Text

NRC Operator Licensing Exam Rept 50-263/OL-96-01 (Including Completed & Graded Tests) for Tests Administered on 960909- 13.All Applicants Passed All Sections of Respective Exams & Issued Individual Licenses
	ML20134H382
Person / Time
Site:	Monticello
Issue date:	11/04/1996
From:	; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:	;
Shared Package
ML20134H363	List: ML20134H360; ML20134H382;
References
	50-263-OL-96-01, 50-263-OL-96-1, NUDOCS 9611140080
	Download: ML20134H382 (204)
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4 U.S. NUCLEAR REGULATORY COMMISSION REGION lli Docket No. 50-263 License No. DPR-22 Report No: 50-263/OL-96-01 Licensee: Northern States Power Company Facility: Monticello Nuclear Generating Station Location: 2807 W. County Road 75 Monticello, MN 55362 Dates: Sept 9 through 13,1996 -

Examiners: M. Bielby, Chief Licensing Examiner Region lli E. Plettner, Licensing Examiner Region ill L. Vick, Licensing Examiner Headquarters Approved by: M. N. Leach, Chief Operator Licensing Branch l

l 9611140080 961104 PDR ADOCK 05000263 V PDR

EXECUTIVE

SUMMARY

Monticello Nuclear Power Station Examination Reoort No. 50-263/OL-96-01 Initial licensed operator examinations were administered to three (3) individuals applying for Reactor Operator licenses and to four (4) individuals applying for Senior Operator licenses.

Results: The applicants appeared well prepared for the examination and their overall performance was good. All seven (7) applicants successfully passed all sections of their respective examinations and were issued individual licenses.

Trainina The training organization responded promptly and effectively to examiner requests during licensed operator examination validation and administration. The written examination level of difficulty, while acceptable, was considered low. Additionally, the quality verification for technical accuracy of job performance measures was lacking.

Plant Staff Operations, Health Physics and Security personnel were professional and cooperative throughout the examination process. Control room operators reduced applicant stress by allowing unlimited access to the control room.

ReDort Details h!mmarv of Examination Status Th'a licensee volunteered to participate in a pilot program in which the NRC initial operator license examination was prepared by the licensee, and reviewed and approved by the NRC.

Examination preparation and administration was prescribed by NUREG 1021, " Operator Licensing Examiner Standards," Revision 7, and superseded in part by Interim Pilot Examination Guidance approved by Nucleat Reactor Regulation / Headquarters Operator Licensing Branch (NRR/HOLB).

The examination was administered to three (3) reactor operator and four (4) senior reactor operator applicants in the form of individual written and operating examinations for licensing determination. The written examination was administered by the licensee at the Monticello Nuclear Power Station Training Center on September 6,1996. The operating examination was administered by NRC examiners at the Monticello Nuclear Power Station Training Center and plant site during the week of September 9,1996. All seven (7) applicants successfully passed all sections of their respective examinations.

1

1. Operations i 05 Operator Training and Qualification 05.1 General Comments Training department personnel were responsive to examiner demands during validation and administration of the written and operational examinations.

Dedication of a separate room with locked access control and off-line computer demonstrated an adequate examination security system for preparation and control of examination paper copies. The licensee personnel contacted demonstrated a cooperative and professional demeanor throughout the examination week.

05.2 Examination Preoaration and Validation The licensee submitted a sample plan, examination outline, and final examination to the NRC regional office for review. NRC validation of the written and operational examination material was conducted at the training facility. The NRC reviews and validation resulted in many revisions to the written and operational examination material. However, these revisions were consistent with previously administered examinations at like facilities.

During validation, the licensee allotted one training supervisor and one instructor to preview the written examination material, and an additional simulator instructor and operations representative to assist with the operating examination review. This effort was necessary to ensure exam validity from a technical content.

Suggestions by both the operations reprosentative and training staff improved the overall operating examination quality. However, during examination administration 3

. - _ . - _ . ~ - . . . . - _ - _ - _ - - . . . .- _ - . .

the NRC examiners observed the following technical discrepancies for job performance measures (JPMs):

) e initial conditions specified for performing the control rod coupling test did not match the JPM specified conditions.

One question on the feedwater regulation valve (FWRV) asked for the effect

, on plant operations if the steam flow or feedwater flow transmitter was i valved out, but did not specify whether the FWRV was in three or single element control.

4

The stem of the second question for use of alternate injection (using residual heat removal service water) for reactor pressure vessel makeup cues the answer to the first question on the same JPM.

The written examination was technically accurate as evidenced by no post j examination comments. NRC examiners concluded the examination met the

! examination standard guidance and would discriminate a competent from less than competent license applicant. However, while acceptable, the administered i

examination level of difficulty was still considered low as evidenced by the following examples of question deficiencies:

1 4

e Distractors which could be eliminated without having to reference information in the question stem (i.e. two distractors that indicated exact opposite responses such as decrease and increase, one being the correct j answer, along with two distractors not related).

e Specific plant conditions or events identified in the question stem instead of l providing symptoms or parameters which would require comprehension or analysis to predict or determine plant or system status. I i

The technical accuracy of pre-examination reviews for the written examination was effective as evidenced by the lack of post examination comments. However, the

level of difficulty of the submitted written exam and quality verification of the JPMs i

was lacking.

05.3 Examination Administration and Suncort

{

The following information is provided for evaluation by the licensee via their Systems Approach to Training (SAT) based program. No response is required,

a. Written Examination l

The written examination was a 100 point multiple choice format prepared by i the licensee, reviewed and approved by the NRC, and administered by the licensee. The examination was technically accurate as evidenced by no post ,

examination comments. '

! l 4

4

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b. Job Performance Measures (JPMs) - Walkthrouah Examination Operator performance during the walkthrough portion (JPMs) was l appropriate for the task assigned. Individual performance deficiencies were I noted on each Operator License Examination Report and should be reviewed l for SAT based program feedback. !

c. Dynamic Simulator Scenarios l

1 Operator performance during the dynamic simulator examination was 1 appropriate for the plant conditions and events observed. No common operator performance deficiencies were identified during the exam administration.

05.4 Hi!pulator Observations he simulator discrepancies were identified, and the simulator performed as wsigned throughout the exam (see Enclosure 2).

Manaaement Meetinas X1 Exit Meeting Summary The examiners presented their observations and findings to members of licensee management at the conclusion of the examination on September 13,1996. The licensee acknowledged the findings presented. The examiners asked the licensee whether any materials reviewed during the examination should be considered proprietary. No proprietary information was identified.

X 1.1 Partial List of Persons Contacted Facility T. Witchen, Acting Plant Manager B. Day, Training Manager B. Sawatzke, Operations Training Superintendent J. Shriver, Senior Technical Instructor K. Markling, Technical Instructor K. Peterson, Technical Instructor J. MacIntyre, Classroom Coordinator U. S. Nuclear Reaulatory Commission (NRC)

A. M. Stone, Senior Resident inspector M. Bugg, Intern 5

1 1

Enclosure 2 SIMULATION FACILITY REPORT l

Facility Licensee: Monticello Nuclear Power Station I Facility Docket No.: 50-263 l

Operating Test Administered on: Week of September 09,1996 I This form is to be used only to report observations. These observations do not constitute audit or inspection findings and are not, without further verification and review, indicative of noncompliance with 10 CFR 55.45(b). These observations do not affect NRC l certification or approval of the simulation facility other than to provide information that may be used in future evaluations. No licensee action is required in response to these ;

observations.

While conducting the simulator portion of the operating tests, the following items were observed (if none, so state):

ITEM DESCRIPTION None.

I l

i y.

Enclosure 3 - f i.

j Post Examination )

Comments and Review l l l l l. NRC Post Written Examination Review:

J l The following are NRC post written examination review of questions for which 50%

i or more of the applicants failed to select the proper response. These are provided j to the Monticello Nuclear Power Station training staff for consideration and

{ implementation into the SAT based program:

4

'i

Question Descriotion of Weakness 3

NO QUESTIONS MEET THE ABOVE CRITERIA.

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t 1

l i

1

i

\

Enclosure 4 d

4 EXAMINATION AND ANSWER KEY (SP.O and RO) t l

l

MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR Revision 0 3

LICENSE EXAMINATION Page 1 of 102 4

1 AII work on this examination is my own. I have neither given nor received any cs:Istance.

i i

Crndidate's Name: Date:

i !

4 1

4

i i ,

s i i 5

\!

j Prepared By: MM@ #

Reviewed By: [kv g Approved By ggg '

Effective Date:h 7 - r- 74

/y Corrected By: Grade Verified By:

Points Total Total

/

i Scored Points Time Authenticated By' 100 NA Date:

! I/mit SEP10 "

~ _ _

MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0

. EXAMINATION - ANSWER KEY Page 2 of 102 Candidate's Name: Date:

ANSWER SHEET

1. C 2. C 3. B 4. B 5. C

6. B 7. B 8. D 9. C 10. A l

11. D 12. D 13. C 14. D 15. B j 16. D 17. B 18. D 19. A 20. C

21. B 22. C 23. C 24. D 25. C

26. B 27. B 28. B 29. A 30. B

31. A 32. B 33. A 34. A 35. C l 36. D 37. D 38. A 39. C 40. C i

41. D 42. B 43. A 44. A 45. D i

d

46. B 47. C 48. B 49. C 50. C

51. B 52. A 53. B 54. C 55. C

56. D 57. D 58. B 59. A 60. D 1

61. B 62. B 63. B 64. C 65. B

66. B 67. A 68. A 69. A 70. C j 71. D 72. D 73. B 74. D 75. C i 76. C 77. B 78. B 79. A 80. B

81. A 82. B- 83. D 84. C 85. A i

86. C 87. B 88. D 89. C 90. C l 91. B 92. B 93. B 94. D 95. A

96. C 97. B 98. D 99. C 100. C I/mif

, MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 3 of 102 l Exam Question Number: 1 Point Value: 1.00 Time (Minutes):

Given:

i = Drywell pressure 14 PSIG

=

Reactor water level-190 inches

! = Torus temperature 118 degrees F

=

3 ADS valves open with reactor pressure at 300 PSIG and decreasing Which of the following operator actions is required?

A. Place drywell sprays in service.

, B. Place all available torus cooling in service.

4 C. Inject with all available systems to the vessel.

D. Place core spray pumps in Pull-to-Lock.

i Answer:

i C J

l i

Question Number: 1-C.5-1000-067

, Reference (s):

1. C.5-1000

2. C.5.1-1200 K/A

Reference:

226001 t

Task Number: A3.05 Rating RO/SRO: 4.0/

i Monticello JTA:

Objective (s):

System Code: NA i

i I/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 4 of 102 Exam Question Number: 2 Point Value: 1.00 Time (Minutes):

The Shift Supervisor directs you to rack out a 4160 breaker. The minimum protective equipment you are requir3d to wear per the Monticello Safety Manual is:

. A. Fireman's outer coat and lining, electrical switching pants and a hard hat with facial shield.

B.

Electrical switching pants, high voltage protective gloves ahd keepers and a hardhat with facial shield.

C. Fireman's outer coat and lining, hard hat with facial shield and high voltage protective l gloves and keepers.

D. Fireman's outer coat and lining, electrical switching pants and high voltage protective gloves and keepers. ,

4 i

Answen C

Question Number: l-NSPSM-007 Reference (s):

1. SM.D8-01-4.5.7 K/A

Reference:

294001 Task Number: K1.07

Rating RO/SRO: 3.3/3.6 Monticello JTA:

l Objective (s):

System Code: NA t

1/mit

MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 5 of 102 Exam Question Number: 3 Point Value: 1.00 Time (Minutes):

When performing stroke time testing on motor operated valves certain criteria must be met to ensure operability requirements of the valve. Which of the following is correct when performing motor operator valve stroke time testing?

A. The closing valve stroke time shall be measured from the time the green indication light comes on until the red indication light goes off.

B. The opening valve stroke time shall be measured from the time the control switch is placed in the open direction until the green indication light goes off.

C. Motor operated valves may be stroked up to 3 times before declarino the valve inoperable.

D. When the recorded time is rounded off to the nearest second, apply the method of always rounding up to the next highest valve. (e.g. a stroke time of 10.3 seconds should be rounded up to 11.0 seconds.)

Answer:

1 B

4 1

Question Number: 1-4AWi-09-001 Reference (s):

1. 4 AWi-09.04.01 K/A Referenco: 294001 Task Number: A1.08 Rating RO/SRO: 3.1/

Monticello JTA:

Objective (s):

System Code: NA I/mlf

l MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 6 of 102 Exam Question Number: 4 Point Value: 1.00 Time (Minutes):

Given:

- Group I auto isolation with all MSIV's closed

Feedwater high pressure heater block valves MO-1614 and MO-1615 closed.

Reactor water level -30 inches.

Drywell pressure 4.5 PSIG.

Reactor pressure 800 PSIG.

Which of the following correctly describes HPCI system operation?

A. HPCI steam supply is available, HPCI will auto start but not inject to the vessel.

B. HPCI steam supply is available and HPCI will inject to the vessel.

C. HPCI steam supply is unavailable.

D. HPCI steam supply available, however HPCI will MQI auto start and inject to the vessel.

Answer:

B Question Number: 1-B.03.02-024 Rsference(s):

1. B.03.02-02 K/A

Reference:

206000 Task Number: K1.04 Rating RO/SRO: 3.6/3.6 Monticello JTA:

Objective (s):

System Code: NA l/mlf

I 1

l MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 ,

TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 l EXAMINATION - ANSWER KEY Page 7 of 102 l Exam Question Number: 5 Point Value: 1.00 Time (Minutes):

Per the operations manual, the reactor building ventilation exhaust high radiation trip closes a 1 number of class B isolation valves which, if inadvertently closed, wou d neither adversely affect i plant safety nor interfere significantly with plant operations. PCIS class B isolation valves are on l process lines that: 1 A. Penetrate the primary containment but do not communicate directly with the reactor vessel or primary containment free space.

B. Communicate directly with the reactor vessel and penetrate primary containment.

C. Do not communicate directly with the reactor vessel but communicate directly with the primary containment free air space. l D. Do not communicate with either the reactor vessel or primary containrnent.

