sink, defines a HOT DRY SG as a SG with its RCS wide range Hot Leg temperature GREATER THAN (1) AND its wide range SG isvel LESS THAN (2) for NORMAL containment conditions.

(1) (2)

A. 500 F 43%

B. 500 F 24 %

C. 550 F 43%

D. 550 F 24 %

ANSWER:

D. 550 F 24 %

K!A #: W/E05G2.4.17 RO IMPORTANCE: 3.1 KA DESCRIPTION: Hot Dry S/G Criteria OBJECTIVE #: S

REFERENCES:

T61.003D.6 LP 26, Page 27 AUTHOR: DGL SOURCE: New - L DISTRACTER EXPLANATION:

A. & B. Must be > 550 F.

C. 43% is for Adverse Containment.

RO Outline #R031

r7 l

QUESTION # 007-The following plant conditions exist:

.- Reactor / Turbine Power is at 75% steady state.

.- Rod Controlis selected to MANUAL.

. 'Auctioneered High Tave is 579.6 F.

Which ONE of ihn following will be the initial rod speed if rod control is placed in AUTOMATIC 7 A. 8 steps / minute B.> 32 steps / minute C. 48 steps / minute D. 72 steps / minute -

ANSWER:

A. 8 steps / minute KIA #: 001K4.14 RO IMPORTANCE: 2.6 KA DESCRIPTION: Determine Rod Speed OBJECTIVE #: - C

REFERENCES:

T61.0110.6 LP 26, Pages 16-19 CMP 98-1038A, Reduced Tave Modification AUTHOR: DGL SOURCE: - New - H DISTRACTER EXPLANATION:

75% power equates to a Tref of 577 6 F. Tave is 2'F higher than program Rod speed is 8 steps / minute with a temperature error between 1.5'F - 3'F.

RO Outline #R037

QUESTION # 008 A plant heatup is in progress.

The following plant conditions exist at 0700:

. RCS pressure is 1780 psig.

. RCS temperature is 482 F.

. S/G pressures are 565 psig.

The following plant conditions exist at 0730:

. RCS pressure is 1880 psig.

. RCS temperature is 487 F.

. S/G pressures are 588 psig.

Which ONE of the following is the FIRST plant response if the current trends continue?

(Assume NO operator actions are taken.)

A. Pzr PORVs OPEN.

~ B. MSIVs CLOSE.

C. Pzr Sprays CLOSE.

D. S/G PORVs OPEN.

ANSWER:

B. MSIVs CLOSE.

~

K/A #: 013A1.01 RO IMPORTANCE: 4.0 KA DESCRIPTION: Monitor Trends for MSLIS OBJECTIVE #: E&G

REFERENCES:

T61.0110.6 LP 27, Pages 38 & 44 AUTHOR: DGL SOURCE: New - H DISTRACTER EXPLANATION:

A. Pzr PORVs won't open until 2335 psig. At 1973 psig, a SLIS will occur.

C. As pressure is increased, Pzr Sprays won't close.

D. S/G PORVs won't open until 1125 psig. SLIS will occur while S/G pressures are still < 615 psig.

RO Outline #R043

QUESTION'# 009 The following plant conditions exist:

. Reactor Power is 100%

.- NE02, 'B' Emergency DG, is out of service for maintenance.

. l All containment cooler fans are running in selected speed (FAST).

Which ONE of the following is the correct status of Containment Cooler Fans one minute after the plant undergoes a reactor trip,' safety :njection, and a trip of the NB02 normal feed breaker?

A. - All four fans are running in FAST speed B. All four fans are running in SLOW speed.

C. 'A' and 'C' fans are running in FAST speed, 'B' and 'D' fans are OFF.

D. 'A' and 'C' fans are running in SLOW speed, 'B' and 'D' fans are OFF.

ANSWER:

' D. 'A' and 'C' fans are running in SLOW speed, 'B' and 'D' fans are OFF. 4 KIA #: 022A3.01 RO IMPORTANCE: 4.1

. KA DESCRIPTION: LOCA Sequencer Operation OBJECTIVE #: F

REFERENCES:

T61.0110.6 LP 51, Page 7 AUTHOR: DGL SOURCE: New - H DISTRACTER EXPLANATION:

A. & B. 'B' and 'D' fans have no power.

C. 'A' and 'C' fans will be running in slow speed.

RO Outline #R049 4-

QUESTION # 010 During Mode 1 at 100% power with all systems in their normal alignment, which ONE of the following is a source of water to the Containment Normal Sumps?

A. Leakoff from the Reactor Vessel Flange.

B. Leakoff from the #2 seals on RCPs.

C. Leakoff from the #3 seals on RCPs.

D. Leakoff from Letdown Hx Valve Compartment.

ANSWER:

C. Leakoff from the #3 seals on RCPs.

KIA #: 068K1.07 RO IMPORTANCE: 2.7 KA DESCRIPTION: CTMT Normal Sump Inputs O2JECTIVE #: G

REFERENCES:

T61.0110.6 LP 9, Pages 20 & 26 AUTHOR: DGL SOURCE: New - L DISTRACTER EXPLANATION:

A. Goes to the RCDT.

B. Goes to the RCDT.

D. Goes to Aux Bldg (CRW) sumps.

RO Outline #R055

c:

QUESTION # 011 To meet the 10CFR50.46 design criteria, the ECCS system is designed such that under Cecident conditions it will maintain:

A. total hydrogen production from zirconium-water reaction below maximum value of 5%.

B. maximum fuel temperature at the inside surface of the cladding not exceeding 2000 F.

C. fuel clad oxidation less than 17% of total clad thickness anywhere within the core. l D. the core at least 5% dK/K shutdown to prevent an inadvertent return to criticality.

ANSWER:

C. fuel ciad oxidation less than 17% of total clad thickness anywhere within the core.

K/A #: 006K3.02 RO IMPORTANCE: 4.3 KA DESCRIPTION: Design Criteria To Protect Fuel OBJECTIVE #: B i

REFERENCES:

T61.0110.6 LP 56, Page 4 AUTHOR: DGL SOURCE: New - H DISTRACTER EXPLANATION:

A. Hydrogen limit is 1%.

B. Clad temperature limit is 2200 F.

D. Design criteria does not address core reactivity.

l RO Outline #R061 i

QUESTION # 012 The fo'jowing plant conditions exist:

. Mode 3, 557*F,2235 psig.-

. NB01 Normal Feeder Breaker is tripped.

. NB02 Normal Feeder Breaker is closed.

. NB01 Bus Voltage'is 0 volts.

. NB02 Bus Voltage is 4160 volts.

. NB01 Bus Lockout Annunciator 18A is lit.

Which ONE of the following sets of equipment are de-energized?

A. 'A' ESW Pump, NK22 Charger, and XNN05 Transformer B .- 'A' MDAFW Pump, 'A' CCW Pump, and XNN06 Transformer C. 'A' CCW Pump, NK26 Charger, and 'A' Class 1E NC D. 'C' CCW Pump, NK23 Charger, and 'A' ESW Pump ANSWER:

D. 'C' CCW Purnp, NK23 Charger, and 'A' ESW Pump K/A #: 062K2.01 RO IMPORTANCE: 3.3 KA DESCRIPTION: Major System Loads OBJECTIVE #: - A&I

REFERENCES:

T61.0110.6 LP 6, Pages 4 & 8 AUTHOR: DGL SOURCE: New - H DISTRACTER EXPLANATION:

A. NK22 is still energized.

B. XNN06 is still energized.

C. NK26 is still energized.

RO Outline #R073

I I

f QUESTION # 013 A fire alarm is received on KC008 panel. When the operator acknowledges the alarm on KC008, the Electric Fire Pump is discovered to be running.

Which ONE of the following could have caused the Electric Fire Pump to start?

1 A. 'A' Diesel Fire Pump failed to start.

B. Fire System pressure decreased to 5; 130 psig.

C. 'B' Diesel Fire Pump battery charger failed.

D. Jockey Pump has excessive run time.

ANSWER:

B. Fire System pressure decreased to s; 130 psig.

KIA #: 086A3.01 RO IMPORTANCE: 2.9 KA DESCRIPTION: Fire Pump Auto Starts OBJECTIVE #: C

REFERENCES:

T61.0110.6 LP 35, Pages 37 & 38 AUTHOR: DGL SOURCE: New - L DISTRACTER EXPLANATION:

A. Causes 'B' Diesel Fire Pump to start.

C. Causes 'B' Diesel Fire Pump to start.

D. Causes alarm only, no fire pump starts.

RO Outline #R079

QUESTION # 014

.e I I

- The following plant conditions exist:

. Mode 3 with shutdown banks withdrawn.

. RCS Temperature - 557'F.

.. RCS Pressure-2235 psig.

. Steam Dumps in Steam Pressure Mode.

. S/G Levels being maintained by the Startup Feed Pump.

Steam Header Pressure Transmitter, ABPT0507, fails to 1400 psig over a 5 minute period.

Which ONE of the following describes the response for this failure?

A. Startup feed pump flow goes to zero due to SLIS.

B. An SIS will occur when steam line pressures reach 615 psig.

C. A reactor trip will occur due to low pressurizer pressure.

D. Steam dump val,ves will maintain RCS Tave at 550 F.

ANSWER:

D. Steam dump valves will maintain RCS Tave at 550'F.

K/A #: 041K4.09 RO IMPORTANCE: 3.0 KA DESCRIPTION: Steam Header Pressure Channel Failure OBJECTIVE #: J&K

REFERENCES:

T61.0110.6 LP 20, Pages 35-37 AUTHOR: DGL SOURCE: Bank (Modified)- H DISTRACTER EXPLANATION:

Stra.m dumps will gradually open and cooldown the RCS to 550*F. At 550 F (P-12 setpoint) the dumps will close. Steam dumps will then cycle as necessary to maintain RCS Tave at 550 F.

RO Outline #R085

QUESTION # 015 -

The following plant conditions exist:

. - Mode 1 at 100% power.

. QPTR results:

N41 N42 N43 N44-Upper Power Tilt Ratio 1.01 1.01 0.97 1.04 Lower Power Tilt Ratio 1.01 '1.01 0.98 1.03 Which ONE of the following could have caused these QPTR results? (Refer to Curve Book Figure 8-7 on the following page.)

A. RCS boron concentration was decreased by 20 ppm.

B. RCS temperature was decreased 3 F by boration.

C. Control Bank 'D' rod H-8 has dropped to zero steps.

D. Control Bank 'D' rod D-4 is misaligned from its group.

ANSWER:

D. Control Bank 'D' rod D-4 is misaligned from its group.

KIA #: 2.2.12 RO IMPORTANCE: 3.0 KA DESCRIPTION: Quadrant Power Tilt Ratio OBJECTIVE #: A

REFERENCES:

T61.003B.6 LP B-55, Page 1 j OTO-SF-00004, Page 1 i AUTHOR: DGL SOURCE: New - H ;

i DISTRACTER EXPLANATION:

A. & B. Would affect Axial Power Distribution, NOT Radial Power Distribution. i C. Appears as a uniform poison in center of the core, would NOT cause a Radial Power Tilt.

RO Outline #R091 ]

(-

l QUESTION # 015 (continu:d) FIGURE B-7 ev. 000 1

RCS LOOP ORIENTATION WITH CONTROL ROD AND

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Superinpptient, Engineering I 3 -30 #

Date RO Outline #R091

QUESTION # 016 Which ONE of the following definitions best defines the word TRY, as it is used in the emergency operating procedures?

j i

1 A. Make a one time effort to perform an evolution, then continue procedure.

B. To make a continued effort when success may not be immediately obtainable.

C. Do not continue procedure until the effort has been successful.

D. Effort only needs to be performed at the discretion of the Shift Supervisor.

ANSWER:

B. To make a continued effort when success may not be immediately obtainable.

K/A #: 2.4.17 RO IMPORTANCE: 3.1 KA DESCRIPTION: EOP Definitions OBJECTIVE #: A.1.L.4

REFERENCES:

T61.003D.6 LP 1, Page 37' AUTHOR: DGL SOURCE: Bank (Modified) - L DISTRACTER EXPLANATION:

B. Only correct definition per Emergency Response Guidelines.

RO Outline #R097

QUESTION # 017 The plant is operating at 40% power and it is necessary to secure the 'A' Reactor Coolant Pump (RCP) due to.a pump seal failure. After the RCP is tripped, the 'A' Loop AT (1) and tho other Loop AT's (2) (Assume unit load is held constant.)

(1) (2)

A. increases decrease B. increases increase C. decreases decrease D. decreases increase ANSWER:

1 D. decreases increase K/A #: 015/017AK1.04 RO IMPORTANCE: 2.9 KA DESCRIPTION: Unbalanced RCS Flows (IPE/PRA)

OBJECTIVE #: A

REFERENCES:

T61.003B.6 LP SB4, Page 5 AUTHOR: DGL SOURCE: Bank (Modified)- H DISTRACTER EXPLANATION:

When stopping an RCP at power, the steam flow in the associated loop will decrease and the steam flows in the remaining 3 loops will increase equally. Loop AT's will follow the changes in steam flows.

RO Outline #R002

5 QUESTION # 018

_ Given the following conditions:

. . RCS Wide Range Pressure is 730 psig

. ; RCS WR Hot Leg Temperatures are 310 F

. RCS WR Cold Leg Temperatures are 280 F

.- Core Exit Thermocouple Temperatures are 305 F Using Curve Book Figure 14.3 on the following page, determine the expected position for each Pressurizer PORV. - (Assume both Pressurizer PORVs are ARMED for Cold Overpressure Protection.)

I A. ' BBPCV0455A Open; BBPCV0456A Closed . l

. B. BBPCV0455A Open; BBPCV0456A Open C. BBPCV0455A Closed; BBPCV0456A Closed D. BBPCV0455A Closed; BBPCV0456A Open AN' SWER: -

A BBPCV0455A Open; BBPCV0456A. Closed, K/A #: E09EK2.1 RO IMPORTANCE: 3.4 KA DESCRIPTION: . Cold Overpressure Protection System OBJECTIVE #: G.

REFERENCES:

-T61.0110.6 LP 30, Pages 10 Curve Book Figure 14.3, Rev.1 AUTHOR: :DGL SOURCE: New - H DISTRACTER EXPLANATION:

B. For T of 280 F, BBPCV0456A won't open until 750 psig.

C. For Tiof 280 F, BBPCV0455A will open at 700 psig.

D. For T. of 280'F. BBPCV0455A will open at 700 psig and BBPCV0456A won't open until 750 psig.

ltO i Outline #R008 i 1 I

- QUESTION.# 018 (continued)

FIGURE 14.3, Rev. i _

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, 76 en i 501 , ', j .

g

' * '" 525 ' ' I '

io 2400 l no 505 520 535 550 l l l l p l 245 2M 600 700 6M 750 l lf l I = = m i I / I g I

'2 23 " 235o

, I I /I i I I I I I I l I i i i l' 15 E '9UU l l I I I i l l l I/

E I I I I I I I f h l I I I Il

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! I i l i i I FI I i i 1 1 ! I i_.14 A :a- # 4 i : I ; ! ! ! I I I I I I I I I I I I I i I I I 400 i 100 200 300 400 500 WR COLD LEG TEMPERATURE (F)

W -PCV-4SSA SETPT

===4 -PCV-456A SETPT

~

RO Outline #R008 kb/96 W J M e g L; _. .

- _ ~ _ .

. - SYSTEMS ENG

g

. QUESTION # 019 Which ONE of the following sets of indications are available on the Auxiliary Shutdown Panel?

A. Emergency Borate Flow, S/G Pressure, Pzr Level.

3. Pzr Pressure, S/G Pressure, RCS Cold Leg Temp.

C. CST Leve!, S/G Level, Containment Pressure. I D. RCS Pressure, RCS Hot Leg Temp, Charging Flow.

{

l ANSWER: '

B. Pzr Pressure, S/G Pressure, RCS Cold Leg Temp.

1 K/A #: 068AA1.12 RO IMPORTANCE: 4.4 KA DESCRIPTION: Aux S/D PanelIndicators i OBJECTIVE #: B

REFERENCES:

T61.0110.6 LP 48, Page 1 AUTHOR: DGL SOURCE: New - L DISTRACTER EXPLANATION:

A. Emergency Borate Flow not available.

C. Containment Pressure not available.

D. Charging Flow not available.

RO Outline #R014 l

1

~ QUESTION # 020 The following plant conditions exist:

. Mode 1 at 100% power.

. PRT pressure is 5 psig.

Which ONE of the following describes the condition of the steam entering the PRT if a Pzr PORV opens?

A. Superheated steam at 659 F.

B. Superheated steam at 653'F.

C. Saturated steam-water mixture at 228 F.

D. Saturated steam-water mixture at 162 F.

ANSWER:

C. Saturated steam-water mixture at 228 F.

KIA #: 008AK1.01 RO IMPORTANCE: 3.2 KA DESCRIPTION: PORV Relieving To PRT OBJECTIVE #: C

REFERENCES:

T61.0070.6 LP 13, Page 33 Steam Tables AUTHOR: 'DGL SOURCE: New - H DISTRACTER EXPLANATION:

C. Only correct answer using Steam Tables and Mollier Diagram.

RO Outline #R020

I QUESTION # 021 Which ONE of the following is the preferred method of immediate Boration per FR-S.1, 4 Response Tc Nuclear Power Generation, if BGHV8104 (Emergency Borate Valve) will NOT open?-

' A. Alternate immediate Borate through BGV0177.

B. From the RWST via BNLCV0112D and BNLCV0112E.

]

C. Manual Safety injection initiation.

D. Injection from the Si Accumulators.

l ANSWER: ;

B. From the RWST via BNLCV0112D and BNLCV0112E.

K/A #: 029EK3.11 RO IMPORTANCE: 4.2 KA DESCRIPTION: Initiating immediate Boration OBJECTIVE #: U

REFERENCES:

T61.003D.6 LP 29, Page 3 FR-S.1, Attachment 1 AUTHOR: DGL SOURCE: New - L DISTRACTER EXPL.ANATION:

A. Second in order of preference.

C. & D. Third in order of preference.

RO Outline #R026 l

m I

QUESTION # 022 An earthquake has caused a Loss of All AC Power. NK12 battery discharge amps are at 200 amps.

Which ONE of the following is the MAXIMUM time that NK12 could supply NK02 bus? (Assume NK12 was fully charged at the time of the earthquake.)

A. 4.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months B. 6.0 hours0 days 0 hours 0 weeks 0 months C .- 7.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months D. 9.0 hours0 days 0 hours 0 weeks 0 months ANSWER:

A. 4.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months K/A #: 058AA1.03 RO IMPORTANCE: 3.1 KA DESCRIPTION: Monitor Battery Capacity (IPE/PRA)

OBJECTIVE #: 1

REFERENCES:

T61.0070.6 LP 17, Page 48 T61.0110.6 LP 6, Page 13

~

AUTHOR: DGL SOURCE: New - H DISTRACTER EXPLANATION:

NK12 is rated at 900 Amp Hours.

Crpacity = Rating + Discharge Rate = 900 AH + 250 A = 4.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months RO Outline #R032

_ . QUESTION # 023 The following' plant conditions exist:

. Si has occurred due to a LOCA in containment.

. NB02 normal feeder breaker opened causing a loss of power on NB02.

. NB01 has remained energized from its normal feeder breaker.

. The SI signal has been RESET.

At the SAME TIME that NB02 is energized from NE02 Emergency DG, a Containment Spray (CS) Actuation Signal was generated.

Which ONE of the following combinations states the times at which the CS pumps will start?

(Assume allinterlocks are met.)

'A' CS Pumo 'B'_CS Pumo A. Immediately Immediately B. Immediately 15 seconds C. 15 seconds 15 seconds D. 15 seconds 40 seconds ANSWER:

C.15 seconds 15 seconds

-K/A #: 026A3.01 RO IMPORTANCE: 4.3 KA DESCRIPTION: Spray Pump Auto Starts OBJECTIVE #: D&F

REFERENCES:

T61.0110.6 LP 51, Pages 7,12, & 13 AUTHOR: DGL SOURCE: Bank (Modified)- H DISTRACTER EXPLANATION:

SI signal had been reset, so CSAS started both sequencers again and both CS pumps will start at 15 s:conds.

RO Outline #R067

E.

QUESTION #024 Which ONE of the following will result from a Regulation Failure in a rod control POWER cabinet?

A. Locks the selected group of rods in that power cabinet by de-energizing both moveable gripper and lift coils.

B. Locks the selected group of rods in that power cabinet by energizing both stationary and moveable gripper coils.

C. Stops the pulsers, stopping all rod motion in manual.

. D. Stops the pulses, stopping all rod motion in automatic.

ANSWER:

B. Locks the selected group of rods in that power cabinet by energizing both stationary and moveable gripper coils.

K/A #: 001A2.14 RO IMPORTANCE: 3.7 KA DESCRIPTION: Power Cabinet Urgent Failure OBJECTIVE #: M

REFERENCES:

T61.0110.6 LP 26, Page 39 AUTHOR: DGL SOURCE: New - H DISTRACTER EXPLANATION:

A. Energizes both stationary and moveable gripper coils.

C. & D. Pulsers are only affected for Logic Cabinet Failures.

RO Outline #R038

r l

. QUESTION # 025 Which ONE of the following describes a components status when the associated ESFAS Status Panel component window is AMBER following an actuation? I l

1 A. The component is in its correct safeguards position.

B. The component did NOT receive an actuation signal.

C. The component is potentially prevented from performing its safeguards function.

D. The component is NOT in its safeguards position, but is capable of being aligned.

i ANSWER:

C. The component is potentially prevented from performing its safeguards function. !

K/A #: 013A4.01 RO IMPORTANCE: 4.5 ;

KA DESCRIPTION: Monitor Failed ESFAS Equipment l OBJECTIVE #: E.2 ;

REFERENCES:

T61.0110.6 LP 52, Pages 31 & 32 I AUTHOR: DGL SOURCE: New - L DISTRACTER EXPLANATION:

A. Window would be white.

B. Window would be dark.

D. Window would be dark.

RO Outline #R044

._ QUESTION # 026 Which ONE of the following is the minimum volume of contained water for the Condensate Storage Tank (CST) to be considered OPERABLE per Technical Specifications in Mode 27 A. 55,416 gallons B. 80,400 gallons C. 281,000 gallons D. 394,000 gallons ANSWER:

C. 281,000 gallons -

K/A #: 056G2.2.22 RO IMPORTANCE: 3.4 KA DESCRIPTION: CST Operability OBJECTIVE #: J

REFERENCES:

T61.0110.6 LP 22, Page 33 AUTHOR: DGL SOURCE: New - L DISTRACTER EXPLANATION:

A. & B. & D. Common misconceptions for other Tech Spec Tank Levels.

RO Outline #R050

QUESTION # 027 l

l Which ONE of the following signals will AUTOMATICALLY isolate the discharge flowpath from l the DMTs by closing the Liquid Radwaste Discharge Valve, HBFV08667 l -

A. Service Water Radiation Monitor HiHi

8. Low liquid radwaste discharge flow rate C. High liquid radwaste discharge flow rate D. Low dilution water flow rate l

ANSWER:

I D. Low dilution water flow rate K/A #: 068A4.04 RO IMPORTANCE: 3.8 KA DESCRIPTION: RW Discharge Auto isolation OBJECTIVE #: F

REFERENCES:

T61.0110.6 LP 16, Pages 51 & 52 AUTHOR: DGL SOURCE: Bank (Modified)- L DISTRACTER EXPLANATION:

! HBRE18 and Low Dilution water flow rate are the only two signals that will AUTOMATICALLY close the ,

i Liquid Radwaste discharge valve. '

l l RO Outline #R056 1

l l

l I

l l

QUESTION # 028 What are the parameters and values used by an operator to ensure the temperature difference between the PZR and the Spray Fluid are within the specified limit (s) in the Technical Specifications when initiating PZR Spray?

l A. For normal spray, the difference between RCS hot leg loop temperature and PZR vapor I space temperature limit is 275 F, and for aux spray, the difference between Regenerative Hx charging inlet temperature and PZR vapor space limit is 583 F. f I

B. For normal spray, the difference between RCS cold leg loop temperature and PZR vapor space temperature limit is 275 F, and for aux spray, the difference between Regenerative Hx charging outlet temperature and PZR vapor space limit is 320 F. )

C. For normal spray, the difference between RCS hot leg loop temperature and PZR vapor space temperature limit is 320 F, and for aux spray, the difference between Regenerative i Hx charging inlet temperature and PZR vapor space limit is 583 F.

D. For normal spray, the difference between RCS cold leg loop temperature and PZR vapor space temperature limit is 320 F, and for aux spray, the difference between Regenerative Hx charging outlet temperature and PZR vapor space limit is 320 F.

ANSWER:

D. For normal spray, the difference between RCS cold leg loop temperature and PZR vapor space temperature limit is 320 F, and for aux spray, the difference between Regenerative Hx charging outlet temperature and PZR vapor space limit is 320 F.

K/A #: 010A1.08 RO IMPORTANCE: 3.2 KA DESCRIPTION: Spray Nozzle AT Limits OTJECTIVE #: C.7 (LP 9), C (LP A-16)

REFERENCES:

T61.0110.6 LP 9, Pages 44 & 47 T61.003A.6 LP A-16, Page 3 OTN-BB-00005, Pages 1 & 5 AUTHOR: DGL SOURCE: New - H DISTRACTER EXPLANATlON:

A. Normal spray limit is 320 F and supplied from cold leg, aux spray supplied from Regen Hx outlet.

B. Normal spray limit is 320 F.

C. Normal spray supplied from cold legs and aux spray from Regen Hx outlet.

l RO Outline #R062

{

I

-o

[d I f

OUESTION # 029 i A containment purge is in progress when a Containment Purge isolation Signal (CPIS) is l rcceived.

1 Which ONE of the following is the cause of the CPIS?

i A. Hi Hi alarm on GT-RE-21 A, CTMT Bldg Unit Vent Monitor.

1 B. Hi Hi alarm on GT-RE-31, CTMT Atmosphere Rad Monitor.

l C. Hi HI alarm on GT-RE-33, CTMT Purge Exhaust Monitor.

l D. Hi Hi alarm on GT-RE-59, CTMT High Range Rad Monitor.

ANSWER:

C. Hi Hi alarm on GT-RE-33, CTMT Purge Exhaust Monitor.

K/A #: 029K4.03 RO IMPORTANCE: 3.2 KA DESCRIPTION: CTMT Purge Isolstion OBJECTIVE #: B.2

REFERENCES:

T61.0110.6 LP 52, Page 7 AUTHOR: DGL SOURCE: New - L DISTRACTER EXPLANATION:

GT-RE-22 and GT-RE-33 are the only two radiation monitors that provide an input to CPIS.

RO Outline #R068 l

_ QUESTION # 030 Which ONE of the following Class 1E 125 VDC Electrical System lineups can be performed to comply with Mode 1 Technical Specification LCO for D.C. Sources?

A. Load Center NG01 to Swing Charger NK25 to Bus NK04 -

B.- Load Center NG04 to Swing Charger NK26 to Bus NK02 C. Load Center NG01 to Swing Charger NK26 to Bus NK03 D. Load Center NG04 to Swing Charger NK25 to Bus NK01 ANSWER:

B. Load Center NG04 to Swing Charger NK26 to Bus NK02 K/A #: 063K1.03 RO IMPORTANCE: ' 2.9 KA DESCRIPTION: NK System Lineup -

~

OBJECTIVE #: A&G

REFERENCES:

_T61.0110.6 LP 6 Pages 4 & 25 AUTHOR:- DGL SOURCE:- - Bank (Modified)- L DISTRACTER EXPLANATION:

A. Can only feed NK01 or NK03.

C. Can only feed NK25 Swing Charger.

D. Can only be fed from NG01.

RO Outline #R074 f

L_

f

_ QUESTION # 031 1

The following plant conditions exist:

l . Reactor has been shutdown for 38 hours4.398148e-4 days 0.0106 hours 6.283069e-5 weeks 1.4459e-5 months .

l- . Mode 4 cooling down per OTG-ZZ-00006.

. RCS temperature is 340'F.

. RCS pressure is 350 psig. ,

. Pzr levelis 33%. l

. 'A' RHR Train is operating in the cooldown lineup. l

. EJFCV618, 'A' RHR Hx Bypass FCV, is in MANUAL at 3500 gpm. l

. EJHCV606, 'A' RHR Hr. FCV, controller demand is at 20%. '

. BGHCV128, RHR Letdown FCV, demand is at 100%.

. BGPCV131, CVCS Letdown Hx Outlet PCV, is in AUTOMATIC at 350 psig.

A controller failure causes EJHCV606 to go CLOSED.

Which ONE of the following is the system response to this failure? (Assume NO operator action is taken.)

A. RCS pressure will increase due to the RCS heatup.

B. EJFCV610, 'A' RHR Miniflow Valve will throttle open due to low flow.

C. Pressurizar level will increase due to decreased letdown flow.

D. BGPCV131 will throttle closed due to the decreece in RHR flow. l l ;

AN3WER:

A. RCS pressure willincrease due to the RCS heatup.

K/A #: 005K4.10 RO IMPORTANCE: 3.1 KA DESCRIPTION: RHR Flow Control l OBJECTIVE #: B.6 l

REFERENCES:

T61.0110.6 LP 7, Pages 6,15, & 16 AUTHOR: DGL SOURCE: New - M i DISTRACTER EXPL.ANATION: ,

l B. EJFCV610 will remain closed due to the 3500 gpm of RHR Hx Bypass Flow.

i C. Pzr level willincrease as the RCS heats up.

l D. More flow is forced through RHR letdown line which may cause BGPCV131 to open.

RO Outline #R080 l~

QUESTION # 032 Which ONE of the following is correct concerning the operation of the Main Turbine Generator Trip System?

A. 24 VDC supplies the Electrical Trip Solenoid. This solenoid is de-energized to trip the system.

B. ' 125 VDC supplies the Electrical Trip Solenoid. This solenoid is energized to trip the system.

C. 24 VDC supplies the Mechanical Trip Solenoid. This solenoid is energized to trip the system.

D.. 125 VDC supplies the Mechanical Trip Solenoid. This solenoid is de-energized to trip the system.

ANSWER:

A. 24 VDC supplies the Electrical Trip Solenoid. This solenoid is de-energized to trip the system.

K/A #: 045A3.04 RO IMPORTANCE: 3.4

~ KA DESCRIPTION: T/G Trip System OBJECTIVE #: L-

REFERENCES:

T61.0110.6 LP 38, Pages 51 & 52 _.

AUTHOR: DGL SOURCE: New - L DISTRACTER EXPLANATION:

B. Describes the Mechanical Trip Solenoid C. Supplied by 125 VDC.

D. Energized to trip.

RO Outline #R086 t

4 7

_,; QUESTION # 033' l ..Which ONE of the following Boric Acid Tank (BAT) conditions meets the operability )

I r quirements for the BATS in Modes 1 - 47 L i A. 17,000 gallons volume, boron concentration of 7200 ppm, and a water temperature of 64*F.

B. 17,700 gallons ' volume, boron concentration of 7300 ppm, and a water temperature of 64*F.

C. 18,000 gallons volume, boron concentration of 7500 ppm, and a water temperature of 68 F.

' D. 18,700 gallons volume, boron concentration of 7800 ppm, and a water temperature of 68*F.

ANSWER:

C. .18,000 gallons volume, boron concentration of 7500 ppm, and a water temperature of 68 F.

K/A #: 2.2.22 RO IMPORTANCE: 3.4 KA DESCRIPTION: BAT Operability Requirements OBJECTIVE #: O

REFERENCES:

T61.0110.6 LP 11, Page 67 FSAR 16.1.2.6 AUTHOR: DGL SOURCE: New - L DISTRACTER EXPLANATION:

A. Volume is low and temperature is low.

i.