Answer:

l C

Question Number: 1-B.05.06-030 Reference (s):

1. B.05.06-01 K/A

Reference:

295020 Task Number: AA1.01 Rating RO/SRO: 3.6/3.6 Monticello JTA:

Objective (s):

System Code: NA I/mif

J MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 8 of 102 Exam Question Number: 6 Point Value: 1.00 Time (Minutes):

I Which one of the following locations is a vital equipment area and could endanger the public h@alth and safety by exposure to radiation if a uncontrollable fire broke out? l

A. Main turbine.

B. 4 KV room.

C. 345 KV subyard.

D. 13 diesel generator.

4 i

Answer:

8 4

Ouestion Number: 1-10CFR-002 Reference (s):

. 1. 10CFR73 2, 4 awl-08.06.01 J

K/A

Reference:

294001 Task Number: K1.05 i Rating RO/SRO: 3.2/3.7 Monticello JTA: 2990020301

. Objective (s): M-8108L-002, EO-5

! System Code: N/A J

2 i

i 1/mif

l MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 9 of 102 Exam Question Number: 7 Point Value: 1.00 Time (Minutes):

Given:

- 100% power

. Both recombiners trip unexpectedly The duty crew has reduced reactor power to 20% with recirc and control rods. A further power reduction is needed. Which of the following is required in accordance with C.4-F (RAPID POWER REDUCTION)?

A. Bypass the RWM to reduce reactor power with control rods.

B. Manually scram the reactor. l C. Trip one recirc pump. l D. Use the emergency rod insertion control switch to insert control rods and reduce reactor power.

l Answer: <

B Question Number: 1-C.4-F-001 Reference (s):

1. C.4-F K/A

Reference:

295015 Task Number: AK3.01 Rating RO/SRO: 3.4/3.7 Monticello JTA:

Objective (s):

System Code: NA I/mif

't MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 10 of 102

, Exam Question Number: 8 Point Value: 1.00 Time (Minutes)-

. Given:

l

Reactor power 30%

Both RBM channels are operable l Reference APRM channel for RBM 7 has failed downscale l RBM 7 will receive a reference signal from...

A. APRM S upon detection of the reference APRM downscale.

B. APRM 1 when the bypass switch for APRM 3 is placed in bypass.

C. the same APRM that supplies RBM 8.

D. APRM 2 when the bypass switch for APRM 3 is placed in bypass.

I Answer:

D Question Number: 1-B.05.01.02-043 Rsference(s):

1. B.05.01.02 K/A

Reference:

215002 Task Number: A2.03 Rating RO/SRO: 3.1/3.3 Monticello JTA:

Objective (s):

System Code: NA l/mlf

MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 11 of 102 Exam Question Number: 9 Point Value: 1.00 Time (Minutes):

A fire in the cable spreading room has required immediate control room evacuation with no time available to perform subsequent operator actions. Which of the following is the correct immediate operator response in accordance with C.4-C (SHUTDOWN OUTSIDE THE CONTROL ROOM)?

A. Do not manually scram with pushbuttons, place Reactor Mode Switch in SHUTDOWN, do

. NOT close MSIVs.

B. Do net manually scram with pushbuttons, leave Reactor Mode Switch in RUN, close MSIVs.

C. Manually scram with pushbuttons, leave Reactor Mode Switch in RUN, do NOT close MSIVs.

D. Manually scram with pushbuttons, place Reactor Mode Switch in SHUTDOWN, close MSIVs.

t Answer:

, C j

l Question Number: l-C.4-C-001 Reference (s):

1. C.4-C K/A

Reference:

295016 Task Number: SG 10 Rating RO/SRO: 3.9/3.7 Monticello JTA:

Objective (s):

System Code: NA I/mif

1 MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 12 of 102 l

l Exam Question Number: 10 Point Value: 1.00 Time (Minutes): l Given:

- Reactor power 100%

Electrical Pressure Regulator (EPR) set at 905 PSIG Mechanical Pressure Reguattor (MPR) set at 925 PSIG

{

= Reactor pressure 1000 PSIG.

1 If the EPR setpoint fails high, reactor pressure will...

A. Increase and reactor power will increase. l B. decrease and reactor power will decrease.

4 C. Increase and reactor power will decrease.

i D. decrease and reactor power will increase.

)

1 Answer:

il A

i

Question Number: 1-C.4-B.05-005 Reference (s):

1. C.4-B.05.09.B 1

K/A

Reference:

295007 Task Number: AK1.03 Rating RO/SRO: 3.8/3.9 Monticello JTA:

Objective (s):

System Code: NA a

j 1/mlf

l MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 13 of 102 Exam Question Number: 11 Point Value: 1.00 Time (Minutes):

The Reactor Recirculating Flow Control system utilizes in auts from the feedwater system. Which of the following describes the bases for this design. The feedwater interlock...

A. 3revents operation of the reactor recirc pumps at speeds greater than 30% until both WO-1614 and MO-1615 (FW Heater Outlet Valves) are open.

4 B. assures that the temperature of the water in the annulus region has been raised above saturation temperature prior to increasing speed of the reactor recirc pumps.

C. reduces reactor recirc pump speeds to 48% on decreasing feedwater flow to assure adequate sub-cooling of the reactor recirc pump suction water such that the pumps NPSH requirements are maintained.

D. prevents high speed operation of the reactor recirc pumps at feedwater flows less than 20% in order to protect the reactor recirc pumps from cavitation.

t Answer:

D Question Number: 1-B.01.04-055 Reference (s):

1. B.01.04-01, 8.05.08-01, C.4-A, DBD-B.01.04 K/A

Reference:

259002 Task Number: K4.01 Rating RO/SRO: 3.0/3.1 Monticello JTA:

Objective (s):

System Code: NA I/mif

l MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 14 of 102 Exam Question Number: 12 Point Value: 1.00 Time (Minutes):

During a reactor startup, the C-05 operator attempts to withdraw a control rod and gets no response. The operator observes the following CRD system indications:

CRD drive pressure is 200 PSIG. l

CRD discharge pressure is 1485 PSIG.

Based on these indications what action shall the operator perform prior to attempting to withdraw the rod again? You should throttle...

A. open the selected CRD flow control valve CV 3-19A or B.

B. close the selected CRD flow control valve CV 3-19A or B.

C. open valve MO 3-20 drive pressure to CRD.

D. close valve MO 3-20 drive pressure to CRD.

Answer:

D Question Number: 1-B.01.03-026 Reference (s):

1. B.01.03-01 K/A

Reference:

201001 Task Number: K4.09 Rating RO/SRO: 2.9/2.8 Monticello JTA:

Objective (s):

System Code: NA I/mlf

(

MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 15 of 102

)

i Exam Question Number: 13 Point Value: 1.00 Time (Minutes):

Given the following information:

t A reactor scram occurred 15 minutes ago and the scram has not been reset. The RWCU system was in service to assist in maintaining reactor water level. RWCU dump flow was routed to the hotwell. The reactor operator observed the closure of the following valves MO-2399, RWCU RETURN ISOLATION and MO-2404, RWCU DUMP TO HOTWELL .

Which of the following caused the valves to close?

A. Temperature at the RWCU non-regenerative heat exchanger inlet is 150 degrees F.

B. Reactor water level has decreased to +2 inches.

C. Temperature at the RWCU filter demineralizer inlet is 150 degrees F.

D. Pressure downstream of RWCU excess FCV CV-2403 is 165 PSIG.

Answer:

C Question Number: 1-B.02.02-020 Reference (s):

1. B.02.02 K/A

Reference:

204000 Task Number: K4.04 Rating RO/SRO: 3.5/3.6 Monticello JTA:

Objective (s):

System Code: NA l/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 16 of 102 4

Exam Question Number: 14 Point Value: 1.00 Time (Minutes):

I The operator is allowed some flexibility when performing the steps in procedure C.1. If conducting a plant startup, which of the following would be correct?

A. Placing the second RFP in service at 80% power.

B. Omitting steps not required.

O. Increasing recirc flow and withdrawing control rods concurrently.

. D. Establishing steam flow to the condenser prior to the second condensate pump being j 4

placed in service. '

l Answer:

D Question Number: 1-C.01-029 R@ference(s):

1. C.01 K/A

Reference:

294001 Task Number: A1.02 Rating RO/SRO: 4.2/4.2 Monticello JTA:

Objective (s):

System Code: NA l/mif

t MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 :

TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 17 of 102

Exam Question Number: 15 Point Value: 1.00 Time (Minutes): ;

1 2

Given: l

. Reactor power 100%

l Plant entered 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months LCO due to loss of LC-104.

If No.11 RBCCW pump trips, which of the following is required in accordance with procedures j C.4-B.2.5.A (LOSS OF RBCCW FLOW)? i 1

A. Manually start No.12 RBCCW pump. I B. Trip both recirc pumps within 60 seconds.

C. Reduce recirc flow to minimum and manually scram the reactor.

D. Isolate SW to RBCCW heat exchangers.

i ll i

Answer:

i B Question Number: 1-C.4-B.02-009 1 !

Reference (s): !

4 1. C.4-B.02.05.A K/A

Reference:

295018 Task Number: AK1.01 Rating RO/SRO: 3.5/3.6 Monticello JTA:

Objective (s):

System Code: NA

)

1/mlf

MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 18 of 102 Exam Question Number: 16 Point Value: 1.00 Time (Minutes):

Which of the following signals will cause the Reactor Recirc pump speed control signal to automatically run back to 45% speed?

A. Reactor is at 75% power and Recirc Pump 11 discharge valve drifts to 90% open.

B. Reactor startup is in progress, one RFP is running, and reactor water level is at +45 inches and rising.

C. Reactor is at 75% power and a " Lockout" of 4160 volt bus 11 occurs.

D. Reactor is at 75% power and Condensate Pump 11 trips.

Answer:

D Question Number: 1-B.05.08-011 Reference (s):

1. B.05.08-01

2. B.01.04-02 K/A

Reference:

295009 Task Number: AK3.01 Rating RO/SRO: 3.2/3.3 Monticello JTA:

Objective (s):

System Code: NA I/mif

l MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 19 of 102 1

Exam Question Number: 17 Point Value: 1.00 Time (Minutes):

During power operations you observe that APRM 1,2, and 3 go downscale. Which of the following caused this event to occur? l A. RPS MG Set No.12 breaker tripping open due to undervoltage relay failure.

B. RPS MG Set No.11 motor bearings seizing the shaft.

C. 125 VDC Div I charger output having decrease to 100 VDC.

D. 125 VDC Div ll inverter failure.

Answer:

B Ouestion Number: 1-B.05.01.02-041 Reference (s):

1. B.05.01.02-02 l K/A

Reference:

215005 Task Number: K6.01 Rating RO/SRO: 3.7/3.8 Monticello JTA:

Objective (s):

System Code: NA I/mif

1 MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 l TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 I

EXAMINATION - ANSWER KEY Page 20 of 102 J

Exam Question Number: 18 Point Value: 1.00 Time (Minutes):

During a loss of normal offsite power No.11DG has been loaded at 2750 KW for 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months . If power cannot be restored, how long can No.11 EDG continue 1o run under these conditions?

. A. 452 hours0.00523 days 0.126 hours 7.473545e-4 weeks 1.71986e-4 months .

B. 952 hours0.011 days 0.264 hours 0.00157 weeks 3.62236e-4 months .

C. 1452 hours0.0168 days 0.403 hours 0.0024 weeks 5.52486e-4 months .

D. 1952 hours0.0226 days 0.542 hours 0.00323 weeks 7.42736e-4 months .

]

i 1

Answer:

D

}

Question Number: 1-B.09.08-046 Reference (s):

! 1. B.09.08-02 K/A

Reference:

264000 i

Task Number: K3.01

Rating RO/SRO: 4.2/4.4 Monticello JTA:

Objective (s):

System Code: NA 4

O I/mlf

MONTICELLO NUCLEAR GENERATING PLANT M81000 9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 21 of 102 Exam Question Number: 19 Point Value: 1.00 Time (Minutes):

Which of the following is NOT an acceptable means of controlling reactor vessel temperature while operating in the shutdown cooling mode with 1 RHR and 1 RHRSW pump in service?

A. Starting and stopping the RHRSW pump.

B. Throttling the RHRSW Hx bypass valve.

C. Throttling the RHR Hx inlet valve 4-1 or 4-2.

i D. Adjusting RHRSW flow between 1800 and 4000 GPM.

'l l

Answer:

A l

Question Number: 1-B.08.01.03-006 i

R ference(s):

1 1. B.08.01.03-05 K/A

Reference:

205000 Task Number: K6.08 i Rating RO/SRO: 3.5/

Monticello JTA:

Objective (s):

System Code: NA 1/mlf

MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 22 of 102 Exam Question Number: 20 Point Value: 1.00 Time (Minutes):

Following 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of operation below 80% power for load following, the Monticello plant is requested to return to 100% power. While increasing power, alarm 4-A-2 (OFF-GAS TIMER ACTUATED) initiates.

Which of the following correctly describes how the Off-gas system will respond with no operator action?

A. Any recombiner train in the operate position will trip immediately.

B. Any off-gas compressor in service will trip immediately.

C. Any recombiner train in operate will trip after a 30 minute time delay.

D. Any off-gas compressor in service will trip after a 30 minute time delay.

Answen C

Question Number: 1-B.05.11-035 Reference (s):

1. B.05.11 K/A

Reference:

271000 Task Number: K6.09 Rating RO/SRO: 3.4/

Monticello JTA:

Objective (s):

System Code: NA I/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 23 of 102 Exam Question Number: 21 Point Value: 1.00 Time (Minutes):

Given:

Reactor water level +9 inches

. Fuel pool monitor indicates 57 mR/hr. I

. Reactor Building vent WRGM indicates 4700 uci/sec.

. Reactor Building vent monitor indicates 20 mr/hr.

. Drywell pressure 1.8 PSIG.

Which of the following automatic responses is correct?

l A. LPCI Loop select logic has energized.

B. SBGT system has auto initiated.

C. RCIC has auto initiated.

D. Core spray pumps have auto initiated.

Answer:

B l

Question Number: 1-B.05.11-036 Reference (s):

1. B.05.11-01 K/A

Reference:

295023 l Task Number: AK2.07 l 1

Rating RO/SRO: 3.6/3.9 .

I Monticello JTA: i 1

Objective (s): )

i System Code: NA I 1/mif

l MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 24 of 102 Exam Question Number: 22 Point Value: 1.00 Time (Minutes):

During your shift the plant experiences a total loss of instrument air. Which of the following correctly describes the operation of the feedwater control valves?

A. Main Feedwater Control valves CV-6-12A & CV-6-128 fail OPEN and Low Flow Control valve CV-6-13 fails CLOSED.

^

B. Main Feedwater Control valves CV-6-12A & CV-6-128 fail CLOSED and Low Flow Control valve CV-6-13 fails OPEN.

C. Main Feedwater Control valves CV-6-12A & CV-6-12B fail AS-IS and Low Flow Control valve CV-6-13 fails OPEN.

, D. Main Feedwater Control valves CV-6-12A & CV-6-12B fail AS-IS and Low Flow Control

! valve CV-6-13 fails CLOSED.

P Answer:

C Question Number: 1-B.05.07-013 Rcference(s):

1. B.05.07-01

2. C.4-B.08.04.01 K/A

Reference:

295019 Task Number: AK2.03 Rating RO/SRO: 3.2/

Monticello JTA:

Objective (s):

System Code: NA I/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 25 of 102

. Exam Question Number: 23 Point Value: 1.00 Time (Minutes):

Which of the following is a refuel interlock failure?

A. Refuel bridge over the core, mode switch in startup, reverse travel blocked.

B. Refuel bridge over the core, mode switch in refuel,1 rod at position 48, reverse travel blocked.

C. Refuel bridge over the core, fuel grapple not full up,1 control rod at position 48, reverse travel permitted.

D. Refuel bridge over the core. Mode switch in refuel, all rods at 00. Reverse travel permitted.

/

Answer:

O i

Question Number: 1-B.05.05-020 Reference (s):

1. B.05.05-06 K/A

Reference:

234000 Task Number: A2.01 Rating RO/SRO: 3.3/3.7

]

Monticello JTA:

Objective (s):

System Code: NA N

1/mif

1 MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 i TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 26 of 102 Exam Question Number: 24 Point Vaiue: 1.00 Time (Minutes):

1 Given:

Reactor at 10% power Turbine / Generator on line Plant staff has decided to remove the Turbine / Generator from service to perform minor work on j the exciter brushes. The Shift Supervisor directs you to place the PRO switch to OPEN. This results in the...

I A. bypass valves opening and removing steam load to the turbine.

B. control valves closing causing a Reactor high pressure scram.

C. stop valves closing causing a. Reactor high pressure scram.

D. control valves opening causing a low main steam line pressure Group i isolation.

Answer:

D Question Number: 1-B.05.09-013 Reference (s):

1. B.05.09-02 K/A

Reference:

245000 Task Number: K6.02 Rating RO/SRO: 3.5/3.7 Monticello JTA:

Objective (s):

System Code: NA l/mlf

' MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 27 of 102 Exam Question Nurnber: 25 Point Value: 1.00 Time (Minutes):

The plant is operating at approximately 56% power with reactor water level at +35 inches. The Feec water Level Control System (FWLCS) is in 3 element control. Which of the followin,g correctly describes the final outcome of reactor water level and the FWLCS when the "A, Feedwater Flow indication suddenly fails high .

A. Reactor water level will remain the same. Steam flow and feed flow will remain matched.

FWLCS will remain in 3 element control.

B. Reactor water level decreased to +30 inches. FWCLS will sense a deviation between steam flow and feed flow and close down on Feedwater control valves. FWLCS will remain in 3 element control.

C. Reactor water level will remain the same. Actual feed flow and steam flow will remain the same. FWLCS will shift to single eiew-i ontrol.

D. Reactor water leve! increased to +4u ...enes. Steam flow will increase to match Feed flow.

FWLCS will shift to single element control.

Answer:

C Question Number: 1-B.05.07-011 Reference (s):

1. B.05.07 K/A

Reference:

295009 Task Number: AA2.02 Rating RO/SRO: 3.6/

Monticello JTA:

Objective (s):

System Code: NA I/mit

MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 28 of 102 Exam Question Number: 26 Point Value: 1.00 Tme (Minutes):

Prior to placing HPCI in service, the operator is directed to place torus cooling in service if time permits. The reason for this procedural requirement is to...

A. ensure that torus temperature will remain below 90 degrees F.

B. prevent localized torus temperature transients.

C. prevent chugging in the HPCI turbine exhaust piping.

D. ensure that a steam environment cannot exist in the torus air space.

Answer:

B l

Question Number: 1-B.03.02-022 I Rsference(s): l

1. B.03.02-05 K/A

Reference:

295013 Task Number: AA2.02 i Rating RO/SRO: 3.2/34.0 ,

Monticello JTA:

Objective (s):

System Code: NA l/mif

1 MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 29 of 102 Exa n Question Number: 27 Point Value: 1.00 Time (Minutes):

During a loss of circulating water event condentar vacuum. decreases to 22" Hg. Which of the following correctly describes plant status?

~

A. The turbine has tripped as a result of low condenser vacuum [ ~

j B. The reactor has scrammed as a result of low condenser vacuum.

C. The turbine bypass valves have closed as a result of low condenser v cuum.

D. There will be no change to plant status provided circulating water system is restored prior to condenser vacuum of 20" Hg.

a e

Answer: !

B Question Number: 1-B.05.06-31 f Rnference(s): .

j 1. B.05.06-02 K/A

Reference:

295002 l Task Number: AA1.03 1 Rating RO/SRO: 3.4/

Monticello JTA:

Objective (s):

System Code: NA

}

1 1/mif

MONTICEL50 NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 30 of 102 Exam Question Number: 28 Point Value: 1.00 Tme (Minutes):

While operating at 100% power you are on duty as a licensed operator along with 2 SRO's and 1 other RO license operator are on shift. If one of your above co-workers were to become ill and 12 ave the site, which requirement if any would need to be fulfilled.

A. No action required as you still meet the minimum manning requirements.

B. Take immediate action to replace the individual within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

C. Ensure a qualified member for the fire brigade is on site and/or take immediate action replace the individual within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

D. Immediately verify the next scheduled operating crew has a full compliment of operators.

Answer:

B Question Number: l-TS-033 Reference (s):

1. Tech Spec 6.0 K/A

Reference:

294001 Task Number: A1.03 Rating RO/SRO: 2.7/3.7 Monticello JTA:

Objective (s):

System Code: NA l/mif

i l

MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 i I

EXAMINATION - ANSWER KEY Page 31 of 102 Exam Question Number: 29 Point Value: 1.00 Time (Minutes):

Five (5) seconds after a reactor scram you attempt to reset the RPS trip logic to close the CRD I scram valves. You cannot reset the scram because...

A. a 10 second time delay prevents resetting the scram to ensure all control rods insert. l B. a 10 second time delay prevents resetting the scram to ensure all SDV vent and drains

cycle close.

C. a 30 second time delay prevents resetting the scram to allow low low set to actuate.

D. a 30 second time delay prevants resetting the scram to allow the CRD flow control valve to i cycle and respond to the increased system flow.

I

, i

]

Answer:

l A

4 l l

Ouestion Number: 1-B.05.06-029 l Reference (s):

1. B.05.06-02 l K/A

Reference:

295006 I Task Number: AK2.01 Rating RO/SRO: 4.3/4.4 Monticello JTA:

Objective (s):

System Code: NA -

1/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 32 of 102 l

Exam Question Number: 30 Point Value: 1.00 Time (Minutes): l i

Given: l Main steam chase temperature is 300 degrees F and increasing.

Numerous turbine building area rad monitors show an increase in radiation.

Reactor vessel cooldown is greater than 100 degrees per hour.

Which of the following is correct?

A. A main steam line rupture has occurred in the condenser room and the Uc , uut panels released at .25 inches of water dp to protect secondary containment.

B. A main steam line rupture has occurred in the steam chase and the blow out panels released at 7 inches of water dp to protect secondary containment integrity.

C. A main turbine casing rupture has occurred resulting in an increase in turbine building radiation.

D. A FW line rupture has occurred on the turbine floor resulting in an increase in turbine

building radiation.

4 h

I i Answer:

B Question Number: 1-B.04.02-021 Rnference(s):

1. B.04.02-02 K/A

Reference:

295035 Task Number: EK1.01 Rating RO/SRO: 3.9/4.2 Monticello JTA:

Objective (s):

System Code: NA l/mif

. MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 33 of 102 j

l Exam Question Number: 31 Point Value: 1.00 Time (Minutes):

While on back shift, LC supply breaker 52-101 develops a fault and fails to open. Due to this failure a fire breaks out in the cubicle, requiring fire brigade response. Which of the following by procedure should you,as a member of the fire brigade, provide?

A. Class C extinguisher, Scott Air Pack, bunker coat G. Class A extinguisher, Scott Air Pack, halogen tool C. Class B extinguisher, Scott Air Pack,2 five gallon pails of foam.

D. Scott Air Pack and bunker coat. The 4KV halon system should extinguish the fire.

/

Answer

A 4

Question Number: l-A.3-002 i

Reference (s):

1. A.3-003 K/A

Reference:

294001 Task Number: K1.16 1

Rating RO/SRO: 3.5/3.8 Monticello JTA:

Objective (s):

System Code: NA 1

1/mlf

MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 34 of 102 l

Exam Question Number: 32 Point Value: 1.00 Tme (Minutes):

l A break has occurred in the "A" loop of the recirc pump suction piping. Current conditions are:

l Drywell pressure 5 PSIG.

l .

Indicated reactor level is 35 inches.

Torus level +1 foot. !

Drywell temperature 250 degrees F.

4

. Reactor pressure 650 PSIG.

Assuming no c aerator actions, which of the following automatic system actions are correct given tha above concitions?

A. Core spray pumps are running and injecting to the reactor vessel.

B. HPCI is injecting to the vessel with its suction aligned to the torus.

C. The ASDS timer is initiated.

i D. RCIC suction has auto transferred at a torus level of +2 inches.

4 Answer:

B Question Number: 1-B.03.02-025 Reference (s):

1. B.03.02-01 K/A

Reference:

295029 Task Number: EK2.02 Rating RO/SRO: 3.4/

Monticello J fA:

Objective (s):

System Code: NA l/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 35 of 102 4

Exam Question Number: 33 Point Value: 1.00 Time (Minutes):

Which of the following is a concern if the SRVs are used to depressurize the RPV when Torus Water Level is below -5.9 feet?

A. Pressurize the Torus from the uncovered SRV discharge device.

B. Induce cavitation of running ECCS pumps taking suction from the Torus. j C. Induce excessive lateral force which would damage the SRV discharge device.

D. Inadequate Torus water is available to prevent temperature stratification within the Torus.

Answer: ,

A Question Number: 1-C.5-1000-075 Reference (s):

1. C.5-1100, C.5-2002, C.S.1-2002

2. EOP Bases K/A

Reference:

295030 Task Number: EK2.08 Rating RO/SRO: 3.5/

Monticello JTA:

Objective (s):

3 /stem Code: NA I/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 36 of 102 i

Exam Question Number: 34 Point Value: 1.00 Time (Minutes):

Which of the following is the correct immediate action if a steam leak in the Reactor Building

exists?

A. Evacuate personnel from the affected area and initiate an investigation.

B. Dispatch the fire brigade to investigate affected area.

C. Notify security to remove personnel from area.

D. There are no immediate actions, guidance for all leaks outside of primary containment is 4 obtained from the EOP for secondary containment control.

Answer:

A 4

1 Question Number: 1-C.4-B.02-001 Rsference(s):

1. C.4-B.02.04.A 1

K/A

Reference:

294001

Task Number: A1.10

. Rating RO/SRO: 3.6/4.2 Monticello JTA:

Objective (s):

i System Code: NA e

J 1/mlf

I MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 37 of 102

~

Exam Question Number: 35 Point Value: 1.00 Tme (Minutes):

Given:

Reactor level -135 inches.

Reactor pressure 200 PSIG.

One core spray purhp operating and injecting into the vessel.

. 3 ADS valves are open.

The Reactor core is:

A. adequately cooled based on core submergence.

B. adequately cooled based on 'he core spray pump spraying on the fuel.

C. adequately cooled based on the level greater than minimum steam cooling RPV water level.

D. not adequately cooled because level is below the minimum zero-injection RPV water level.

ADEWE O

Question Number: 1-C.5.1-1000-001 Reference (s):

1. C.5.1-1000

2. EOP Bases K/A

Reference:

295031 Task Number: EA2.04 Rating RO/SRO: 4.6/

Monticello JTA:

Objective (s):

System Code: NA I/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9G02 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - AWSWER KEY Page 38 of 102 Exam Question Number: 36 Point Value: 1.00 Time (Minutes):

Given:

Reactor power 75%

No.12 emergency diesel in service for testing No.12 EDG emergency service water pump C-08 handswitch in Pull-to-Lock Plant service water supplying No.12 EDG with cooling if the normal service water system is lost, which of the following is the correct plant response with no operator action taken?

A. No.11 EDG SW pump will auto start and supply No.12 EDG through the ESW cross-tie.

B. No.12 EDG will trip on low. raw water flow.

C. No.12 EDG will trip on high engine temperature.

D. No.12 EDG ESW pump will auto start when No.12 EDG hot engine relay picks up.

Answer:

D Question Number: 1-B.05.17-015 Rnference(s):

1. B.05.17-01 K/A

Reference:

295016 Task Number: AK2.01 Rating RO/SRO: 4.4/

Monticello JTA:

Objective (s):

System Code: NA l/mlf

MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 39 of 102 Exam Question Number: 37 Point Value: 1.00 1 Time (Minutes):

,ma RHR is in the shutdown cooling mode with normal power avr.<tle, which of the followin0 i s correct?

A. Div i shutdown cooling pumps are powered from 16 bus via the 1 AR transformer.

B. Div ll shutdown cooling pumps are powered from 16 bus via the 1 AR transformer. .

C. Div i shutdown cooling pumps are powered from 13 bus via the 2R transformer.

D. Div ll shutdown cooling pumps are powered from 16 bus via the 2R transformer.

Answer: ,

D Question Number: 1-B.09.06-038 Reference (s):

1. B.09.06 02 j K/A

Reference:

203000 l l

Task Number: K2.01 j Rating RO/SRO: 3.5/ l Monticello JTA: i Objective (s): j i

System Code: NA I/mlf

l MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 i TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 l EXAMINATION - ANSWER KEY Page 40 of 102 Exam Question Number: 38 Point Value: 1.00 Time (Minutes):

Which of the following set of conditions is a valid level reading with a main steam line leak in primary containment?