B. Temperature is low.

i D. Boron concentration is high.

RO Outline #R092 1

g

QUESTION # 034 Which ONE of the following is the BASIS for isolating all feedwater to a faulted steam generator?

A. ' To reduce the probability of occurrence of a steam generator tube rupture in the faulted

- steam generator.

B. To minimize RCS cooldown and mass energy release following a steam line break.

-C.' : To prevent all feedwater flow from entering the faulted steam generator and filling the generator, causing the PORV's to lift.

D. To ensure the release to the environment remains below the 10CFR100 limits on a design

. basis event.

-ANSWER:

B. To minimize RCS cooldown and mass energy release following a steam line break.

- K/A #: 2.4.18 RO IMPORTANCE: 2.7 KA DESCRIPTION: SOP Bases OBJECTIVE #: C.

REFERENCES:

T61.003D.6 LP 15, Page 20 AUTHOR: DGL SOURCE: LBank - L-DiSTRACTER EXPLANATION:

A. Orily thermal shock from feed flow would cause SGTR.

C. Faulted S/G would continue to steam off and decrease pressure.

D.' No rad release from faulted S/G unless ruptured also.

RO Outline #R098 s

l'>

i l

l

_. QUESTION # 035 The following plant conditions exist:

. A natural circulation cooldown is in progress per ES-0.2, Natural Circulation Cooldown.

. Pressurizer pressure is being controlled using Auxiliary Spray and Pressurizer Heaters.

. As pressure is being lowered through 1300 psig, a rapid increase in Pressurizer Level is ]

noted. '

. Charging and letdown are in manual and are balanced.

l Which ONE of the following actions are required to be taken by the operators?

l A. Repressurize the RCS.

B. Isolate the SI Accumulators.

C. Establish excess letdown. I D. Increase the RCS cooldown rate. l ANSWER:

A. Repressurize the RCS.

K/A #: W/E09EK3,1 RO IMPORTANCE: 3.3 !

KA DESCRIPTION: Natural Circulation Conditions / Limitations OBJECTIVE #: E

REFERENCES:

T61.003D.6 LP SD-3, Page 15 ES-0.2, Natural Circulation Cooldown, Page 13 AUTHOR: DGL SOURCE: New - H DISTRACTER EXPLANATION:

Per ES-0.2, if abnormal RCS conditions such as large variations in pressurizer level occur, a steam void may be present in the vessel head. To collapse the void, the RCS is repressurized.

RO Outline #R003

' QUESTION # 036 -

A loss of condenser vacuum is occurring due to unknown reasons and power has been reduced from 100% to 75% over the last 4 minutes.

The following plant conditions exist:

. Auctioneered HIGH Tave is 590*F

. Reactor / Turbine power is stable at 75%

._ LP 'A' Condenser Pressure is 5.8 Hga

._ IP 'B' Condenser Pressure is 6.2 Hga -

. . HP 'C' Condenser Pressure is 6.5 Hga Which ONE of the following describes the expected operation of the condenser steam dumps ~

with these conditions?

A. Less than 12 steam dumps are available and all available dumps are FULLY OPEN.

B .' All 12 condenser steam dumps are available and all are FULLY OPEN.

' C. Less than 12 steam dumps are available and all available dumps are PARTIALLY OPEN.

D. Less than 12 steam dumps are available and all are CLOSED.

ANSWER:

A. Less than 12 steam dumps are evailable and all available dumps are FULLY OPEN.

KIA #: 051 AK3.01- RO IMPORTANCE: 2.0 KA DESCRIPTION: Loss of Steam Dump Capability OBJECTIVE #: J&K

REFERENCES:

-T61.0110.6 LP 20, Pages 32-39 CMP 98-1038A, Reduced Tave/ Tref Modification AUTHOR: DGL SOURCE: Bank (Modified)- H DISTRACTER EXPLANATION:

Tr;f at 75% is 577.6 F. Actual AT = Tave - Tref = 590 - 577.6 = 12.4 F. In the load reject mode,100%

st:am dump demand is generated with a AT of 15.7*F A AT of 12.4*F would generate a demand of 79%

(Group 1,2, and 3 dumps fully open and Group 4 modulating open). Because the IP and HP Condensers fra above the C-9 setpoint (6 Hga), only the 7 dumps for the LP Condenser are available. Therefore, 7 dumps are available and they are fully open.

RO Outline #R009

.. QUESTION # 037 When inadequate core cooling exists, which ONE of the following sets of actions state the.

proper sequence of the major action categories to be performed in accordance with FR-C.1, Response To inadequate Core Cooling, for removing decay heat from the core?

A. Rapid secondary depressurization, reinitiation of safety injection, RCP restart.

B. Rapid secondary depressurization, RCP restart, reinitiation of safety injection.

C. Reinitiation of safety injection, rapid secondary depressurization, RCP restart.

D. Reinitiation of safety injection, RCP restart, rapid secondary depressurization.

1 ANSWER:

C. Reinitiation of safety injection, rapid secondary depressurization, RCP restart {

)

KIA #: 074EK1.03 RO IMPORTANCE: 4.5 .

KA DESCRIPTION: Decay Heat Removal Methods OBJECTIVE #: A

REFERENCES:

T61.003D.6 LP 25, Page 7 AUTHOR: DGL SOURCE: New - L ;

DISTRACTER EXPLANATION: l A. & B. Reinitiation of safety injection is first in sequence. I I

D. RCP restart is last in sequence.

RO Outline #R015 j 1

l i

p

\

QUESTION # 038 j

An RCS leak has occurred and the CRS has instructed you to determine the size of the leak.

(Assume Pzr Volume is 60 gallons per %.) Given the following information: 1 Time = 0 Time = 1 minute

. Reactor Power (%) 100 100

. RCS Tave (*F) 584.4 584.4

. Charging Flow (gpm) 100 100

. Letdown Flow (gpm) 75 75

. - Pzr Level (%)' 57 56.63

. Total Seal Injection Flow (gpm) 32 32

. Total Seal Leakoff Flow (gpm) 12 12 Which ONE of the following is the approximate RCS Leak Rate?

A.- 25 gpm B. 30 gpm C. 35 gpm D. 40 gpm.

ANSWER:

C. 35 gpm KIA #: 009EK3.06 RO IMPORTAIJCE: 3.9 KA DESCRIPTION: RCS Inventory Balance (IPE/PRA)

OBJECTIVE #: D

REFERENCES:

T61.003B.6 LP SB-32, Page 6 AUTHOR: DGL i SOURCE: New - H i DISTRACTER EXPLANATION:

~

Leak Rate = Charging Flow-(Letdown Flow + Seal Leakoff) + (A Pzr Level x 60 gal /%)

= 100 -(75 + 12) + (0.37 x 60) !

= 100- 87 + 22 = 35 gpm

' RO Outline #R021

___j

n l

QUESTION # 039 The following plant conditions exist:

. Plant startup is in progress.

. Intermediate Range Nls indicate 2.5 E-5 amps (SEN135) and 2.8 E-5 amps (SEN136).

. Source Range Permissive P-6 light is LIT.

. Source Range Channel SENI31 high voltage power supply fails to HALF its normal voltage.

.Which ONE of the following indication (s) would be available to alert operators to this failure?

A. None, until power is lowered below the P-6 setpoint, and then the Source Range SEN131 indication will indicate lower than expected.

B. None, until power is lowered below the P 6 setpoint, and then the Source Range SENI31 indication will indicate higher than expected.

C. SR Hi Flux Reactor Trip will occur when power is lowered below the P-6 setpoint.

D. SR Permissive P-6 light will immediately extinguish due to the 1 of 2 coincidence.

ANSWER:

A. None, until power is lowered below the P-6 setpoint, and then the Source Range SENI31 indication will indicate lower than expected.

K/A #: 032AK1.01 RO IMPORTANCE: 2.5 KA DESCRIPTION: SR High Voltage Degradation OBJECTIVE #: A

REFERENCES:

T61.0110.6 LP 28, Pages 3 & 4 Gas-Filled Detector Characteristic Curve AUTHOR: DGL SOURCE: New - H DISTRACTER EXPLANATION:

B.' & C. Based on region lll of the curve, the number of counts would be lower D. P-6 is fed from the IR Nis.

RO Outline #R027

F

_ QUESTION # 040 Which ONE of the following valves will AUTOMATICALLY close from a Hi Hi (Red) Radiation Signal on EG-RE-9, 'A' Train CCW Radiation Monitor?

A. EGLV1, DI WTR TO CCW SRG TK 'A' LV B. EGRV10, CCW SRG TK 'B' VENT CTRL VLV C. EGHV69A, CCW TO RW PROT 'A' SPLY ISO HV D. EGHV72, CCW TO PASS UPSTRM ISO HV ANSWER:

A. EGLV1, DI WTR TO CCW SRG TK 'A' LV KIA #: 059AK2.01 RO IMPORTANCE: 2.7 KA DESCRIPTION: CCW High Radiation OBJECTIVE #: E

REFERENCES:

T61.0110.6 LP 10, Page 15 AUTHOR: DGL SOURCE: New - L DISTRACTER EXPLANATION:

B. & C. & D. Incorrect because equipment not affected by high radiation alarm on EG-RE-9.

RO Outline #R033

QUESTION # 041 The following plant conditions exist:

. Reactor Power is 26%.

. Pressurizer Pressure is 2235 psig.

. Pressurizer Levelis 33%.

.- 'A' RCP breaker trips due to a failed undervoltage relay in PT cubicle PA03. (No other RCP is affected.)

Which ONE of the following is the expected result of the trip of the 'A' RCP7 A. _ The reactor will trip due to the 'A' RCP undervoltage failure.

)

B. The reactor will trip due to the RCS Flow Low conditions.

C. A plant shutdown will be performed.

D. The reactor will be manually tripped.

l ANSWER:

C. A plant shutdown will be performed.

K/A #: 003K2.01 RO IMPORTANCE: 3.1 KA DESCRIPTION: RCP Bus Undervoltage OBJECTIVE #: D

REFERENCES:

T61.0110.6 LP 27, Pages 24 & 25 OTO-BB-00002 AUTHOR: DGL SOURCE: New - H DISTRACTER EXPLANATION:

A. Requires 1/2 RCPs on 2/2 buses to trip the reactor.

9. Be!ow P-8 setpoint, will NOT trip reactor.

D. Off-Normal procedure directs a plant shutdown.

RO Outline #R039 I

I QUESTION # 042 '

Power Range Channels currently read as follows:

SEN141 - 78.5%

SEN142 - 77.5%

! SEN143 - 77.0%

SEN144 - 75.5%

[

, The results of OSP-SE-00004, Nis Power Range Heat Balance, show that calculated power

!- is 77%.

In accordance with OSP-SE-00004, which ONE of the following describes the current number of Power Range Channels that must be adjusted?

A. O B. 1 C. 2 D. 3 I

ANSWER:

l C, 2:

K/A #: 015A1.01 - RO IMPORTANCE: 3.5 )

KA DESCRIPTION: Power Range Heat Balance OBJECTIVE #: F.2 .

REFERENCES:

T61.003A.6 LP A-3, Page 4-OSP-SE-00004, Page 1 AUTHOR: DGL SOURCE: Bank (Modified)- H DISTRACTER EXPLANATION:

Channel must be adjusted if the absolute difference between indicated power and calculated power is

>1% or if indicated power is less than calculated power. SEN141 & SENI44 require adjustment.

,.RO Outline #R045 j

u .- - - - - - - - ----.-------_---------------.-- -.--------- _ - - - )

QUESTION # 043 The following plant conditions exist:

. . Reactor Power is 100%.

. ABFT0512 is the selected steam flow channel for 'A' S/G.

Which ONE of the following describes the effect of the steam pressure transmitter associated with ABFT0512 failing to zero? (Assume NO operator action is taken.)

A. Feed pump speed will decrease and S/G level will decrease below the low level trip setpoint.

B. Feed pump speed is unaffected and S/G level will decrease below the low level trip setpoint.

C. Feed pump speed will increase and S/G level will return to normal.

D. Feed pump speed is unaffected and S/G level will return to normal.

ANSWER:

A. Feed pump speed will decrease and S/G level will decrease below the low level trip setpoint.

K/A #: 059K1.04 RO IMPORTANCE: 3.4 KA DESCRIPTION: Steam Pressure Channel Failure

! OBJECTIVE #: A (LP B-4), B (LP SB-1)

REFERENCES:

T61.003B.6 LP B-4, Page 1 T61.003B.6 LP SB-1, Pages 7 & 8 OTO-AB-00003, Page 1 AUTHOR: DGL SOURCE: New - H DISTRACTER EXPLANATION:

B. & D. Feed pump speed will decrease due to total steam flow decrease.

C. S/G level will NOT retum to normal.

RO Outline #R051

QUESTION # 044 Which ONE of the following will AUTOMATICALLY terminate a release from the Gas Decay Tcnks through the Radwaste Unit Vent?

A. .HiHi Radiation Alarm on GH-RE-10B, RW Bldg Exh Fan Disch B. HiHi Radiation Alarm on HB-RE-18, RW Bldg Liquid Disch C. HiHi Radiation Alarm on GH-RE-22, RW Bldg Fixed Filter D. HiHi Radiation Alarm on GH-RE-23, Gas Decay Tank Compartment ANSWER:

A. HiHi Radiation Alarm on GH-RE-10B, RW Bldg Exh Fan Disch K/A #: 071A3.03 RO IMPORTANCE: 3.6 KA DESCRIPTION: Rad Monitor Auto isolation OBJECTIVE #: A.4

REFERENCES:

T61.0110.6 LP 16, Pages 17 & 18 OTA-SP-RM011 AUTHOR: DGL SOURCE: New - L DISTRACTER EXPLANATION:

B. & C. & D. Incorrect because they do NOT provide on input to automatically isolate release.

RO Outline #R057

1 L J QUESTION # 045 l

The following plant conditions exist:

. Reactor Power is stable at 30%.

. RCS Tave is 565.2 F. j

. Pu Pressure is 2235 psig.

. Pzr Levelis 35%.

. Pzr Level Controller Selector Switch, BBLS459D, is selected to the 459 (Upper) / 460 (Lower) position.

. 'A' CCP is in service.

Which ONE of the following is the correct plant response if the Pzr Level Controller BBLK459 I OUTPUT fails LOW? (Assume NO operator action is taken.) l l

l A. Pzr level will not change due to BBLT460 being the controlling channel.

B. The reactor will trip on high Pzr level due to letdown isolation. l i

C. Pzr level will control at 25% due to low output from the controller.

D. Pzr level will control at 57% due to low output from the controller.

l ANSWER:

B, -The reactor will trip on high Pzr level due to letdown isolation.

K/A #: 011K1.04 RO IMPORTANCE: 3.8 '

KA DESCRIPTION: PZR Level Controller Malfunction OBJECTIVE #: J&K

REFERENCES:

T61.0110.6 LP 30, Pages 21,22,26, & 31 AUTHOR: DGL SOURCE: New - H DISTRACTER EXPLANATION:

This failure causes charging flow to reduce to minimum (45 gpm). Pzr level will decrease until letdown isolates at 17%. Charging will continue at 45 gpm until Pzr level rises to the Hi Level Rx Trip Setpoint.

RO Outline #R063

QUESTION # 046 -

Which ONE of the following is a design feature to prevent draining of the Spent Fuel Pool (SFP)?

A. Fuel Pool Cooling pumps trip automatically on a low level in the fuel pool.

B. Fuel Pool Cooling pumps receive a Load Shed signal during a loss of coolant accident.

C. SFP Transfer Tube Gate Valve AUTOMATICALLY closes on a low level in the fuel pool.

D. Fuel Pool Cooling pumps take a suction on the fuel pool at a leve.1 of six feet below normal.

ANSWER:

D. Fuel Pool Cooling pumps take a suction on the fuel pool at a level of six feet below normal.

K/A #: 033K4.03 RO IMPORTANCE: 2.6 KA DESCRIPTION: Anti-Siphon Design OBJECTIVE #: H

REFERENCES:

T61.0110.6 LP 24, Page 8 AUTHOR: DGL SOURCE: New - L DISTRACTER EXPLANATION:

A. This trip is for pump protection.

B. Load Shed is for Emergency Diesel protection.

C. Gate valve has no auto close capability.

RO Outline #R069

QUESTION # 047 NE02, 'B' Emergency Diesel Generator, is operating in parallel with an off-site power source.

i Which ONE of the following describes how the Emergency Diesel Generator REACTIVE load is controlled?

A. By varying generator realload.

B. By varying generator frequency.

C. By varying diesel engine speed.

D. By varying generator excitation voltage.

ANSWER:

D. By varying generator excitation voltage.

K/A #: 064A4.02 RO IMPORTANCE: 3.3 -

KA DESCRIPTION: Reactive Load Control OBJECTIVE #: N

REFERENCES:

T61.0070.6 LP 25, Pages 67-69 AUTHOR: DGL SOURCE: New - H DISTRACTER EXPLANATION:

The DG Generator Control Switch will control real load while the voltage regulator switch (generator excitation) will control reactive load when in the parallel mode of operation.

RO Outline #R075

QUESTION # 048 q L The following plant conditions exist:

L

'.- The' plant is in Mode 3.-

. Replacement of the 'C' CTMT Cooler Fan Motor is in progress.

Which ONE of the following is the MINIMUM required condition for the Personnel Air Lock (PAL) cnd the Emergency Air Lock (EAL) doors per Technical Specifications?

A. - Both doors in the EAL must remain closed and both doors in the PAL must remain closed.

BI Both' doors in the EAL must remain closed and at least one door in the PAL must remain closed.

C. ~ Both doors in the EAL must remain closed and both doors in the PAL may remain open for transit entry and exits.

D. . Both doors in the PAL must remain closed and both doors in the EAL may remain open for transit entry and exits.

ANSWER:

B.- Both doors in the EAL must remain closed and at least one door in the PAL must remain

closed.

- K/A #: ' 103G2.2.22 RO IMPORTANCE: 3A KA DESCRIPTION: - Air Lock Requirements ,

i 02JECTIVE #: F.2

REFERENCES:

T61.003A.6 LP A-6, Page 5 Technical Specifications 3.6.1.3 AUTHOR: DGL SOURCE: New - L DISTRACTER EXPLANATION: .

A. One door in each air lock may be open.

C. & D. At least one door in each air lock must be closed.

RO Outline'#R087-L. . -- .

7 QUESTION # 049 Which ONE of the following is the MAXIMUM amount of radioactive material that may be ,

contained in the RWST7 {

I i

A. 100 Rem /hr B. 50 Curies C. 500 Rem /hr D. 150 Curies ANSWER:

D.150 Curies K/A #: 2.3.1 RO IMPORTANCE: 2.6 KA DESCRIPTION: RWST Radioactive Material Limit ,

I OBJECTIVE #: C.1 l

REFERENCES:

T61.003A.6 LP A-23, Page 3 !

I FSAR 16.11.1.5 AUTHOR: DGL SOURCE: Bank (Modified) - L I DISTRACTER EXPLANATION: ;

FSAR limit is s 150 curies. l RO Outline #R093

OUESTION # 050 A caution in FR-C.1, Response to inadequate Core Cooling, states, " Hydrogen Recombiner should not be turned on if hydrogen concentration is greater than or equal to ,

due to the danger of a hydrogen burn or explosion."

]

l A. 1%

B. 4%

C. 6%

D. 10%

ANSWER:

C.6%

K/A #: 2.4.20 RO IMPORTANCE: 3.3 KA DESCRIPTION: EOP Cautions OBJECTIVE #: B

REFERENCES:

T61.003D.6 LP 25, Page 24 AUTHOR: DGL SOURCE: Bank - L DISTRACTER EXPLANATION:

A. & B. & D. Incorrect, procedure limit is < 6%.

RO Outline #R099

z

_ QUESTION # 051 3

Dunng shift turnover, the Reactor Operator notes the following parameters:

.- RCS Tave-5814 F

. Pu Pressure -2235 psig

.- Pzr Level- 57%

.- PRT Pressure -4 psig

.- PRT Level- 74%

._ PRT Temperature - 98*F One (1) hour later, annunciator 34F, PRT LEV HILO, alarms and the following parameters are noted:

.. RCS Tave - 584.3 F

. .Pzr Pressure - 2234 psig

. Pzr Level- 57%

.? PRT Pressure - 5.9 psig

. PRT Level- 88%

. PRT Temperature - 96 F

~

Which ONE of the following conditions caused the change in parameters?

A. - Pzr PORV BBPCV455A opened and reclosed.

B, CVCS Letdown Relief BG8117 lifted.

C, PRT to RCDT Viv BBHV8031 opened.

D. PRT Rx M/U Supply BBHV8045 opened.

ANSWER:

D.' PRT Rx M/U Supply BBHV8045 opened.

K/A #: 007A3.01 RO IMPORTANCE: 2.7

~ KA DESCRIPTION: Inputs to the PRT OBJECTIVE #: E

REFERENCES:

T61.0110.6 LP 9, Page 44 AUTHOR: DGL SOURCE: New - H DISTRACTER EXPLANATION:

BBHV8045 is the only valve that could cause a level increase and temperature decrease.

RO Outline #R081 I

QUESTION # 052

. The following plant conditions exist:

. 'B' Circ Water Pump Lockout.

. Turbine Setback is in progress.

. MCB Annunciator 81D, Rod Bank Lo Limit, is lit.

. MCB Annunciator 81C, Rod Bank Lo Lo Limit, is lit.

Which ONE of the following indications will meet the requirements for given plant conditions?

A. 40 gpm flow indicated on BGFY111B, Combined M/U and BA Batch Counter.

B. 40 gpm flow indicated on BGF1183A, Emerg Borate To CCP 'A' & 'B' Hdr Flow lnd 'A'.

C. BG HIS-5A, 'A' Boric Acid Xfer Pmp PBG02A Hand ind SW, red light is lit.

D. BG HIS-8104, Emerg Borate To CCP 'A' & 'B' Hdr Iso HV, red light is lit.

ANSWER:

B. 40 gpm flow indicated on BGFl183A, Emerg Borate To CCP 'A' & 'B' Hdr Flow Ind 'A'.

K/A #: 024AA2.01 RO IMPORTANCE: 3.8 KA DESCRIPTION: Verification of Emergency Borate Flow -

OBJECTIVE #: A&B

REFERENCES:

T61.003B.6 LP B-61, Page 1 OTO-ZZ-00003, Pages 1 & 2 AUTHOR: DGL SOURCE: New - H DISTRACTER EXPLANATION:

A. This counter will not indicate during emergency boration.

B. Correct, verifies > 30 gpm emergency borate flow.

C. The pump running by itself will not provide the required emergency borate flow.

D. The valve open by itself will not provide the required emergency borate flow.

RO Outline #R004

l l _

QUESTION # 053 L

The following plant conditions exist:

. ECA-0.0, Loss of All AC Power, is being implemented.

. The Steam Generators (SIGs) are being depressurized.

. A caution s'ates that "SIG pressures should not be decreased to less than 120 psig" Which ONE of the following is the basis for maintaining S/G pressures above 120 psig during the depressurization?

A. To prevent steam void formation in the reactor vessel head.

B. To ensure RCS integrity is not challenged by pressurized thermal shock.

C. To maintain main steam, extraction steam, and steam dumps available.

D. To ensure that nitrogen from the accumulators is not injected into the RCS.

ANSWER:

D. To ensure that nitrogen from the accumulators is not injected into the RCS.

K/A #: 055EK3.02 RO IMPORTANCE: 4.3 KA DESCRIPTION: S/G Depressurization Limit (IPE/PRA)

OBJECTIVE #: Q i

REFERENCES:

T61,003D.6 LP 22, Page 48 ECA-0.0, Loss of All AC Power, Page 18 AUTHOR: DGL SOURCE: New - H DISTRACTER EXPLANATION:

l A. Depressurization should not be stopped to prevent voiding in the vessel head.

B. RCS temperature is maintained greater than 275'F. PTS is not a concem.

C. Not required since depressurization is accomplished using S/G PORVs.

RO Outline #R010 i

n QUESTION # 054 The following plant conditions exist:

. Mode 1,.100% Reactor Power.

~

. - RCS specific activity is 50 microcuries per gram DOSE EQUIVALENT l-131.

Which ONE of the following is the Chemistry sampling requirements per OTO-BB-00005, Reactor Coolant System High Activity?

A.- Normal 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months sample requirements are necessary.

' B. Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months until activity decreases for 3 consecutive days.

C .- As directed by the On-Shift Chemistry Supervisor.

D. Once per 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months until activity decreases on 3 consecutive samples.

ANSWER:

D. Once per 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months until activity decreases on 3 consecutive samples.

{

KIA #: 076AA2.02 RO IMPORTANCE: 2.8 KA DESCRIPTION: High RCS Activity Sampling Requirements OBJECTIVE #: A

REFERENCES:

T61.003B.6 LP B-18, Page 1 OTO-BB-00005 AUTHOR: DGL SOURCE: New - L DISTRACTER EXPLANATION:

A. RCS activity is above Tech Spec limit. Increased sampling required.

B. Incorrect sample frequency.

C. Incorrect sample frequency.

RO Outline #R016

I l

l C MS CION # 055 l

Which ONE of the following describes the correct guidance for use of ADVERSE CONTAINMENT values during a LOCA?

l A. Once in Adverse Containment, a return to NORMAL procedure values can be made immediately if containment temperature was the ONLY reason Adverse Containment had been declared and has returned to less than 160 F.

B. If containment temperature OR radiation exceeds their Adverse Containment criteria, then Adverse Containment values must be used for the duration of the event regardless if either decreases below the Adverse Containment criteria.

C. Once in Adverse Containment, a retum to NORMAL procedure values can be made immediately if containment radiation was the ONLY reason Adverse Containment had been declared and has returned to less than 1.0E5 R/HR.

D. If Adverse Containment was entered due to BOTH temperature and radiation, a return to NORMAL procedure values is allowed any time after temperature is less than 160 F and radiation is less than 1.0E5 R/HR.

ANSWER:

A. Once in Adverse Containment, a return to NORMAL procedure values can be made j immediately if containment temperature was the ONLY reason Adverse Containment had '

been declared and has returned to less than 160 F.

K/A #: 011EK3.12 RO IMPORTANCE: 4.4 KA DESCRIPTION: Adverse Containment Requirements OBJECTIVE #: J

REFERENCES:

T61.003D.6 LP 8, Page 33 AUTHOR: DGL l SOURCE: New - H I

DISTRACTER EXPLANATION:

B. Containment Temperature doesn't prevent using normal values after < 160*F.

C. & D. Can't use normal values after exceeding 1.0E5 R/HR.

RO Outline #R022

{ f QUESTION # 056

. The following plant conditions exist:

. - Plant shutdown is in progress.-

. . Intermediate Range Channel SENI36 fails HIGH.

Power Range Nis indicate: SENI41 9%

SEN142 :10%

SEN143 11 %

SEN144 11 %

Which ONE of the following describes the plant response to this failure?

A. The reactor will immediately trip on IR High Flux and Source Range Trip will reinstate automatically when SEN135 decreases below P-6 setpoint.

B. The reactor will immediately trip on IR High Flux and Source Range Trip will NOT -

reinstate automatically when SEN135 decreases below P-6 setpoint.

C.' The reactor will NOT immediately trip, but will trip when the Source Range Trip is reinstated when power decreases below the P-6 setpoint.

~ D. The reactor will NOT immediately trip, but will trip when the Intermediate Range Trip is reinstated when power decreases below the P-10 setpoint.

ANSWER:

D.- The reactor will NOT immediately trip, but will trip when the intermediate Range Trip is reinstated when power decreases below the P-10 setpoint.

KIA #: 033AA2.02 RO IMPORTANCE: 3.3 KA DESCRIPTION: IR Channel Failure During Shutdown -

OBJECTIVE #: D&E

REFERENCES:

T61.0110.6 LP ~27, Pages 23, 36 & 37 AUTHOR: DGL l' SOURCE: New - H DISTRACTER EXPLANATION:

A. & B. Power is still above P-10 setpoint, IR High Flux Trip is blocked.

C. SR Trip will not automatically reinstate below P-6 due to SEN136 being failed HIGH.

RO Outline #R028 n ,a .- . .. .

4

' QUESTION # 057 The following plant conditions exist:

. Reactor Power is 100%. a

. - Pressurizer Level Control is in AUTOMATIC.

. BBLT0459 is the UPPER selected control channel.

Which ONE of the following describes the plant response to BBLT0459 failing LOW 7 (Assume NO Operator Action is taken.)~

A. Letdown isolates, backup heaters tum on, charging flow decreases, actual pressurizer level decreases, and the reactor trips on low pressurizer level.

B. Letdown temperature increases, backup heaters de-energize, charging flow increases, actual pressurizer level increases, and the reactor trips on high pressurizer level.

C. ' Letdown isolates, backup heaters de-energize, charging flow increases, actual pressurizer ;

level increases, and the reactor trips on high pressurizer level.

l I

D. Letdown temperature increases, backup heaters de-energize, charging flow decreases, actual pressurizer level decreases, and the reactor trips on low pressurizer level.

1 ANSWER:

C. Letdown isolates, backup heaters de-energize, charging flow increases, actual pressurizer

~

. level increases, and the reactor trips on high pressurizer level.

K/A #: 028AA1.01 - RO IMPORTANCE: 3.8 J

KA DESCRIPTION: Reactor Trip From PZR Level Failure .

OBJECTIVE #: ~J&K

REFERENCES:

LT61.0110.6 LP 30, Pages 21,22 & 31 >

,k.

AUTHOR: DGL SOURCE: Bank (Modified)- H DISTRACTER EXPLANATION:

A. & D. There is no Pzr Low Level Reactor Trip.

B. Letdown willisolate. l l

RO Outline #R034-'

l l

k:

QUESTION # 058

. Which ONE of the following is the basis for isolating RCP #1 seal leakoff at RCS pressures below 100 psig?

A. #1 seal leakoff flow decreases at lower pressures, so #1 seal leakoff is isolated to force more flow to #2 seal.

' B. To prevent exceeding the Tech Spec controlled leakage limit due to excessive seal injection flow through the #1 seal at low pressures.

C. The leakoff flow instruments are not accurate at low pressures which could result in excessive leakoff going undetected.

D. To prevent contamination being forced into the seal chamber from the seal leakoff line.

ANSWER:

D. To prevent contamination being forced into the seal chamber from the seal leakoff line.

K/A #: 003A1.09 RO IMPORTANCE: 2.8 KA DESCRIPTION: Isolation of Seal Leakoff OBJECTIVE #: C.1.c

REFERENCES:

T61.003A.6 LP A-20, Page 3 OTN-BB-00003, Page 1 AUTHOR: DGL SOURCE: New - H DISTRACTER EXPLANATION:

A. #2 seal will have adequate flow.

B. Controlled Leakage Tech Spec limit won't be exceeded unless seal fails.

C. Leakoff flow instruments are accurate over entire range of pressures.

RO Outline #R040

l

_ QUESTION # 059 Which ONE of the following describes the affect on a Source Range Channelif the pulse height discriminator failed to a lower value?

The output would:

A. decrease due to the filtering which narrows the pulse height window.

B. decrease due to the removal of the higher amplitude neutron pulses.

C. increase due to the increased gamma interaction inside the detector.

D. increase due to counting of some of the lower amplitude gamma pulses.

ANSWER:

D. increase due to counting of some of the lower amplitude gamma pulses.

K/A #: 015A2.02 RO IMPORTANCE: 3.1 KA DESCRIPTION: SR Discriminator Failure OBJECTIVE #: A

REFERENCES:

T61.0110.6 LP 28, Pages 3-5 J

l AUTHOR: DGL I SOURCE: New - H J DISTRACTER EXPLANATIONI J A. Output increases due to a narrower pulse height window. !