Condition A Condition B

Safeguard level indicators read -35"

Vessel flood indication reads -5"

RPV pressure is 200 PSIG = RPV pressure 100 PSIG

Average DW temp is 350*F

Average DW temp is 330*F

Secondary Containment temp is 210*F

Secondary Containment temp is 70*F Condition C Condition D

= Fuel zone level indicator reads -130" = Feedwater level indicator reads +9"

RPV pressure is 150 PSIG RPV pressure is 15 PSIG

Average DW temp is 390 F Average DW temp is 290*F

Secondary Containment temp is 450*F Secondary Containment temp is 100 F l

Answer:

A Question Number: 1-C.5-1000-070 Reference (s):

1. C.5-1100, Detail A, Figures B and C K/A

Reference:

295032 Task Number: EK2.08 Rating RO/SRO: 3.8/3.9 Monticello JTA:

Objective (s):

System Code: NA I/mlf

MONTICELLO NUCLEAR GENERATING PLANT M81000-9602

! TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 41 of 102

. Exam Question Number: 39 Point Value: 1.00 Time (Minutes):

Given:

i . A Reactor startup is in progress.

. Reactor pressure is approximately 500 PSIG.

The Pressure Regulator Override (PRO) is maintaining No.1 Turbine bypass i valve 10-15% open.

I .

Mechanical Pressure Regulator (MPR) is in standby with the setpoint 50 PSIG above reactor pressure.

Which of the following describes the Turbine Bypass valve response given a Turbine Vacuum Trip 2? Turbine Bypass valves will...

A. not change position. Turbine Vacuum Trip 2 generates a Turbine trip and will close only the Turbine Stop and Control valves.

I B. Initially close. Reactor pressure will increase to the MPR setpoint at which time the Turbine Bypass valves will open to control reactor pressure at the higher value.

C. close and remain closed until the Turbine Vacuum Trip 2 is reset.

] D. open to control reactor pressure as a result of the closing of the Turbine Stop and Control valve drains.

Answer:

j C

}

4 Question Number: 1-B.06.01-049 i

Rnference(s):

1. B.06.01 -02.07 K/A

Reference:

295002 Task Number: AK3.04 Rating RO/SRO: 3.4/3.6 Monticello JTA:

Objective (s):

System Code: NA l/mlf

MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 42 of 102 Exam Question Number: 40 Point Value: 1.00 Tme (Minutes):

Given:

Reactor power 43%

Core flow 25 mlb/hr

. The C-05 operator is adjusting recirc flow to exit the exclusion area of the power to flow map.

If reactor power as indicated by the APRMs begins to slowly increase and decrease with an increasing magnitude the immeidate operator action (s) is/are to...

A. notify the nuclear engineer.

B. enter rapid power reduction and reduce power with control rods until APRM traces are steady.

C. manually scram the reactor.

D. place the MPR in service to stop control valve hunting.

Answer:

C Question Number: 1-C.4-B.05-006 Rsference(s):

1. C.4-B.05.01.02.A K/A

Reference:

216000 Task Number: SG 15 Rating RO/SRO: 4.1/4.4 Monticello JTA: l Objective (s):

System Code: NA l/mif

l MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 43 of 102 Exam Question Number: 41 Point Value: 1.00 Time (Minutes):

Which of the following is an acceptable value concerning the recirc system and core flow or loop flow?

A. A core plate DP of 3 and 60% core flow.

B. A 50% loop flow and No.11 recirc pump at 50% speed.

C. A 40% loop flow and No.12 recirc pump at 40% speed.

D. 25,000 GPM loop flow and No.11 recirc pump at 80% speed.

Answer: '

D Question Number: 1-B.01.04-056 Reference (s):

1. B.01.04-06.02, Fig 1,2,3 and 4 K/A

Reference:

202001 Task Number: A1.03 Rating RO/SRO: 3.6/3.6 Monticello JTA:

Objective (s):

System Code: NA I/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 44 of 102 Exam Question Number: 42 Point Value: 1.00 Time (Minutes):

With the plant at full power an automatic 2R to 1R transfer occurs. No abnormalities exist. Which of the following identify the status of the Reactor Feed Pumps (RFP)?

A. Both 11 and 12 RFPs are operating.

B. 11 RFP is operating,12 RFP breaker is closed but 12 bus is de-energized.

C. 12 RFP is operating,11 RFP breaker is closed but 11 bus is de-energized.

D. Both 11 and 12 RFP have tripped on undervoltage. I Answer: ,

B i

Question Number: 1-B.09.06-035 Reference (s):

1. B.09.06 K/A

Reference:

295003 Task Number: AK3.03 Rating RO/SRO: 3.5/3.6 Monticello JTA:

Objective (s):

System Code: NA l/mif

{ MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 45 of 102 i

Exam Question Number: 43 Point Value: 1.00 Time (Minutes):

1 Which of the following describe how the Condensate and Feedwater system will react to a complete loss of 480 Volt AC Uninterruptible Power Supply Y-917 A. The controllers for the feedpump recirc valves will lose power and the feedpump recirc valves will fail in the closed position. Position indication will remain available from C-06.

. B. The condensate recirc valves will lose power and the condensate recirc valves will fail open. Position indication is not available from C-06.

]

C. The backup power supply for the Feedwater Digital Control system process modules will lose power. Computer afarm 5-B-47 (FW CONTROL HARDWARE TROUBLE) will annunciate.

D. Feedwater heater dump valves will fail open and the feedwater heater drain valves will fail j closed upon lose of power. Position indication is not available from C-20. ,

i j

Answer:

J

. A a

Question Number: 1-B.06.05-018 Reference (s):

1. B.06.05-05.01 K/A

Reference:

259001 l Task Number: SG 07 Rating RO/SRO: 3.5/3.5 Monticello JTA:

Objective (s): -

System Code: NA I/mlf

MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 46 of 102 Exam Question Number: 44 Point Value: 1.00 Time (Minutes):

Plant staff has determined that an entry into the waste collector tank is required to remove sludge buildup. Which of the following is correct concerning entry into the waste collector tank?

A. A confined space entry permit is required and is issued by the safety administrator.

B. If the initial oxygen concentration is approximately 21% no ventilation or continuous monitoring is required.

C. A job specific emergency rescue plan is not required if the tank contents are non-flammable.

D. A confined space entry permit is not required if the entrance to the tank will last less than 10 minutes.

i

! Answer:

A

! Question Number: l-NSPSM-006 Reference (s):

4

1. Safety Manual Lesson Plan SM-23.01 K/A

Reference:

294001 Task Number: K1.14 Rating RO/SRO: 3.2/3.4 Monticello JTA:

Objective (s):

System Code: NA I/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 47 of 102 Exam Question Number: 45 Point Value: 1.00 Time (Minutes):

A leak in the drywell while at power has just occurred. Which of the following concerning leakage to the drywell sumps is correct?

A. A 2 GPM increase in unidentified leakage within any 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months period requires cold shutdown conditions within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

B. Unidentified leakage greater than 10 GPM requires cold shutdown conditions within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

C. Identified leakage of 10 GPM requires cold shutdown conditions within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

D. Identified leakage of greater than 20 GPM requires cold shutdown conditions within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Answer D

Question Number: 1-TS-032 Reference (s):

1. Tech Specs 3.6 K/A

Reference:

268000 Task Number: A4.01 Rating RO/SRO: 3.4/3.6 Monticello JTA:

Objective (s):

System Code: NA l/mif

1 MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 48 of 102 Exam Question Number: 46 Point Value: 1.00 Time (Minutes):

During a reactor startup the following conditions exist:

Reactor water temperature 200 degrees F.

Reactor level +42 inches.

j R: actor water level has been increasing as water temperature increases. The Shift Supervisor

, directs you to lower reactor level using RWCU.

Which of the following is correct when using RWCU to lower level?

A. Water can be routed to the CSTs and the RWCU excess FCV will close on high upstream pressure.

B. Water can be routed to the condenser and the RWCU excess FCV will close on high j downstream pressure.

C. Water can be routed to theWaste Surge Tank and the RWCU excess FCV will close on

high upstream pressure.

- D. Water can be routed to the Torus and the RWCU excess FCV will close on low upstream pressure.

! Answer:

B Question Number: 1-B.02.02-021 j Roference(s):

t

1. B.02.02-01 K/A

Reference:

204000 t

Task Number: A4.03 Rating RO/SRO:

3.2/

Monticello JTA:

Objective (s):

System Code: NA 1/mlf

MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE _ Revision 0 EXAMINATION - ANSWER KEY Page 49 of 102 i

Exam Question Number: 47 Point Value: 1.00 Time (Minutes):

While performing the quarterly RCIC operability tests, A-16 (RCIC ROOM RAD MONITOR) reaches the alarm setpoint. The Reactor Building Operator has reported a steam enviro ~nment .

i exists in the RCIC pump room. As the reactor operator you want to isolate steam flow to the

RCIC room. ~

Which of the following by procedure is the correct action (s)?

A. Depress the RCIC turbine trip button.

B. Close MO-2078 (STEAM ADMISSION VALVE).

C. Close MO-2075 and MO-2076 (RCIC STEAM ISOLATION VALVES).

D. Manually scram the reactor.

Answer:

C Question Number: 1-B.02.03-018 Reference (s):

1. B.02.03-05

2. EOP 1300 K/A

Reference:

295033 Task Number: EK3.03 Rating RO/SRO: 3.8/3.9 Monticello JTA:

Objective (s):

System Code: NA I/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 50 of 102 Exam Question Number: 48 Point Value: 1.00 Tme (Minutes):

} Upon an automatic initiation signal to Standby Gas Treatment (SBGT) with normal AC power available Train A can only maintain a flow of 2000 SCFM. Which of the following describe how the SBGT system would respond?

A. If flow on Train A is not above 3000 SCFM within 30 seconds Train B flow control valve will i open to achieve the desired flow.

B. If flow on Train A is not above 2800 SCFM within 10 seconds Train B will auto start to achieve the desired flow.

. C. Train B immediately received an auto start signal and will operate in parallel with Train A until manually secured by an operator.

D. Initially Train A will receive a start and 5 seconds later Train B will receive an auto start.

Low flow of 3000 SCFM on Train A will annunciate the low flow alarm.on C-24. Train B will maintain the desired flow -

Answer:

B l l

Question Number: 1-B.04.02-024 Reference (s):

1. B.04.02-01 K/A

Reference:

295034 Task Number: EA1.04 ,

Rating RO/SRO: 4.1/4.2 i

Monticello JTA: '

Objective (s):

System Code: NA I/mif

I I

MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 51 of 102 Exam Question Number: 49 Point Value: 1.00 Time (Minutes):

The Monticello plant is in the initial stages of a reactor startup when a small LOCA occurs. The following conditions are currently present:

. Core flooding instruments indicate -130 inches

. Drywell temperature 110 degrees F

. Reactor pressure 620 PSIG The Shift Supervisor is concerned that the fuel is uncovered and asks you to determine what actual water level is. Actual water level is...

A. -120 inches B. -130 inches

-140 inches C.

D. -160 inches Answer:

C Question Number: 1-B.01.01-031 R;ference(s):

1. B.01.01-06.02, Fig.17 K/A

Reference:

216000 Task Number: A3.01 Rating RO/SRO: 3.4/3.4 Monticello JTA:

Objective (s):

System Code: NA l/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 52 of 102 Exam Question Number: 50 Point Value: 1.00 Time (Minutes):

The on duty reactor operator was reviewing the computer point RPV 506 (10 Minute Average Core Thermal Power) which was indicating 1671 MWth. By procedure, which of the following is tha correct operator response?

A. Verify that the daily average for core thermal power has been less than 1670 MWth.

B. No action needs to be taken provided hourly MWth average is less than 1670 MWth.

C. Take action to reduce core thermal power to less than1670 MWth.

D. No action needs to be taken. There is a 1% deviation allowed to the 1670 MWth limit.

Answer:

C Question Number: 1-C.2-014 Reference (s):

1. C.2-01 K/A

Reference:

294001 Task Number: A1.15 Rating RO/SRO: 3.2/3.4 Monticello JTA:

Objective (s):

System Code: NA I/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 53 of 102 i Exam Question Number: 51 Point Value: 1.00 Ime (Minutes):

The Reactor is operating at 100% power. The Spent Fuel Pool Exhaust Fan, V-EF-28, has tripped. Which of the following c'3 scribes how the reactor building pressure will be maintained?

A. Manually adjust the inlet dampers of the Reactor Building Main Plenum Exhaust Fans V-EF-20.

i B. The Refuel Floor Supply Fans, V-AH-4 A&B, will trip.

C. The Reactor Building Main Supply HVAC Fans, V-AC-10 A&B, will cycle.

, D. The Reactor Building Exhaust Fan, V-EF-24B will auto start.

i 1

T 1 Answer:

1 B i

l Question Number: 1-B.08.07-033 Reference (s):

1 1. B.08.07-02 K/A

Reference:

290001 Task Number: A4.01 Rating RO/SRO: 3.3/

Monticello JTA:

Objective (s):

I System Code: NA 1

4 4

1/mlf

MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 54 of 102 Exam Question Number: 52 Point Value: 1.00 Time (Minutes):

Given:

Normal shutdown cooling unavailable j =

No recirc pumps are running a

i Reactor water level +65 inches a

Reactor water temperature 160 degrees F and increasing Which of the following is the correct operator action to place the RWCU system into the heat rcj:ction mode?

A. Maximize RBCCW flow through the non-regenative heat exchanger.

B. Minimize RWCU flow through the clean-up system non-regenative heat exchanger.

C. Line up RWCU to dump to the condenser.

D. Maximize RBCCW flow through the regenative heat exchanger.

1

[ Answer:

A I

4 Quastion Number: l-C.4-B.03-009 Reference (s):

4

1. C.4-B.03.04.A K/A

Reference:

295021 i Task Number: AA1.01 Rating RO/SRO: 3.4/3.4 Monticello JTA:

Objective (s):

. System Code: NA I/mlf

MONTICELLO NUCLEAR GENERATING PLANT MG1000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 l EXAMINATION - ANSWER KEY Page 55 of 102 Exam Question Number: 53 Point Value: 1.00 Time (Minutes):

l

! The maximum design pressure limit for the drywell at Monticello is:

i A. 65 PSIG B. 56 PSIG C. 60 PSIG D. 58 PSIG I

Answer:

) B l

1 Question Number: 1-B.04.01 -019 i

Reference (s):

i i 1. B.04.01 -02.01 K/A

Reference:

295024 l

Task Number:

.01 Rating RO/SRE .1/4.2 Monticello JTA:

1 Objective (s):

l 1 System Code: NA 4

e 4

i 4

4 1/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 56 of 102 Exam Question Number: 54 Point Value: 1.00 Time (Minutes):

During 100% aower operation, alarm 5-A-46 (SRV OPEN) is received. The amber l'ight is on for SRV A. Whic1 of the following is the immediate operator action per C.4-B.3.3.A (STUCK OPEN 3 RELIEF VALVE)?

A. Scram the Reactor; enter C.4-A (REACTOR SCRAM); and execute concurrently with this l procedure.

B. Place Div 11 Lo-Lo Set Logic switch on Control Room Panel C-253D in BYPASS (HS-S3B).

C. Place the handswitch for the affected SRV to the OPEN position and then return it to the

normal position.

i D. Execute C.4-F (RAPID POWER REDUCTION) concurrently and CLOSE the MSIVs to

! control reactor cooldown.

Answer:

C l i

Question Number: 1-C.4-B.03-010

Rsference(s)

1. C.4-B.03.03.A K/A

Reference:

239002 ,

i Task Number: SG 14 I Rating RO/SRO: 4.1/3.9 l Monticello JTA:

Objective (s):

System Code: NA 1/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 57 of 102 Exam Question Number: 55 Point Value: 1.00 Time (Minutes):

Given:

A trip of a reactor feedpump Reactor water level decreases to 0 inches l

The reactor scrammed l

i a All control rods inserted a Remaining feed pump restored level to +35 inches The recirc sample line isolation valves (CV-2790 & CV-2791) are closed due to: I A. a Group I isolation.

9 B. a Group 11 isolation. -

I

C. a Group 111 isolation. l 3

D. a Group IV isolation.

I l Answer:

4 C ,

Question Number: 1-TS-034 Reference (s):

3

1. Tech Spec 3.7.2 K/A

Reference:

223002 Task Number: A1.01 Rating RO/SR'O: 3.5/3.4 Monticello JTA:

Objective (s):

System Code: NA l/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 58 of 102 Exam Question Number: 56 Point Value: 1.00 Time (Minutes):

The plant has experienced a small LOCA and the following plant conditions exist:

Reactor pressure 700 PSIG

- Reactor level 35 inches a Drywell pressure 3 PSIG

Torus water temperature 82 degrees F Which EOPs should be entered?

A. 1200 and 1300 B. 1205 and 1100 C. 1100 and 1300 D. 1100 and 1200 4

Answer:

D Question Number: 1-C.5-1000-073 R ,ference(s):

1. C.5-1100

2. C.5-1200 K/A

Reference:

295010 Task Number: SG 11 Rating RO/SRO: 4.2/4.5 Monticello JTA:

Objective (s):

System Code: NA 1/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 !

EXAMINATION - ANSWER KEY Page 59 of 102 ;

1 Exam Question Number: 57 Point Value: 1.00 Time (Minutes);

An ECCS initiation signal occurs with normal pump bus voltage available. Which of the following correctly identifies the start sequence for the ECCS pumps?

A. 11 and 12 Core Spray pumps start after a five (5) second delay.

B. 11 and 13 RHR pumps start after a five (5) second delay.

C. 12 and 14 RHR pumps start after a five (5) second delay.

D. 11 and 12 RHR pumps start after a five (5) second delay.

Answer:

D Question Number: 1-B.09.06-040 Reference (s):

1. B.09.06-01 K/A

Reference:

262001 Task Number: A3.04 Rating RO/SRO: 3.4/

Monticello JTA:

Objective (s):

System Code: NA I/mif

i MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 60 of 102 Exam Question Number: 58 Point Value: 1.00 Time (Minutes):

ll 1 Given:

i o 1,000 GPM leak from recirc 1 o No RHR pumps available o No.11 and No.12 core spray pumps running 4

o ADS timer reads 100 sec. and is timing down 2

Which of the following will prevent the ADS relief valves from opening?

A. Placing the ADS relief valve hand switches in the CLOSED position.

B. Removing both core spray pumps from service.

C. Decrease drywell pressure to 1.7 PSIG.

D. Resetting reactor scram. '

Answer:

B Question Number: 1-B.03.03-016 R ference(s):

1. B.03.03-01 K/A

Reference:

209001 Task Number: K3.02 Rating RO/SRO: 3.8/3.9 Monticello JTA:

Objective (s):

System Code: NA l

1/mif

' MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 61 of 102

)

Exam Question Number: 59 Point Value: 1.00 Time (Minutes):

i An event resulted in an automatic initiation of the HPCI system. Reactor water level was restored to greater than +48 inches. Drywell pressure currently reads 2.5 PSIG. Which of the following automatically restarts the HPCI system?

A. Reactor water level drops below -48 inches.

l B. Reactor water level drops below +48 inches.

l C. Reactor water level drops below +9 inches.

3 D. The reactor operator depresses the GROUP IV ISOLATION RESET pushbutton.

/

Answer:

A Question Number: 1-B.03.02-023 Rsference(s):

1. B.03.02-1 K/A

Reference:

206000 Task Number: K6.12 Rating RO/SRO: 4.2/4.3 Monticello JTA:

Objective (s):

System Code: NA I/mlf

i 1

MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 \

TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 l EXAMINATION - ANSWER KEY Page 62 of 102 l

l Exam Question Number: 60 Point Value: 1.00 Time (Minutes): .

During a Station Blackout (SBO) event, the reactor operator is directed to control reactor water ,

level utilizing the RCIC system. RCIC may be restarted... '

A. only once after the initial automatic initiation due to possible depletion of Div i 250 VDC battery along with loss of Y-71 inverter.

B. up to three times after the initial automatic initiation due to possible depletion of Div ll 250 '

VDC battery along with loss of Y-81 inverter.

C. only once after the initial automatic initiation due to possible depletion of Div 11125 VDC battery along with loss of Y-81 inverter.

D. up to three times after the initial automatic initiation due to possible depletion of Div i 250 VDC battery along with loss of Y-71 inverter.

Answer:

D Question Number: 1-C.4-B.09-010 Reference (s):

1. C.4-B.09.02.A K/A

Reference:

259001 Task Number: A2.06 Rating RO/SRO: 3.2/

Monticello JTA:

Objective (s):

System Code: NA 1/mlf

1 MONTICELLO NUCLEAR GENERATING PLANT M8100G-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 63 of 102 Exam Question Number: 61 Point Value: 1.00 Time (Minutes):

Given:

Drywell temperature 145 degrees F.

Drywell pressure 1.5 PSIG.

. Torus temperature 85 degrees F.

' . Torus water level +3.5 inches.

I

Reactor level +20 inches.

Reador pressure 900 PSIG. l Which EOP should be entered:

A. C.5 -1100 ,

B. C.5-1200

! C. C.5-1205 l I D. C.5-1300 Answer:

B Question Number: 1-C.5-1200-001 Rsference(s):

1. C.5-1200 K/A

Reference:

219000 Task Number: A1.04 Rating RO/SRO: 3.2/3.2 Monticello JTA:

Objective (s):

System Code: NA l/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 l TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 64 of 102 l

l Exam Question Number: 62 Point Value: 1.00 Time (Minutes): ,

Given:

. Small break LOCA

. DW pressure 4 PSIG and increasing slowly Reactor pressure 1000 PSIG and holding steady

. Reactor level at +35 inches and holding steady To place the "A" loop of RHR in service for torus cooling / torus spray, the operator shall perform which of the following?

A. Place Containment Spray 2/3 Height Bypass Core switch in the MANUAL OVERRIDE position.

B. Momentarily place the Containment Spray / Cooling LPCI initiation Bypass switch in the BYPASS position.

C. Depress the LPCI Loop Select Logic Reset pushbutton.

D. Depress the Shutdown Cooling Group 11 Isolation Reset pushbutton.

Answer:

B ,

Question Number: 1-B.03.04-031 Rnference(s):

1. B.03.04-05 K/A

Reference:

230000 Task Number: A3.01 Rating RO/SRO: 3.4/3.3 Monticello JTA:

Objective (s):

System Code: NA l/mif

I MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 65 of 102 Exam Question Number: 63 Point Value: 1.00 Time (Minutes):

You are on duty in the control room when you receive annunciator 5-B-31 (LOSS OF CONTINUITY TO SOUlB VALVE). While investigating you notice that both white squib valve ready indicating lights are de-energized. Which of the folloiwng actions shall the operator perform?

A. Check the computer alarm typer in the contro! room to identify which valve is reading low milliamps.

B. Read the values on the meter relays 11-67-A/B (behind C-05) to determine which valve indication initiated the alarm.

C. Read the values on the squib valve indicators located in the cable spreading room to determine which valve indication initiated the alarm.

D. Read the values on the indicators located at the squib valves to determine which valve circuit initiated the alarm. -

A[1SE9E B

Ouestion Number: 1-B.03.05-022 Reference (s):

1. B.03.05-02 K/A

Reference:

211000 Task Number: K4.04 Rating RO/SRO: 3.8/3.9 Monticello JTA:

Objective (s):

System Code: NA l/mlf

. _ -_ = . .

MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 66 of 102 J

Exam Question Number: 64 Point Value: 1.00 Time (Minutes):

A Reactor scram signal has been generated and ALL control rods fail to insert. The shift supervisor gives the order to initiate SBLC. Which of the following describe the effect on the RWCU system due to the initiation of SBLC.

A. MO-2397, MO-2399, MO-2404 and MO-2405 receive a close signal. The RWCU pumps trip from the subsequent valve closure.

B. MO-2397, MO-2398 and MO-2399 receive a close signal. The RWCU pumps trip directly from the SBLC signal.

C. MO-2397, MO-2398 and MO-2399 receive a close signal. The RWCU pumps trip from the

subsequent valve closure.

D. MO-2397, MO-2399, MO-2404 and MO-2405 receive a close signal. The RWCU pumps trip directly from the SBLC signal.

Answer:

C Question Number: 1-B.03.05-023 Reference (s):

1. B.03.05-01 K/A

Reference:

211000 Task Number: A3.06 Rating RO/SRO: 4.0/4.1 Monticello JTA:

Objective (s):

System Code: NA l/mif

^

MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 67 of 102 Exam Question Number: 65 Point Value: 1.00 Time (Minutes):

After a failure of the reactor pressure control system the following conditions existed:

Reactor pressure peaked at 1150 PSIG.

Reactor level reached 0 inches and is now being maintained at +35 inches.

All control rods inseded !

Recirc pumps will trip...

A. immediately due to low reactor level.

B. Immediately due to high reactor pressure.

l C. after a 9 second time delay due to low level.

D. after a 9 second time delay due to high reactor pressure.

Answer:

B Question Number: 1-B.05.06-030 Rnference(s):

1. B.05.06-02 K/A

Reference:

202002 Task Number: A1.05 Rating RO/SRO: 3.6 Monticello JTA:

Objective (s):

System Code: NA I/mif

MONT! CELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 68 of 102

~

Exam Question Number: 66 Point Value: 1.00 Ome (Minutes):

The 115% TRIP SET indicating light is illuminated on the RBM 7 cabinet. This light indicates that tha...

A. RBM output signal is above the trip reference level and a rod block trip has occurred.

B. power biased rod block trip is set to the intermediate power level. ,

C. APRM/RBM TRIP LEVEL pushbutton on C-05 has been depressed to determine the RBM l trip setpoint in effect.

D. reference APRM output signal is above the trip reference level.

l

/

Answen B

Ouestion Number: 1-B.05.01.02-042 R:,ference(s):

1. B.05.01.02-03 K/A

Reference:

201005 Task Number: K5.09 Rating RO/SRO: 3.5/3.5 Monticello JTA:

Objective (s):

System Code: NA I/mit

MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 69 of 102 4

Exam Question Number: 67 Point Value: 1.00 Ime (Minutes): ;

R: actor recirc pump speeds became mismatched with reactor power at 75%. Which one of the following states the reason for maintaining the speed of the faster recirc pump within 130% of the spred of the slower pump?

A. To enhance the capability of the LPCI loop select logic ability to select the broken loop.

B. Prevent jet pump cavitation.

C. Prevent stub tube vibration in the lower core area.

D. Prevent impro aer mixing in the lower core which could result in thermal stress of the lower j stub tube welc s.

I

/

i Answer:

A Question Number: 1-B.01.04-054 Reference (s):

1. B.1.4-05.01 K/A

Reference:

202002 Task Number: A2.04 Rating RO/SRO: 3.0/3.0 Monticello JTA:

Objective (s):

System Code: NA I/mif

l MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 70 of 102 i

Exam Question Number: 68 Point Value: 1.0 Time (Minutes):

A LPCI initiation signal occurs due to low-low water level for 20 minutes. Which of the following is

correct if Loop "B" RHR is selected by LPCI Loop select logic? (Assume Reactor oressure 900 PSIG).

A. The RHR injection (inboard and outboard) valves on the non-selecied loop will close and remain closed. The outboard injection valve on the selected loo a will remain open, the inboard injection valve will open when Reactor pressure is less t1an 460 PSIG.

B. The RHR injection (inboard and outboard) valves on both loops will remain open until Reactor pressure decreases to 460 PSIG. The non-selected loop outboard injection valve will then close and the selected loop outboard injection valves will open.

C. The RHR injection (inboard and outboard) valves all close until Reactor pressure is less than 460 PSIG, then the selected loop injection valves open.

D. The RHR injection (inboard and outboard) valves on the selected loop open at 460 PSIG and remain open for 5 minutes and then auto close. The non-selected loop (inboard and outboard) injection valves close and remain closed due to the initiation signal.