B. Failure will NOT remove any neutron pulses.

C. Failure does NOT affect interactions inside the detector.

RO Outline #R046

n- 1 QUESTION # 060

. The following plant conditions exist:

. Reactor Power is 35%.

. ACPT0505 is the selected impulse Pressure Channel.

. All control systems are in their normal lineup.

Which ONE of the fobowing failures would cause an INITIAL decrease in feedwater flow to all j S/Gs?

A. Turbine Impulse Pressure ACPT0505 fails low.

B. Main Steam Header Pressure ABPT0507 fails low.

C. Turbine impulse Pressure ACPT0506 fails low.

D. Main Feed Header Pressure AEPT0508 fails low.

ANSWER:

B. Main Steam Header Pressure ABPT0507 fails low.

K/A #: 059K4.05 RO IMPORTANCE: 2.5 KA DESCRIPTION: MFP Speed Control OBJECTIVE #: E

REFERENCES:

T61.0110.6 LP 23, Pages 37-39 A.UTHOR: DGL SOURCE: New - H DISTRACTER EXPLANATION:

A. No affect, steam dumps are not armed.

C. No affect, ACPT0505 is selected channel.

D. This will increase feed pump speed and increase feed flow to S/Gs.

RO Outline #R052

r l

QUESTION # 061 l

l l GG-RE-27, Process Radiation Monitor, increases to the HiHi (Red) alarm setpoint on the gas j channel due to a fuel handling accident in the Fuel Bldg. ,

Which ONE of the following is an expected result from this alarm? r A. Only the 'A' Fuel Bldg Supply Air Unit (SGG01 A) starts.

B. Only the 'A' Emergency Exhaust Fan (CGG02A) starts.

C. Both Fuel Bldg Supply Air Units (SGG01 A & SGG01B) start.

D. Both Emergency Exhaust Fans (CGG02A & CGG02B) start.

ANSWER:

D. Both Emergency Exhaust Fans (CGG02A & CGG028) start.

K/A #: 072K4.02 RO IMPORTANCE: 3.2 KA DESCRIPTION: Fuel Bldg Isolation Signal OBJECTIVE #: D

REFERENCES:

T61.0110.6 LP 39, Pages 22-25 AUTHOR: DGL SOURCE: New - H DISTRACTER EXPLANATION:

A. & C. Fuel Bldg Supply Air Units stop on a FBVIS.

B. Rad Monitor starts both Emergency Exhaust Fans.

RO Ovtline #R058 I

l l

g L.

QUESTION # 062 The'following plant conditions exist:

.- ' Power Range Nls - 100%

. Loop Teoto Temperature - 554*F.

. Loop Tsor Temperature -615 F.

. . RCS Total Flow - 383,000 gpm.

. Pzr Pressure -2235 psig..

L Which ONE of the following describes the change in OTAT setpoint when the listed parameter is changed? (Consider each change individually.)-

. A. Setpoint increases if PZR pressure increases to 2240 psig.

B. Setpoint decreases if RCS total flow decreases to 380,000 gpm.

C. Setpoint increases if Loop Tsor increases to 625*F.

D. Setpoint decreases if Power Range Nis increase to 102%.

ANSWER:

. A. Setpoint increases if PZR pressure increases to 2240 psig.-

. K/A #: 012K4.02 RO IMPORTANCE: 3.9

. KA DESCRIPTION: OTAT Setpoint Changes OBJECTIVE #:, E

REFERENCES:

T61.0110.6 LP 30, Pages 13 & 14 AUTHOR: DGL SOURCE: New - H DISTRACTER EXPLANATION:

B.- RCS flow is not an input.

C.~ Setpoint will decrease.

D. NI input is only for exceeding +10 or-23 on Al.

RO Outline #R064 L

p--

l; QUESTION # 063 During an ATWS event, the 'D' SIG PORV will NOT open due to a controller malfunction.

Which ONE of the following combinations describes the correct pressures that the 'D' loop main steam safety valves will open?

l A. 1125,1185,1197,1210, and 1222 psig.

l l B. 1165,1185,1197,1210, and 1222 psig.

C. 1185,1197,1210,1222, snd 1234 psig. ,

D, 1197,1210,1222,1234, and 1246 psig. /

ANSWER:

C.1185,1197,1210,1222, and 1234 psig. J K/A #: 035K6.02 RO IMPORTANCE: 3.1 KA DESCRIPTION: S/G Safety Setpoints j OBJECTIVE #: F

REFERENCES:

T61.0110.6 LP 20, Page 25 AUTHOR: DGL SOURCE: New - L i DISTRACTER EXPLANATION:

l C. This is the only combination of correct relief setpoints.

RO Outline #R070 l

l l

l

r I

QUESTION # 064 M:in Control Board Annunciator 61C, Process Rad Monitor Failure has alarmed. When you check the status at the RM-11 panel, you find channel 223 CTMT Purge Monitor is flashing and its color is MAGENTA.

Which ONE of the following could be causing the failure of channel 2237 i A. Monitor Communications Failure B. Filter Paper Not Moving C. Loss Of Process Flow D. Low Alarm Vacuum ANSWER:

A. Monitor Communications Failure K/A #: 073A4.02 RO IMPORTANCE: 3.7 KA DESCRIPTION: RM-11 Status Panel OBJECTIVE #: B

REFERENCES:

T61.0110.6 LP 36, Pages 11 & 12 AUTHOR: DGL SOURCE: New- L DISTRACTER EXPLANATION:

B. Color would be dark blue.

C. Color would be light blue.

_D. Color would be light blue.

RO Outline #R076

. QUESTION # 065 The following plant conditions exist:

. A LOCA has occurred.

. Safety injection is INITIATED.

. CIS-B Isolation is INITIATED.

. NB01 and NB02 are powered from their respective D/Gs.

. All equipment has properly sequenced onto the buses. j Which ONE of the following loads are being supplied by Component Cooling Water (CCW) in this condition? ,

A. RW Recycle Evaporator B. Excess Letdown Heat Exchanger C. 'A' CCP Oil Cooler ;

i D. RCP Thermal Barrier Hxs l ANSWER:

1 C. 'A' CCP Oil Cooler I

K/A #: 008K1.02 RO IMPORTANCE: 3.3 KA DESCRIPTION: Loads Cooled by CCW i OBJECTIVE #: -C&D

REFERENCES:

T61.0110.6 LP 10, Pages 6,7,17, & 19 AUTHOR: DGL '

SOURCE: New - H DISTRACTER EXPLANATION:

A. Radwaste isolates on SI.

B. & D. Isolates on CIS-B.

RO Outline #R082 1

QUESTION # 066 You are the on-shift Reactor Operator. In accordance with plant procedure, which ONE of the following non-licensed individuals may you allow to start the 'A' Safety injection (SI) pump from p nel RLO17 in the Control Room?

A. Any system engineer authorized by the Shift Supervisor who is perforrning SI system surveillance.

B. Any assistant equipment operator performing OJT on the Sl system who is being monitored by the CRS.

C. Any individual who is enrolled in a license training program under my direct observation.

D. Any electrical maintenance supervisor troubleshooting why the SI pump vibration readings are abnormal.

ANSWER:

C. Any individual who is enrolled in a license training program under my direct observation.

K/A #: 2.1.2 RO IMPORTANCE: 3.0 KA DESCRIPTION: Operator Responsibilities OBJECTIVE #: H.1

REFERENCES:

T61.003A.6 LP A-4, Page 4 ODP-ZZ-00010, Page 4 AUTHOR: DGL SOURCE: Bank (Modified)- L

]

)

DISTRACTER EXPLANATION:

Must be in a licensed training program under the direct control of the on-shift license operator to operate miin control board controls.

RO Outline #R088

r I

QUESTION # 067 An AmerenUE radiation worker has received 500 mrem Total Effective Dose Equivelent (TEDE) whole body exposure so far this year. This worker has NOT received any exposure at other sites and has a complete exposure history record on file.

Which ONE of the following is the MAXIMUM TEDE whole body exposure this radiation worker can receive during the remainder of the year and NOT exceed the annual Callaway Plant l

Administrative Exposure Limit for TEDE Whole Body?

A. 1500 mrem l

B. 3500 mrem C. 4000 mrem l

l D. 4500 mrem ANSWER: l A.1500 mrem l

KIA #: 2.3.4 RO IMPORTANCE: 2.5 l KA DESCRIPTION: 'Nhole Body Admin Limits 1

OBJECTIVE #: B.8.a

REFERENCES:

T61.003A.6 LP A-31, Page 2 l APA-ZZ-01000, Attachment 1 l

l AUTHOR: DGL SOURCE: New - H DISTRACTER EXPLANATION:

l B. Limit including prior site exposure.

C, 10CFR20 incomplete history extended limit.

D. 10CFR20 Limit.

RO Outline #R094 I

)

1

QUESTION # 068 Following a reactor trip and transition to E-1, " Loss of Reactor or Secondary Coolant", an ORANGE path is identified under SUBCRITICALITY.

Which ONE of the following should be performed with regard to implementing FR-S.1,

" Response to Nuclear Power Generation"?

A. Implement FR-S.1 at the discretion of the Shift Supervisor.

B. Immediately suspend the performance of E-1 and implement FR-S.1.

C. Continue monitoring status trees, if no RED path is encountered, complete E-1 and then implement FR-S.1.

D. Monitor the remaining status trees, if no RED path is encountered, then implement FR-S.1.

ANSWER:

D. Monitor the remaining status trees, if no RED path is encountered, then implement FR-S.1.

K/A #: 2.4.22 RO IMPORTANCE: 3.0 KA DESCRIPTION: Prioritizing Safety Functions OBJECTIVE #: B.7

REFERENCES:

T61.003D.6 LP 1, Pages 44 & 45 AUTHOR: DGL i SOURCE: Bank - H {

DISTRACTER EXPLANATION: l A. & B.' Must check for red path prior to implementing orange path. l C. E-1 is suspended as soon as complete pass through status trees is finished and a red or orange path is present.

RO Outline #R100 1

5 _

)

L l r .)

~ QUESTION # 069 !

l .-

L r.

The following plant conditions' exist: ,

i

. The plant is in Mode 4

. 'B' RHR Train is in the cooldown alignment ~

. RCS temperature is 300 F .

l- .~ RCS pressure is 200 psig

. _'B' CCW Surge Tank level is DECREASING l

j - Which ONE of the following leak locations could produce these plant conditions?

l- A. 'B' RHR Heat Exchanger B. Thermal Barrier Heat Exchanger

/C. Letdown Heat Exchanger ;

D. Seal Water Heat Exchanger

~~

ANSWER:

2 D. Seal Water Heat Exchanger

' K/A #: 026AA1.05 RO IMPORTANCE: 3.1 KA DESCRIPTION: Evaluation of CCW Leak OBJECTIVE #: H

REFERENCES:

T61.0110.6 LP 10, Pages 22 & 33 AUTHOR: DGL' SOURCE: New - H ,

1 DISTRACTER EXPLANATION:

Only D. has a fluid pressure less than CCW pressure.

A. 'B' RHR Heat Exchanger pressure is = 395 psig. CCW pressure is 100 psig.

B. & C. Thermal Barner and Letdown Heat Exchanger pressures are = 200 psig. CCW pressure is 100 psig.-

D. Seal Water Heat Exchanger pressure is = 20 psig. CCW pressure is 100 psig.

i RO Outline #R005 ;

I

. QUESTION # 070 While operating at 100% power the following occurs:

. Intermediate Range Channel SEN135 fails low.

. Charging pump suction swapped from the VCT to the RWST.

. Pzr Level Indicator BBLl459A fails low.

Which ONE of the following could be the cause?

A. NN01 instrument Bus Failure B. PN07 Instrument Bus Failure C. NNO3 Instrument Bus Failure D. PN08 Instrument Bus Failure

~ ANSWER:

. A. NN01 Instrument Bus Failure K/A #: 057G2.1.7 RO IMPORTANCE: 3.7 KA DESCRIPTION: Diagnosis of NN Bus Failure.

OBJECTIVE #: A (LP B-45), G (LP SB-9)

REFERENCES:

T61.003B.6 LP B-45, Page 1 OTO-NN-00001 T61.003B.6 LP SB-9, Page 8 AUTHOR: .DGL SOURCE: New - H l

DISTRACTER EXPLANATION:

B. & C. & D. Common misconceptions.

RO Outline #R011 l

QUESTION # 071

The following plant conditions exist:

. Reactor Power is 30%.

. Rod Controlis in AUTOMATIC.

. ACPT0505 is the SELECTED impulse pressure channel.

. Tref is 565'F.

. ' Tave values: Loop 1 - 565 F, Loop 2 - 566'F, Loop 3 - 566*F, Loop 4 - 565*F.

. PR Nis: SEN141 - 31 %, SEN142 - 30%, SEN143 -29%, SEN144 - 30%.

. Control Bank 'D' is at 150 steps.

Which ONE of the following conditions would result in an automatic rod WITHDRAWAL 7 A. Pimp ACPT0505 fails to 100%.

B. PR NI SENI41 fails to 20%.

C.- Loop 1 Tema fails to 510 F.

D. Tref signal fails to 557 F.

ANSWER:

A. Pimp ACPT0505 fails to 100%.

K/A #: 001AA2.05 RO IMPORTANCE: 4.4 KA DESCRIPTION: Indications of Rod Withdrawal Malfunction OBJECTIVE #: B&C

REFERENCES:

T61.0110.6 LP 26, Page 16-19 AUTHOR: DGL SOURCE: New - H DISTRACTER EXPLANATION:

B. Rod Control uses Auctioneered HIGH PR Nis. PR Nl failing low has no effect.

C. Rod Control uses Auctioneered HIGH Tave. T failing low has no effect.

D Tref failing low would cause rods to insert.

RO Outline #RO17

QUESTION # 072 A reactor trip and safety injection have occurred. All immediate actions have been completed.

The following plant conditions exist:

. CTMT Radiation 1000 r/hr

. CTMT Pressure 2 psig

. CTMT Recirc Sump Level 50 inches

. RCS Pressure 175 psig

. RHR Pump Flow 500 gpm

. Pzr Level 0%

. RWST Level 86 %

Which ONE of the following procedures would be used for plant recovery?

A. ES-1.1, SI Termination B. ES-1.2, Post LOCA Cooldown and Depressurization C. ES-1.3, Transfer to Cold Leg Recirculation D. ECA-1.1, Loss of Emergency Coolant Recirculation ANSWER:

B. ES-1.2, Post LOCA Cooldown and Depressurization KIA #: W/E03EA2.1 RO IMPORTANCE: 3.4 KA DESCRIPTION: Selection of Recovery Procedure OBJECTIVE #: U

REFERENCES:

T61.003D.6 LP 8, Page 52 AUTHOR: DGL SOURCE: Bank (Modified)- H DISTRACTER EXPLANATION:

A. Si Termination Criteria is not met.

C. Cold Leg Recirculation Switchover Criteria is not met.

D. Cold Leg Recirculation Capability is available.

RO Outline #R023

QUESTION # 073 Which ONE of the following describes the RCP trip criteria while responding to a SGTR per E-3, Steam Generator Tube Rupture?

A. RCPs should be tripped anytime during E-3 if the trip criteria are met.

B. RCPs should be tripped during E-3 only if the trip criteria are met when specifically required to check the criteria.

C. RCPs should be tripped during E-3 only if the trip criteria are met before initiating a cooldown.

D. RCPs should be tripped during E-3 only if the trip criteria are met before isolating the ruptured S/G.

ANSWER:

C. RCPs should be tripped during E-3 only if the trip criteria are met before initiating a cooldown.

K/A #: 038EK3.08 RO IMPORTANCE: 4.1 KA DESCRIPTION: RCP Trip Criteria OBJECTIVE #: H

REFERENCES:

T61.003D.6 LP 17, Page 34 AUTHOR: DGL SOURCE: New - L DISTRACTER EXPLANATION:

A. & B. & C. Trip criteria applies until an operator controlled cooldown is initiated.

RO Outline #R029 l

l

QUESTION # 074 The plant has experienced a total loss of instrurrient air.

'Which ONE of the following valves is in its correct failed position?

A. EJHCV0606, RHR HX 'A' OUTLET FCV is CLOSED B. BGHV8149A, CVCS LTDN ORIFICE 'A' ISO is OPEN C. BGFCV0111B, M/U TO VCT IN HDR FCV is OPEN D. EJFCV0619, RHR HX 'B' BYP FLOW CTRL VLV is CLOSED ANSWER:

D. EJFCV0619, RHR HX 'B' BYP FLOW CTRL VLV is CLOSED KIA #: 065AA2.08 ' RO IMPORTANCE: 2.9 KA DESCRIPTION: Valve Failure on Loss of Air OBJECTIVE #: B

REFERENCES:

T61.0110.6 LP 7, Page 16 OTO-KA-00001, Attachments 5 & 6 AUTHOR: DGL SOURCE: New - H DISTRACTER EXPLANATION:

A. EJHCV0606 fails OPEN.

B. BGHV8149A fails CLOSED.

C. BGFCV01118 fails CLOSED.

RO Outline #R035

QUESTION # 075 The, following plant conditions exist at 0400:

. Tave is 557*F.

. Pzr Pressure is 2235 psig.

. SR Channel SEN131 indicates 19 cps.

. SR Channel SEN132 indicates 20 cps.

The following plant conditions exist at 0409:

. Tave is 556 F.

. Pzr Pressure is 2237 psig.

. SR Channel SEN131 indicates 39 cps.

. SR Channel SEN132 indicates 46 cps.

I Which ONE of the following describes the plant response to these conditions?

A. The Containment Evacuation Alarm sounds.

J B. The High Flux at Shutdown Alarm sounds.

C. The reactor trip breakers open on high source range counts.

D. CCP suctions swap from the VCT to the RWST.

I i

ANSWER:

l . D. CCP suctions swap from the VCT to the RWST.

1 K/A #: 004K1.07 RO IMPORTANCE: 2.6 KA DESCRIPTION: Response to Flux Doubling i

OBJECTIVE #: E

REFERENCES:

T61.0110.6 LP 28, Pages 6 & 7 AUTHOR: DGL' SOURCE: Bank (Modified)- H l

DISTRACTER EXPLANATION:

A. & B.Both occur at 200 cps.

C. SR High Flux Trip is at 105 cps.

RO Outline #R041

QUESTION # 076

' Which ONE of the following Core Exit Thermocouple (CETC) readings indicates the highest t::mperature during accident conditions at which a CETC will operate satisfactorily?

A.' 700 F B. 1200 F C. 2300 F D. 3200 F ANSWER:

C.' 2300 F K/A #: 017K6.01 RO IMPORTANCE: 2.7 KA DESCRIPTION: Thermocouple Failures OBJECTIVE #: J

REFERENCES:

T61.0110.6 LP 29, Page 11 AUTHOR: DGL SOURCE: New - L DISTRACTER EXPLANATION:

A. FR-C.2 Orange Path criteria.

B. FR-C.1 Red Path criteria.

D. Common misconception.

RO Outline #R047

!~ I QUESTION # 077 The following plant conditions exist: 1 i

. Reactor startup was in progress when the reactor tripped at 104 amps.

. Containment pressure is normal. l

. NB01 bus had a spurious trip of the normal feeder breaker.

{

. NE01, 'A' Emergency DG, automatically started and is supplying NB01. '

. Lowest S/G NR levels reached were: 'A' - 20%, 'B' - 18%, 'C' - 19%, 'D' - 21 %.

3 Which ONE of the following is the correct status of the Auxiliary Feedwater Pumps (AFPs)?

A. Only the TDAFP is running.

B. 'A' MDAFP and the TDAFP are running.

C. 'B' MDAFP and the TDAFP are running.

D. All three AFPs are running.

ANSWER:

B. 'A' MDAFP and the TDAFP are running.

K/A #: 061K4.02 RO IMPORTANCE: 4.5 KA DESCRIPTION: AFW Pump Auto Starts .

l OBJECTIVE #: H

REFERENCES:

T61.0110.6 LP 25, Pages 19 & 20 AUTHOR: DGL SOURCE: New - H DISTRACTER EXPLANATION:

A. 'A' MDAFP started on the S/D sequencer. l C. 'A' MDAFP is running, NOT 'B' MDAFP. !

D. 'B' MDAFP is NOT running.

RO Outline #R053

QUESTION # 078 l

Which ONE of the following Area Radiation Monitors is required by Technical Specifications?

A. SD-RE-27, CTMT Purge Filter Unit '

B. SD-RE-33, Control Room Area C. SD-RE-38, Spent Fuel Pool Area D. SD-RE-42, Containment Building ANSWER:

C. SD-RE-38, Spent Fuel Pool Area K/A #: 072G2.2.22 RO IMPORTANCE: 3.4 KA DESCRIPTION: ARMS Required By T/S OBJECTIVE #: G

REFERENCES:

T61.0110.6 LP 36, Page 24 AUTHOR: DGL SOURCE: New - L DISTRACTER EXPLANATION:

Only Area Rad Monitors required by T/S are SD-RE-35,36,37, & 38.

RO Outline #R059

7 l

QUESTION # 079 m.

l. The following plant conditions exist:-

.. Mode 1 at 100% power.

. - Annunciator 808, RPI NON-URG ALARM is lit.

. DRPI General Warning LED is flashing for rod H-8.

.. DRPI Data 'A' Failure LED is lit.

. Rod Bottom Light for H-8 is NOT lit.

. NO Rod Control System alarms are lit.

Which ONE of the following describes the operability of DRPI and the accuracy of determining I the position of rod H-87 A. Operable; accuracy is +10, -4 steps.

B. Inoperable; accuracy is -10, +4 steps.

C. Operable; accuracyisi4 steps.

D. Inoperable; no measureable accuracy.

ANSWER:

A. Operable; accuracy is +10,-4 steps.

K/A #: 014G2.2.22 RO IMPORTANCE: 3.4 KA DESCRIPTION: Determine DRPI Operability OBJECTIVE #: S&U ,

REFERENCES:

. T61.0110.6 LP 26, Pages 26 & 66 I AUTHOR: DGL ,

SOURCE: New - H I DISTRACTER EXPLANATION:

B. DRPIis still operable with half accuracy. i C. Accuracy is +10,-4 steps.

D. DRPI is still operable and accuracy is +10, -4 steps. )

. RO Outline #R065 !

E ;

l

-~ QUESTION # 080 The plant is operating at steady state, end-of-life,70% power. A power change is commenced by the BOP operator by increasing turbine load.

Which ONE of the following describes the affect on Reactor Power? (Consider only the effect of tha increased steam flow.)

A. Reactor power increases due to the positive moderator temperature coefficient adding positive reactivity.

B. Reactor power increases due to the negative moderator temperature coefficient adding positive reactivity.

C. Reactor power decreases due to the positive moderator temperature coefficient adding negative reactivity.

. D. Reactor power decreases due to the negative moderator temperature coefficient adding negative reactivity.

ANSWER:

B. Reactor power increases due to the negative moderator temperature coefficient adding positive reactivity.

K/A #: 039A2.05 RO IMPORTANCE: 3.3 KA DESCRIPTION: Rx Power / Steam Demand OBJECTIVE #: G

REFERENCES:

T61.0070.6 LP 4, Pages 100-103 AUTHOR: DGL SOURCE: - New - H DISTRACTER EXPLANATION:

A. MTC is negative.

C. Power increases because MTC is negative which adds positive reactivity.

D. Power increases due to' adding positive reactivity.

RO Outline #R071

E QUESTION # 081

, The plant has experienced a loss of all Circ Water Pumps which resulted in a reactor trip. All l ~ systems have responded as designed. Significant decay heat causes RCS temperature to l increase following the trip.

l l Which ONE of the following is the RCS temperature at which the plant will stabilize?

l A. 550 F B. 557 F C. 561 F D. 565 F ANSWER:

C. 561*F K/A #: 075A2.02 RO IMPORTANCE: 2.5 KA DESCRIPTION: Cire Water Pump Trips OBJECTIVE #: F (LP 20), B (LP 13)

REFERENCES:

T61.0110.6 LP 20 Pages 22 & 23 T61.0070.6 LP 13, Page 18 AUTHOR: DGL SOURCE: New - H DISTRACTER EXPLANATION:

Condenser steam dumps are not available due to the loss of vacuum. RCS temperature will be controlled by the S/G PORVs. The PORVs open at 1125 psig (1140 psia). Tsu for 1140 psia is 561 F.

RO Outline #R077

QUESTION # 082 Which ONE of the following is a CHIEF CONTRIBUTOR Post-LOCA hydrogen source in containment?

A. Zirconium-Water Reaction B. Corrosion of Metal and Paint C. Dissolved Hydrogen in Reactor Coolant D. Oxidation of Aluminum ANSWER:

A. Zirconium-Water Reaction K/A #: 028K5.03 RO IMPORTANCE: 2.9 KA DESCRIPTION: Post-LOCA H2 Sources OBJECTIVE #: 1

REFERENCES:

T61.0110.6 LP 40, Page 33 AUTHOR: DGL SOURCE: New - L DISTRACTER EXPLANATION:

B. Minorcontribution.

C.' Minor contribution.

D. No contribution.

RO Outline #R083

QUESTION # 083 You are the on-coming Unit Reactor Operator for the February 7* AM Shift (0700). Your last shift was finished at 0700 on February 5*. Which ONE of the following describes the minimum cmount of RO logs that you must review prior to watch relief?

I

' \

A. Back to February 6* at 2300.

B. Back to February 6'h at 0700.

C. Back to February 5* at 2300.

1 D. Back to February 5* at 0700.

l I

I ANSWER:

B. Back to February 6* at 0700.

, I KIA #: 2.1.3 RO IMPORTANCE: 3.0 KA DESCRIPTION: Shift Tumover Practices l

l OBJECTIVE #: A.2.b i

REFERENCES:

T61.003A.6 LP A-2, Page 2 ODP-ZZ-00003, Page 4 AUTHOR: DGL SOURCE: New - H DISTRACTER EXPLANATION: l Must review last 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or their last watch whichever is shorter. Last watch was 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months ago, therefore must review 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (February 6"' at 0700).

RO Outline #R089 l

l l

1 l

c QUESTION # 084 A purpose of the Control Building Ventilation System is to limit radiation doses of Conirol Room a personnel during a design basis accident to:

A. less than 5 Rem whole body dose during the first 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months of the accident.

B. less than 10 Rem whole body dose during the first 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months of the accident.

C. less than 5 Rem whole body dose during the entire period of the accident.

D. less than 10 Rem whole body dose during the entire period of the accident.

ANSWER:

C. less than 5 Rem whole body dose during the entire period of the accident.

KIA #: 2.3.10 RO IMPORTANCE: 2.9 KA DESCRIPTION: Personnel Exposure Control OBJECTIVE #: A

REFERENCES:

T61.0110.6 LP 60, Page 41 -

~

AUTHOR: DGL SOURCE: Bank (Modified) - L DISTRACTER EXPLANATION:

A. For entire accident, not 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

B. Limit is 5 Rem, not 10 Rem and for entire accident, not 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

D. Limit is 5 Rem, not 10 Rem.

RO Outline #R095

QUESTION # 085 The following plant conditions exist:

. Mode 1.at 100% power.

.. All systems are in AUTOMATIC.

'l .. Pressurizer Pressure Channel BBPT0455 is inoperable with it's appropriate bistables placed in the TRIPPED condition.

. Pressurizer Pressure Control Selector Switch, BB PS-455F is selected to BBPT0457 (Upper Selected Channel) and BBPT0456 (Lower Selected Channel).

Which ONE of the following is the correct plant response if Pressurizer Pressure Channel BBPT0457 fails HIGH INSTANTANEOUSLY 7 (Assume NO Operator Action taken.)

. A. Both PORVs and both Spray Valves open resulting in a reactor trip on low pressurizer pressure followed by Si actuation.

B. The reactor will trip on high pressurizer pressure and SI will actuate on low pressurizer pressure due to spray valve operation.

C. Both PORVs and both Spray Valves will remain closed and all pressurizer heaters will de-energize.-

D. The reactor will trip on OPAT and SI will actuate on low pressurizer pressure due to both spray valves opening.

~~ ANSWER:

B. The reactor will trip on high pressurizer pressure and Sl will actuate on low pressurizer pressure due to spray valve operation.

KIA #: 027AA1.01 RO IMPORTANCE: 4.0 KA DESCRIPTION: Pressurizer Pressure Channel Failure OBJECTIVE #: J&K

REFERENCES:

T61.0110.6 LP 30, Pages 19 & 20 AUTHOR: DGL SOURCE: New - H DISTRACTER EXPLANATION:

A. Only one PORV will open (BBPCV0455A).

C. Both spray valves and one PORV will open.

D. The reactor will trip on high pressurizer pressure, not OPAT.

L RO Outline #R006 1

t QUESTION # 086 The following plant conditions exist:

. Reactor tripped from 100% power due to an EARTHQUAKE.

. The Condensate Storage Tank (CST) ruptured and is EMPTY.

. All three (3) Auxiliary Feedwater Pumps (AFPs) are running.

. No cther plant equipment was damaged.

Which ONE cithe following is a consequence of this event? (Assume NO Operator Action is 1:: ken.)

A. ' The Auxiliary Feedwater Pumps ii.:ve no suction supply.

B. The Auxiliary Feedwater Pumps will trip on CST LoLo Level.

C. The UHS level will drecrease due to water being pumped from the UHS to the AFPs suction and the Cooling Tower Basin.

D. The Service Water System is supplying the Auxiliary Feedwater Pumps suction and UHS Pond level will remain stable.

ANSWER:

C. The UHS level will drecrease due to water being pumped from the UHS to the AFPs suction and the Cooling Tower Basin.

K/A #: 062AK3.02 RO IMPORTANCE: 3.6 KA DESCRIPTION: ESW Response To ESFAS Signals OBJECTIVE #: D-

REFERENCES:

T61.0110.6 LP 5, Page 32 i

AUTHOR: DGL SOURCE: New - H DISTRACTER EXPLANATION:

A. Suctions are supplied by ESW.

B. MCB alarm only, no automatic pump trips. l D. ESW is supplying and UHS level will decrease.

RO Outline #R012

. . . . . . . . . . . . . . . . - . . . . .. i

g n

QUESTION # 087

. The following plant conditions exist:

l' . Turbine load - STABLE.

. Reactor Power - 98%.

. RODS AT BOTTOM Annunciator-LIT

. - Bank 'D' Control Rods - Stepping outward in AUTOMATIC.

. ' .Tave - 3 F below Tref.

. RPI ROD DEV Annunciator- LIT.

. TWO / MORE RODS AT BOTTOM Annunciator- LIT.

.~ PR CHANNEL DEV Annunciator - LIT Which ONE of the followii.g IMMEDIATE ACTIONS should be taken?

A. Place rod control in manual and reduce turbine load to maintain Tave and Tref AT less than 3*F.

B.' Manually trip the reactor and proceed to E-0, Reactor Trip or Safety injection.

C .' Place rod control in manual and withdraw rods as required to maintain Tave and Tref

~

matched. ,

D. Manually trip the reactor ONLY if RCS Tave decreases to < 551*F. I ANSWER:

1 B. Manually trip the reactor and proceed to E-0, Reactor Trip or Safety Injection. !

K/A #: 003AA2.01 RO IMPORTANCE: 3.7 KA DESCRIPTION: Indications of Multiple Dropped Rods OBJECTIVE #: B

REFERENCES:

T61.003B.6 LP 54, Page 1 OTO-SF-00003 AUTHOR: DGL SOURCE: Bank (Modified)- H ;

DISTRACTER EXPLANATION:

A. Only correct if one rod is dropped.

C. Requires trip for multiple dropped rods.

D. Requires trip regardless of RCS temperature.

RO Outline #RO18

QUESTION # 088

The following plant conditions exist:

. A Small Break LOCA has occurred.