Answer:

A l Question Number: 1-B.03.04-004 Reference (s);

i

1. B.03.04-02 K/A

Reference:

295031 Task Number: EA1.01 Rating RO/SRO: 4.4/4.4 Monticello JTA: 2050080101 Objective (s): M-8107L-023, EO-7 System Code: RHR 1/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 l EXAMINATION - ANSWER KEY Page 71 of 102 1

Exam Question Number: 69 Point Value: 1.00 Time (Minutes): )

The system engineer has requested that the 2R source breaker for bus 12 be removed for I breaker maintenance. You have been directed to transfer Bus 12 from the 2R transformer to the 1R transformer. Which of the following cautions apply.

A. Minimize circulating currents when transformers are paralleled.

B. Transfer shall always be performed as a " Break Before Make".

C. Paralleling of transformers shall only be performed on Bus 15 and Bus 16.

D. Paralleling of transformers shall only be performed when load tap changers for '

transformers are in AUTO.

&lSWE A

Question Number: 1-B.09.06-037 Reference (s):

1. B.09.06-05 K/A

Reference:

262001 Task Number: K5.01 Rating RO/SRO: 3.1/

Monticello JTA:

Objective (s):

System Code: NA l

1 i

I 1/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9602

. TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 72 of 102 Exam Question Number: 70 Point Value: 1.00 Time (Minutes):

The plant has experienced a loss of off-site power. Which of the following is required to allow the ditsel generators to automatically supply the essential buses?

A. The emergency diesel generator speed is greater than 600 RPM.

B. ECCS load shed logic energized.

C. Essential bus transfer switches are in SETUP.

D. Zero voltage on the 2R and 1R transformers, or the 2R to 1 R transfer logic complete.

Answer:

C Question Number: 1-B.09.06-040 Rsference(s):

1. B.09.06-01 K/A

Reference:

262001 Task Number: K2.01 Rating RO/SRO: 3.3/

Monticello JTA:

Objective (s):

System Code: NA I/mlf

i i

1 MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 I TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 4

EXAMINATION - ANSWER KEY Page 73 of 102 Exam Question Number: 71 Point Value: 1.00 Time (Minutes):

While shutting down the reactor, a RWM insert block is enforced. Which of the following will occur when the Emergency in/ Notch override switch is placed in the Emergency in position? The s@lected rod...

A. moves in, followed by the normal settle function.

B. moves in, the normal settle function is bypassed.

C. moves in, a " Rod Drift alarm is generated. I D. doec not move.

/

Answer:

1 '

D Ouestion Number: 1-B.05.02-035 Reference (s): 1

1. B.05.02-02 j

2. B.05.05-01 '

K/A

Reference:

201006 Task Number: K1.01 Rating RO/SRO: 3.4/

Monticello JTA:

Objective (s):

System Code: NA '

l l

1/mlf

MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 ,

TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 {

EXAMINATION - ANSWER KEY Page 74 of 102 !

l Exam Question Number: 72 Point Value: 1.00 Time (Minutes). :

1 Following a reactor scram all scram signals are clear except the scram discharge volume high !

level. Subsequent operator actions in C.4-A (REACTOR SCRAM) direct the operator to reset the scram as soon as possible. The reason is to reduce...

A. DP across the CRD piston and to reduce thermal stress on the CRD stub tubes. 3 I

B. CRD flow to the vessel and to reduce thermal stress on the feedwater inlet nozzles.

C. DP across the CRD flow control valve and to ensure cooling water header is not .

overpressurized. I D. cold water injection into the RPV and to mir: ..a stratification in the lower head.

I l

Answer:

D I

Question Number: 1-C.4-A-019 Reference (s):

1. C.4-A K/A

Reference:

295006 i

Task Number: AA1.06 l l

Rating RO/SRO: 3.5/3.6 1 1

Monticello JTA:

Objective (s):

System Code: NA l l

l I/mif

=_. _.

' MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0

, EXAMINATION - ANSWER KEY Page 75 of 102 Exam Question Number: 73 Point Value: 1.00 Time (Minutes):

I While on dut in the control room you receive annunciator 3-B-25 (UNDERVOLTAGE HPCI DC MCC). Whic of the following caused this event to occur?

A. 250 VDC Division I had a battery cell short to ground. l B. 250 VDC Division 11 distribution panel D-100 circuit breaker 11 tripped on high voltage.

i

) C. 125 VDC Division I Charger output having decreased to 100 VDC.

D. 125 VDC Division 11 inverter failure. I 4

J Answer:

B Question Number: 1-B.09.09-007 Reference (s):

3

1. B.09.09-01

'NA

Reference:

263000 Task Number: K2.01 Rating RO/SRO: 3.1/3.4 Monticello JTA:

Objective (s):

System Code: NA 4

1/mlf

MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: J 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 76 of 102 Exam Question Number: 74 Point Value: 1.00 Time (Minutes):

The electric fire pump is removed from service for maintenance. The screen wash system is in service. A fire in the plant has caused fire header pressure to decrease, starting the diesel fire pump. After approximately 5 minutes, the diesel fire pump trips. Which of the following is the correct system response? The screen wash...

A. fire pump auto starts at 75 PSIG and supplies the fire header.

B. header valve CV-1971, closes at 75 PSIG after a 20 second time delay to allow the screen wash pump to supply the fire header.

C. header valve CV-1971, closes immediately at 70 PSIG to allow the screen wash pump to ,

supply the fire header. l D. header valve CV-1971, closes at 70 PSIG after a 20 second time delay to allow the screen wash pump to supply the fire header.

l Answer:

D Question Number: 1-B.08.05-017 Reference (s):

1. B.08.05-02 K/A

Reference:

286000 Task Number: A2.05 Rating RO/SRO: 3.1/

Monticello JTA:

Objective (s):

System Code: NA I/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 77 of 102 Exam Question Number: 75 Point Value: 1.00 Time (Minutes):

While on duty in the control room you receive annunciator 8-B-31 (NO.101480V LD CTR MCC FEEDER TRIP). Investigation indicates that the supply breaker to MCC-111 has tripped. 30 minutes after the loss of MCC-111 all procedural follow-up is completed. MCC-111 has not been r: turned to service. The status of RPS is:

A. 1/2 scram on B RPS.

B. Both RPS busses reset with B RPS being supplied by alternate source.

i C. 1/2 scram on A RPS.

D. Both RPS busses reset with A RPS being supplied by alternate source.

Answer:

C Ouestion Number: 1-B.09.12-008 Rcference(s): ,

1. B.09.12-02 K/A

Reference:

212000 Task Number: K2.01 Rating RO/SRO: 3.2/3.3 Monticello JTA:

Objective (s):

System Code: NA 1/mlf

=. - _ _- . .- . _. . -_

_M_ONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 78 of 102

~

Exam Question Number: 76 Point Value: 1.00 Time (Minutes):

You are performing the Core Spray System Prestart Valve Checklist in preparation for Reactor startup following a refueling outage, when you identify valve MO-1741 (11 CS PUMP TORUS of the follo) wing action (s) are you required to perform? SUCTION closed with a ho A. Open MO-1741 and notify the Shift Supervisor.

B. Sign for the item on the checklist since the normal work control process will re-align MO-1741.

C. Circle the item on the checklist in red.

D. Notify the system engineer to determine the status of MO-1741.

l j Answer:

C l

Question Number: 1-C.1 -027 i

Reference (s):

1. C.1

2. 2154-XX System Prestart Valve Checklists K/A

Reference:

294001 j Task Number: K1.01 Rating RO/SRO: 3.7/

Monticello JTA:

, Objective (s):

System Code: NA 1/mlf

1 MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 79 of 102 Exam Question Number: 77 Point Value: 1.00 Time (Minutes):

With Reactor power at 100%. You are given an isolation to perform on No.12 CRD pump.

During your review you identify that HOLD Card No.1 positions ACB 152-606 in the DISCONNECT position. You shall:

A. Place ACB 152-606 in the DISCONNECT position as this is the position required by the 4

HOLD card and the IR Worksheet.

B. Discontinue the isolation and notify the Shift Supervisor that the DISCONNECT position is not an appropriate position for ACB 152-606 given the existing Reactor conditions.

i C. Place ACB 152-606 in the TEST position, change the IR worksheet and notify the Shift 1 Supervisor.

D. Place the local breaker control switch for ACB 152-606 in the tripped condition and notify 4 the Shift Supervisor.

Answer:

B 1

Question Number: 1-B.09.06-036 l Reference (s):

1. B.09.06-05 K/A

Reference:

294001 Task Number: K1.02 Rating RO/SRO: 3.9/

Monticello JTA:

Objective (s):

System Code: NA I/mlf

MONTICELLO NUCLEAR GENERATING PLANT M81000 9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 80 of 102 I

Exam Question Number: 78 Point Value: 1.00 Time (Minutes):

Which of the following explains why the logic for the Reactor Protection System is normally energized?

A. A two-out-of-four logic can only be accomplished with a system logic that is normally l energized.

B. This results in a fail safe condition if power to the reactor protection system logic were to i be completely lost.

C. Power from the RPS logic must always be available in order to supply the IRM and SRM neutron detectors.

D. In the event that all power to the RPS logic was lost, the reactor could still be manually scrammed. l l

/

Answer:

B l Question Number: 1-B.05.06-011 Reference (s):

1. B.05.06-01 K/A

Reference:

212000 Task Number: K3.05 Rating RO/SRO: 3.7/3.8 Monticello JTA: 2120050101 Objective (s): M-8107L-072 System Code: PPS 1/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0

~=

EXAMINATION - ANSWER KEY Page 81 of 102 Exam Question Number: 79 Point Value: 1.00 Time (Minutes):

Given:

o Reactor water level-55 inches o Drywell pressure 7.5 PSIG o Station power from 1 AR l o RCIC steam line pressure is 100 PSIG l c RCIC Room temperature is 160 degrees F '

o RCIC steam flow 40,000 LB/Hr Which of the following is correct? RCIC will...

A. continue injecting to the reactor vessel.

B. auto isolate due to a valid Group 5 signal from low steam line pressure.

C. auto isolate due to a valid Group 5 signal from high area temperature. i D. auto isolate in 5 seconds from steam line flow if signal is still present.

l Answer:

A Question Number: 1-B.02.03-017 Reference (s):

1. B.02.03-01 K/A

Reference:

217000 Task Number: A2.02 Rating RO/SRO: 3.8/3.7 Monticello JTA:

Objective (s):

System Code: NA I/mif

l MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 82 of 102 Exam Question Number: 80 Point Value: 1.00 Ime (Minutes):

V-EF-18A stack dilution fan has been declared inoperable. V-EF-188 stack dilution fan is in service. What is the status of SBGT?

A. "A" and "B" SBGT are inoperable.

B. "A" SBGT train is inoperable.

C. As long as V-EF-18B is operable, there are no operational concerns.

D. "B" SBGT train is inoperable.

Answer: ,

B Question Number: 1-B.04.02-022 Reference (s):

1. B.04.02-05

2. Tech Spec 3.7 K/A

Reference:

261000 Task Number: SG 11 Rating RO/SRO: 3.3/4.2 Monticello JTA:

Objective (s):

System Code: NA l/mlf

MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 83 of 102 Exam Question Number: 81 Point Value: 1.00 Time (Minutes):

A small leak in containment has developed causing drywell pressure to increase to 2.5 PSIG.

3 The feedwater system has held level constant at +35 inches. Assuming no operator action since the start of the leak, what is the status of HPCl?

A. In service supplying water to the reactor vessel.

B. In service with outboard discharge valve closed and minimum flow valve open.

} C. In standby.

j D. In service with flow on test return to CSTs.

l Answer:

l A n

Question Number: 1-B.03.02-021 l Reference (s):

j 1. B.03.02-01 K/A

Reference:

295024 i

Task Number: EK2.01 4

Rating RO/SRO: 3.9/4.0 Monticello JTA:

Objective (s):

2 System Code: NA 4

i 1/mlf

4 i

, MONTICELLO NUCLEAR GENERATING PLANT M61000-9602 ,

TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 l EXAMINATION - ANSWER KEY Page 84 of 102 '

4 Exam Question Number: 82 Point Value: 1.00 Time (Minutes):

Which of the following describes the flow path of the Standby Gas Treatment System (SBGT) l when it initiates on high drywell pressure? Draws air from the... l a A. Drywell and exhausts to the off-gas stack. I B. Reactor Building and exhausts to the off-gas stack. ;

C. Drywell and exhausts to the Reactor Building Plenum.

D. Reactor Building and exhausts to the Reactor Building Plenum. !

l Answer: ,

B 1

l Question Number: 1-B.04.02-023 Reference (s):

1. B.04.02-01 -

K/A

Reference:

288000 Task Number: K1.03 Rating RO/SRO: 3.7/

Monticello JTA:

Objective (s):

System Code: NA 1/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 85 of 102 I

Exam Question Number: 83 Point Value: 1.00 Time (Minutes):

Given:

o Reactor pressure 650 PSIG o Steam line break in drywell.

o Drywell pressure 2.3 PSIG and slowly increasing.

o Reactor water level normal.

Assuming normal plant configuration and no operator actions, which of the following is correct concerning the core spray system operation?

A. Core spray pumps running. Outboard valves closed and inboard valves open.

B. Core spray pumps not running. Auto start at low reactor pressure.

C. Core spray pumps not running. Auto start at low low level.

D. Core spray pumps running.' Outboard valves open and inboard valves closed.

Answer:

D l

Question Number: 1-B.03.01-072 R:ference(s):

1. B.03.01-01 K/A

Reference:

209001 Task Number: A1.08 Rating RO/SRO: 3.3/3.3 Monticello JTA:

Objective (s):

System Code: NA l/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0

EXAMINATION - ANSWER KEY Page 86 of 102 '

Exam Question Number: 84 Point Value: 1.00 mme (Minutes):

While operating at 100% power a Group I auto isolation occurs and the reactor scrams. Low low

set actuates to control pressure. How many safety / relief valves will be open when reactor pr@ssure reaches 975 PSIG7 A. 3 B. 2 C. 1 D. 0

/

Answer:

C Question Number: 1-B.03.03-017 Reference (s):

1. B.03.03-01 K/A

Reference:

295025 Task Number: EK3.09 Rating RO/SRO: 3.7/3.7 Monticello JTA:

Objective (s):

System Code: NA I/mlf

MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0

' EXAMINATION - ANSWER KEY Page 87 of 102 Exam Question Number: 85 Point Value: 1.00 Time (Minutes):

Which of the following could cause a reactor vessel overfill transient?