.- - No Adverse Containment conditions exist.

Which ONE of the following conditions would prevent Si Termination?

k Pressurizer Level is 16% and increasing.

B. RCS Pressure is 1650 psig and stable.

. C. 'D' S/G NR Level is 8% and increasing.

. D. RCS Subcooling is 16 F and stable.

- ANSWER:

D. RCS Subcooling is 16*F and stable.

K/A #: W/E02EK1.2 RO IMPORTANCE: 3.4 KA DESCRIPTION: St Termination Criteria

~

OBJECTIVE #: P

REFERENCES:

T61.003D.B LP 8, Page 40 AUTHOR: DGL SOURCE: New - L DISTRACTER EXPLANATION:

A. & B. & C. Meet Si Termination Criteria.

D. Correct- Less subcooled than instrument error.

RO Outline #R024

i L QUESTION # 089 Which ONE of the following differentiates between an unisolable feedwater line break and an unisolable steam line break of the same size inside containment?

l A. RCS depressurization rate would be greater for a feedwater line break. I B. RCS heat removal would be greater for a steam line break.

C. The affected S/G will begin to depressurize sooner for a feedwater line break.

D. Containment pressure would be lower for a steam line break.

ANSWER:

i I

B. RCS heat removal would be greater for a steam line break.

KIA #: 054AK1.01 RO IMPORTANCE: 4.1 i KA DESCRIPTION: Differences Between Feed / Steam Line Break I OBJECTIVE #: A (LP 15), F (LP 3)

REFERENCES:

T61.003D.6 LP 15, Pages 4,6 & 7 T61.003D.6 LP 3, Pages 29-33 AUTHOR: DGL SOURCE: New - H DISTRACTER EXPLANATION:

A. RCS temperature initially increases due to loss of cold feedwater causing RCS pressure to increase.

C. S/G pressure initially increases due to loss of cold feedwater.

D. Higher energy steam leak will result in greater containment pressure.

RO Outline #R030

QUESTION # 090 Which ONE of the following correctly describes why the 'B' and 'C' SI Accumulators have two v:nt valves?

A. The two vent valves are both powered from a non-safety related power supply.

B. Their outlet isolation valves are below the calculated Post-LOCA water level.

C, The accumulators vent piping is a smaller diameter than the vent piping on 'A' and 'D'. l 1

D. Their outlet isolation valves are powered from a non-safety related power supply.

ANSWER:

B. Their outlet isolation valves are below the calculated Post-LOCA water level.

K/A #: W/E15EK2.1 RO IMPORTANCE: 2.8 KA DESCRIPTION: Flooding Effects on Accumulator Iso Valves OBJECTIVE #: B

REFERENCES:

T61.0110.6 LP 19, Page 6 AUTHOR: DGL SOURCE: New - H DISTRACTER EXPLANATION:

A. & D. All valves have a safety-related power supply.

C. All vent piping is same size diameter.

RO Outline #R036

[

l-I' QUESTION # 091 The following plant conditions exist: '

. Operating at 90% power, MOL.

. CCW flow through the letdown heat exchanger is decreased.

l (Assume NO automatic actions occur in the CVCS and NO operator actions are taken.)

Which ONE of the following describes how RCS temperature will be INITIALLY affected?

A. Decrease because the CVCS ion exchangers are releasing boron into the letdown flow. i B. Increase because the CVCS ion exchangers are absorbing boron from the letdown flow.

C. Decrease because Loop AT is being decreased by hotter CVCS charging flow.

D .- Increase because Loop AT is being increased by hotter CVCS charging flow.

i ANSWER:

A. Decrease because the CVCS ion exchangers are releasing boron into the letdown flow. )

KIA #: 004KS.20 RO IMPORTANCE: 3.6 l KA DESCRIPTION: Effects of Boration OBJECTIVE #: C.1.h

REFERENCES:

T61.003A.6 LP A-9, Page 3 OTN-EG-00001, Page 4 AUTHOR: DGL SOURCE: New - H DISTRACTER EXPLANATION:

B. Temperature decreases due to boron release.

C. & D. Charging temperature has insignificant impact on RCS temperature.

RO Outline #R042

p

-QUESTION # 092

~

The plant is in Mode 5 with an RCS temperature of 145 F.

Which ONE of the following fan combinations must be in service to meet the MINIMUM rcquirement to prevent damage to equipment in containment (CTMT)?

A. 'A' and 'D' CTMT Cooler Fans and 'B' Cavity Cooling Fan B. 'A' and 'C' CTMT Cooler Fans and 'A' CRDM Fan

'C. 'B' and 'C' CTMT Cooler Fans and Pzr Cooling Fan D. - 'B' and 'O' CTMT Cooler Fans and 'B' CRDM Fan

' ANSWER:

A. .'A' and 'D' CTMT Cooler Fans and 'B' Cavity Cooling Fan K/A #: 022K3.01 RO IMPORTANCE: 2.9 KA DESCRIPTION: Fans Required to Prevent Damage OBJECTIVE #: 1.1.b,1.1.c, & l.1.f

REFERENCES:

T61.003A.6 LP A-20, Page 6.

OTN-GN-00001, Pages 1 & 2 AUTHOR: DGL SOURCE: New- H DISTRACTER EXPLANATION:

Fen lineup required is: 'A' or 'C' CTMT Cooler Fan One Cavity Cooling Fan Pzr Cooling Fan or 'D' CTMT Cooler Fan RO Outline #R048

l QUESTION # 093 Which ONE of the following RTD failures will result in Tave and AT indications both reading I erroneously HIGH7 l

l A. -Tcoto RTD opens i 1 l B. Tsor RTD opens i l

C. Teoto RTD shorts D. Tsor RTD shorts l

ANSWER:

l B. Tsor RTD opens K/A #: 002K5.12 RO IMPORTANCE: 3.7 KA DESCRIPTION: Tave / AT Response To RTD Failure OBJECTIVE #: A (LP SB-2), B (LP 10)

REFERENCES:

T61.0038.6 LP SB-2, Page 5 T61.0070.6 LP 10, Page 8 AUTHOR: DGL SOURCE: New - H l

DISTRACTER EXPLANATION: l l A. Tcom increases, AT decreases, Tave increases.

l B. Tecx.o decreases, AT increases, Tave decreases.

i D. Ter decreases, AT decreases, Tave decreases.

l RO Outline #R060 i !

l l .,

l l

QUESTION # 094 Which ONE of the following describes the normal alignment of the air systems for the TDAFP

-flow control valves?

A. Instrument Air and N2 backup are both normally unisolated. N2 Pressure is maintained

= 10 psi LOWER than' Instrument Air pressure.

B. Instrument Air and N2 backup are both normally isolated. Both automatically unisolate during a Turbine Driven Auxiliary Feedwater Actuation Signal.

C. Instrument Air and N2 backup are both normally unisolated. N2 pressure is maintained

= 10 psi HIGHER than Instrument Air pressure.

D. Instrument Air and N2 backup are both normally isolated. Both automatically unisolate during a Motor Driven Auxiliary Feedwater Actuation Signal.

ANSWER:

A. Instrument Air and N 2backup are both normally unisolated. N2 Pressure is maintained

= 10 psi LOWER than Instrument Air pressure.

K/A #: 061A2.07 RO IMPORTANCE: 3.4 KA DESCRIPTION: Air Operated Flow Control Valves OBJECTIVE #: C

REFERENCES:

T61.0110.6 LP 25, Page 13 AUTHOR: DGL SOURCE: New - L DISTRACTER EXPLANATION:

B.- Both supplies are normally unisolated.

C. N 2is maintained = 10 psi LOWER.

D. Both supplies are normally unisolated.

RO Outline #R054 -

E

, QUESTION # 095 The following plant conditions exist:

. . Reactor Power - 50%

. Pzr Pressure. -

2235 psig .

.- Pzr Level - . 41 %

Looo 1 Looo2 Looo 3 Looo 4

. . . RCS Loop Tave 571*F 570*F 570*F 571 F

. RCS Loop Tsor 586 F 585*F 585*F 587 F

. RCS Loop Tcoto 556 F 555*F 555*F 555 F I

Which ONE of the following is the correct Pzr Level response if Loop 2 Tsor channel fails LOW?

A. Increases to 57%.

B. Remains the same.

'C. ' Decreases to 25%.

l D. Decreases to 17%.

ANSWER:

B. Remains the same, j i

K/A #: 016K3.02 RO IMPORTANCE: 3.4 i KA DESCRIPTION: RTD Channel Failure OBJECTIVE #: D&J

REFERENCES:

T61.0110.6 LP 30, Pages 17 & 21 CMP 98-1039A AUTHOR: DGL SOURCE: New - H l DISTRACTER EXPLANATION:

Ta fails to 530*F, making Loop 2 Tave 542.5*F. Pzr Level uses Auctioneered High Tave so level will remain the same.

A. High End of Pzr Level Band.

C. - Low End of Pzr Level Band.

, D. Letdown Isolation Setpoint.

RO Outline #R066 i )

QUESTION # 096 A seal water malfunction on the running condenser vacuum pump results in a degrading main condenser vacuum.

Which ONE of the following is the setpoint at which the standby condenser vacuum pump will cutomatically start?

A. 5.0 inches Hga B. 5.5 inches Hga C. 6.0 inches Hga D. 6.5 inches Hga ANSWER:

A. : 5.0 inches Hga KIA #: 055K3.01 RO IMPORTANCE: 2.5 KA DESCRIPTION: Vacuum Pump Auto Starts OBJECTIVE #: M

REFERENCES:

T61.0110.6 LP 22, Page 24 AUTHOR: DGL SOURCE: New- L DISTRACTER EXPLANATION:

B. No automatic action.

C. Blocks condenser steam dumps.

D. No automatic action.

RO Outline #R072

1 I

. .QUESTION # 097. l 1

The following plant conditions exist:

. - Compressor Sequencer Selector Switch, KAHS0043, is selected to the CAB position.

. : All three air compressors are selected to AUTOMATIC. ,

.- .'A' Air Compressor (CKA01 A) is running unloaded.

.' 'B' Air Compressor (CKA01B) is not running.' l

. 'C' Air Compressor (CKA01C) is running loaded. l

. KA-PV-11, Service Air Isolation Valve is open.

Which ONE of the following describes the correct system response to an air leak that results in cir system pressure decreasing to 105 psig?

A. Only 'CKA01 A and CKA01C are running and both are loaded.

l B. All three air compressors are running, but only two are loaded.

C. Only CKA01 A and CKA01C are running and both are loaded, KA-PV-11 is closed.

D .' All three air compressors are running and all three are loaded, KA-PV-11 is closed.

- ANSWER: i D. All three air compressors are running and all three are loaded, KA-PV-11 is closed.

KIA #: 079A4.01 RO IMPORTANCE: 2.7 KA DESCRIPTION: Loss of instrument Air Pressure OBJECTIVE #: D

REFERENCES:

T61.0110.6 LP 14, Page 24 AUTHOR: DGL SOURCE: New - H DISTRACTER EXPLANATION:

For this failure, the 2"d air compressor would load, the 3'd air compressor would start and load, and service tir would isolate.

RO Outline #R078 l

l k

u

QUESTION # 098 !

The following plant conditions exist:

. Mode 6 with Core Alterations in progress.

. Source Range Channels: 9999 0910 !

SEN131 150 cps 210 cps i' SEN132 155 cps 215 cps i

Which ONE of the following is an expected response for these conditions? )

1 A. MCB Annunciator 57A, SR Flux Doubled, it lit '

1 i B. MCB Annunciator 65A, SR Hi Flux at S/D, is lit.

C. MCB Annunciator 77E, SR Hi Volt Fail, is lit.

D. MCB Annunciator 85E, SR Hi Flux Rx Trip, is lit.

ANSWEP.:

- B. MCB Annunciator 65A, SR Hi Flux at S/D, is lit.

K/A #: 034A3.03 RO IMPORTANCE: 2.9 KA DESCRIPTION: High Flux at S/D

)

OBJECTIVE #: E

REFERENCES:

T61.0110.6 LP 28, Page 8 AUTHOR: DGL SOURCE: New - H -

DISTRACTER EXPLANATION:

A. Flux inc;anos by 1.7 in 10 minutes.

B. 120 VDC oelow setpoint. '

C. 10s cps and not blocked.

I RO Outline #R084 I i

QUESTION # 099 Which ONE of the following describes how an operator shou!d enter into the RO logs that he secured the 'A' RCP at 0830? (The time NOW is 0950.)

A. *0830" is entered in the time column of the logs and "(Late Entry) Secured the 'A' RCP" is entered in the information column.

B. "0830" is entered in the time column of the logs and "(0950) Secured the 'A' RCP" is entered in the information column.

C. "0950" is entered in the time column of the logs and "(0830) Secured the 'A' RCP" is entered in the information column.

D. " Late Entry" is entered in the time column of the logs and "(0830) Secured the 'A' RCP" is entered in the information column.

ANSWER:

A. "0830" is entered in the time column of the logs and "(Late Entry) Secured the 'A' RCP" is entered in the information column.

KIA #: 2.1.18 RO IMPORTANCE: 2.9 KA DESCRIPTION: Narrative Log Entries OBJECTIVE #: B.1

REFERENCES:

T61.003A.6 LP A-2, Page 2 ODP-ZZ-00006, Page 2 AUTHOR: DGL SOURCE: Bank (Modified)- L DISTRACTER EXPLANATION:

When a late entry must be made, the following should be done:

1. Time the event actually happened is entered in the time column.

2. (Late Entry) The event as it happened is entered in the information column.

RO Outline #R090

L -

QUESTION # 100 L Which ONE of the following actions should be taken per EOP Rules of Usage -

when a step can NOT be performed and NO contingency action is given?

A. Transition to ES-0.0, Rediagnosis, to determine what procedure should be used.

B. Implement FRG that most closely relates to the task that could not be performed.

C. Continue on in t'he' current guideline in effect in the left-hand column.

D. Stop and consult the EDO for assistance. Do not continue in the current guideline.

ANSWER:

C. Continue on in the current guideline in effect in the left-hand column.

K/A #: 2.4.16 RO IMPORTANCE: 3.0 KA DESCRIPTION: EOP Rules of Usage OBJECTIVE #: B.4.c

REFERENCES:

T61.003D.6 LP 1, Page 40 AUTHOR: DGL SOURCE: Bank (Modified) - L DISTRACTER EXPLANATION:

A. ES-0.0 is only used to determine appropriate recovery procedures.

B. FRGs are only implemented when directed by procedure step or per CSF-1.

D. Current guideline should be continued.

RO Outline #R096 s e w-

{ SORT BY l

! RO QUESTION NUMBER l

L RO Exam RO Exam l ._ Question Outline Question Outline Number R Number Number R Number l 001 R001 051 R081 L 002 R007 052 R004 l

003 RO13 053 RO10 ;

004 R019 054 RO16 005 R025 055 R022 006 R031 056 R028 007 R037 057 R034 008 R043 058 R040 009 R049 059 R046 010 ROSS 060 R052 011 R061 061 R058 3

1 012 R073 062 R064 013 R079 063 R070 014 R085 064 R076 015 R091 065 R082 016 R097 066 R088 017 R002 067 R094 018 R008 068 R100 1 019 R014 069 R005 020 R020 070 RO11 3 021 R026 071 R017 1 022 R032 072 R023 023 R067 073 R029 024 R038 ~

074 R035 025 RO44 075 R041 026 ROSO 076 R047 027 R056 077 R053 028 ROG2 078 R059 029 R068 079 R065 030 R074 080 R071 031 R080 081 R077 i 032 R086 082 R083 033 R092 083 R089 034 R098 084 R095 035 R003 085 R006 036 R009 086 R012 037 R015 087 RO18 038 R021 088 R024 039 R027 089 R030 040 R033 090 R036 l 041 R039 091 R042 !

042 R045 092 R048 !

043 R051 093 R060 _ I 044 R057 094 R054 045 R063 095 R066 046 R069 096 R072 i

- 047 R075 097 R078 j 048 R087 098 R084 l 049 R093 099 R090 l 050 R099 100 R096 I

F- /

SORTBY j OUTLINE R NUMZER RO Exam RO Exam Outline Question Outline Question R Number Number R Number Number R001 001 R051 043 R002 017 R052 060 R003 035 R053 077 R004 052 R054 094 R005 069 R055 010 R006 085 R056 027 R007 002 R057 044 R008 018 R058 061 R009 036 R059 078 R010 053 R060 093 RO11 070 R061 011 RO12 086 R062 028 R013 003 R063 045 RO14 019 R064 062 RO15 037 R065 079 R016 054 R066 095 RO17 071 R067 023 RO18 087 R068 029 R019 004 R069 046 R020 020 R070 063 R021 038 R071 080 R022 055 R072 096 R023 072 R073 012 R024 088 R074 030 R025 005 R075 047 R026 021 R076 064 R027 039 R077 081 R028 056 R078 097 R029 073 R079 013 R030 089 R080 031 R031 006 R081 051 R032 022 R082 065 R033 040 R083 082 R034 057 R084 098 R035 074 R085 014 q R036 090 R086 032 i R037 007 R087 048 )

R038 024 R088 066 l R039 041 R089 083 R040 058 R090 099 R041 -075 R091 015 R042 091 R092 033 R043 008 R093 049 R044 025 R094 067 R045 042 R095 084 R046 059 R096 100

_- R047 076 R097 016 R048 092 R098 034 R049 009 R099 050 ROSO 026 R100 066

- )

J l I AV A%E we 6%%% \ S l

III 4

t J

CALLAWAY RO RETAKE o 4/99 REGION IV WRITTEN EXAMINATION TEST ITEM OUALITY REVIEW MATRIX

1. 2. 3. Psychometric Errors 4. Job Content Errors 5. 6.

O# LOK LOD Explanation (F/H) (1-5) Stem Cues T/F Cred Part- Job- Minu- #/ Back- U/R (See below for instructions)

Focu Dist tal Link tia units ward s !

1 F 2 U 2 H 2 U 3 H 2 U I I

4 H 2 X U indications. . provides assurance that requirements are met.

Incorporated.

l 5 H 2 U 6 H 3 U 7 H 3 U 8 H 2 X R Revise WR temp. to make question more challenging.

Ancorporated.

1 9 H 3 U )

10 F 2 X U Can main steam be deleted in Dist. C7 incorporated.

11 H 2 U 12 H 3 X U Make formatting more consistent for Choices C and D.

Incorporated.

I 13 F 1 X X X R Could Choice D be correct? SS could assume role. Choice l D could not be correct. SS cannot assume role. No change.

14 F 2 U 15 F 3 U 16 F 2 X x U Could B and D both decrease on 3 consecutive samples?

Modified Choice B for consistency.

17 H 3 U 18 F 3 U 19 F 2 U 20 H 2 U 21 H 2 R is it necessary to give rule of thumb? Deleted thumb-rule.

22 F 3 U 23 H 3 X U ROlevel? Yes. Nochange.

24 F 3 U 25 H 3 X R Why tell effect of failure in stem? Could also argue D correct.

Modified stem and Choice D.

26 F 2 U 27 H 2 U 28 H 2 U 29 F 3 X R Choice B is not credible. Modified to make credible.

30 H 2 R 31 F 2 U

. Page 1

CALLAWAY RO RETAKE - 4/99 REGION IV WRITTEN EXAMINATION TEST ITEM OUALITY REVIEW MATRIX

1. 2. 3. Psychometric Errors 4. Job Content Errors 5. 6.

O# LOK LOD Explanation (F/H) (1-5) Stem Cues T/F Cred Part- Job- Minu- #/ Back- U/R (See below for instructions)

Focu Dist tal Link tia units ward a

32 F 2 X U 33 F 2 X U Answer is partially cued by format. Modified Choice B to eliminated cue.

34 H 2 X R Could Choice B be construed as correct? Modified Choice B.

35 F 2 U 36 F 2 U 37 H 2 U 38 F 2 X R 11 is better to give indications and ask what caused it.

Incorporated.

39 H 3 X R Make it clear in Choices C and D that operators perform actions. Incorporated.

40 F 2 X R Reduce wordiness in distractors. Delete "at lower pressures."

Incorporated.

41 H 3 X U Make formatting consistent in choices. Incorporporated.

42 H 3 X X R Could applicant argue that Choice C is correct? Modified Choices C and D for consistency and to ensure C is wrong.

43 H 3 U 44 F 2 X R Choice D appears incredible by statement " capable of being aligned." No change. Words are from training manual.

45 H 3 U 46 F 2 X X R GFES. No change. Valid systems application.

47 F 2 U C8 F 3 U 49 H 3 U 50 F 2 X R Acceptable w/o reference? No change. Expected RO basic knowledge.

51 H 3 X R Why state level retums to normal in Choices C and D?

Replaced question in response to comment on Question 85.

52 H 3 X R Stem disqualifies Choice C. Modified stem and replaced Choice C.

53 H 3 U 54 F 2 X R Choices B and D are incredible. Replaced with credsble answers.

55 F 2 U 56 H 3 U 57 H 3 U 58 H 3 U 59 F 3 X R Acceptable for RO? No change. Expected RO Knowledge.

60 F 2 U Page 2

CALLAWAY RO RETAKE - 4/99 REGION IV WRITTEN EXAMINATION TEST ITEM OUALITY REVIEW MATRIX

1. 2. 3. Psychometric Errors 4. Job Content Errors 5. 6.

O# LOK LOD Explanation (F/H) (1-5) Stem Cues T/F Cred Part- Job- Minu- #/ Back- U/R (See below for instructions)

Focu Dist ial Link tia units ward a

61 F 2 U 62 F 3 R Wordychoices. Revisedformat.

63 H 2 R Same knowledge as Question 347 No change. Opposite system response.

64 H 3 U Values not needed in choices. Deleted values from choices.

65 H 3 U 66 H 2 U 67 H 2 U 68 F 2 X R Answer is only choice stating " containment purge? Changed Distractor B to include additionalpurge monitor.

69 F 2 U 70 F 2 X R Applicant only needs to know one pressure, the first one listed. Revised choices to add extra challenge.

71 F 2 X R Ouestion is quite easy. Why not test plant characteristics at BOL in that they are more unique? Incorporated.

72 F 2 U 73 F 3 U 74 F 3 U 75 F 2 U 76 F 2 U 77 H 3 U 78 H 3 U 79 F 2 X U Choice D incredible. Replaced.

80 H 3 U 81 H 2 U 82 H 3 U 83 F 2 U 84 H 2 U Change.it to is in Choice A. Correct explanation.

Incorporated.

85 H 3 R Very similar system knowledge is required to answer Questions 51,52, and 85. Review for over-emphasis. No change. ReplacedQuestion51.

86 F 2 U 87 F 2 U 88 F 2 U 89 H 2 U 90 F 2 U

. Page 3

CALLAWAY RO RETAKE - 4/99 e.- -

REGloN Iv WRITTEN EXAMINATION TEST ITEM QuAUTY REVIEW MATRlx

1. 2. 3. Psychometric Errors 4. Job Content Errors 5. 6.

Os lok lod Explanation (F/H) (1-5) stem cues T/F Cred Part- Job. Minu- #/ Back- u/R (See below for instructions)

Focu Dist tal unk tia units ward 1 s

91 H 4 U 92 F 3 X U Acceptable for Ro w/o reference? No change. Expected knowledge.

93 F 2 X R How important is this for Ro? No change. Knowledge necessary to protectpublic.

94 H 2 U 95 F 2 U 96 F 2 X U Acceptable for Ro? No change. Expected RO knowledge.

97 F 2 X U Could Choice D also be correct? Modified Choice D to make it clearly wrong.

98 F 2 U 99 F 2 U 100 H 3 X U Acceptable for Ro? No change. Expected RO knowledge.

Instructions for Completing Matrix (Complete for either all items or all items requiring comment):

1. Classify level of knowledge (LOK) as either (F)undamental or (H)lgher cognitive level.

2. Determine level of difficulty (LOD) using established 1-5 rating scale.

3. Check the appropriate box when a psychometric error is identified:

Stem is overly wordy OR lacks sufficient focus to solicit only one of the answers listed (e.g.,

unclear on intent, answer needed, or unnecessarily negatively phrased)

Stem or distractors contains item cues (i.e., clues, specific determiners, phrasing, length, etc),

Answers are a collection of unrelated true/ false statements,

One or more distractors are not credible, or

Partially correct but not complete distractors (e.g., possible if unstated assumptions not contradicted by stem are added).

4. Check the appropriate box if a job content error is identified:

Topics not linked to job content (i.e., valid K/A, required in real world from memory),

Recall'of too specific or detailed knowledge for the closed reference test mode,

Numbers with false accuracy or non-job-linked units (e.g., unnecessary accuracy or units inconsistent [ panel meter in percent, item in gallons]), and a Reverse logic or application compared to job.

5. Can the question be (U) sed as-is [ comment is for enhancement) or is (R)epair/ replacement required?

6. Provide a brief description of problem in the explanation column.

. Page 4 -

I

""# 6 c, UNITED STATES 3 % NUCLEAR REGULATORY COMMISSION 4 3 5 l j REGION IV ,

- 611 RYAN PLAZA DRIVE, sNITE 400 l

y,,. ARUNGToN. TEXAS 760118064 WAY - 31999 Garry L. Randolph, Vice President and Chief Nuclear Officer Union Electric Company P.O. Box 620 Fulton, Missouri 65251

SUBJECT:

NRC INSPECTION REPORT NO.'50-483/99-302

Dear Mr. Randolph:

This refers to the inspection conducted on April 16,1999, an operator licensing inspection was conducted at the Callaway Plant facility. The enclosed report presents the results of this inspection.

The inspection included an evaluation of an applicant for a reactor operator license. This was a licensee-authored retake written examination only that did not involve an NRC site visit. We determined that the applicant satisfied the requirements of 10 CFR Part 55, and his license has been issued.

In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter and its enclosure will be placed in the NRC Public Document Room (PDR).

Should you have any questions concerning this inspection, we will be pleased to discuss them with you.

Sincerely, GLAM John L. Pellet, Chief Operations Branch Division of Reactor Safety Docket No.: 50-483 License No.: NPF-30

Enclosure:

NRC Inspection Report No.

50-483/99-302 (g(yo-1W W l1

i Union Electric Company !

cc w/ enclosure (w/ Attachments 1 and 2):

Mr. Gary Czeschin, Superintendent Training

- P.O. Box 620 Fulton, Missouri 65251 cc w/ enclosure'(w/ Attachment 1 only):

Professional Nuclear Consulting, Inc.

19041 Raines Drive Derwood, Maryland 20855 John O'Neill, Esq. I Shaw, Pittman, Potts & Trowbridge 2300 N. Street, N.W.

Washington, D.C. 20037 i H. D. Bono, Supervising Engineer Quality Assurance Regulatory Support Union Electric Company P.O. Box 620 Fulton, Missouri 65251 Manager- Electric Department l Missouri Public Service Commission i 301 W. High )

P.O. Box 360 - l Jefferson City, Missouri 65102 Ronald A. Kucera, Deputy Director Department of Natural Resources P.O. Box 176 Jefferson City, Missouri 65102 Otto L Maynard, President and Chief Executive Officer-Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, Kansas 66839 Dan 1. Bolef, President Kay Drey, Representative Board of Directors Coalition for the Environment ,

6267 Delmar Bo'ulevard University City, Missouri 63130 t

i l

l ' Union Electric Company l Lee Fritz, Presiding Commissioner Callaway County Court House 10 East Fifth Street Fulton, Missouri 65151 Alan C. Passwater, Manager Licensing and Fuels AmerenUE One Ameren Plaza 1901 Chouteau Avenue P.O. Box 66149 St. Louis, Missouri 63166-6149 J. V. Laux, Manager Quality Assurance Union Electric Company P.O. Box 620 Fulton, Missouri 65E51

- Jerry Uhlmann, Director State Emergency Management Agency P.O. Box 116 Jefferson City, Missouri 65101 !

l l

1

l l

Union Electric Company E-Mail report to T.'Frye (TJF)

E-Mail report to D. Lange (DJL)

E-Mail report to NRR Event Tracking System (IPAS)

E-Mail report to Document Control Desk (DOCDESK) bec to DCD (IE01)(IE42) bec distrib. by RIV w/ enclosure and Attachment 1 only:

Regional Administrator Resident inspector i DRP Director DRS-PSB j DRS Director MIS System i Branch Chief (DRP/B) RIV File i Project Engineer (DRP/B) i Branch Chief (DRP/TSS) bec w/ enclosure and Attachments 1 and 2: l I

R. Gallo (HOHB/NRR)(MS:D4)

L. Hurley l 1

l l

l DOCUMENT NAME: R:\_CW\CW9302RP.HFB.WPD To receive copy of document, Indicate in bor: "C" a Copy without enclosures *E" = Copy with enclosures "N" = No copy RIV:SRE:OB E C:OB 4 AC:PBB l C:OB/v l l HFBundy/imb M JLPellet DGraves % JLPMiet 04/0/99 04/ ^/99 04/fy99 ' 04/P/99 OFFICIAL RECORD COPY

ENCLOSURE U.S. NUCLEAR REGULATORY COMMISSION REGION IV Docket No.: 50-483 License No.: NPF-30 Report No.: 50-483/99-302 Licensee: Union Electric Company Facility: Callaway Plant Location: Junction Hwy. CC and Hwy. O Fulton, Missouri Dates: ' April 16,1999 Inspectors: Howard F. Bundy, Chief Examiner, Operations Branch Approved By: John L. Pellet, Chief Operations Branch Division of Reactor Safety ATTACHMENTS:

Attachment 1: Supplemental Information Attachment 2: Final Written Examination and Answer Key g ukW ~

l

7 2-1 EXECUTIVE

SUMMARY

l- Callaway Plant l ,

NRC Inspection Report No. 50-483/99-302

-r l

l l NRC examiners evaluated the competency of a reactor operator license applicant for issuance of an operating license at the Callaway Plant. The licensee developed the retake written ,

examination using NUREG-1021, interim Revision 8, January 1997. NRC examiners reviewed, and approved the examination. The written examination was administered on April 16,1999, by facility proctors in accordance with the guidance in NUREG-1021, interim Revision 8.

Operations

' The reactor operator license applicant passed the examination (Section 04.1).

. The test material was adequate for administration as submitted (Section 05.1).

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l l l Recort Details

1. Operations 1

04 Operator Knowledge and Performance 04.1 initial Written Examination

a. Inspection Scoce 1 l

On April 16,1999, the facility licensee proctored the administration of the written j examination approved by the NRC to the individual who had reapplied for a reactor I operator license. The licensee proposed his grade for the written examinations and evaluated the results for question validity and training weaknesses. The examiner reviewed the licensee's results.

1

b. Observations and Findinas The minimum passing score was 80 percent. The applicant's score for the written examination was 91 percent. The licensee's post-administration analysis identified that the administered examination was acceptable. There were no post-examination comments or changes to the written examination recommended by the licensee or identified by examiner review of the results. The licensee and chief examiner reviewed the results for any knowledge deficiencies in common areas and concluded that there were none.

c. Conclusions The applicant passed the written examination. There were no commonalities in the questions missed.

05 Operator Training and Qualification 05.1 Initial Licensina Examination Development The facility licensee developed the initial licensing examination in accordance with guidanca provided in NUREG-1021," Operating Licensing Examination Standards,"

Interim Revision 8, dated January 1997.