A. Main FW reg valve bias set positive.

B. Loss of electrical control signal to the low flow reg valve.

C. Main FW reg valve bias set negative.

D. Feedwater control system swaps to single element control.

Answer: ,

A Qu stion Number: 1-B.05.07-014 Reference (s):

1. B.05.07-05 K/A

Reference:

259002 Task Number: K1.03 Rating RO/SRO: 3.8/

Monticello JTA:

Objective (s):

System Code: NA i

I/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 4 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 i EXAMINATION - ANSWER KEY Page 88 of 102

)

i Exam Question Number: 86 Point Value: 1.00 Time (Minutes):

The reactor is at 50% power when you lose all drywell cooling fans. Drywell pressure and

tamperature will:

4 A. Increase causing a reactor scram at 150 degrees F drywell temperature.

B. increase causing a RCIC initiation at 2 PSIG drywell pressure.

j C. Increase causing a reactor scram at 2 PSIG drywell pressure.

l D. will remain constant due to the continuous cooling provided by the N2 atmosphere.

Answer: ,

C 3

Question Number: 1-B.04.01-019 R:,ference(s):

l 1. B.04.01 -01 ,

K/A

Reference:

295012 I Task Number: AA2.02 Rating RO/SRO: 3.9/4.1 l Monticello JTA:

i Objective (s):

System Code: NA I

l/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9602

, TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 89 of 102 Exam Question Number: 87 Point Value: 1.00 Time (Minutes):

Given:

Loss of 125 VDC. Bus A 3-A-25 (AC INTERLOCK ALARM) ON

. Reactor water level-30" and decreasing

Reactor pressure 900 PSIG Assuming reactor water level continues to decrease to -60 inches, which of the following is correct?

, A. ADS valves E, G, H will open.

l B. ADS valves A, C, D will open.

C. ADS will not auto initiate due to loss of 125 VAC Bus A.

D. ADS valves E, F, G will open.

i

Answer

B i

Question Number: 1-B.03.03-018 Reference (s):

~

1. B.03.03-02 K/A

Reference:

218000 Task Number: K5.01 Rating RO/SRO: 3.8/3.8 Monticello JTA:

Objective (s):

System Code: NA l/mlf

MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 90 of 102 l Exam Question Number: 88 Point Value: 1.00 Time (Minutes):

While performing an annunciator check at the start of a shift, the operator identifies that the annunciators for panel C-06, C-07 and C-08 failed to respond. Which of the following would be a possible reason for the failure?

A. Inverter failure in the 250 VDC system.

B. 24 VDC charger output for 24 VDC reads 20 VDC.

C. Y-20 fuse disconnect failed in Y-20.

D. A 125 VDC cell in the 125 VDC battery bank shorted to ground.

Answer:

D Question Number: 1-C.4-B.09-009 Reference (s):

1. C.4-B.9.10.A K/A

Reference:

295004 Task Number: AA2.02 Rating RO/SRO: 3.5/3.9 Monticello JTA:

Objective (s):

System Code: NA 4

1/mlf

1 I

~

MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 91 of 102

Exam Question Number: 89 Point Value: 1.00 Time (Minutes):

A reactor startup and heatup is in progress. Reactor pressure is 900 PSIG. Which of the following actions must be taken if ALL CRD flow is lost and two (2) CRD accumulators low l l

prcssure alarms come in?

A. Hold at present power level until you recharge the accumulators then proceed with startup.

B. Restore CRD flow within two hours and if unsuccessful, perform a reactor scram. l C. Manually scram the reactor.

D. Manually scram the reactor when any CRD drive high temperature alarm is received.

Answer:

2 C

1 4

Question Number: 1-C.4-B.01-019 Reference (s):

1. C.4-B.01.03.A K/A

Reference:

295022

, Task Number: AA1.02 Rating RO/SRO: 3.6/3.6 i Monticello JTA:

j Objective (s):

System Code: NA 4

1/mif

l MONTICELLO NUCLEAR GENERATING PLANT M81000-9602

, TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0

EXAMINATION - ANSWER KEY Page 92 of 102 j

4 Exam Question Number: 90 Point Value: 1.00 Time (Minutes):

During a fire in the plant, the fire header pressure decreased to 75 PSIG. Current fire header is reading 115 PSIG. Which one of the following correctly describes the fire system operating lineup? Assume no operator actions have been taken.

A. Fire jockey pump is off and diesel fire pump running.

B. Screen wash pump is running supplying fire header.

C. Both fire jockey pump and electric fire pump running.

D. Both diesel fire pump and electric fire pump running.

Answer:

C Question Number: 1-B.08.05-016 Rnference(s):

1. B.08.05-01 K/A

Reference:

286000 Task Number: K4.01 Rating RO/SRO: 3.4/

Monticello JTA:

Objective (s):

Systern Code: NA I/mif

-= _

l i

MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 93 of 102 l

Exam Question Number: 91 Point Value: 1.00 Time (Minutes):

4 4

Which of the following is a function of the fuel pool skimmer surge tanks?

A. To prevent uncovering of stored fuel in the event of a fuel pool rupture.

B. Provide a means to monitor system make-up requirements.

C. Provides for cooling of fuel pool water.

D. Provides natural circulation in the event both fuel pool cooling pumps are unavailable. !

l Answer: ,

B Question Number: 1-B.02.01-013 Reference (s): ,

1. B.02.01-01 K/A

Reference:

233000 Task Number: SG 7 l Rating RO/SRO: 3.2/3.3 Monticello JTA:

Objective (s):

System Code: NA l/mlf

MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 1 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 i EXAMINATION - ANSWER KEY Page 94 of 102 l

Exam Question Number: 92 Point Value: 1.00 Time (Minutes):

While startincI RCIC the operator observes turbine RPM increasing to 5700 then dropping to zero.

MO-2080 ind cates closed and the amber mechanical overspeed light is ON. Which of the following operator actions will restore the RCIC system to operation?

A. Take the handswitch for MO-2080 located on C-04 to the CLOSE position and then to the 1 OPEN position.

B. You must send an operator to reset the trip throttle valve locally.

C. Use the pushbuttons on C-296 located in the RCIC room to CLOSE and then re-open the

, valve.

D. Take the handswitch for MO-2080 located on C-04 to the OPEN position.

Answer:

B Question Number: 1-A.4-003 Reference (s):

1. B.2.3-02 K/A

Reference:

217000 Task Number: A4.02 Rating RO/SRO: 3.9/3.9 Monticello JTA:

Objective (s):

System Code: NA l/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 95 of 102 Exam Question Number: 93 Point Value: 1.00 Time (Minutes):

i The radiation protection department has determined entrance into an area of the plant could

r: :sult in personnel receiving 1200 mr/hr,30 centimeters from the radiation source. Which one of the following is the required posting for the area?

A. High Radiation Area

! B. Locked High Radiation Area i C. Strange Area D. Locked High High Radiation Area 4

i

/

Answer:

B 4

Question Number: 1-4AWi-08-009 Rsference(s):

1. 4 AWi-08.04.01 i K/A

Reference:

294001 Task Number: K1.03 !

Rating RO/SRO: 3.3/3.8 Monticello JTA:

Objective (s):

System Code: NA l l

l I/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 l 1 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 l EXAMINATION - ANSWER KEY Page 96 of 102 Exam Question Number: 94 Point Value: 1.00 Time (Minutes):

. Initial Conditions:

1 . Reactor power 100%

- HPCI testing in progress

, . Torus temperature 92*F ;

i

All available torus cooling in service. l 1

An inadvertent Group I atuo isolation occurs causing a reactor scram. Five (5) control rods

rcmain at position 48. Which of the following EOPs have an entry condition present?

A. 1100,1300 B. 1200,1300 ,

j C. 1200,1400 j D. 1100,1200 1

4

, Answer:

j D d

4 Question Number: 1-C.5-1000-068 Reference (s):

1. C.5-1100,1200 K/A

Reference:

295037 Task Number: SG 11 Rating RO/SRO: 4.4/4.7 Monticello JTA:

Objective (s):

System Code: NA l/mlf

MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 4

TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 97 of 102 Exam Question Number: 95 Point Value: 1.00 Time (Minutes):

Given:

. Off-site release rate above Alert level ;

. Reactor Building DP .5 inches

. Exhaust plenum radiation 10 mR/hr Which one of the following EOPs shall be entered?

A. C.5-1400 B. C.5-1300 C. C.5-1200 D. C.5-1100

)

Answer:

A Question Number: 1-C.5-1000-082 R3ference(s):

1. C.5-1400 K/A

Reference:

295038 Task Number: EK1.02 Rating RO/SRO: 4.2/4.4 Monticello JTA: .

Objective (s):

System Code: NA l/mlf

d MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 98 of 102 Exam Question Number: 96 Point Value: 1.00 Time (Minutes):

The procedure for station blackout gives a reactor water level band of -126" to +48". This band...

A. Maximizes the heat removing capacity of the water injected into the vessel by HPCI or RCIC.

B. Minimizes the chance of a HPCI or RCIC turbine trip from repeated starting and stopping.

C. Maximizes the battery capacity for HPCI or RCIC operation.

D. Reduces the heating loads in HPCI and RCIC rooms due to reduced HPCI and RCIC operating times.

Answer:

C Question Number: 1-C.4-B.09-012 Reference (s):

1. C.4-B.09.02.A K/A

Reference:

295003 Task Number: AA2.03 Rating RO/SRO: 3.5 Monticello JTA:

Objective (s):

System Code: ,

NA I/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0

. EXAMINATION - ANSWER KEY Page 99 of 102 l

Exam Question Number: 97 Point Value: 1.00 Ime (Minutes):

Given:

a Reactor power is 55%.

Core flow is 25 MLB/hr.

Suddenly the No.12 recirc MG set trips while the auxiliary operator was unlocking the scoop tube.

Which of the following operator actions shall be performed?

A. Begin withdrawing control rods.

B. Begin increasing flow on the No.11 recirc pump.

l C. Immediately restart the No,12 recirc pump and return flow to greater than 25 MLB/hr D. Immediately scram the reactor before core oscillations develop.

Answer:

B Question Number: 1-C.4-B.05-004 Reference (s):

1. C.04-B.05.01.02.A K/A

Reference:

295001 Task Number: AK1.02 Rating RO/SRO: 3.3/

Monticello JTA:

Objective (s):

System Code: NA I/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION- ANSWER KEY Page 100 of 102 Exam Question Number: 98 Point Value: 1.00 Time (Minutes):

You are on duty in the Control Room when annunciators are received that indicate a loss of Y-30.

Which of the following is/are the required immediate operator action (s)?

A. Determine status of fused disconnect Y-84.

B. Take manual control of CV-3-19A or CV-3-19B to maintain proper CRD flow.

C. Maintain both SJAE steam pressures at 19.5 PSIG by throttling the respective pressure ,

control outlet valve (MS-23-1 and MS-23-2).

D. Execute C.4-B.05.07.A (LOSS OF REACTOR WATER LEVEL CONTROL) concurrently.

Answer:

D 1 Question Number: l-C.4-B.09-011 Reference (s):

1. C.4-B.09.13.E K/A

Reference:

262002 Task Number: SG 14 Rating RO/SRO: 3.3/3.4 Monticello JTA:

Objective (s):

System Code: NA 1/mlf

l 4

MONTICELLO NUCLEAR GENERATING PLANT M81000-9602 4

TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revision 0 EXAMINATION - ANSWER KEY Page 101 of 102 Exam Question Number: 99 Point Value: 1.00 Time (Minutes):

Using the attached portion of a P&lD, determine the TYPE and POSITION of the circled valve (SW-112-2).

A. Normally OPEN globe valve.

i B. Normally CLOSED gate valve.

C. Normally OPEN gate valve.

l D. Normally CLOSED globe valve. )

1 ;

! Answer:

! C 1

4 Question Number: l-P&lD-001 Reference (s):

1. P&lD K/A

Reference:

294001 Task Number: A1.07 Rating RO/SRO: /3.7 Monticello JTA:

lr.ctive(s):

6 /stem Code: NA 1/mlf

MONTICELLO NUCLEAR GENERATING PLANT M81000-9602

, TITLE: 1996 NRC REACTOR OPERATOR LICENSE Revislon 0 EXAMINATION - ANSWER KEY Paga 102 of 102 Exam Question Number: 100 Point Value: 1.00 Time (Minutes): l l

RCIC is in service and the exhaust line suddenly breaks at the water ilne in the torus. What effect

will this have on primary containment? Torus pressure will...

A. Increase, drywell pressure will remain the same. ;

B. remain the same, drywell pressure will increase.

C. increase, drywell pressure will increase, j D. increase, drywell pressure will decrease.

Answer:

C l Question Number: 1-B.04.01-020 Reference (s):

1. B.04.01-02.02 K/A

Reference:

230000 Task Number: K3.01 Rating RO/SRO: 3.7/

Monticello JTA:

Objective (s):

System Code: NA I/mif

e MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION Page 1 of 102 4

i a

! l 4

1 AII work on this examination is my own. I have neither given nor received any l ccsistance.

1 CIndidate's Name: Date:

4 i

i

i l

i hA ,

Prepared By: M /Vl4 Reviewed By:

ak ,

I

/

Approved By:4 y gg Effective Date:() p_f_ g

,y , -

Corrected By: Grade Verified By:

Points Total Total Scored Points /

Time Authenticated By-100 NA Date:

,e - - -

q7 I/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 i

LICENSE EXAMINATION - ANSWER KEY Page 2 of 102 i

i Candidate's Name: Date:

1 ANSWER SHEET l

! 1. C 2. C 3. B 4. B 5. C i

6.

B 7. B 8. D 9. C 10. A

! 11. D 12. D 13. C 14. D 15. B

16. D 17. B 18. D 19. B 20. B

21. B 22. B <

23. C 24. D 25. B

26. B 27. B 28. B 29. A 30. B

31. A 32. A 33. C 34. A 35. A

36. A 37. C 38. A 39. C 40. C

41. D 42. B 43. A 44. A 45. D

46. B 47. C 48. B 49. C 50. C

51. A 52. A 53. B 54. C 55. C l

56. D 57. B 58. B 59. A 60. B

61. B 62. A 63. B 64. C 65. C

66. B 67. A 68. A 69. D 70. C

71. D 72. D 73. B 74. C 75. C

76. A 77. C 78. B 79. A 80. B

81. A 82. B 83. D 84. C 85. A

86. C 87. B 88. D 89. C 90. B

91. B 92. B 93. B 94. D 95. A

96. C 97. A 98. D 99. C 100. D I/mif

_ _ _ _ _ _ _ _ _ _ _ a

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 3 of 102 Exam Question Number: 1 Point Value: 1.00 Time (Minutes):

As the shift supervisor you have just declared a Notification of Unusual Event (NUE). What is the maximum time you have to notify the NRC.