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05.1.1 Examination Outline

a. Insoection Scope The facility licensee submitted the initial examination outline on February 19,1999.

L Examiners reviewed the submittal against the requirements of NUREG-1021, interim Revision 8.=

b. Observations and Findinas t

The chief examiner determined that the initial examination outline satisfied NRC requirements.

c. . Conclusions -

The licensee submitted an adequate examination outline. .

- 05.1.2 Examination Packaoe -

a. 'Insoection Scone .

The draft examination was transmitted by the licensee to the NRC on March 12,1999.

The examiners reviewed the' examination against the requirements of NUREG-1021, Interim Revision 8. The licensee submitted the completed final examination package on

- April 9,1999.

b. Observations and Findinas LThe draft written examination contained 100 questions. The draft examination was technically valid, discriminated at the proper level, and was responsive to the outline submitted by the licensee. The written examination was considered adequate for administration as submitted. The examiners developed clarification or enhancement comments on about one fourth of the questions. The licensee staff incorporated these comments promptly in an excellent manner and all proposed enhancements were' accepted by the examiners.

c. Conclusions The test material was adequate for administration as submitted by the licensee.

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l l V. Manaaement Meetinas X1 Exit Meeting Summary The chief examiner telephonically presented the inspection results to David Lantz at the i p conclusion of the inspection on April 26,1999. Mr. Lantz acknowledged the findings 1 j presented.

The licensee did not identify as proprietary any information or materials examined during this inspection.

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ATTACHMENT 1 i

SUPPLEMENTAL INFORMATION 1

l l PARTIAL LIST OF PERSONS CONTACTED Licensee D. Lantz: Operating Supervisor D. Neil, Shift Supervisor, Operations Training NRC None INSPECTION PROCEDURES USED NUREG-1021 NUREG-1021, Operating Licensing Examination Standards," Interim Revision 8, January 1997 l

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ATTACHMENT 2 l

FINALWRITTEN EXAMINATION AND ANSWER KEY I

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ATTACHMENT 2 l I

FINAL WRITTEN EXAMINATION AND ANSWER KEY l

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l ES-401 Written Examination Covtr Sheet Form ES-401-7 l _

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U. S. NUCLEAR REGULATORY COMMISSION WRITTEN EXAMINATION APPLICANT INFORMATION Name: Region: IV Date: April 16,1999 Facility / Unit: CallawayPlant/ Unit 1 License Level: RO Reactor Type: Westinghouse Start Time: Finish Time:

l Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. The passing grade requires a final grade of at least 80.00 percent.

(~'

\ Examination papers will be collected four hours after the examination stans.

l Applicant Certification ,

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

Applicant's Signature RESULTS Examination Value 100 Points l

Applicant's Score Points Percent Applicant's Grade O

Interim Rev. 8, January 1997 NUREC-iO21 l

f. ,

CALLAWAY PLANT EXAMINATION COVER SHEET EY -

TRAINING DEPARTMENT COURSE TITLE: RO INITIAL LICENSE RETAKE EXAMINATION DATE: 4/16/1999 NAME (Print): SCORING:

l SIGNATURE: Points Possible: 100 Points Missed:

l Grade:

DIRECTIONS: BLACK OUT CORRECT ANSWEPJi

1. l A l l B l El D l 26 l A l l B l E*l D l 51. l A l l B l l C l E 76. l A l l B l E l D l

2. l A l l B l E l D l 27. l A l l B l l C l E 52. l A l E l C l l D l 77. l A l E l C l l D l

' 3. l A l E j C l l D l 28. l A l l B l l C l E 53. l A l l B l l C l E 78. l A l l B l E l D l

4. l A l l B l l C l E 29. l A l l B l E l D l 54. l A l l B l l C l E 79. E l B l l C l l D l S. l A l l B l E l D l 30. l A l E l C l l D l 55. E l B l l C l l D l 80. l A l E l C l l D l

6. l A l l B l l C l E 31. E l B l W l D l 56. l A l l B l l C l E 81. l A l l B l E l D l

7. E l B l l C l l D l 32. E l B l l C l l D l 57. l A l l B l E l D j 82. E l B l l C l l D l l

8. l A l E l C l l D l 33. l A l l B l E l D l 58. l A l l B l l C l E 83. l A l E l C l l D l 1

9. l A l l B l l C l E 34. l A l E l C l l D l 59 l All B ll Cl E 84. l A l l B l E l D l

10. l A ] l B l E l D l 35. E l B l l C l % 60. l A l E l C l l D j 85. l A l E l C l l D l

11. l A l l B l E l D l 36. E l B l l C l l D j 61. l A l l B l l C l E 86. l A l l B I E l D l

12. l A l l B l l C l E 37. l A l l B l E l D l 62. E l B l l C l l D l 87. l A l M I c I l o l l 13. l A l E l C l l D l 38. l A l l B l E l D l 63. l A l l B l E l D l 88. l A l l B l l C l E

14. l A l l B l l C l E 39. E l B l l C l l D l 64. E l B l l C l l D l 89. l A l E l C l l D l

15. l A l l B l l C l E 40. E l B l l C l l D l 65. l A l l B l E l D l 90. l A l E l C l l D l

16. l A l E l C l l D l 41. l A l l B l E l D l 66. l A l l B l E l D l 91. E l B l l C l l D l

17. l A l l B l l C l E 42. l A l l B l E l D l 67. E l B l l C l l D l 92. E l B l l C l l D l

18. E l B l l C l l D l 43. E l B l l C l l D l 68. l A l l B l l C l E 93. l A l E l C l l D l

19. l A l E l C l l D l 44. E l B l l C l l D l 69. l A l l B l l C l E 94. M 18 l l c l l o l

20. l A l l B l E l D l 45. l A l E l C l l D l 70. E l B l l C l l D l 95. l A l E l C l l D l

21. l A l E l C l l D l 46. l A l l B l l C l E 71. E l 3 l l C l l D l 96. E l B l l C l l D l

22. E l B l l C l l D l 47. l A l l B l l C l E 72. l A l E l C l l D l 97. l A l l B l l C l E

23. l A l l B l E l D l 48. l A l E l C l l D l 73. l A l l B l E l D l 98. l A l E l C l ! D l

24. l A l E $ l D l 49. l A l l B l l C l E 74. l A l l B l l C l E 99. E l B l l C l l D l lAllB] E lDl 100. l A l l B l E l D l 25 50. l A l l B l E l D l 75. l A l l B l l C l E

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QUESTION # 001 t

A

' V The following plant conditions exist:

~

'. A~power Controlreduction from Bank 'D' rods are80%

at 83to 60%with steps hasthejust been completed.

exception of rod M-4.

Which ONE of the following M-4 rod positions meets the MINIMUM difference in position that would require the rods to be considered misaligned per Technical Specifications?

A. 90 steps .

B. 91 steps C, 96 steps .

DJ 97 steps ANSWER: .

C. 96 steps K/A #: 005AA1.05 RO IMPORTANCE: 3.4 KA DESCRIPTION: Misaligned Control Rod OBJECTIVE #: A

REFERENCES:

T61.0038.6 LP B-55, Page 1 OTO-SF-00004, Page 1 Technical Specification 3.1.3.1 l

AUTHOR: DGL SOURCE: New- H DISTRACTER EXPLANATION:

Technical Specification 3.1.3.1 requires rods to be within 12 steps of their group to be operable, therefore the minimum difference to be inoperable would be 13 steps (83 steps + 13 steps = 96 steps).

I RO Outline #R001 l

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l l ' QUESTION # 002 ' )

(3

k/ The following plant conditions exist:

l Reactor TRIPPED from 100% power

.- Pressurizer levelis 0%

)

i

. Containment pressure is 16 psig

. Tm is 420*F for all four loops

]

Which ONE of the following events is in progress? i

)

1 A. RCS leak on Loop 1 Cold Leg.

B. S/G Tube leakin the 'C' S/G. ~ )

I C. Main Steam Line leak from the 'B' S/G 2 feet downstream of the S/G.

D. Main Feedwater Line leak between the 'D' MF5V and the 'D' MFIV.

I ANSWER: :

'q l V C. Main Steam Line leak from the 'B' S/G 2 feet downstream of the S/G. !

K/A #: 040AK1.06 RO IMPORTANCE: 3.7 i KA DESCRIPTION: Identification of Steam Line Break ;

OBJECTIVE #: H (LP SD-4)

REFERENCES:

T61.003D.6 LP SD-4, Page 0 T61.003D.6 LP 15, Pages 6 & 7 AUTHOR: DGL SOURCE: New - H ,

DISTRACTER EXPLANATION:

A. Would NOT cause cold leg temperature to decrease to 420*F.

B. & D. Would NOT cause cold leg temperature decrease or containment pressure increase.

RO Outline #R007 r.

f. 1 1 ;

QUESTION # 003 g ~

(f Which ONE of the following best describes the organization of the Fire Brigade? I A. Fire Brigade personnel are under the control of the Safety Supervisor. !

l B. . The Fire Brigade Leader is one of the On-Shift Operating Supervisors.

C. The Fire Brigade team consists of at least six members from the operating shift who can respond to an emergency. ;

D. The Shift Supervisor assumes the role of Fire Brigade Leader if the Leader fails to report to the fire or is incapacitated.

ANSWER:

B. The Fire Brigade Leaderis one of the On-Shift Operating Supervisors.

K/A #: 067G2.4.26 - RO IMPORTANCE: 2.9 KA DESCRIPTION: Fire Brigade Organization O

(,) OBJECTIVE #: E.1

REFERENCES:

T61.003A.6 LP A-30, Page 3 i' APA-ZZ-00743 AUTHOR: DGL SOURCE: Bank (Modified)- L DISTRACTER EXPLANATION:

A. They are under control of the Fire Brigade Leader.

C. Only five members are required.

D. The Assistant Fire Brigade Leader would assume command.

RO Outline #RO13 0

p

~

QUESTION # 004

, /'s Which ONE of the following conditions will result in an automatic reactor trip while operating at 100% power?

A. 'B' S/G NR Level (%): 22(LT-527), 23(LT-528), 23(LT-529), 24(LT-552)

8. Power Range Nls (%): 107(N41 ), 108(N42), 108(N43), 109(N44)

C. Pressurizer Pressure (psig): 2375(PT-455), 2380(PT-458), 2385(PT-457), 2380(PT-458)

D. RCP Bus Frequency (Hz): 56.9( 'A'), 57.1('B'), 57.0 ('C'), 57.4('D')

ANSWER:

D. RCP Bus Frequency (Hz): 56.9( 'A'), 57.1('B'), 57.0 ('C'), 573('D')

K/A #: 007EK2.03 RO IMPORTANCE: 3.5 KA DESCRIPTION: Reactor Trip Signals OBJECTIVE #: 'D (3

V j

REFERENCES:

T61.0110.6 LP 27, Pages 24 & 25 E-0, Attachment 1 AUTHOR: DGL SOURCE: New - L DISTRACTER EXPLANATION:

A. Requires 2 of 4 less than 14.8 (Normal) or 20.2 (EAM).

B. Requires 2 of 4 greater than 109.

C. Requires 2 of 4 greater than 2385.

~

RO Outline #R019

p ,

! QUESTION # 005 1

L i (q) The following plant conditions exist: i

. Reactor Power is 90%.

ALL controls are in AUTOMATIC. l VCT Level Transmitter BGLT0149 fails HIGH.

. At the time of the VCT Level Channel failure,-actual VCT level was 50%.

Which ONE of the following describes the correct plant response? (Assume NO Operator Actions are taken.)

VCT level decreases:

A. until Auto makeup starts and maintains VCT level. l B. until charging pumps lose suction and start to cavitate. .

1 C. with NO Auto makeup capability and charging suctions swap to the RWST. I D. faster than Auto makeup input and charging suctions do not swap to the RWST.

ANSWER:

C. with NO Auto makeup capability and charging suctions swap to the RWST.

l KIA #: 022AA1.08 RO IMPORTANCE: 3.4 l KA DESCRIPTION: VCT Level Channel Failure OBJECTIVE #: F

REFERENCES:

T61.0110.6 LP 11, Page 22 AUTHOR: DGL SOURCE: New - H 4 DISTRACTER EXPLANATION:

A. Auto makeup is fed from channel BGLT0149 (failed high).

B. Suetions will swap to RWST at 5% level.

D. Auto makeup is fed from channel BGLT0149 (failed high).

RO Outline #R025 I

r l QUESTION # 006 -

LA t

FR-H.1, Response to Loss of Secondary Heat Sink, defines a HOT DRY SG as a SG with its RCS wide range Hot Leg temperature GREATER THAN (1) AND its wide range SG level LESS THAN (2) for normal containment.

! .(1) (2)

A. ' 500 F 43% -

l B. 500'F 24 %

C. 550'F 43%

l

- D. 550*F 24 %

1 L ANSWER:

D. 550 F 24 %

l K/A #: W/E05G2.4.17 RO IMPORTANCE: 3.1 KA DESCRIPTION: Hot Dry S/G Criteria OBJECTIVE #: S

REFERENCES:

.T61.003D.6 LP 26, Page 27 l

AUTHOR: DGL l SOURCE: New - L _

l DISTRACTER EXPLANATION:

i A. & B. Must be > 550*F.

C. 43% is for Adverse Containment.

RO Outline #R031 l

l l

I O !

r-QUESTION # 607 I

~ The following plant conditions exist:

. Reactor / Turbine Power is at 75% steady state.

. Rod Controlis selected to MANUAL. l l

. Auctioneered High Tave is 579.6 F.

Which ONE of the following will be the initial rod speed if rod control is placed in AUTOMATIC? ;

1 A. _8 steps / minute i i

B. 32 steps / minute C. 48 steps / minute ,

D. 72 steps / minute l

ANSWER:

A. 8 steps / minute KIA #: 001K4.14 RO IMPORTANCE: 2.6 KA DESCRIPTION: Determine Rod Speed OBJECTIVr; p. C i REFERE'dCES: T61.0110.6 LP 26, Pages 16-19 CMP 98-1038A, Reduced Tave Modification j AUTHOR: DGL SOURCE: New - H .

DISTRACTER EXPLANATION:

75% power equates to a Tref of 577.6'F. Tave is 2*F higher than program. Rod speed is 8 steps / minute with a temperature error between 1.5'F - 3*F.

RO Outline #R037

(./

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ps I

~

i l QUESTION # 008

['

D) A plant heatup is in progress.- ~ l l

The following plant conditions exist at 0700:

. RCS pressure is 1780 psig.

. . RCS temperature is 480*F.'

. . _ S/G pressures are 565 psig.

The following plant conditions exist at 0730:

]

. RCS pressure is.1880 psig.

.- RCS temperature is 484'F;

. S/G pressures are 588 psig.

Which ONE of the following is the FIRST plant response if the curr,ent trends continue?

' (Assume NO operator actions are taken.) i l

l A. Pzr PORVs OPEN. )

i B. MSIVs CLOSE. l j

'&g . C. Pzr Sprays CLOSE. !

D. S/G PORVs OPEN.

ANSWER:

B.- MSIVs CLOSE. ;

K/A #: 013A1.01 RO IMPORTANCE: 4.0 KA DESCRIPTION: Monitor Tren'ds for MSLIS OBJECTIVE #: E&G

REFERENCES:

T61.0110.6 LP 27, Pages 38 & 44 <

l AUTHOR: DGL SOURCE: New - H DISTRACTER EXPLANATION: '

A. Pzr PORVs won't open until 2335 psig. At 1970 psig, a SLIS will occur.

C. As pressure is increased, Pzr Sprays won't close. '

i D. S/G PORVs won't open until 1125 psig. SLIS will occur while S/G pressures sre still < 615 psig.

RO Outline #R043 .

L

~

QUESTION # 009 !

m i 's V~ The following piant conditions exist

. Reactor Power is 100%.

. NE02, 'B' Emergency DG, is out of service for maintenance.

. All contain,aent cooler fans are running in selected speed (FAST). !

Which ONE of the following is the correct status of Containment Cooler Fans one minute after j the plant undergoes a reactor trip, safety injection, and a trip of the NB02 normal feed breaker?

i

' A. All four fans are running in FAST speed. q B. All four fans are running in SLOW speed.

C. 'A' and 'C' fans are running in FAST speed, 'B' and 'D' fans are OFF. 1 D. 'A' and 'C' fans are running in SLOW speed, 'B' and 'D' fans are OFF.

ANSWER: ;

). D. 'A' and 'C' fans are running in SLOW speed, 'B' and 'D' fans are OFF.

l K/A #: 022A3.01 RO IMPORTANCE: 4.1 i KA DESCRIPTION: LOCA Sequencer Operation OBJECTIVE #: F ~'

REFERENCES:

T61.0110.6 LP 51, Page 7 AUTHOR: DGL SOURCE: New - H DISTRACTER EXPLANATION:

A & B. 'B' and 'D' fans have no power.

C. 'A' and 'C' fans will be running in slow speed. )

RO Outline #R049 i

f) '.

V

~

) ,

o QUESTION # 010 l O

V During Mode 1 at 100% power with all systems in their normal alignment, which ONE of the following is a source of water to the Containment Normal Sumps?

l A. Leakoff from the Reactor Vessel Flange.

1 B. Leakoff from the #2 seals on RCPs.

C. Leakoff from the #3 seals on RCPs.

D. Leakoff from Letdown Hx Valve Compartment.

ANSWER:

~

C. Leakoff from the #3 seals on RCPs.

K/A #: 068K1.07 RO IMPORTANCE: 2.7 KA DESCRIPTION: CTMT Normal Sump inputs -

OBJECTIVE #: G

[]

%d

REFERENCES:

- T61.0110.6 LP 9, Pages 20 & 26 AUTHOR: DGL SOURCE: New - L DISTRACTER EXPLANATION:

A. Goes to the RCDT.

B, Goes to the RCDT.

D. Goes to Aux Bldg (CRW) sumps. ,-

l

+.n, l RO Outline #R055 O

i

QUESTION # 011 O To meet the 10CFR50.46 design criteria, the ECCS system is designed such th'at under a'ccident conditions it will maintain:

A. total hydrogen production from zirconium-water reaction below maximum value of 5%.

B. maximum fuel temperature at the inside surface of the cladding not exceeding 2000*F.

C. fuel clad oxidation less than 17% of total clad thickness anywhere within the core.

D. the core at least 5% dK/K shutdown to prevent an inadvertent return to criticality.

ANSWER:

~ ~

C. fuel clad oxidation less than 17% of total clad thickness anywhere within the core.

K/A #: 006K3.02 RO IMPORTANCE: 4.3 KA DESCRIPTION: Design Criteria To Protect Fuel OBJECTIVE #: B

[

REFERENCES:

T61.0110.6 LP 56, Page 4 AUTHOR: DGL SOURCE: New - H DISTRACTER EXPLANATION:

A. Hydrogen limit is 1%.

B. Clad temperature limit is 2200*F.

D. Design criteria does not address core reactivity.

RO Outline #R061

~

- QUESTION # 012 _

,m

~

The following plant conditions exist:

. Mode 3,557 F,2235 psig.

. NB01 Normal Feeder Breaker is tripped.

. NB02 Normal Feeder Breaker is closed.

. NB01 Bus Voltage is 0 volts.

. NB02 Bus Voltage is 4160 volts.

. NB01 Bus Lockout Annunciator 18A is lit.

Which ONE of the following sets of equipment are de-energized?

A. 'A' ESW Pump, NK22 Charger, and XNN05 Transformer B. - A' MDAFW Pump, 'A' CCW Pump, and XNN06 Transformer ,

C. 'A' CCW Pump, NK26 Charger, and 'A' Class 1E A/C D.- 'C' CCW Pump, NK23 Charger, and 'A' ESW Pump n

Q ANSWER:

D. 'C' CCW Pump, NK23 Charger, and 'A' ESW Pump KlA #: 062K2.01 RO IMPORTANCE: 3.3 KA DESCRIPTION: Major System Loads OBJECTIVE #: A&I -

REFERENCES:

T61.0110.6 LP 6, Pages 4 & 8

' AUTHOR: DGL SOURCE: New - H DISTRACTER EXPLANATION:

A. NK22 is still energized.

B. ' XNN06 is still energized. l C. NK26 is still energized. l l

RO Outline #R073 1

n !

U l

I

~ QUESTION # 013 O

O A fire alarm is received on KC008 panel. When the operator acknowledges the alarm on KC008, the Electric Fire Pump is discovered to be nanning.

- Which ONE of the following could have caused the Electric Fire Pump to start?

l A. 'A' Diesel Fire Pump failed to start.

B. Fire System pressure decreased to s 130 psig.

C. 'B' Diesel Fire Pump battery charger failed.

D. 'A' Diesel Fire Pump battery charger failed.

ANSWER: -

i B. Fire System pressure decreased to s 130 psig.

KIA #: 086A3.01 RO IMPORTANCE: 2.9 KA DESCRIPTION: Fire Pump Auto Starts OBJECTIVE #: C

REFERENCES:

T61.0110.6 LP 35, Pages 37 & 38 AUTHOR: DGL ;

SOURCE: New - L DISTRACTER EXPLANATION:

A. Causes 'B' Diesel Fire Pump to start.

C. Causes 'B' Diesel Fire Pump to start.

D. Causes alarm only, no fire pump starts.

RO Outline #R079 O

QUESTION # 014 O

g. .

The following plant conditions exist:

. l Mode 3 with shutdown banks withdrawn.

. RCS Temperature - 557'F.

. RCS Pressure-2235 psig.

. Steam Dumps in Steam Pressure Mode.

. S/G Levels being maintained by the Startup Feed Pump.

Steam Header Pressure Transmitter, ABPT0507, fails to 1400 psig over a 5 minute period.

Which ONE of the following describes the response for this failure?

A. - Startup feed pump flow goes to zero due to SLIS.

B. An SIS will occur when steam line pressures reach 615 psig.

C. A reactor trip will occur due to low pressurizer pressure.-

D. Steam dump valves will maintain RCS Tave at 550'F.

O ANSWER:

D. Steam dump valves will maintain RCS Tave at 550*F.

K/A #: 041 K4.09 RO IMPORTANCE: 3.0 KA DESCRIPTION: Steam Header Pressure Channel Failure OBJECTIVE #: J&K

REFERENCES:

T61.0110.6 LP 20, Pages 35-37 AUTHOR: DGL SOURCE: Bank (Modified)- H DISTRACTER EXPLANATION:

Steam dumps will gradually open and cooldown the PCS to 550*F. At 550*F (P-12 setpoint) the dumps will close.' Steam dumps will then cycle as necega,y a maintain RCS Tave at 550*F.

RO Outline #R085 O

.U t=.

~

QUESTION # 015 im T.he following plant conditions exist:

. Mode 1 at 100% power.

. QPTR results:

N41 N42 N43 N44 Upper Power Tilt Ratio 1.01 1.01 0.97 1.04 Lower Power Tilt Ratio 1.01 1.01 0.98 1.03 Which ONE of the following could have caused these QPTR results? (Refer to Curve Book Figure 8-7 on the following page.)

A. RCS boron concentration was decreased by 20 ppm.

B. RCS temperature was decreased 3*F by boration. -

C. Control Bank 'D' rod H-8 has dropped to zero steps.

D. Control Bank 'D' rod D-4 is misaligned from its group.

O lg ANSWER:

l D. Control Bank 'D' rod D-4 is misaligned from its group.

K/A #: 2.2.12 RO IMPORTANCE: 3.0 ;

KA DESCRIPTION: Quadrant Power Tilt Ratio I OBJECTIVE #: A

REFERENCES:

T61.0038.6 LP B-55, Page 1 OTO-SF-00004, Page 1 AUTHOR: DGL SOURCE: New - H DISTRACTER EXPLANATION:

A. & B. Would affect Axial Power Distribution, NOT Radial Power Distribution.

C. Appears as a uniforrn poison in center of the core, would NOT cause a Radial Power Tilt.

RO Outline #R091

i QUESTION # 015 (continued) _

rIGURE 8-7 Rev. 000 '

RCS LOOP ORIENTATION WITH CONTROL R00 AND O

N.)

EXCORE NEUTRON DETECTOR LOCATIONS ;

2 eust 7 NORTH nas (v,,. )

u n %-er) 4 nu o au a - a = ' " ' "***

uso i ."e '

I ___

= e. @ @ kD' G cu

" E E 6

= @

s4 g @ [ @- G

. g @

=

7 @

@ 0 @ @ @' E O ne S

~, .o u ,.< g g

@ @i -@

to n g f 6

g 0 @i '@

a @ l a O T @ @ ce cu ,. ,g @ @ @ Gi is ,

Out

,,9 l

au as hecur) e, u .)

=,3..g :g

= 00, :"t: _-.2=_

""". - se sm.J

_ ". - ' ' ~ _

} Q_WJ

- - * - 9 . _ _ _ _ _ _ _ _ .__

n

.r. _f_ M,,x,,, _w f N)Y$

superinpftient,~ Engineering

/ 3 -30Nnf6 Date RO Outline #R091

l 1

l QUESTION # 016 Which ONE of the following definitions best defines the word TRY, as it is used in the emergency operatino procedures?

A. Make a one time effort to perform an evolution, then continue procedure.

B. To make a continued effort when success may not be immediately obtainable.

C. Do not continue procedure until the effort has been successful. 1 D. Effort only needs to be performed at the discretion of the Reactor Operator.

ANSWER:

B. To make a continued effort when success may not be immediately obtainable.

KIA #: 2.4.17 RO IMPORTANCE: 3.1 KA DESCRIPTION: EOP Definitions OBJECTIVE #: A.1.L.4

REFERENCES:

T61.003D.6 LP 1, Page 37 d AUTHOR: DGL

~

SOURCE: Bank (Modified) - L DISTRACTER EXPLANATION:

B. Only correct definition per Emergency Response Guidelines.

RO Outline #R097 l

l#

r l

QUESTlON # 017-O V The plant is operating at 40% power and it is necessary to secure the 'A' Reactor Coolant Pump l

(RCP) due to a pump seal failure. After the'RCP is tripped, the 'A' Loop AT (1) and the other Loop ATs (2) . (Assume unit load is held constant.)

(1) (2)

A. increases decrease ,

B. increases increase C. decreases decrease D. decreases increase ANSWER:

D. decreases increase K/A #: 015/017AK1.04 RO IMPORTANCE: 2.9 >

KA DESCRIPTION: Unbalanced RCS Flows (IPE/PRA)

OBJECTIVE #: A

REFERENCES:

T61.0038.6 LP SB-6, Page 5 AUTHOR: DGL SOURCE: Bank (Modified)- H DISTRACTER EXPLANATION:

When stopping an RCP at power, the steam flow in the associated loop will decrease and the steam flows in the remaining 3 loops will increase equally. Loop AT's will follow the changes in steam flows.

RO Outline #R002 l

l l

-l l

I.

L'

1 l

' QUESTION # 018 !

~ Given the following conditions:

O .

.' RCS Wide Range Pressure is 690 psig 1

. RCS WR Hot Leg Temperatures are 280 F

- . RCS WR _ Cold Leg Temperatures are 260 F. '

l . Core Exit Thermocouple Temperatures are 275'F Using Curve Book Figure 14.3 on the following page, determine the expected position for each Pressurizer PORV. (Assume both Pressurizer PORVs are ARMED for Cold Overpressure

~ Protection )

. A. BBPCV0455A Open; BBPCV0456A Closed B. BBPCV0455A Open; BBPCV0456A Open C. BBPCV0455A Closed; BBPCV0456A Closed .

l D. BBPCV0455A Closed; BBPCV0456A Open ANSWER:

- ' A. BBPCV0455A Open; BBPCV0456A Closed ,

KIA #: E09EK2.1 ' RO IMPORTANCE: 3.4 KA DESCRIPTION: Cold Overpressure Protection System OBJECTIVE #: 'G

REFERENCES:

T61.0110.6 LP 30, Pages 10 Curve Book Figure 14.3, Rev.1 AUTHOR: DGL SOURCE: New - .H DISTRACTER EXPLANATION:

B. For T. of 260'F, BBPCV0456A won't open until 710 psig.

C. For T. of 200*F, BBPCV0455A will open at 664 psig.

l D. For T. of 260'F, BBPCV0455A will open at 664 psig and BBPCV0456A won't open until 710 psig.

RO Outline #R008

[

F QUESTION.# 018 (continue 4 F'IGURE 14.3, Rev.1 -

/3 .

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~

RCS COLD OVERPRESSURE CURVES

( .;

e ACCEPTABLE REGION IS BELOW THE CURVE 2900 g j j } l } } } l l l l l }

WR Cold og F CV-455 A FCV 456A 1 '

T emp. (~i) Sacyoinc (p g) Sacy aint (p sig) l l 6C 4 71 50t l

6 4 71 1 50t ,

9 l

N00 '

L70 505 535 l p 57.0 550 l

200 m = = l / i f

270 700 750 a = m l l l g ?

' = := , I / I l

, I I i 1 /

- I i l i i a (',

i m I I I I

Il i

e, pV L-l l[

'4 8 I I I Il l /& , a, m I I I I I Il l T5:i e' E a -

1 I I I I I J l 'i!I si J 1 I I IJ @, # /

I I I I ll I % 9 e /

S I

I I l

I le- + -- H ht l I I ll I I I

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IT f' I l $1' l l I I l ~l l I i- 1 L u ._e d- F r I i I I i ! l ! I I I ,

400 TTjl ~l i I I I I I I ! i il I l l 100 200 300 400 500 j WR COLD LEG TEMPERATURE (F)

--CI-PCV-455A SETPT

--o -PCV-456A SETPT f

i RO Outline #R008 4 e hf?S_. i

11 l

l

' QUESTION # 019 1 Which ONE of the following sets of indications are available on the Auxiliary Shutdown Panel? :

i A;- Emergency Borate Flow, S/G Pressure, Pzr Level.

B.~ Pzr Pressure, SIG Pressure, RCS Cold Leg Temp.-

C. CST Level, S/G Level, Containment Pressure. l l

D. RCS Pressure, RCS Hot Leg Temp, Charging Flow.

ANSWER: j B. Pzr Pressure, S/G Pressure, RCS Cold Leg Temp. . .-

K/A #: 068AA1.12 RO IMPORTANCE: 4.4 KA DESCRIPTION: Aux S/D Panel Indicators , ;

8 OBJECTIVE #: B ;

REFERENCES:

T61.0110.6 LP 48, Page 1-AUTHOR: DGL SOURCE: New - L !

1 DISTRACTER EXPLANATION: !

H A. Emergency Borate Flow not available.

C. - Containment Pressure not available. ,

D. Charging Flow not available. I i

RO Outline #R014 I

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O. !

I

- QUESTION # 020

^ (^'y The following plant conditions exist:

. Mode 1 at 100% power.

. PRT pressure is 5 psig.

Which ONE of the following describes the condition of the steam entering the PRT if a Pzr PORV opens?

A. Superheated stea'm at 659"F. , )

B. ~' Superheated steam at 653*F.

C. Saturated steam-water mixture at 228*F. -

D. Saturated steam-water mixture at 162'F.

ANSWER- '

e~

l

. C. Saturated steam-water mixture at 228*F. j I

K/A #: 008AK1.01 RO IMPORTANCE: 3.2 KA DESCRIPTION: PORV Relieving To PRT OBJECTIVE #: C

REFERENCES:

T61.0070.6 LP 13, Page 33 Steam Tables

. AUTHOR: DGL .

SOURCE: New - H DISTRACTER EXPLANATION:

C. Only correct answer using Steam Tables and Mollier Diagram.

4 RO Outline #R020 1

z.

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QUESTION # 021 O

O Which ONE of the following is the preferred method of immediate Boration per FR-S.1, Response To Nuclear Power Generation, if BGHV8104 (Emergency Borate Valve) will NOT open?

A. Alternate immediate Borate through BGV0177. ;

j

8. From the RWST via BNLCV0112D a'n'd BNLCV0112E. ,

C. Manual Safety injection initiation.

D. Injection from the St Accumulators. !

I ANSWER: _

B. From the RWST via BNLCV0112D and BNLCV0112E.

KIA #: 029EK3.11 RO IMPORTANCE: 4.2 KA DESCRIPTION: Initiating Immediate Boration m

i OBJECTIVE #: -U '

REFERENCES:

T61.003D.6 LP 29, Page 3 I FR-S.1, Attachment 1 AUTHOR: DGL SOURCE: New - L DISTRACTER EXPLANATION: j A. Second in order of preference.

C. & D. Third in order of preference.

RO Outline #R026 l

[ 1 QUE5 TION # 022 D

An earthquake has caused a Loss of All AC Power. NK12 battery discharge amps are at 200 amps.

-Which ONE of the following is the MAXIMUM time that NK12 could supply NK02 bus? (Assume NK12 was fully charged at the time of the earthquake.)

A. 4.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months B. 6.0 hours0 days 0 hours 0 weeks 0 months -i C. 7.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months D. 9.0 hours0 days 0 hours 0 weeks 0 months ANSWER: ._

A. 4.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months

f. K/A #: 058AA1.03 RO IMPORTANCE: 3.1 _

KA DESCRIPTION: Monitor Battery Capacity (IPE/PRA)

OBJECTIVE #: 1

REFERENCES:

T61.0070.6 LP 17, Page 48 T61.0110.6 LP 6, Page 13 AUTHOR: DGL _

SOURCE: New - H DISTRACTER EXPLANATION:

NK12 is rated at 900 Amp Hours.

Capacity = Rating + Discharge Rate = 900 AH + 250 A = 4.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months RO Outline #R032 i

I l

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a QUESTION # 023 The following plant conditions exist:

. Si has' occurred due to a LOCA in containment.

I

. NB02 normal feeder breaker opened causing a loss of power on NB02.

. NB01 has remained energized from its normal feeder breaker.

. The SI signal has been RESET.

At the SAME TIME that NB02 is energized from NE02 Emergency DG,'a Containment Spray (CS) Actuation Signal was generated.

Which ONE of the following combinations states the times at which the CS pumps will start?

_ (Assume all interlocks are met.) .

'A' CS Pumo 'B' CS Pumo

^

A. ' -Immediately immediately B .- Immediately 15 seconds C. 15 seconds 15 seconds

.D. '15 seconds 40 seconds ANSWER:

C.15 seconds 15 seconds K/A #: 026A3.01 RO IMPORTANCE: 4.3 KA DESCRIPTION: Spray Pump Auto Starts OBJECTIVE #: D&F

REFERENCES:

T61.0110.6 LP 51, Pages 7,12, & 13 AUTHOR: DGL SOURCE: Bank (Modified)- H -

DISTRACTER EXPLANATION:

SI signal had been reset, so CSAS started both sequencers again and both CS pumps will start at 15 seconds.

RO Outline #R067

s QUESTION #024 A Rod Control failure has resulted in a group of rods being "locke'd " by energizing both the stationary and moveable gripper coils.

Which ONE of the following failures could be the cause?

A. One of the instrumentation power supplies in a power cabinet has failed.

B. A regulation failure has occurred in one of the power cabinets.

C. A pulser failure has occurred in the logic cabinet.

D. One of the DC power supplies in the logic cabinet has failed.

. ANSWER: -

B. A regulation failure has occurred in one of the power cabinets.

K/A #: 001A2.14 RO IMPORTANCE: 3.7 KA DESCRIPTION: Power Cabinet Urgent Failure OBJECTIVE #: M

REFERENCES:

T61.0110.6 LP 26, Page 39 AUTHOR: DGL SOURCE: New - H DISTRACTER EXPLANATION:

A. Only causes a non-urgent failure.

C. Causes the pulsers to stop D. Only causes a non-urgent failure. .

RO Outline #R038 O

l ~ QUESTION # 025 -

O Which ONE of the following describes a components status when the associate'd ESFAS Status Panel component window is AMBER following an actuation?

A. The component is in its correct safeguards position.

B. The component did NOT receive an actuation signal.

C. The component is potentially prevented from performing its safeguards function.

D. The component is NOT in its safeguards position, but is capable of being aligned.

ANSWER:

^

C. The component is potentially prevented from performing .its safeguards function.

K/A #: 013A4.01 RO IMPORTANCE: 4.5 KA DESCRIPTION: Monitor Failed ESFAS Equipment OBJECTIVE #: E.2

REFERENCES:

TB1.0110.6 LP 52, Pages 31 & 32 AUTHOR: DGL

]

SOURCE: New - L DISTRACTER EXPLANATION:

A. Window would be white.

B.' Window would be dark.

D. Window would be dark.

RO Outline #R044 l

1 l

l O !

QUESTION # 026

,o

)

Which ONE of the following is the minimum volume of contained water for the Condensate Storage Tank (CST) to be considered OPERABLE per Technical Specifications in Mode 27 A. 55,416 gallons B. 80,400 gallons C. 281,000 gallons D. 394,000 gallons ANSWER:

C. 281,000 gallons K/A #: 056G2.2.22 RO IMPORTANCE: 3.4 KA DESCRIPTION: CST Operability

, OBJECTIVE #: J

REFERENCES:

T61.0110.6 LP 22, Page 33 AUTHOR: DGL SOURCE: New - L DISTRACTER EXPLANATION:

A. & B. & D. Common misconceptions for other Tech Spec Tank Levels.

RO Outline #R050 4

l O

$v) 4 1

I

, QUESTION # 027 U ~

4 Which ONE of the following signals will AUTOMATICALLY isolate the discharge flowpath from I the DMTs by closing the Liquid Radwaste Discharge Valve, HBFV0866?

A. Service Water Radiation Monitor HiHi i

B. Low liquid radwaste discharge flow rate C. High liquid radwaste discharge flow rate D. Low dilution water' flow rate ANSWER:

D. Low dilution water flow rate K/A #: 068A4.04 RO IMPORTANCE: 3.8 KA DESCRIPTION: RW Discharge Auto isolation rg OBJECTIVE #: F Qi

REFERENCES:

T61.0110.6 LP 16, Pages 51 & 52 AUTHOR: DGL SOURCE: Bank (Modified)- L DISTRACTER EXPLANATION.

HBRE18 and Low Dilution water flow rate are the only two signals that will AUTOMATICALLY close the Liquid Radwaste discharge valve.

RO Outline #ROSS n

QUESTION # 028

~

l (

l V What are the parameters and values used by an operator to ensure the tempe'rature difference between the PZR and the Spray Fluid are within the specified limit (s) in the Technical Specifications when initiating PZR Spray?

Spray Source AT Limit Parameters Monitored To Satisfy AT Limit A. Normal Spray 275 F RCS hot leg loop temperature and PZR vapor space temperature.

Aux Spray 583 F Regen HX charging inlet temperature and PZR vapor space temperature.

B. Normal Spray 275'F RCS cold leg loop temperature and PZR vapor space temperature. ;

Aux Spray 320 F Regen HX charging outlet temperature and PZR vapor space temperature.

i C. Normal Spray 320 F RCS hot leg loop temperature and PZR vapor space temperature.

Aux Spray 583*F Regen HX charging inlet temperature and PZR vapor space temperature.

D. Normal Spray 320*F RCS cold leg loop temperature and PZR vapor space temperature. l Aux Spray 320 F Regen HX charging outlet temperature and PZR vapor space temperature.

(3

() 1 ANSWER:

1 D. Normal Spray 320 F RCS cold leg loop temperature and PZR vapor space temperature.

Aux Spray 320 F Regen HX charging outlet temperature and PZR vapor space temperature.

I K/A #: 010A1.08 RO IMPORTANCE: 3.2 KA DESCRIPTION: Spray Nozzle AT Limits OBJECTIVE #: C.7 (LP 9), C (LP A-16)

REFERENCES:

T61.0110.6 LP 9, Pages 44 & 47 T61.003A.6 LP A-16, Page 3 OTN-BB-00005, Pages 1 & 5 AUTHOR: DGL SOURCE: New - H DISTRACTER EXPLANATION:

A. Normal spray limit is 320 F and supplied from cold leg, aux spray supplied from Regen Hx outlet.

B. Normal spray limit is 320 F.

C. Normal spray supplied from cold legs and aux spray from Regen Hx outlet.

b,o RO Outline #R062 l

L m

V .

QUESTION # 029 A containment purge is in progress when a Containment Purge isolation Signal (CPIS) is received.

Which ONE of the following is the cause of the CPIS7 A. Hi (Yellow) alarm on GT-RE-21 A, CTMT Bldg Unit Vent Monitor.

B. Hi (Yellow) alarm on GT-RE-22, CTMT Purge Exhaust Monitor.

C. Hi Hi (Red) alarm on GT-RE-33, CTMT Purge Exhaust Monitor.

D. Hi Hi(Red) alarm on GT-RE-59, CTMT High Range Rad Monitor.

ANSWER: -

' C. Hi Hi (Red) alarm on GT-RE-33, CTMT Purge Exhaust Monitor.

K!A #: 029K4.03 RO IMPORTANCE: 3.2 KA DESCRIPTION: CTMT Purge Isolation OBJECTIVE #: B.2

REFERENCES:

T61.0110.6 LP 52, Page 7 AUTHOR: DGL SOURCE: New - L DISTRACTER EXPLANATION: l GT-RE-22 and GT-RE-33 are the only two radiation monitors that provide an input to CPIS. Must receive the Hi Hi (Red) alarm to cause actuation.

1 RO Outline #R068

/~m

QUESTION # 030 -

O ; Which ONE of the following Class 1E 125 VDC Electrical System lineups can be performed to

' comply with Mode 1 Technical Specification LCO for D.C. Sources?

A. Load Center NG01 to Swing Charger NK25 to Bus NK04 B. Load Center NG04 to Swing Charger NK26 to Bus NK02 C. Load Center NG01' to Swing Charger NK26 to Bus NK03 D. Load Center NG04'to Swing Charger NK25 to Bus NK01 ANSWER:

B. Load Center NG04 to Swing Charger NK26 to Bus NK02 K/A #: 063K1.03 RO IMPORTANCE: 2.9 KA DESCRIPTION: NK System Lineup OBJECTIVE #:. A&G

REFERENCES:

' T61.0110.6 LP 6, Pages 4 & 25 1 AUTHOR: DGL SOURCE: Bank (Modified)- L -

DISTRACTER EXPLANATION:

A. Can only feed NK01 or NK03.

C. Can only feed NK25 Swing Charger.

D.- Can only be fed from NG01.

RO Outline #R074 l

O

p 1 s - QUESTION # 031 l The following plant conditions exist:

. Reactor has been shutdown for 38 hours4.398148e-4 days 0.0106 hours 6.283069e-5 weeks 1.4459e-5 months .

. Mode 4 cooling down per OTG-ZZ-00006.

. RCS temperature is 340*F. ]

l . RCS pressure is 350 psig. i l . Pzr level is 33%.

. 'A' RHR Train is operating in the cooldown lineup.

. EJFCV618, 'A' RHR Hx Bypass FCV, is in MANUAL at 3500 gpm.

. EJHCV606, 'A' RHRs Hx FCV, controller demand is at 20%. j

. BGHCV128, RHR Letdown FCV, demand is at 100%. '

. BGPCV131, CVCS Letdown Hx Outlet PCV, is in AUTOMATIC at 350 psig.

A controller failure causes EJHCV606 to go CLOSED.

Which ONE of the following is the system response to this failure? (Assume NO operator action is taken.)

A. RCS pressure will increase due to the RCS heatup.

O

\J B. E'JFCV610, 'A' RHR Miniflow Valve will throttle open due to low flow.

C. Pressurizer level will increase due to decreased letdown flow. ]

D. BGPCV131 will throttle closed due to the decrease in RHR flow.

ANSWER:

A. RCS pressure willincrease due to the RCS heatup.

l KIA #: 005K4.10 RO IMPORTANCE: 3.1 KA DESCRIPTION: RHR Flow Control OBJECTIVE #: B.6

REFERENCES:

T61.0110.6 LP 7, Pages 6,15, & 16 1 AUTHOR: DGL SOURCE: New - H DISTRACTER EXPLANATION:

B. EJFCV610 will remain closed due to the 3500 gpm of RHR Hx Bypass Flow.

C. Pzr level will increase as the RCS ' heats up.

( )-

D.' More flow is forced through RHR letdown line which may cause BGPCV131 to open.

RO Outline #R080 j i

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QUESTION # 032

(~

\

Which ONE of the following is correct concerning the operation.of the Main Turbine Generator Trip System? ,

A. 24 VDC supplies the Electrical Trip Solenoid. This solenoid is de-energized to trip the ,

system.

B. 125 VDC supplies the Electrical Trip Solenoid. This solenoid is energized to trip the system.

C. 24 VDC supplies the Mechanical Trip Solenoid. This solenoid is energized to trip the system.

D. 125 VDC supplies the Mechanical Trip Solenoid. This solenoid is de-energized to trip the system. , l ANSWER:

A. 24 VDC supplies the Electrical Trip Solenoid. This solenoid is de-energized to trip the system.

K/A #: 045A3.04 RO IMPORTANCE: 3.4 _._

KA DESCRIPTION: T/G Trip System OBJECTIVE #: L

REFERENCES:

T61.0110.6 LP 38, Pages 51 & 52

)

AUTHOR: DGL SOURCE: New - L DISTRACTER EXPLANATION:

B. Describes the MechanicalTrip Solenoid. l C. Supplied by 125 VDC. l D. Energized to trip.

RO Outline #R086 i

. o

QUESTION # 033 Which ONE of the following Boric Acid Tank (BAT) conditions meets the operability requirements for the BATS in Modes 1 - 47 A. 17,000 gallons volume, boron concentration of 7200 ppm, and a water temperature of 64*F.

B. 17,700 gallons volume, boron concentration of 7300 ppm, and a water temperature of 64*F.

C. 18,000 gallons volume, boron concentration of_7500 ppm, and a water temperature of 68'F.

D. 18,700 gallons volume, boron' concentration of 7800 ppm, and a water temperature

~

of 68'F.

ANSWER:

C .18,000 gallons volume, boron concentration of 7500 ppm, and a water temperature of 68'F.

O K/A #: 2.2.22 RO IMPORTANCE: 3.4 KA DESCRIPTION: BAT Operability Requirements OBJECTIVE #: O

REFERENCES:

T61.0110.6 LP 11, Page 67 FSAR 16.1.2.6 AUTHOR: DGL SOURCE: New - L .

DISTRACTER EXPLANATION:

A. Volume is low and temperature is low.

B. Temperature is low.

D. Boron concentration is high.

RO Outline #R092 i

O

QUESTION # 034

( )

Which ONE of the following is the BASIS for isolating all feedwater to a faulted steam generator?

l A. To reduce the probability of occurrence of a steam generator tube rupture in the faulted steam generator.

B. To minimize RCS cooldown and mass energy release following a steam line break.

C. To prevent all feedwater flow from entering the faulted steam generator and filling the generator, causing' the PORV's to lift.

D. To ensure the release to the environment remains below the 10CFR100 limits on a design basis event.

ANSWER:

B. To minimize RCS cooldown and mass energy reiesse following a steam line break. j l

('; K/A #: 2.4.18 RO IMPORTANCE: 2.7 ;

't) KA DESCRIPTION: EOP Bases !

OBJECTIVE #: G I

REFERENCES:

T61.003D.6 LP 15, Page 20 ;

1 AUTHOR: DGL SOURCE: Bank - L DISTRACTER EXPLANATION:

A. Only thermal shock from feed flow would cause SGTR.

C. Faulted S/G would continue to steam off and decrease pressure.

D. No rad release from faulted S/G unless ruptured also.

RO Outline #R098 (3

V

r p QUESTION # 035 V

The following plant conditions exist

. A natural circulation cooldown is in progress per ES-0.2, Natural Circulation Cooldown.

. Pressurizer pressure is being controlled using Auxiliary Spray and Pressurizer Heaters.

. As pressure is being lowered through 1300 psig, a rapid increase in Pressurizer Level is noted.

. Charging and letdown are in manual and are balanced.

Which ONE of the following actions are required to be taken by the operators?

A. Repressurize the RCS.

B. Isolate the Si Accumulators.

l C. Establish excess letdown.

D. Increase the RCS cooldown rate.

tm. ' ,

U ANSWER:

A. Repressurize the RCS.

K/A #: W/E09EK3.1 RO IMPORTANCE: 3.3 KA DESCRIPTION: Natural Circulation Conditions / Limitations OBJECTIVE #: E

REFERENCES:

T61.003D.6 LP SD-3, Page 15 ES-0.2, Natural Circulation Cooldown, Page 13 AUTHOR: DGL SOURCE: New - H DISTRACTER EXPLANATION:

Per ES-0.2, if abnormal RCS conditions such as large variations in pressurizer level occur, a steam void may be present in the vessel head. To collapse the void, the RCS is repressurized.

RO Outline #R003 i :

(,r'

QUESTION # 036 A loss of condenser vacuum is occurring due to unknown reasons and power has been reduced from 100% to 75% over the last 4 minutes.

The following plant conditions exist:

. Auctioneered HIGH Tave is 590 F

. Reactor / Turbine power is stab!e at 75%

. LP 'A' Condenser Pressure is 5.8 Hga

. IP 'B' Condenser Pressure is 6.2 Hga j

. HP 'C' Condenser Pressure is 6.5 Hga l Which ONE of the following describes the expected operation of the condenser steam dumps with these conditions?

A. Less than 12 steam dumps are available and all available dumps are FULLY OPEN. ,

B. All 12 condenser steam dumps are available and all are FULLY OPEN.

C. Less than 12 steam dumps are available and all available dumps are PARTIALLY OPEN.

( \

Less than 12 steam dumps are available and all are CLOSED.

(3) D.

i ANSWER:

A. Less than 12 steam dumps are evailable and all available dumps are FULLY OPEN.

K/A #: 051AK3.01 RO IMPORTANCE: 2.8 KA DESCRIPTION: Loss of Steam Dump Capability OBJECTIVE #: J&K

REFERENCES:

T61.0110.6 LP 20, Pages 32-39 CMP 98-1038A, Reduced Tave/ Tref Modification AUTHOR: DGL SOURCE: Bank (Modified)- H DISTRACTER EXPLANATION:

Tref at 75% is 577.6*F. Actual AT = Tave - Tref = 590 - 577.6 = 12.4*F. In the load reject mode,100%

steam dump demand is generated with a AT of 15.7'F. A AT of 12.4*F would generate a demand of 79%

(Group 1,2, and 3 dumps fully open and Group 4 modulating open). Because the IP and HP Condensers , ,

are above the C-9 setpoint (6 Hga), only the 7 dumps for the LP Condenser are available. Therefore, p 7 dumps are available and they are fully open.

O RO Outline #R009

r QUESTION # 037

( ) .

-When inadequate core cooling exists, which ONE of the following sets of actions state the proper sequence of the major action categories to be performed in accordance with FR-C.1, Response To inadequate Core Cooling, for removing decay heat from the core?

A. Rapid secondary depressurization, reinitiation of safety injection, RCP restart.

B. Rapid secondary depressurization, RCP restart, reinitiation of safety injection.

C. Reinitiation of safe,ty injection, rapid secondary depressurization, RCP restart.

D. Reinitiation of safety injection, RCP restart, rapid secondary depressurization.

ANSWER: -

C. Reinitiation of safety injection, rapid secondary depressurization, RCP restart.

K/A #: 074EK1.03 RO IMPORTANCE: 4.5 i KA DESCRIPTION: Decay Heat Removal Methods l OBJECTIVE #: A

REFERENCES:

T61.003D.6 LP 25, Page 7 AUTHOR: DGL SOURCE: New - L DISTRACTER EXPLANATION:

A. & B. Reinitiation of safety injection is first in sequence.

D. RCP restart is last in sequence.

RO Outline #RO15 m

3

QUESTION # 038 ~

O (V An RCS leak has occurred and the CRS has instructed you to determine the size of the leak.

Given the following information:

Time = 0 Time = 1 minute Reactor Power (%) 100 100 RCS Tave ( F) 584.4 584.4

. Charging Flow (gpm) 100 100

. Letdown Flow (gpm) 75 75 Pzr Level (%) 57 56.63

. Total Seal injection Flow (gpm) 32 32

. Total Seal Leakoff Flow (gpm) 12 12 Which ONE of the following is the approximate RCS Leak Rate?

A. 25 gpm B. 30 gpm C. 35 gpm D. 40 gpm ANSWER:

C. 35 gpm K/A #: 009EK3.06 RO IMPORTANCE: 3.9 KA DESCRIPTION: RCS Inventory Balance (IPE/PRA)

OBJECTIVE #: D

REFERENCES:

T61.003B.6 LP SB-32, Page 6 AUTHOR: DGL SOURCE: New - H DISTRACTER EXPLANATION:

Leak Rate = Charging Flow-(Letdown Flow + Seal Leakoff) + (a Pzr Level x 60 gal /%)

= 100-(75 + 12) + (0.37 x 60)

' = 100 - 87 + 22 = 35 gpm t RO Outline #R021 z

- QUESTION # 039

(' -

The following plant conditions exist:

. Plant startup is in progress. I

. Intermediate Range Nis indicate 2.5 E-5 amps (SEN135) and 2.8 E-5 amps (SENI36). l

. Source Range Permissive P-6 light is LIT.

. Source Range Channel SEN131 high voltage power supply fails to HALF its normal voltage.

Which ONE of the fellowing indication (s) would be available to alert operators to this failure?

A. None, until power is lowered below the P-6 setpoint, and then the Source Range SEN131 indication will indicate lower than expected.

B. None, until power is lowered below the P-6 setpoint, and the,n the Source Range SEN!31 indication will indicate higher than expected.

C. ' SR Hi Flux Reactor Trip will occur when power is lowered below the P-6 setpoint.

D. SR Permissive P4 light will immediately extinguish due to the 1 of 2 coincidence.

n ANSWER:

A. None, until power is lowered below the P-6 setpoint, and then the Source Range SENI31 indication will indicate lower than expected.

K/A #: 032AK1.01 RO IMPORTANCE: 2.5 KA DESCRIPTION: SR High Voltage Degradation OBJECTIVE #: A

REFERENCES:

T61.0110.6 LP 28, Pages 3 & 4 Gas-Filled Detector Characteristic Curve AUTHOR: DGL SOURCE: New - H DISTRACTER EXPLANATION:

B. & C. Based on region lli of the curve, the number of counts would be lower D. P-6 is fed from the IR Nis.

RO Outline #R027 r,-

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f l

QUESTION # 040 A

U Which ONE of the following valves will AUTOMATICALLY close from a Hi Hi (Red) Radiation ;

Signal on EG-RE-9, 'A' Train CCW Radiation Monitor?

A. EGLV1, DI WTR TO CCW SRG TK 'A' LV i B. EGHV11, ESW TO CCW TRN 'A' UPSTRM HV ;

C. EGHV69A, CCW TO RW PROT 'A' SPLY ISO HV D. EGHV72, CCW TQ PASS UPSTRM ISO HV ANSWER:

A. EGLV1, DI WTR TO CCW SRG TK 'A' LV -

K/A #: 059AK2.01 RO IMPORTANCE: 2.7 KA DESCRIPTION: CCW High Radiation OBJECTIVE #: E

REFERENCES:

T61.0110.6 LP 10, Page 15 AUTHOR: DGL SOURCE: New - L DISTRACTER EXPLANATION:

B. & C. & D. Incorrect because equipment not affected by high radiation alarm on EG-RE-9.

RO Outline #R033 i

1 QUESTION # 041

'Q

' N The following plant conditions exist:

. Reactor Power is 26%.

. Pressurizer Pressure is 2235 psig.

. Pressurizer Levelis 33%.

. 'A' RCP breaker trips due to a failed undervoltage relay in PT cubicle PA03. (No other RCP is affected.) -

Whteh ONE of the following is the expected result of the trip of the 'A' RCP?

A. The reactor will trip due to the 'A' RCP undervoltage failure.

B. The reactor will trip due to the RCS Flow Low conditions.

C. A plant shutdown will be performed per OTG-ZZ-00004.

D. The reactor will be manually tripped by the operators.

l l

ANSWER: -

C. A plant shutdown will be performed per OTG-ZZ-00004. j i

KIA #: 003K2.01 RO IMPORTANCE: - 3.1.

KA DESCRIPTION: RCP Bus Undervoltage j i

OBJECTIVE #: D

REFERENCES:

-T61.0110.6 LP 27, Pages 24 & 25 '

OTO-BB-00002 AUTHOR: DGL SOURCE: New - H :

DISTRACTER EXPLANATION:

A. Requires 1/2 RCPs on 2/2 buses to trip the reactor.

B. Below P-8 setpoint, will NOT trip reactor.

D. Off-Normal procedure directs a plant. shutdown.

RO Outline #R039 O

I

.,3 QUESTION # 042 k) -

' : Power Range Channels currently read as follows:

SENI41 - 78.5%

SEN142 - 77.5%

SEN143 - 77.0%

SEN144 - 75.5% - -

The results of OSP-SE-00004, Nis Power Range Heat Balance, show that calculated power is 77%.

In accordance with OSP-SE-00004, which ONE of the following describes the current number of Power Range Channels that must be adjusted?

A. 0 -

B. 1 C. 2 D. 3 ANSWERi C. 2 K/A #: 015A1.01 RO IMPORTANCE: 3.5 KA DESCRIPTION: Power Range Heat Balance i OBJECTIVE #: F.2

REFERENCES:

T61.003A.6 LP A-3, Page 4 OSP-SE-00004, Page 1 AUTHOR: DGL SOURCE: Bank (Modified)- H DISTRACTER EXPLANATION:

Channel must be adjusted if the absolute difference between indicated power and calculated power is

>1% or if indicated power is less than calculated power. SEN141 & SEN144 require adjustment.

RO Outline #R045 l

u.-? ,

QUESTION # 043

,n Which ONE of the following is correct concerning Steam Generator Water Level Control?

l Each S/Gs NR level / Program level mismatch and Power Range Nis are used to control its A.

Feed Reg Bypass Valve position.

l l B. Each S/Gs Steam Flow / Feed Flow mismatch is the only signal controlling its Main Feed Reg Valve position.

C. Total Steam Flow / Feed Flow mismatch controls Main Feed Pump speed.

D. Total Feed Flow /No Load D/P Setpoint controls Program D/P for MFP speed.

ANSWER:

A. Each SIGs NR level / Program level mismatch and Power Range Nis are used to control its Feed Reg Bypass Ve've position.

KIA #: 059K1.04 RO IMPORTANCE: 3.4 KA DESCRIPTION: SGWLC System OBJECTIVE #: E, F, and G

REFERENCES:

T81.0110.6 LP 23, Pages 39,42, and 46 AUTHOR: DGL SOURCE: New - H i

DISTRACTER EXPLANATION:

1 B. Also uses steam flow and steam pressure.

C. Does not use feed flow as an input.

D. Total steam flow is used as input to program D/P.

i RO Outline #R051 l

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QUESTION # 044 Which ONE of the following will AUTOMATICALLY terminate a release from the Gas Decay I Tanks through the Radwaste Unit Vent?

1 A. HiHi Radiation Alarm on GH-RE-108, RW Bldg Exh Fan Disch l B. HiHi Radiation Alarm on HB-RE-18, RW Bldg Liquid Disch l C. HiHi Radiation Alarm on GH-RE-22, RW Bldg Fixed Filter D. HiHi Radiation Alarm on GH-RE-23, Gas Decay Tank Compartment ANSWER:

A. HiHi Radiation Alarm on GH-RE-108, RW Bldg Exh Fan Disch ;

K/A #: 071A3.03 RO IMPORTANCE: 3.6 KA DESCRIPTION: Rad Monitor Auto Isolation OBJECTIVE #: A.4

REFERENCES:

T61.0110.6 LP 16, Pages 17 & 18 (m'-] OTA-SP-RM011 AUTHOR: DGL SOURCE: New - L DISTRACTER EXPLANATION:

B. & C. & D. Incorrect because they do NOT provide on input to automatically isolate release.

RO Outline #R057 Nm /

O*

Q QUESTION # 045

~

~ The following plant conditions exist:

.. Reactor Power is stable at 30%.

. RCS Tave is 565.2*F.

. Pzr Pressure is 2235 psig.

. Pzr Level is 35%.

. Pzr Level Controller Selector Switch, BBLS459D, is selected to the 459 (Upper) / 460 (Lower) position.

. 'A' CCP is in service.

Which ONE of the following is the correct plant response if the Pzr Level Controller BBLK459 OUTPUT fails LOW 7 (Assume NO operator action is taken.)

A. Pzr level will not change due to BBLT460 being the controlling channel.

B. The reactor will trip on high Pzr level due to letdown isolation.

C. Pzr level will control at 25% due to low output from the controller.

1 D. Pzr level will control at 57% due to low output from the controller. l l

ANSWER: l P.. The reactor will trip on high Pzr level due to letdown isolation.

K/A #: , 011K1.04 RO IMPORTANCE: 3.8 l

KA DESCRIPTION: PZR Level Controller Malfunction OBJECTIVE #: J&K

REFERENCES:

T61.0110.6 LP 30, Pages 21,22,26, & 31 AUTHOR: DGL SOURCE: New - H DISTRACTER EXPLANATION:

This failure causes charging flow to reduce to minimum (45 gpm). Pzr level will decrease until letdown isolates at 17%. Charging will continue at 45 gpm until Pzr level rises to the Hi Level Rx Trip Setpoint.

RO Outline #R063 J

,, - QUESTION # 046

d Which ONE of the following is a design feature to prevent draining of the Spent Fuel Pool (SFP)?

A. Fuel Pool Cooling pumps trip automatically on a low level in the fuel pool.

B. Fuel Pool Cooling pumps receive a Load Shed signal during a loss of coolant accident.

C. SFP Transfer Tube Gate Valve AUTOMATICALLY closes on a low level in the fuel pool.

D. Fuel Pool Cooling pumps take a suction on the fuel pool at a level of six feet below normal.

ANSWER:

D. Fuel Pool Cooling pumps take a suction on the fuel pool at a level of six feet below normal.

K/A #: 033K4.03 RO IMPORTANCE: 2,6 KA DESCRIPTION: Anti-Siphon Design n OBJECTIVE #: H

REFERENCES:

T61.0110.6 LP 24, Page 8

()

AUTHOR: DGL SOURCE: New - L DISTRACTER EXPLANATION:

A. This trip is for pump protection.

B. Load Shed is for Emergency Diesel protection.

C. Gate valve has no auto close capability.

RO Outline #R069 1

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QUESTION # 047

/,,;

L) NE02, 'B' Emergency Diesel Generator, is operating in parallel with an off-site power source.

Which ONE of the following describes how the Emergency Diesel Generator REACTIVE load is controlled?

A. By varying generator real load.

B. By varying generator frequency.

C. By varying diesel e~ngine speed.

D. By varying generator excitation voltage.

1 l

l ANSWER-l D. By varying generator excitation voltage.

K/A #: 064A4.02 RO IMPORTANCE: 3.3 7'N KA DESCRIPTION: Reactive Load Control

( )

OBJECTIVE #: N

REFERENCES:

T61.0070.6 LP 25, Pages 67-69 AUTHOR: DGL i

SOURCE: New - H DISTRACTER EXPLANATION:

j The DG Generator Control Switch will control real load while the voltage regulator switch (generator excitation) will control reactive load when in the parallel mode of operation. l RO Outline #R075 l

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-QUESTIO.N # 048 '

C (The following plant conditions exist:

.: The plant is in Mode 3.

. . Replacement of the 'C' CTMT Cooler Fan Motor is in progress.

1Which_'ONE of the_ following is the MINIMUM required condition for the Personnel Air Lock (PAL) !

and the Emergency Air Lock (EAL) doors per Technical Specifications? i

, A. L Both doors in the EAL must remain closed and both doors in the PAL must remain closed.

~

B. Both doors in the EAL must rernain closed and at least one door in the PAL must remain closed.' .

C. ~ Both doors in the EAL must remain closed and both doors in the PAL may remain open for transit entry and exits.

D.- Both doors in the PAL must remain closed snd both doors in the EAL may remain open for j

. transit entry and exits. !

l NNSWER:-

8. Both doors in the EAL must remain closed and at least one door in the PAL must remain closed.'

. K/A #: 103G2.2.22 ' RO IMPORTANCE: 3.4 KA DESCRIPTION: Air Lock Requirements OBJECTIVE #: F.2

REFERENCES:

T61.003A.6 LP A-6, Page 5 -

Technical Specifications 3.6.1.3 AUTHOR: DGL-SOURCE: New - L DISTRACTER EXPLANATION:

A. One doorin each air lock may be open. j C. & D. At least one door in each airlock must be closed.

..RO Outline #R087 -

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4 QUESTION # 049

[h l

V Which ONE of the following is the MAXIMUM amount of radioactive material that may be .

I contained in the RWST7 A. 100 Rem /hr B. 50 Curies C. 500 Rem /hr D. 150 Curies ANSWER:

I D.150 Curies K/A #: 2.3.1 RO IMPORTANCE: 2.6 KA DESCRIPTION: RWST Radioactive Material Limit OBJECTIVE #: C.1

REFERENCES:

T61.003A.6 LP A-23, Page 3 FSAR 16.11.1.5 AUTHOR: DGL SOURCE: Bank (Modified) - L DISTRACTER EXPLANATION:

FSAR limit is 5150 curies.

RO Outline #R093 ;

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QUESTION # 050 n )

A caution in FR-C.1, Response to inadequate Core Cooling, states, " Hydrogen Recombiner should not be turned on if hydrogen concentration is greater than or equal to -

due to the danger of a hydrogen burn or explosion."

A. 1%

B. 4%

C. 6%

D. 10 %

ANSWER: -

l C,6%

i K/A #: 2.4.20 RO IMPORTANCE: 3.3 KA DESCRIPTION: EOP Cautions

,O OBJECTIVE #: B C/

REFERENCES:

T61.003D.6 LP 25, Page 24 AUTHOR: DGL SOURCE: Bank -L 1

DISTRACTER EXPLANATION:

A. & B. & D. Incorrect, procedure limit is < 6%.

RO Outline #R099 9

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QUESTION # 051

\_/

During shift turnover, the Reactor Operator notes the following parameters:

1

. RCS Tave - 584.4 F

. Pzr Pressure - 2235 psig

. Pzr Level- 57%

. PRT Pressure - 4 psig

. PRT Level- 74%

. PRT Temperature - 98'F ;

One (1) hour later, annunciator 34F, PRT LEV HILO, alarm.s and the following parameters are noted: ,

. RCS Tave - 584.3 F -

. Pzr Pressure - 2234 psig

. Pzr Level - 57% -

. PRT Pressure - 5.9 psig !

. PRT Level- 88%

. PRT Temperature - 96'F Which ONE of the following conditions caused the enange in parameters?

p .

C/ A. Pzr PORV BBPCV455A opened and reclosed.

B. CVCS Letdown Relief BG8117 lifted.

C. PRT to RCDT Viv BBHV8031 opened.

D. PRT Rx M/U Supply BBHV8045. opened.

ANSWER:

D. PRT Rx M/U Supply BBHV8045 opened. l K/A #: 007A3.01 RO IMPORTANCE: 2.7 KA DESCRIPTION: Inputs to the PRT OBJECTIVE #: E l

REFERENCES:

T61.0110.6 LP 9, Page 44 AUTHOR: DGL SOURCE: New - H l ,~-

)

('" DISTRACTER EXPLANATION:

BBHV8045 is the only valve that could cause a level increase and temperature decrease.

I RO Outline #R081 l

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- QUESTION # 052 i O

Q' ' The following plant conditions exist:

. 'B' Cire Water Pump Lockout.

. Turbine Setback is in progress.

. MCB Annunciator 81D, Rod Bank Lo Limit, is lit.

. MCB Annunciator 81C, Rod Bank Lo Lo Limit, is lit.

Which ONE of the following indications ensures that proper operator actions have been taken?

A. 40 gpm flow indicsted on BGFY1118, Combined M/U and BA Batch Counter.

B. 40 gpm flow indicated on BGF1183A, Emerg Borate To CCP 'A' & 'B' Hdr Flow Ind 'A'.

C. BG HIS-SA, 'A' Boric Acid Xfer Pmp PBG02A Hand ind SW, red light is lit.

D. BG HIS-8104, Emerg Borate To CCP 'A' & 'B' Hdr Iso HV, red light is lit.

ANSWER: I B. 40 gpm flow indicated on BGFl183A, Emerg Borate To CCP 'A' & 'B' Hdr Flow Ind 'A'.

K/A #: 024AA2.01 RO IMPORTANCE: 3.8 KA DESCRIPTION: Verification of Emergency Borate Flow OBJECTIVE #: A&B ;

REFERENCES:

T61.003B.6 LP B-61, Page 1 ;

OTO-ZZ-00003, Pages 1 & 2 MJTHOR: DGL SOURCE: New - H

=

DISTRACTER EXPLANATION:

A. This counter will not indicate during emergency boration.

B._ Correct, verifies > 30 gpm emergency borate flow.

C. The pump running by itself will not provide the required emergency borate flow.

l- D. The valve open by itself will not provide the required emergency borate flow.

RO Outline #R004 ,

l

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p QUESTION # 053 -

im Q The following plant conditions exist:

. ECA-0.0, Loss of All AC Power, is being implemented. j

. The Steam Generators (S/Gs) are being depressurized. '

. ' A caution states that "S/G pressures should not be decreased to less than 120 psig". ,

Which ONE of the following is the basis for maintaining S/G pressures above 120 psig during the depressurization?

1' A. .To prevent steam' void formation in the reactor vessel head.

B. To ensure RCS integrity is not challenged by pressurized thermal shock.

C. To maintain extraction steam and steam dumps available. .

D.' To ensure that nitrogen from the accumulators is not injected into the RCS.

ANSWER:

[ D. To ensure that nitrogen from the accumulators is not injected into the RCS.

. v K/A #: 055EK3.02 RO IMPORTANCE: 4.3 l KA DESCRIPTION: S/G Depressurization Limit (IPE/PRA) ,

OBJECTIVE #: Q l

REFERENCES:

T61.003D.6 LP 22, Page 48 ECA-0.0, Loss of All AC Power, Page 18 l

AUTHOR: DGL SOURCE: New - H DISTRACTER EXPLANATION:

A. Depressurization should not be stopped to prevent voiding in the vessel head.

8. RCS temperature is maintained greater than 275 F. PTS is not a concem.

C. Not required since depressurization is accomplished using S/G PORVs.

RO Outline #RO10 i

QUESTION # 054 1

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(

The following plant conditions exist-

.- Mode 1,100% Reactor Power.

. RCS specific activity is 50 microcuries per gram DOSE EQUIVALENT l-131.

Which ONE of the following is the Chemistry sampling requirements per OTO-BB-00005, i Reactor Coolant System High Activity? !

A. Normal 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months sample requirements are necessary.

I B. Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months until activity decreases for 3 consecutive samples. l C. As directed by the On-Shift Chemistry Supervisor.

D. Once per 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months until activity decreases on 3 consecutive samples.

ANSWER- !

l D. Once per 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months until activity decreases on 3 consecutive samples. j K/A #: 076AA2.02 RO IMPORTANCE: 2.8 KA DESCRIPTION: High RCS Activity Sampling Requirements OBJECTIVE #: A

REFERENCES:

T61.0038.6 LP B-18, Page 1 OTO-BB-00005 AUTHOR: DGL SOURCE: New - L DISTRACTER EXPLANATION:

A.- RCS activity is above Tech Spec limit. Increased sampling required.

B. Incorrect sample fraquency.

C. Incorrect sample frequency.

RO Outline #R016 l

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4 QUESTION # 055 Whici 'ONE of the following describes the correct guidance for use of ADVERSE CONTAINMENT values during a LOCA7 A. Once in Adverse Containment, a return to NORMAL procedure values can be made immediately if containment temperature was the ONLY reason Adverse Containment had been declared and has returned to less than 160*F.

B. If containment temperature OR radiation exceeds their Adverse Containment criteria, then Adverse Containment values must be used for the duration of the event regardless if either decreases below the Adverse Containment criteria.

C. Once in Adverse Containment, a return to NORMAL procedure values can be made immediately if containment radiation was the ONLY reason Adverse Containment had been declared and has returned to less than 1.0E5 R/HR. ,

D. If Adverse Containment was entered due to BOTH temperature and radiation, a return to NORMAL procedure values is allowed any time after temperature'is less than 160*F and radiation is less than 1.0E5 R/HR.

ANSWER:

A. Once in Adverse Containment, a retum to NORMAL procedure values can be made immediately if containment temperature was the ONLY reason Adverse Containment had been declared and has returned to less than 160*F.

K/A #: 011EK3.12 RO IMPORTANCE: 4.4 KA DESCRIPTION: Adverse Containment Requirements OBJECTIVE #: J-

REFERENCES:

T61.003D.6 LP 8, Page 33 l AUTHOR: DGL .

SOURCE: New - H DISTRACTER EXPLANATION B. Containment Temperature doesn't prevent using normal values after < 160*F. j C. & D. Can't use normal values after exceeding 1.0E5 R/HR.

i RO Outline #R022 i O !

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QUESTION # 056 g

Nv' i ~

The following plant conditions exist:

. Plant shutdown is in progress.

. Intermediate Range Channel SENI36 fails HIGH.

. Power Range Nls indicate: SEN141 9%

SEN142 10%

SENI43 11 %

SEN144 11 %

Which ONE of the following describes the plant response to this failure?

A. The reactor will immediately trip on IR High Flux and Source Range Trip will reinstate automatically when SEN135 decreases below P-6 setpoint.

B. The reactor will immediately trip on IR High Flux and Source Range Trip will NOT reinstate automatically when SEN135 decreases below P-6 setpoint.

C. The reactor will NOT immediately trip, but will trip when the Source Range Trip is reinstated when power decreases below the P-6 setpoint.

f D. The reactor will NOT immediately trip, but will trip when the intermediate Range Trip is reinstated when power decreases below the P-10 setpoint.

ANSWER:

D. The reactor will NOT immediately trip, but will trip when the Intermediate Range Trip is reinstated when power decreases below the P-10 setpoint.

KIA #: 033AA2.02 RO IMPORTANCE: 3.3 KA DESCRIPTION: IR Channel Failure During Shutdown l

OBJECTIVE #: D&E .

REFERENCES:

T61.0110.6 LP 27, Pages 23,36 & 37 !

AUTHOR: DGL 3 SOURCE: New - H l

DISTRACTER EXPLANATION:

l A. & B. Power is stiIl above P-10 setpoint, IR High Flux Trip is blocked.

C. SR Trip will not automatically reinstate below P-6 due to SEN136 being failed HIGH.

l

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V RO Outline #R028 L

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QUESTION # 057 he following plant conditions exist

. Reactor Power is 100%.

. - Pressurizer Level Controlis in AUTOMATIC.

. BBLT0459 is the UPPER selected control channel.

) Which ONE of the following describes the plant response to BBLT0459 failing LOW 7 (Assume i NO Operator Action is taken.)

A. Letdown isolates, backup heaters turn on, charging flow decreases, actual pressurizer level decreases, and the reactor trips on low pressurizer level.

B. Letdown temperature increases, backup heaters energize, charging flow increases, actual pressurizer level increases, and the reactor trips on high press _urizer level.

C. Letdown isolates, backup heaters de-energize, charging ficw increases, actual pressurizer level increases, and the reactor trips on high pressurizer level.

D. Letdown temperature increases, backup heaters de-energize, charging flow decreases, actual pressurizer level decreases, and the reactor trips on low pressurizer level.

ANSWER:

C. Letdown isolates, backup heaters de-energize, charging flow increases, actual pressurizer level increases, and the reactor trips on high pressurizer level, i

KIA #: 028AA1.01 RO IMPORTANCE: 3.8 KA DESCRIPTION: ReactorTrip From PZR Level Failure OBJECTIVE #: J&K

REFERENCES:

T61.0110.61930, Pages 21,22 & 31 AUTHOR: DGL ,

SOURCE: Bank (Modified)- H DISTRACTER EXPLANATION:

A. & D; There is no Pzr Low Level Reactor Trip.

B. Letdown will isolate and B/U heaters will de-energize.

RO Outline #R034 4 4 O

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QUESTION # 058 13 1 V Which ONE of the following is the basis for isolating RCP #1 seat leakoff at RCS pressures

~

l below 100 psig?

l A. #1 seal leakoff flow decreases, so #1 seal leakoff is isolated to force more flow to #2 seal.

B. To prevent exceeding the Tech Spec controlled leakage limit due to excessive seal I injection flow through the #1 seal.

C. The leakoff flow instruments are not as accurate which could result in excessive leakoff j going undetected. l l

D. To prevent contamination being forced into the seal chamber from the seal leakoff line.

i ANSWER: -

D. To prevent contamination being forced into the seal chamber from the seal leakoff line.

KIA #: 003A1.09 RO IMPORTANCE: 2.8 KA DESCRIPTION: Isolation of Seal Leakoff OBJECTIVE #: C.1.c

REFERENCES:

T61.003A.6 LP A-20, Page 3 OTN-BB-00003, Page 1 AUTHOR: DGL SOURCE: New - H DISTRACTER EXPLANATION:

A. #2 seal will have adequate flow.

l B. Controlled Leakage Tech Spec limit won't be exceeded unless seat fails.

C. Leakoff flow instruments are accurate over entire range of pressures.

RO Outline #R040 l

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QUESTION # 059

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Which ONE of the following describes the affect on a Source Range Channel if the pulse height discriminator failed to a lower value?

The output would: 1 i

A. decrease due to the filtering which narrows the pulse height window.

B. decrease due to the removal of the higher amplitude neutron pulses.

C. increase due to the increased gamma interaction inside the detector.

D. increase due to counting of some of the lower amplitude gamma pulses.

ANSWER: .

D. increase due to counting cf some of the lower amplitude gamma pulses.

K/A #: 015A2.02 RO !MPORTANCE: 3.1 KA DESCRIPTION: SR Discriminator Failure

'O OBJECTIVE #: A

REFERENCES:

T61.0110.6 LP 28, Pages 3 AUTHOR: DGL ,._

SOURCE: New - H DISTRACTER EXPLANATION:

A. Output increases due to a narrower pulse height window.

B. Failure will NOT remove any neutron pulses.

C. Failure does NOT affect interactions inside the detector.

RO Outline #R046 i

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QUESTION # 060 '

. The following plant conditions exist:

Reactor Power is 35%

. ACPT0505 is the selected impulse Pressure Channel.

. ABFT0512 is the selected 'A' S/G Steam Flow Channet

. All control systems are in their normal lineup.

Which ONE of the following failures would cause an INITIAL decrease in feedwater flow to all S/Gs?

A.' Turbine impulse Pressure ACPT0505 fails low.- 1 J

B. Main Steam Header Pressure ABPT0507 fails low.-

-- C . 'A' S/G Steam Flow ABFT0512 fails high.

D. Main Feed Header Pressure AEPT0508 fails low.

ANSWER:

. B. Main Steam Header Pressure ABPT0507 fails low.

K/A #: 059K4.05 RO IMPORTANCE: 2.5 KA DESCRIPTION: .MFP Speed Control OBJECTIVE #: E

REFERENCES:

. T61.0110.6 LP 23, Pages 37-39 AUTHOR: DGL i SOURCE: New - H I DISTRACTER EXPLANATION: i

'A. No affect, steam dumps are not armed. !

C. & D. This will increase feed pump speed and increase feed flow to S/Gs.

RO Outline #R052-l

i i QUESTION # 061 l

' GG-RE-27, Process Radiation Monitor, increases to the HiHi (Red) alarm setpoint on the gas channel due to a fuel handling accident in the Fuel Bldg.

Which ONE of the following is an expected result from this alarm?

A. Only the 'A' Fuel Bldg Supply Air Unit (SGG01 A) starts.

B. Only the 'A' Emergency Exhaust Fan (CGG02A) starts.

C. Both Fuel Bldg Supply Air Units (SGG01 A & SGG018) start.

D. Both Emergency Exhaust Fans (CGG02A & CGG028) start.

ANSWER:

O. Both Emergency Exhaust Fans (CGG02A & CGG028) start.

K/A #: 072K4.02 RO IMPORTANCE: 3.2

,. KA DESCRIPTION: Fuel Bldg Isolation Signal

(

'v' OBJECTIVE #: D

REFERENCES:

T61.0110.6 LP 39, Pages 22-25 AUTHOR: DGL SOURCE: New - H DISTRACTER EXPLANATION:

A. & C. Fuel Bldg Supply Air Units stop on a FBVIS.

B. Rad Monitor starts both Emergency Exhaust Fans.

RO Outline #R058

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QUESTION # 062 The following plant conditions exist:

. Power Range Nis - 100%.

. Loop Teoto Temperature - 554 F.

. Loop Taor Temperature -615 F.

. RCS Total Flow- 383,000 gpm.

. Pzr Pressure -2235 psig.

Which ONE of the following describes the change in OTAT setpoint when the listed parameter is changed? (Consider each change individually.)

A. Setpoint increases if PZR pressure increases.

B. Setpoint decreases if RCS total flow decreases. l l

C. Setpoint increases if Loop Thor increases.

D. Setpoint decreases if Power Range Nls increase. .!

f~ <

\- ANSWER:

A. , Setpoint increases if PZR pressure increases.

K/A #: 012K4.02 RO IMPORTANCE: 3.9 KA DESCRIPTION: OTAT Setpoint Changes OBJECTIVE #: E

REFERENCES:

T61.0110.6 LP 30, Pages 13 & 14 AUTHOR: DGL SOURCE: New - H DISTRACTER EXPLANATION:

B. RCS flow is not an input.

C. Setpoint will decrease.

D. NI input is only for exceeding +10 or-23 on Al.

RO Outline #R064

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- QUESTION # 063 ,

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During an ATWS event, the 'D' S/G PORV will NOT open due to a controller malfunction.

Which ONE of the following combinations describes the correct pressures that the 'D' loop main i steam safety valves will open?

A. 1165,1185,1197,1210, and 1222 psig.

B. 1165,1185,1197,1210, and 1234 psig.

C. 1185,1197,1210,1222, and 1234 psig.

1 D. 1185,1210,1222,1234, and 1246 psig.

l ANSWER: - '

C.1185,1197,1210,1222, and 1234 psig. '

l K/A #: 035K6.02 RO IMPORTANCE: 3.1 ;

KA DESCRIPTION: S/G Safety Setpoints h i (V OBJECTIVE #: F

REFERENCES:

T61.0110.6 LP 20, Page 25 AUTHOR: DGL SOURCE: New - L DISTRACTER EXPLANATION:

C. This is the only combination of correct relief setpoints.

RO Outline #R070 rm

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QUESTION # 064 g

\ Main Control Board Annunciator 61C, Process Rad Monitor Failure has alarmed. When you check the status at the RM-11 panel, you find channel 223 CTMT Purge Monitor is flashing and its color is MAGENTA.

Which ONE of the following could be causing the failure of channel 223?

A. Monitor Communications Failure B. Filter Paper Not Moving C. Loss Of Process Flow D. Low Alarm Vacuum ANSWER:

A. Monitor Communications Failure s K/A #: 073A4.02 RO IMPORTANCE: 3.7

) KA DESCRIPTION: RM-11 Status Panel OBJECTIVE #: B !

REFERENCES:

T61.0110.6 LP 36, Pages 11 & 12 AUTHOR: DGL i SOURCE: New - L DISTRACTER EXPLANATION:

B. Color would be dark blue.

C. Color would be light blue. ,

D. Color would be light blue. I RO Outline #R076 (s3 l

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- QUESTION # 065

,a The following plant conditions exist:

. A LOCA has occurred.

. Safety injection is INITIATED. ,

. CIS-B Isolation is INITIATED. .

. NB01 and NB02 are powered from their respective D/Gs. j

. All equipment has properly sequenced onto the buses.

Which ONE of the following loads are being supplied by Component Cooling Water (CCW)in this condition?

i A. RW Recycle Evaporator B. Excess Letdown Heat Exchanger ,

C. 'A' CCP Oil Cooler l l

- D. 'RCP Thermal Barrier Hxs l

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[ ANSWER:

C. 'A' CCP Oil Cooler RO IMPORTANCE: 3.3 I I KIA #: 008K1.02 KA DESCRIPTION: Loads Cooled by CCW ,

)

OBJECTIVE #: C&D

REFERENCES:

T61.0110.6 LP 10, Pages 6,7,17, & 19 AUTHOR: DGL SOURCE: New - H DISTRACTER EXPLANATION:

A. Radwaste isolates on St.

B. & D. Isolates on CIS-B.

RO Outline #R082 -

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i QUESTION # 066 You are the on-shift Reactor Operator. In accordance with plant procedure, which ONE of the following non-licensed individuals may you allow to start the 'A' Safety injection (SI) pump from panel RLO17 in the Control Room?

A. Any system engineer authorized by the Shift Supervisor who is performing Si system surveillance, j B. Any assistant equipment operator performing OJT on the SI system who is being monitored by the CRS.

C. Any individual who is enrolled in a license training program under my direct observation.

. D. Any electrical maintenance supervisor troubleshooting why the SI pump vibration readings l are abnormal.

ANSWER:

C. Any individual who is enrolled in a license training program under my direct observation.

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K/A #: 2.1.2 RO IMPORTANCE: 3.0 KA DESCRIPTION: Operator Responsibilities OBJECTIVE #: H.1

REFERENCES:

T61.003A.6 LP A-4, Page 4 ODP-ZZ-00010, Page 4 AUTHOR: DGL SOURCE: Bank (Modified)- L DISTRACTER EXPLANATION:

Must be in a licensed training program under the direct control of the on-shift license operator to operate main control board controls.

RO Outline #R086 O

QUESTION # 067 10 O An AmerenUE radiation worker has received 500 mrem Total Effective Dose Equiveient (TEDE) whole body exposure so far this year. This worker has NOT received any exposure at other sites and has a complete exposure history record on file.

Which ONE of the following is the MAXIMUM TEDE whole body exposure this radiation worker can receive during the remainder of the year and NOT exceed the annual Callaway Plant Administrative Exposure Limit for TEDE Whole Body?

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A. 1500 mrem 1

B. 3500 mrem l l

C. 4000 mrem j

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D. 4500 mrem ANSWER: l A.1500 mrem K/A #: 2.3.4 RO IMPORTANCE: 2.5 KA DESCRIPTION: Whole Body Admin Limits ,

OBJECTIVE #: B.8.a 4

REFERENCES:

T61.003A.6 LP A-31, Page 2 APA-ZZ-01000, Attachment 1 ;

AUTHOR: DGL SOURCE: New - H i DISTRACTER EXPLANATION:

B. Limit including prior site exposure.

C.10CFR20 incomplete history extended limit.

D. 10CFR20 Limit.

RO Outline #R094 O

QUESTION # 068

\- Following a reactor trip and transition to E-1," Loss of Reactor or Secondary Coolant", an ORANGE path is identified under SUBCRITICALITY.

Which ONE of the following should be performed with regard to implementing FR-S,1.

" Response to Nuclear Power Generation"?

A. Implement FR-S.1 at the discretion of the Shift Supervisor.

B. Immediately suspend the performance of E-1 and implement FR-S.1.

C. Continue monitoring status trees, if no RED path is encountered, complete E-1 and then implement FR-S.1.

D. Monitor the remaining status trees, if no RED path is encountered, then implement FR-S.1.

ANSWER.

D. Monitor the remaining status trees, if no RED path is encountered, then implement FR-S.1.

( l K/A #: 2.4.22 RO IMPORTANCE: 3.0 i'

KA DESCRIPTION: Prioritizing Safety Functions OBJECTIVE #: B.7

REFERENCES:

T61.003D.6 LP 1, Pages 44 & 45 AUTHOR: DGL SOURCE: Bank - H DISTRACTER EXPLANATION:

A. & B. Must check for red path prior to implementing orange path.

C. E-1 is suspended as soon as complete pass through status trees is finished and a red or orange path is present.

RO Outline #R100

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QUESTION # 069

. Q'v The following plant conditions exist:

. The plant is in Mode 4

. 'B' RHR Train is in the cooldown alignment

. RCS temperature is 300*F

. RCS pressure is 200 psig

. 'B' CCW Surge Tank level is DECREASING Which ONE of the following leak locations could produce these plant conditions?

A. 'B' RHR Heat Exchanger B. Thermal Barrier Heat Exchanger .

C. Letdown Heat Exchanger D. Seal Water Heat Exchanger

' ANSWER:

D. Seal Water Heat Exchanger K/A #: 026AA1.05 RO IMPORTANCE: 3.1

- KA DESCRIPTION: Evaluation of CCW Leak OBJECTIVE #: H

REFERENCES:

T61.0110.6 LP 10, Pages 22 & 33 AUTHOR: DGL SOURCE: New - H DISTRACTER EXPLANATION:

Only D. has a fluid pressure less than CCW pressure.

A. 'B' RHR Heat Exchanger pressure is = 395 psig. CCW pressure is 100 psig.

B. & C. Thermal Barrier and Letdown Heat Exchanger pressures are = ?00 psig.- CCW pressure is 100 psig.

D. Seal Water Heat Exchanger pressure is = 20 psig. CCW pressure is 100 psig.

. RO Outline #R005

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QUESTION # 070

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While operating at 100% power the following occurs:

. Intermediate Range Channel SEN135 fails low.

. Charging pump suction swapped from the VCT to the RWST.

. Pzr Level Indicator BBLl459A fails low.

Which ONE of the following could be the cause?

A. NN01' instrument Bus Failure B .- PN07 Instrument Bus Failure C. NNO3 Instrument Bus Failure

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D. PN08 Instrument Bus Failure ANSWER:

A. NN01 Instrument Bus Failure O J K/A #: 057G2.1.7 RO IMPORTANCE: ' 3.7 KA DESCRIPTION: . Diagnosis of NN Bus Failure ,

OBJECTIVE #: A (LP B-45), G (LP SB-9)

REFERENCES:

T61.0038.6 LP B-45, Page 1 OTO-NN-00001 T61.0038.6 LP SB-9, Page 8 AUTHOR: DGL ,

SOURCE: New - H DISTRACTER EXPLANATION:

B; & C. & D. Common misconceptions.

RO Outline #RO11 O

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QUESTION # 071 q'

The following plant conditions exist:

. Reactor Power is 30%.

. Rod Controlis in AUTOMATIC.

. Tref is 565*F. 4

. Tave values: Loop 1 - 565'F, Loop 2 - 566 F, Loop 3 - 566*F, Loop 4 - 565'F.

. PR Nis: SENI41 - 31%, SEN142 - 30%, SENI43 -29%, SENI44 - 30%.

. Control Bank 'D' is at 150 steps.

Which ONE of the following conditions would result in ark automa'.ic rod WITHDRAWAL 7 l

A. Pup ACPT0505 fails to 100%.

B. PR NI SEN141 fails to 20%.

C. Loop 1 Tem fails to 510'F.

D. Tref signal fails to 557aF.

(^3 ANSWER:

A. Pimp ACPT0505 fails to 100%.

KIA #: 001AA2.05 RO IMPORTANCE: 4.4 KA DESCRIPTION: Indications of Rod Withdrawal Malfunction OBJECTIVE #: B&C

REFERENCES:

T61.0110.6 LP 26, Page 16-19 AUTHOR: DGL SOURCE: New - H DISTRACTER EXPLANATION:

B. Rod Control uses Auctioneered HIGH PR Nis. PR NI failing low has no effect.

C. Rod Control uses Auctioneered HIGH Tave. T.failing low has no effect.

D. Tref failing low would cause rods to insert.

RO Outline #RO17 v

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! QUESTION # 072 l c

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A reactor trip and safety injection have occurred. All immediate actions have been completed.

The following plant conditions exist:

4

. CTMT Radiation . 1000 r/hr

. CTMT Pressure 2 psig I

. CTMT Recirc Sump Level 50 inches

. RCS Pressure 175 psig

. RHR Pump Flow 500 gpm l

. Pzr Level 0% l

. RWST Level 86 %

Which ONE of the following procedures would be used for plant recovery? i l

4 A. ES-1.1, SI Termination !

l B. ES-1.2, Post LOCA Cooldown and Depressurization C. ES-1.3, Transfer to Cold Leg Recirculation D. ECA-1.1, Loss of Emergency Coolant Recirculation ANSWER:

i S. ES-1.2, Post LOCA Cooldown and Depressurization i

K/A #: W/E03EA2.1 RO IMPORTANCE: 3.4 KA DESCRIPTION: Selection of Recovery Procedure OBJECTIVE #: U

REFERENCES:

T61.003D.6 LP 8, Page 52 AUTHOR: DGL .

SOURCE: Bank (Modified)- H DISTRACTER EXPLANATION:

A. Si Termination Criteria is not met.

C. Cold Leg Recirculation Switchover Criteria is not met. .

D. Cold Leg Recirculation Capability is available.

[D ' RO Outline #R023 AJ .

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' QUESTION # 073 -

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Which ONE of the following describes the RCP trip criteria while responding to a SGTR per E-3, Steam Generator Tube Rupture?

A. RCPs should be tripped anytime during E-3 if the trip criteria are met.

B. RCPs should be tripped during E-3 only if the trip criteria are met after verifying at least one RHR pump is running.

C. RCPs should be tripped during E-3 only if the trip criteria are met before initiating a cooldown.

D. RCPs should be tripped during E-3 only if the trip criteria are met before isolating the ruptured SIG.

ANSWER:

C. RCPs should be tripped during E-3 only if the trip criteria are met before initiating a cooldown.

K/A #: 038EK3.08 RO IMPORTANCE: 4.1

% KA DESCRIPTION: RCP Trip Criteria OBJECTIVE #: 'H

REFERENCES:

T61.003D.6 LP 17, Page 34 ,

AUTHOR: DGL l SOURCE: New - L l 1

DISTRACTER EXPLANATION: l A. & B. & C. Trip criteria applies until an operator controlled cooldown is initiated.

RO Outline #R029 l

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dUESTION # 074

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The plant has experienced a total loss of instrument air.

^ ' Which ONE of the following valves is in its correct failed position?

A. EJHCV0606. RHR HX 'A' OUTLET FCV is CLOSED B. BGHV8149A, CVCS LTDN ORIFICE 'A' ISO is OPEN.

C. BGFCV0111B, M/U TO VCT IN HDR FCV is OPEN D. EJFCV0619, RHR HX 'B' BYP FLOW CTRL VLV is CLOSED j ANSWER: ,

1 D. EJFCV0619, RHR HX 'B' BYP FLOW CTRL VLV is CLOSED

'K/A #: 065AA2.08 RO IMPORTANCE: 2.9 ,

KA DESCRIPTION: . Valve Failure on Loss of Air OBJECTIVE #: B O'

REFERENCES:

- T61.0110.6 LP 7, Page 16 i OTO-KA-00001, Attachments 5 & 6 AUTHOR: DGL SOURCE: New - H i

DISTRACTER EXPLANATION:

A. EJHCV0606 fails OPEN.

B. BGHV8149A fails CLOSED.

C. BGFCV01118 fails CLOSED.

RO Outline #R035 0 .

QUESTION # 075 The following plant conditions exist at 0400:

. Tave is 557 F.

. Pzr Pressure is 2235 psig.

. SR Channel SEN131 indicates 19 cps.

. ' SR Channel SEN132 indicates 20 cps.

The following plant conditions exist at 0409:

. Tave is 556*F.

. Pzr Pressure is 2237.psig.

. SR Channel SEN131 indicates 39 cps.

. SR Channel SEN132 indicates 46 cps.

Which ONE of the following describes the plant response to these conditions?

A. ' Containment Evacuation Alarm sounds.

B. High Flux at Shutdown Alarm sounds.

j C. Reactor trip breakers open on high source range counts.

D. CCP suctions swap from the VCT to the RWST.

ANSWER:

D. CCP suctions swap from the VCT to the RWST.-

KIA #: 004K1.07 RO IMPORTANCE: 2.6 KA DESCRIPTION: Response to Flux Doubling OBJECTIVE #: E

REFERENCES:

T61.0110.6 LP 28, Pages 6 & 7 AUTHOR: DGL SOURCE: Bank (Modified)- H DISTRACTER EXPLANATION:

A. & B. Both occur at 200 cps.

5 C. SR High Flux Trip is at 10 cps.

r- RO Outline #R041

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- QUESTION # 076 +

O Which ONE of the following Core Exit Thermocouple (CETC) readings indicates the highest )'

temperature during accident conditions at which a CETC will operate satisfactorily?

A. 700*F B. 1200 F C. 2300*F D. 3200 F ANSWER: J C. 2300*F K/A #: 017K6.01 RO IMPORTANCE: 2.7 KA DESCRIPTION: Thermocouple Failures

% OBJECTIVE #: J

REFERENCES:

T61.0110.6 LP 29, Page 11 AUTHOR: DGL SOURCE: New - L DISTRACTER EXPLANATION:

A. FR-C.2 Orange Path criteria.

B. FR-C.1 Red Path criteria.

D. Common misconception.

l RO Outline #R047 i

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, QUESTION # 077

( )

v The following plant conditions exist:

. Reactor startup was in progress when the reactor tripped at 10-8 amps.

. Containment pressure is normal.

. NB01 bus had a spurious trip of the normal feeder breaker.

. NE01, 'A' Emergency DG, automatically started and is supplying NB01.

. Lowest S/G NR levels reached were: 'A' - 20%, 'B' - 18%, 'C' - 19%, 'D' - 21 %.

Which ONE of the following is the correct status of the Auxiliary Feedwater Pumps (AFPs)?

A. Only the TDAFP is running.

B. 'A' MDAFP and the TDAFP are running. -

C. 'B' MDAFP and the TDAFP are running.

D. All three AFPs are running.

(g! ANSWER:

B. 'A' MDAFP and the TDAFP are running.

K/A #: 061K4.02 RO IMPORTANCE: 4.5 KA DESCRIPTION: AFW Pump Auto Starts OBJECTIVE #: H

REFERENCES:

T61.0110.6 LP 25, Pages 19 & 20 l AUTHOR: DGL SOURCE: New - H !

DISTRACTER EXPLANATION: l A. 'A' MDAFP started on the S/D sequencer. l C. 'A' MDAFP is running, NOT 'B' MDAFP. l D. 'B' MDAFP is NOT running. l RO Outline #R053 l

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i QUESTION # 078 l

O Which ONE of the following Area Radiation Monitors is required by Technical Specifications?

A. SD-RE-27, CTMT Purge Filter Unit B. SD-RE-33, Control Room Area C. SD-RE-38, Spent Fuel Pool Area i l

D. SD-RE-42, Containment Building ANSWER:

C. SD-RE-38, Spent Fuel Pool Area . j l

K/A #: 072G2.2.22 RO IMPORTANCE: 3.4 i KA DESCRIPTION: ARMS Required By T/S j OBJECTIVE #: G

REFERENCES:

T61.0110.6 LP 36, Page 24 O AUTHOR: DGL !

SOURCE: New - L DISTRACTER EXPLANATION:

Only Area Rad Monitors required by T/S are SD-RE-35,36,37, & 38.

RO Outline #R059

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QUESTION # 079

,y V The following plant conditions exist:

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. Mode 1 at 100% power.

. Annunciator 808, RPI NON-URG ALARM is lit.

. DRPI General Warning LED is flashing for rod H-8.

. DRPI Data 'A' Failure LED is lit.

. Rod Bottom Light for H-8 is NOT lit. l

. NO Rod Control System alarms are lit. ;

Which ONE of the following describes the operability of DRPI and the accuracy of determining the position of rod H-8?

A. Operable; accuracy is +10, -4 steps. -

B. Inoperable; accuracy is -10, +4 steps.

C. Operable; accuracyis 4 steps.

p D. Inoperable; no measureable accuracy.

V ANSWER:

A. Operable; accuracy is +10, -4 steps.

K/A #: 014G2.2.22 RO IMPORTANCE: 3.4 KA DESCRIPTION: Determine DRPI Operability OBJECTIVE #: S&U

REFERENCES:

T61.0110.6 LP 26, Pages 26 & 66 .

AUTHOR: DGL SOURCE: New - H DISTRACTER EXPLANATION:

B. DRPI is still operable with half accuracy.

C. Accuracy is +10, -4 steps.

D. DRPI is still operable and accuracy is +10,-4 steps.

RO Outline #R065

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. QUESTION # 080 -

The plant is operating at steady state, BEGtNNING-OF-LIFE,30% power. A power change is commenced by the BOP operator by increasing turbine load.

Which ONE of the following describes the affect on Reactor Power? (Consider only the effect of the increased steam flow.) -

A. _ Recctor power increases due to the positive moderator temperature coefficient adding positive reactivity.

B. Reactor power decreases due to the positive moderator temperature coefficient adding negative reactivity.

C. Reactor power increases due to the negative moderator temperature coefficient adding positive reactivity.

D. Reactor power decreases due to the negative moderator temperature coefficient adding negative reactivity.

ANSWER:

B. Reactor power decreases due to the por.tive moderator temperature coefficient adding negative reactivity.

K/A #: 039A2.05 RO IMPORTANCE: 3.3 KA DESCRIPTION: Rx Power / Steam Demand OBJECTIVE #: G

REFERENCES:

T61.0070.6 LP 4, Pages 100-103 AUTHOR: DGL SOURCE: New- H DISTRACTER EXPLANATION:

Ac Power decreases due to adding negative reactivity.

C. Power decreases because MTC is positive which adds negative reactivity.

D. MTC is positive.

RO Outline #R071 0 ,

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QUESTION # 081 O The plant has experienced a loss of all Cire Water Pumps which resulted in a reactor trip. All systems have responded as designed. Significant decay heat causes RCS temperature to increase following the trip.

Which ONE of the following is the RCS temperature at which the plant will stabilize?

A. 550*F B. 557'F - -

C. 561*F D.- 565'F ANSWER:

C. 561*F K/A #: 075A2.02 RO IMPORTANCE: 2.5 O' KA DESCRIPTION: Cire Water Pump Trips OBJECTIVE #: F (LP 20), B (LP 13)

REFERENCES:

T61.0110.6 LP 20, Pages 22 & 23 T61.0070.6 LP 13, Page 18 AUTHOR: DGL SOURCE: New - H DISTRACTER EXPLANATION:

Condenser steam dumps are not available due to the loss of vacuum. RCS temperature will be controlled by the S/G PORVs. The PORVs open at 1125 psig (1140 psia). T AT S for 1140 psia is 561*F.

RO Outline #R077 V

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. QUESTION # 082 l .

Which ONE of the following is a CHIEF CONTRIBUTOR Post-LOCA hydrogen source in containment?

A. Zirconium-Water Reaction B. Corrosien of Metal and Paint C. Dissolved Hydrogen in Reactor Coolant D. Oxidation of Aluminum ANSWER:

A. Zirconium-Water Reaction K/A #: 028K5.03 RO IMPORTANCE: 2.9 KA DESCRIPTION: Post-LOCA H2 Sources OBJECTIVE #: I O

REFERENCES:

T61.0110.6 LP 40, Page 33 AUTHOR: DGL SOURCE: New - L DISTRACTER EXPLANATION:

B. Minor contribution.

C. Minor contribution.

D. No contribution.

RO Outline #R083 O

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QUESTIO # 083 O You are the on-coming Unit Reactor Operator for the February 7* AM Shift (0700). Your last shift was finished at 0700 on February 5*. Which ONE of the following describes the minimum amount of RO logs that you must review prior to watch relief?

A. Back to February 6* at 2300.

B. Back to February 6* at 0700.

C. Back to February 5* at 2300.

D. Back to February 5* at 0700.

ANSWER: ,

B. - Back to February 6* at 0700.

K/A #: 2.1.3 RO IMPORTANCE: 3.0 KA DESCRIPTION: Shift Tumover Practices OBJECTIVE #: A.2.b

REFERENCES:

T61.003A.6 LP A-2, Page 2 ODP-ZZ-00003, Page 4 AUTHOR: DGL SOURCE: New - H DISTRACTER EXPLANATION:

Must review last 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or their last watch whichever is shorter. Last watch was 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months ago, therefore must review 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (February 6* at 0700).

RO Outline #R089 l

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QUESTION # 084 o

b A purpose of the Control Building Ventilation System is to limit radiation doses of Control Room i

personnel during a design basis accident to: ;

i A. less than 5 Rem whole body dose during the first 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months of the accident.

-.- B . less than 10 Rem whole body dose during the first 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months of the accident.

C. less than 5 Rem whole body dose during the entire period of the accident.

D. less than 10 Rem whole body dose during the entire period of the accident.

ANSWER: j

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C. less than 5 Rem whole body dose during the entire period of the accident.

KIA #: 2.3.10 RO IMPORTANCE: 2.9 j KA DESCRIPTION: Personnel Exposure Control s OBJECTIVE #: A

REFERENCES:

T61.0110.6 LP 60, Page 41 1 AUTHOR: DGL SOURCE: Bank (Modified) - L DISTRACTER EXPLANATION:

A. For entire accident, not 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

B. Umit is 5 Rem, not 10 Rem and for entire accident, not 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

D. Limit is 5 Rem, not 10 Rem.

RO Outline #R095 i

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b L-QUESTION # 085 The following plant conditions exist:

. Mode 1 at 100% power.' I

. All systems are in AUTOMATICJ . .

L . Pressurizer Pressure Channel BBPT0455 is inoperable with it's appropriate bistables placed l in the TRIPPED condition.

. . Pressurizer Pressure Control . Selector Switch, BB PS-455F is selected to BBPT0457 (Upper Selected Channel) and BBPT0456 (Lower Selected Channel).

. Which ONE of the following is the correct plant response if Pressurizer Pressure Channel .

l BBPT0457 fails HIGH INSTANTANEOUSLY 7 (Assume NO Operator Action taken.)

1 A. . Both PORVs and both Spray Valves open resulting in a reactor trip on low pressurizer l pressure followed by Si actuation.' , m j

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' B. The reactor will trip on high pressurizer pressure and SI will actuate on low pressurizer !

_ pressure due to spray valve operation. ;

1 C. . Both PORVs and both Spray Valves will remain closed and all pressurizer heaters will i de-energize.

' D. The reactor will trip on OPAT and SI will actuate on low pressurizer pressure due to both spray valves opening; ANSWER:

i

' B.' The reactor will trip on high pressurizer pressure and SI will actuate on low pressurizer I pressure due to spray valve operation.-

K/A #: 027AA1.01 RO IMPORTANCE: 4.0 KA DESCRIPTION: Pressurizer Pressure Channel Failure OBJECTIVE #: J&K.

REFERENCES:

T61.0110.6 LP 30. Pages 19 & 20 ;

i AUTHOR: DGL i SOURCE: New - H i i- DISTRACTER EXPLANATION:

A. Only one PORV will open (BBPCV0455A). !

C. Both spray valves and one PORV will open. l l

D. The reactor will trip on high pressurizer pressure, not OPAT.

RO Outline #R006 1 Lc

- QUESTION # 086 r) .

The following plant conditions exist:

.. . . Reactor tripped from 100% power due to an EARTHQUAKE. j

. The Condensate Storage Tank (CST) ruptured and is EMPTY.

. All.three (3) Auxiliary Feedwater Pumps (AFPs) are running.

. - No'other plant equipment was damaged.

Which ONE of the following is a consequence of this event? (Assume NO Operator Action is

taken.) .

l A.- .The Auxiliary Feedwater Pumps have no suction supply.

B. The Auxiliary Feedwater Pumps will trip on CST Lolo Level.

i C .- The Auxiliary Feedwater Pumps suction is being supplied by Essential Service Water. l D. The Auxiliary Feedwater Pumps suction is being supplied by the Service Water System. ;

', ANSWER:

C. The Auxiliary Feedwater Pumps ~ suction is being supplied by Essential Service Water.

KIA #: 062AK3.02 RO IMPORTANCE: 3.6 KA DESCRIPTION: ESW Response To ESFAS Signals OBJECTIVE #: D

REFERENCES:

T61.0110.6 LP 5, Page 32 AUTHOR: DGL SOURCE: New - H DISTRACTER EXPLANATION:

A. Suctions are supplied by ESW.

B. MCB alarm only, no automatic pump trips.

D. - Suctions are supplied by ESW.

RO Outline #RO12

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l QUESTION # 087 l

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The following plant conditions exist:

. Turbine load - STABLE.

. Reactor Power - 98%. 1

. RODS AT BOTTOM Annunciator-LIT I

. Bank 'O' Control Rods - Stepping outward in AUTOMATIC. j

. Tave - 3*F below Tref. j

-. RPI ROD DEV Annunciator- LIT.

. TWO / MORE RODS AT BOTTOM Annunciator- LIT.

. PR CHANNEL DEV Annunciator - LIT 1

Which ONE of the following IMMEDIATE ACTIONS should be taken?

A. Place rod control in manual and reduce turbine load to mainiain Tave and Tref AT less than 3*F.

8. Manually trip the reactor and proceed to E-0, Reactor Trip or Safety injection.

1

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< C. Place rod control in manual and withdraw rods as required to maintain Tave and Tref ;

Q matched.

D. Manually trip the reactor ONLY if RCS Tave decreases to < 551*F. ,

ANSWER:

B. Manually trip the reactor and proceed to E-0, Reactor Trip or Safety injection.

K/A #: 003AA2.01 RO IMPORTANCE: 3.7 KA DESCRIPTION: Indications of Multiple Dropped Rods OBJECTIVE #: B

REFERENCES:

T61.003B.6 LP 54, Page 1 I OTO-SF-00003

' AUTHOR: DGL SOURCE: Bank (Modified)- H DISTRACTER EXPLANATION:

A. Only correct if one rod is dropped.

C. Requires trip for multiple dropped rods.

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v D. Requires trip regardless of RCS temperature.

RO Outline #R018 L.

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QUESTION # 088 ,

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The following plant conditions exist:

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. A Small Break LOCA has occurred. ,

. No Adverse Containment conditions exist.

Which ONE of the following conditions would prevent St Termination?

A. Pressurizer Level is 16% and increasing. l

8. RCS Pressure is 1650 psig and stable. )

~

C. 'D' S/G NR Level is 8% and increasing. l 1

D. RCS Subcooling is 16*F and stable. i 1

ANSWER: )

i 7q D. RCS Subcooling is 16*F and stable. !

k.) i KIA #: W/E02EK1.2 RO IMPORTANCE: 3.4 KA DESCRIPTION: Si Termination Criteria OBJECTIVE #: P l

REFERENCES:

T61.003D.6 LP 8, Page 40 AUTHOR: DGL SOURCE: New - L i l

DISTRACTER EXPLANATION: l A. & B. & C. Meet Si Termination Criteria. ~

D. Correct - Less subcooled than instrument error.

1 RO Outline #R024

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QUESTION # 089 g

i Which ONE of the following differentiates between an unisolable feedwater line break and an unisolable steam line break of the same s;ze inside containment?

A. RCS depressurization rate would be greater for a feedwater line break.

B. RCS heat removal would be greater for a steam line break.

C. The affected S/G will begin to depressurize sooner for a feedwater line break.

D. Containment pressure would be lower for a steam line break.

ANSWER:

B. RCS heat removal would be greater for a steam line break.

KIA #: 054AK1.01 RO IMPORTANCE: 4.1 KA DESCRIPTION: Differences Between Feed / Steam Line Break

,,s OBJECTIVE #: A (LP 15), F (LP 3)

( )

REFERENCES:

T61.003D.6 LP 15. Pages 4,6 & 7 v' T61.003D.6 LP 3. Pages 29-33 AUTHOR: DGL SOURCE: New - H DISTRACTER EXPLANATION:

A. RCS temperature initially increases due to loss of cold feedwater causing RCS pressure to increase.

C. S/G pressure initially increases due to loss of cold feedwater.

D. Higher energy steam leak will result in greater containment pressure.

RO Outline #R030 r, J N-m/

L

~

~ QUESTION # 090-Which ONE of the following correctly describes why the 'B' and 'C' Si Accumulators have two vent valves?

A. The two vent valves are both powered from a non-safety related power supply.

B. Their outlet isolation valves are below the calculated Post-LOCA water level.

C. The accumulators vent piping is a smaller diameter than the vent piping on 'A' and 'D'.

D. Their outlet isolation valves are powered from a non-safety related power supply.

ANSWER:

B. Their outlet isolation valves are below the calculated Post-LOC'A water level.

K/A #: W/E15EK2.1 RO IMPORTANCE: 2.8 KA DESCRIPTION: Flooding Effects on Accumulator Iso Valves I

OBJECTIVE #: B i

REFERENCES:

T61.0110.6 LP 19, Page 6 -

O("

AUTHOR: DGL SOURCE: New - H DISTRACTER EXPLANATION:

A. & D. All valves have a safety-related power supply.

C. All vent piping is same size diameter.

RO Outline #R036 I ,

o L-

QUESTION # 091 r)

The following plant conditions exist:

. Operating at 90% power, MOL. )

. CCW flow through the letdown heat exchanger is decreased.

' (Assume NO automatic actions occur in the CVCS and NO operator actions are taken.)

Which ONE of the following describes how RCS temperature will be INITIALLY affected?

A. Decrease because the CVCS lon exchangers are releasing boron into the letdown flow.

B. Increase because the CVCS lon exchangers are absorbing boron from the letdown flow.

C. Decrease because Loop AT is being decreased by colder CVCS charging flow.

D. Increase because Loop AT is being increased by colder CVCS charging flow.

L l

ANSWER:

A. Decrease because the CVCS lon exchangers are releasing boron into the letdown flow.

K/A #: 004K5.20 RO IMPORTANCE: 3.6 KA DESCRIPTION: Effects of Boration l l

OBJECTIVE #: C.1.h l

REFERENCES:

T61.003A.6 LP A-9, Page 3 - )

OTN-EG-00001, Page 4 l i

AUTHOR: DGL SOURCE: New - H l DISTRACTER EXPLANATION:

B. Temperature decreases due to boron release.

C. & D. Charging temperature will be higher and has insignificant impact on RCS temperature.

i f

RO Outline #R042

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I- - QUESTION # 092 l .r-

! i

. The plant is in Mode 5 with an RCS temperature of 145'F?

I Which ONE of the following fan combinations must be in service to meet the MINIMUM requirement to prevent damage to equipment in containment (CTMT)?

\

A. 'A' and 'D' CTMT Cooler Fans and 'B' Cavity Cooling Fan B. 'A' and 'C' CTMT Cooler Fans and 'A' CRDM Fan C. 'B' and 'C' CTMT Cooler Fans and Pzr Cooling Fan D. 'B' and 'D' CTMT Cooler Fans and 'B' CRDM Fan ANSWER:

A. 'A' and 'D' CTMT Cooler Fans and 'B' Cavity Cooling Fan KIA #: 022K3.01 RO IMPORTANCE: 2.9 O

(g KA DESCRIPTION: Fans Required to Prevent Damage OBJECTIVE #: 1.1.b,1.1.c, & l.1.f

REFERENCES:

T61.003A.6 LP A-20, Page 6 OTN-GN-00001, Pages 1 & 2 AUTHOR: DGL SOURCE: New - H DISTRACTER EXPLANATION:

Fan lineup required is: 'A' or 'C' CTMT Cooler Fan One Cavity Cooling Fan Pzr Cooling Fan or 'D' CTMT Cooler Fan RO Outline #R048 I

i O l t

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H l

l QUESTION # 093

(-

l V l l Which ONE of the following RTD failures will result in Tave and AT indications both reading erroneously HIGH7 I

A. Tcoto RTD opens B. Tsor RTD opens C. Tcoto RTD shorts D. Tsor RTD shorts ,

1 i

l ANSWER:

B. Tsor RTO opens KIA #: 002K5.12 RO IMPORTANCE: 3.7 l KA DESCRIPTION: Tave / AT Response To RTD Failure

,n, OBJECTIVE #: A (LP SB-2), B (LP 10) i,'")

REFERENCES:

T61.0038.6 LP SB-2, Page 5 T61.0070.6 LP 10, Page 8 AUTHOR: DGL SOURCE: New - H DISTRACTER EXPLANATION:

A. Tcom increases, AT decreases, Tave increases.

B. Teow decreases, ATincreases, Tave decreases.

D. Tmr decreases, AT decreases, Tave decreases.

RO Outline #R060

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l l QUESTION #'094 r

i . .

L Which ONE of the following describes the normal alignment of the air systems for the TDAFP flow control valves?

A.- Instrument Air and N2 backup are both normally unisolated. N 2pressure is maintained

= 10 psi LOWER than instrument Air pressure.

B. N2 backup accumulator is normally charged to 370 psig and must be > 150 psia to be considered operable.

C. Instrument Air and N2 backup are both normally unisolated. N2 pressure is maintained

= 10 psi HIGHER than Instrument Air pressure.

- D. N2 backup accumulator is normally charged to 750 psig and must be > 270 psia to be considered operable.

ANSWER:

A. Instrument Air and N2 backup are both normally unisolated. N2 Pressure is maintained

= 10 psi LOWER than Instrument Air pressure.

O K/A #: 061A2.07 RO IMPORTANCE: 3.4 KA DESCRIPTION: Air Operated Flow Control Valves OBJECTIVE #: C

REFERENCES:

T61.0110.6 LP 25, Page 13 AUTHOR: DGL SOURCE: New- L DISTRACTER EXPLANATION:

B. & D. Normal pressure is 750 psig and operability pressure is 370 psia.

C. N2 si maintained = 10 psi LOWER.

RO Outline #R054 o

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r l

. . . QUESTION'# 095

.Q Q 'The following plant conditions exist L

. Reactor Power' - 50%

. :Pzr Pressure -- 2235 psig

. . Pzr Level -

41 %

Loop 1 Looo2 Looo 3 Loop 4

. ~ RCS Loop Tave 571*F 570*F 570*F 571*F

.. RCS Loop Tsor 586*F 585'F 585'F 587*F

. RCS Loop Teot.o 556*F 555*F 555*F 555'F l

Which ONE of tne following is the correct Pzr Level response if Loop 2 Tsorchannel fails LOW?

AJ increases to 57%.

B. Remains the same.

C. Decreases to 25%. I D. - Decreases to 17%.

ANSWER:

B. Remains the same. ,

K/A #: 016K3.02 RO IMPORTANCE: 3.4 KA DESCRIPTION: RTD Channel Failure OBJECTIVE #: D&J

REFERENCES:

T61.0110.6 LP 30, Pages 17 & 21 CMP 98-1039A '

AUTHOR: DGL SOURCE: ' New - H DISTRACTER EXPLANATION:

). Tsor fa:Is to 530*F, making Loop 2 Tave 542.5"F. Pzr Level uses Auctioneered High Tave so level will remain the same.

A. High End of Pzr Level Band.

. C. - Low End of Pzr Level Band.

'() D. Letdown isolation Setpoint.

RO Outline #RC66 1

V

QUESTION # 096 A seal water malfunction on the running condenser vacuum pump results in a d'egrading main condenser vacuum.

Which ONE of the following is the setpoint at which the standby condenser vacuum pump will automatically start?

A. 5.0 inches Hga - )

'B. 5.5 inches Hga C. 6.0 inches Hga D. 6.5 inches Hga ANSWER:

A. 5.0 inches Hga KIA #: 055K3.01 RO IMPORTANCE: 2.5

'0 KA DESCRIPTION: Vacuum Pump Auto Starts OBJECTIVE #: M'

REFERENCES:

T61.0110.6 LP 22, Page 24 l

AUTHOR: DGL SOURCE: New - L DISTRACTER EXPLANATION: .

B. No automatic action.

C. Blocks condenser steam dumps.

D. No automatic action.

RO Outline #R072 ,

, V t a

l QUESTION # 097

('~')

The following plant conditions exist: !

. Compressor Sequencer Selector Switch, KAHS0043, is selected to the CAB position.

. All three air compressors are selected to AUTOMATIC. j

. 'A' Air Compressor (CKA01 A)is running unloaded. l

. 'B' Air Compressor (CKA018) is not running. l

. 'C' Air Compressor (CKA01C) is running loaded. l

. KA-PV-11, Service Air isolation Valve is open.

Which ONE of the following describes the correct system response to an air leak that results in i air system pressure decreasing to 105 psig? )

l l

I A. Only CKA01 A and CKA01C are running and both are loaded.

B. All three air compressors are running, but only two are loaded.

C. Only CKA01 A and CKA01C are running and both are loaded, KA-PV-11 is closed.

D. All three air compressors are running and all three are loaded, KA-PV-11 is closed.

g

~

ANSWER:

D. All three air compressors are running and all three are loaded, KA-PV-11 is closed.

KIA #: 079A4.01 RO IMPORTANCE: 2.7 KA DESCRIPTION: Loss of Instrument Air Pressure OBJECTIVE #: D

REFERENCES:

T61.0110.6 LP 14, Page 24 AUTHOR: DGL SOURCE: New - H DISTRACTER EXPLANATION:

For this failure, the 2" air compressor would load, the 3" air compressor would start and load, and service air would isolate.

RO Outline #R078 (m

1 I

l C

l-QUESTION # 098 i

49 N/ The following plant conditions exist:

. Mode 6 with Core Alterations in progress.

. Source Range Channels: .0900 0910 SEN131 150 cps 210 cps SEN132 155 cps ; 215 cps Which ONE of the following is an expected response for these conditions?

A. MCB Annunciator 57A, SR Flux Doubled, is lit B. MCB Annunciator 65A, SR Hi Flux at S/D, is lit.

C. MCB Annunciator 77E, SR Hi Volt Fail, is lit.

D. MCB Annunciator 85E, SR Hi Flux Rx Trip, is lit.

ANSWER:

B. MCB Annunciator 65A, SR Hi Flux at S/D, is lit.

K/A #: 034A3.03 RO IMPORTANCE: 2.9

~< -KA DESCRIPTION: High Flux at S/D OBJECTIVE #: E

REFERENCES:

T61.0110.6 LP 28, Page 8 AUTHOR: DGL SOURCE: New - H DISTRACTER EXPLANATION:

A. Flux increases by 1.7 in 10 minutes.

C. 120 VDC below setpoint.

5 D.10 cps and not blocked.

RO Outline #R084 i

i Y

r L

. QUESTION # 099 d0 Which ONE of the following describes how an operator should enter into the RO logs that he i secured the 'A' RCP at 08307 (The time NOW is 0950.)

i A. "0830" is entered in the time column of the logs and "(Late Entry) Secured the 'A' RCP" is entered in the information column.

B. "0830" is entered in the time column of the logs and "(0950) Secured the 'A' RCP" is entered in the information column.

C. "0950"is entered in the time column of the logs and "(0830) Secured the 'A' RCP" is entered in the information column.

D. " Late Entry" is entered in the time column of the logs and "(0830) Secured the 'A' RCP" is entered in the information column. .

ANSWER:

A. "0830" is entered in the time column of the logs and "(Late Entry) Secured the 'A' RCP" is entered in the information column.

.O K/A #: 2.1.18 RO IMPORTANCE: 2.9 KA DESCRIPTION: Narrative Log Entries OBJECTIVE #: B.1 !

REFERENCES:

T61.003A.6 LP A-2, Page 2 I ODP-ZZ-00006, Page 2 AUTHOR: DGL .

SOURCE: Bank (Modified)- L ,

DISTRACTER EXPLANATION:

When a late' entry must be made, the following should be done:

1. Time the event actually happened is entered in the time column.

2. (Late Entry) The event as it happened is entered in the information column.

RO Outline #R090

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j--

I

. QUESTION # 100 Which ONE of the following actions should be taken per EOP Rules of Usage when a step can NOT be performed and NO contingency action is given?

l A. Transition to ES-0.0, Rediagnosis, to determine what procedure should be used.'

l

8. Implement FRG that most closely relates to the task that could not be l performed. l l C. Continue on in the current guideline in effect in the left-hand column.

D. Stop and consult the EDO for assistance. Do not continue in the current guideline.

ANSWER:

l C. Continue on in the current guideline in effect in the left-hand column.

O K/A #: 2.4.16 KA DESCRIPTION: EOP Rules of Usage RO IMPORTANCE: 3.0 OBJECTIVE #: 8.4.c

REFERENCES:

T61.003D5 LP 1, Page 40 AUTHOR: DGL SOURCE: Bank (Modified) -1.

l DISTRACTER EXPLANATION:

A. ES-0.0 is only used to determine appropriate recovery procedures.

l B. FRGs are only implemented when directed by procedure step or per CSF-1.

l D. Current guideline should be continued.

l RO Outline #R096 l

l O

1O l

l

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ES-401 Written Examination Form ES-401-6 Quality Assurance Checklist Facility: C a, U a w' Date of Exam: '//Z3['I'l Exam level: dO')SRO Initial Item Description a b c

1. Questions and answers technically accurate and ps aDDlicable to facility W $h kn

2. NRC K/As and learning objectives referenced for all ouestions g b5,) %

3. R0/SRO overlap is no more than 75 ercent, and SRO #IA #I^ g ouestionsareappropriateper10ChR55.43 % 41d

4. Question duplication from (practice exams, quizzes, and] the last two licensing exams is no more than 25 A7#

k!$

h percent IN/A for NRC-developed examsl BL m-

5. No question duplication from the license screenina/ audit exam g g54 ps ss

6. Bank use meets limits (no more than 50 percent from ps hi the bank / at least 10 percent new) 4 %{fff A

7. At least 50 percent of the questions on the exam %

(including all new questions 6b A9 comprehension / analysis level) are written at the , I\

8. References / handouts provided do not aive away answers b A7d b

9. Question distribution meets previously approved examination outline: deviations are justified 4 MM A

10. Que'stion )sychometric quality and format meet ES, Appendix L auidelines bp (5,J Q

II. The exam contains 100, one-point, multiple choice th items; the total is correct and corresponds to value on cover sheet U 6g l' b i

Printed Name / Signa ure Date

a. Author h<:JG.LahJ<./ '

./I J/"/99 )

b. Facility Reviewer (*) bdard T Neil b9 M 2[n/99

c. NRC Chief Examiner (*) fw W/w) E.LSarlf fdainCY S$1

d. NRC Regional Supervisor (*) John L eld M 4 ,lo\ @

Note: (*) The facility reviewer's signature is not applicable for NRC-developed examinations; two independent NRC reviews are required.

() See special instructions (Section E.2.c) for shaded boxes.

NUREG-1021 Interim Rev. 8, January 1997 L . d

ML20207C363

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