A. 15 minutes B. 30 minutes C. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

~

D. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Answer:

C Question Number: 1-4AWi-04-028 Reference (s):

1. 4 AWi-04.08.02 K/A

Reference:

294001 Task Number: A1.16 Rating RO/SRO: /4.7 Monticello JTA:

Objective (s):

System Code: NA 1Imit

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 4 of 102 Exam Question Number: 2 Point Value: 1.00 Time (Minutes):

The Shift Supervisor directs you to rack out a 4160 breaker. The minimum protective equipment ,

you are required to wear per the Monticello Safety Manual is:

A. Fireman's outer coat and lining, electrical switching pants and a hard hat with facial shield.

B. Electrical switching pants, high voltage protective gloves and keepers and a hardhat with facial shield.

C. Fireman's outer coat and lining, hard hat with facial shield and high voltage protective gloves and keepers.

D. Fireman's outer coat and lining, electrical switching pants and high voltage protective gloves and keepers.

l Answer: I C

Ouestion Number: 1-NSPSM-007 Reference (s):

1. SM.08-01-4.5.7 l

K/A

Reference:

294001 !

Task Number: K1.07 j l

Rating RO/SRO: 3.3/3.6 j Monticello JTA: !

l Objective (s):

System Code: NA l i

I

$ /ml4

1 MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 5 of 102 Exam Question Number: 3 Point Value: 1.00 Eme (Minutes):

You as the senior reactor operator are notified that the stroke time of a motor operated valve tasted during a quarterly tech spec surveillance exceeded its Limiting Stroke Time (LST). Which of the following shall be taken?

A. Immediately retest the valve. If the retest time does not exceed the LST then notify the system engineer.

B. Immediately declare the valve inoperable and notify personnel in accordance with 4 awl-04.08.01 (INITIAL NOTIFICATIONS).

C. Since the LST was exceeded form 3107, inservice Test Deviation frcm Acceptable Criteria Shift Supervisor's Immediate Action must be completed. The valve may remain operable for twenty-four (24) hours to allow the data to be analyzed.

D. Secure the valve breaker in the OPEN position until electricians can perform preventive maintenance on the valve.

Answer:

B Ouestion Number: 1-4 awl-09-001 Reference (s):

1. 4 awl-09.04.01 K/A

Reference:

294001 Task Number: A1.08 Rating RO/SRO: /3.6 Monticello JTA: SS332.004 Objective (s): M-8108L-029, EO-1 System Code: NA 1/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 6 of 102 4

1

Exam Question Number: 4 Point Value: 1.00 Time (Minutes):

Given:

. Group I auto isolation with all MSIVs closed

. Feedwater high pressure heater block valves MO-1614 and MO-1615 closed, d

. Reactor water level -30 inches.

. Drywell pressure 4.5 PSIG.

. Reactor pressure 800 PSIG.

Which of the following correctly describes HPCI system operation?

!' A. HPCI steam supply is available, HPCI will auto start but not inject to the vessel.

B. HPCI steam supply is available awJ HPCI will inject to the vessel.

C. HPCI steam supply is unavailable.

D. HPCI steam supply available, however HPCI will NQI auto start and inject to the vessel.

Answer:

B Ouestion Number: 1-B.03.02-024 Reference (s):

1. B.03.02-02 K/A

Reference:

206000 Task Number: K1.04 Rating RO/SRO: 3.6/3.6 Monticello JTA:

Objective (s):

System Code: NA I/mif

l l

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 7 of 102 Exam Question Number: 5 Point Value: 1.00 Time (Minutes):

Par the operations manual, the reactor building ventilation exhaust high radiation trip closes a l number of class B isolation valves which, if inadvertently closed, wou d neither adversely affect plant safety nor interfere significantly with plant operations. PCIS class B isolation valves are on process lines that:

A. Penetrate the primary containment but do not communicate directly with the reactor vessel or primary containment free space.

B. Communicate directly with the reactor vessel and penetrate primary containment.

C. Do not communicate directly with the reactor vessel but communicate directly with the primary containment free air space. l D. Do not communicate with either the reactor vessel or primary containment.

Answer: 1 C

Question Number: 1-B.05.06-030 Reference (s):

1. B.05.06-01 K/A

Reference:

295020 Task Number: AA1.01 Rating RO/SRO: 3.6/3.6 Monticello JTA:

Objective (s):

System Code: NA unn j

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 8 of 102 Exam Question Number: 6 Point Value: 1.00 Time (Minutes):

Which one of the following locations is a vital equipment area and could endanger the public h@alth and safety by exposure to radiation if a uncontrollable fire broke out?

A. Main turbine.

B. 4 KV room.

C. 345 KV subyard.

D. 13 diesel generator.

Answer:

B Ouestion Number: 1-10CFR-002 Reference (s):

1. 10CFR73

2. 4 AWi-08.06.01 K/A

Reference:

294001 l Task Number: K1.05 Rating RO/SRO: 3.2/3.7 Monticello JTA: 2990020301 Objective (s): M-8108L-002, EO-5 System Code: N/A 1

l

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 i LICENSE EXAMINATION - ANSWER KEY Page 9 of 102

=

Exam Question Number: 7 Point \ alue: 1.00 Time (Minutes):

Given:

a 100% power 1 - Both recombiners trip unexpectedly i

The duty crew has reduced reactor power to 20% with recirc and control rods. A further power rcduction is needed. Which of the following is required in accordance with C.4-F (RAPID POWER REDUCTION)?

A. Bypass the RWM to reduce reactor power with control rods.

j B. Manually scram the reactor.

i C. Trip one recirc pump.

{ D. Use the emergency rod insertion control switch to insert control rods and reduce reactor power.

l l

Answer:

B l

Question Number: 1-C.4-F-001 R ference(s):

1. C.4-F K/A

Reference:

295015 Task Number: AK3.01 Rating RO/SRO: 3.4/3.7 Monticello JTA:

Objective (s):

System Code: NA l/mif ;

1 MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 l LICENSE EXAMINATION - ANSWER KEY Page 10 of 102 l l

Exam Question Number: 8 Point Value: 1.00 Time (Minutes):

1 Given: l

. Reactor power 30%

= Both RBM channels are operable Reference APRM channel for RBM 7 has failed downscale RBM 7 will receive a reference signal from...

A. APRM 5 upon detection of the reference APRM downscale. l B. APRM 1 when the bypass switch for APRM 3 is placed in bypass. l C. the same APRM that supplies RBM 8. l D. APRM 2 when the bypass switch for APRM 3 is placed in bypass. !

l l

Answer:

D Question Number: 1-B.05.01.02-043 Reference (s):

1. B.05.01.02 K/A

Reference:

215001 Task Number: A2.03 Rating RO/SRO: 3.1/3.3 Monticello JTA:

Objective (s):

System Code: NA i/mif

i i

l MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 11 of 102 Exam Question Number: 9 Point Value: 1.00 Time (Minutes):

A fire in the cable spreading room has required immediate control room evacuation with no time available to perform subsequent operator actions. Which of the following is the correct immediate operator response in accordance with C.4-0 (SHUTDOWN OUTSIDE THE CONTROL ROOM)?

A. Do not manually scram with pushbuttons, place Reactor Mode Switch in SHUTDOWN, do NOT close MSIVs. )

B. Do not manually scram with pushbuttons, leave Reactor Mode Switch in RUN, close l MSIVs.

C. Manually scram with pushbuttons, leave Reactor Mode Switch in RUN, do NOT close MSIVs. ,

D. Manually scram with pushbuttons, place Reactor Mode Switch in SHUTDOWN, close l MSIVs. ,

Answer:

C l

Question Number: 1-C.4-C-001 Reference (s):

1. C.4-C K/A

Reference:

295016 Task Number: SG 10 Rating RO/SRO: 3.9/3.7 Monticello JTA:

Objective (s):

System Code: NA limil

b MONTICELLO NUCLEAR 1ENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 12 of 102 i

1 Exam Question Number: 10 Point Value: 1.00 Tme (Minutes):

Given:

- Reactor power 100%

Electrical Pressure Regulator (EPR) set at 905 PSIG

=

Mechanical Pressure Reguattor (MPR) set at 925 PSIG

. Reactor pressure 1000 PSIG. l If the EPR setpoint fails high, reactor pressure will...

A. increase and reactor power will increase.

B. decrease and reactor power will decrease.

C. Increase and reactor power will decrease. l D. decrease and reactor power will increase. I Answer:

A Question Number: 1-C.4-B.05-005 R ference(s):

1. C.4-B.05.07.B K/A

Reference:

295007 Task Number: AK1.03 Rating RO/SRO: 3.8/3.9 Monticello JTA:

Objective (s):

System Code: NA l/mtf

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 13 of 102 j

Exam Question Number: 11 Point Value: 1.00 Ime (Minutes): i 1

4 The Reactor Recirculating Flow Control system utilizes in auts from the feedwater system. Which of the following describes the bases for this deQn. The feedwater interlock...

A. prevents operation of the reactor recirc pumps at speeds greater than 30% until both MO-1614 and MO-1615 (FW Heater Outlet Valves) are open.

i B. assures that the temperature of the water in the annulus region has been raised above j saturation temperature prior to increasing speed of the reactor recirc pumps.

C. reduces reactor recirc pump speeds to 48% on decreasing feedwater flow to assure adequate sub-cooling of the reactor recirc pump suction water such that the pumps NPSH requirements are maintained.

D. prevents high speed operation of the reactor recirc pumps at feedwater flows less than 20% in order to protect the reactor recirc pumps from cavitation.

l Answer:

D Question Number: 1-B.01.04-055 Reference (s):

1. B.01.04-01, B.05.08-01, C.4-A, DBD-B.01.04 K/A

Reference:

259002 Task Number: K4.01 Rating RO/SRO: 3.0/3.1 Monticello JTA:

Objective (s):

System Code: NA I lmtf

1 l

l l

MONTICELLO NUCLEAR GENERATING PLANT M81000-9f>01 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 14 of 102 Exam Question Number: 12 Point Value: 1.00 Time (Minutes):

During a reactor startup, the C-05 operator attempts to withdraw a control rod and gets no response. The operator observes the following CRD system indications:

. CRD drive pressure is 200 PSIG.

i CRD discharge pressure is 1485 PSIG. l Based on these indications what action shall the operator perform prior to attempting to withdraw th3 rod again? You should throttle... 4 A. open the selected CRD flow control valve CV 3-19A or B.

B. close the selected CRD flow control valve CV 3-19A or B.

C. open valve MO 3-20 drive pressure to CRD.

D. close valve MO 3-20 drive pressure to CRD.

l Answer:

D Question Number: 1-B.01.03-026 Reference (s):

1. B.01.03-05 K/A

Reference:

201001 Task Number: K4.09 Rating RO/SRO: 2.9/2.8 Monticello JTA:

Objective (s):

System Code: NA l/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 15 of 102 Exam Question Number: 13 Point Vafue: 1.00 Time (Minutes):

NI Given the following information:

1 A reactor scram occurred 15 minutes ago and the scram has not been reset. The RWCU system was in service to assist in maintaining reactor water level. RWCU dump flow was routed to the hotwell. The reactor operator observed the closure of the following valves MO-2399, RWCU RETURN ISOLATION and MO-2404, RWCU DUMP TO HO1WELL .

)

Which of the following caused the valves to close? l A. Temperature at the RWCU non-regenerative heat exchanger inlet is 150 degrees F.

B. Reactor water level has decreased to +2 inches.

C. Temperature at the RWCU filter demineralizer inlet is 150 degrees F.

D. Pressure downstream of RWCU excess FCV CV-2403 is 165 PSIG.

l Answen C

Question Number: 1-B.02.02-020 Reference (s):

1. B.02.02 K/A

Reference:

204000 Task Number: K4.04 ,

1 Rating RO/SRO: 3.5/3.6 Monticello JTA:

Objective (s):

System Code: NA l/mif j

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 16 of 102 Exam Question Number: 14 Point Value: 1.00 Time (Minutes):

The operator is allowed some flexibility when performing the steps in procedure C.1. If l conducting a plant startup, which of the following would be correct?

A. Placing the second RFP in service at 80% power. '

B. Omitting steps not required.

C. Increasing recirc flow and withdrawing control rods concurrently.

D. Establishing steam flow to the condenser prior to the second condensate pump being placed in service.

Answer:

D Question Number: l-C.03-029 Reference (s):

1. C.01 K/A

Reference:

294001 Task Number: A1.02 Rating RO/SRO: 4.2/4.2 Monticello JTA:

Objective (s):

System Code: NA l/mif

MGNTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 17 of 102 Exam Question Number: 15 Point Value: 1.00 Time (Minutes):

Given:

Reactor power 100%

=

Plant entered 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months LCO due to loss of LC-104.

If No.11 RBCCW pump trips, which of the following is required in accordance with procedures C.4-B.2.5.A (LOSS OF RBCCW FLOW)?

A. Manually start No.12 RBCCW pump.

B. Trip both recirc pumps within 60 seconds.

l C. Reduce recirc flow to minimum and manually scram the reactor.

D. Isolate SW to RBCCW heat exchangers.

Answer:

B l

I l

Question Number: 1-C.4-B.02-009 Reference (s):

1. C.4-B.02.05.A K/A

Reference:

295018 Task Number: AK1.01 Rating RO/SRO: 3.5/3.6 Monticello JTA:

Objective (s):

System Code: NA l/mif l

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 ,

LICENSE EXAMINATION - ANSWER KEY Page 18 of 102 )

Exam Question Number: 16 Point Value: 1.00 Time (Minutes):

Which of the following signals will cause the Reactor Recirc pump speed control signal to automatically run back to 45% speed?

A. Reactor is at 75% power and Recirc Pump 11 discharge valve drifts to 90% open.

B. Reactor startup is in progress, one RFP is running, and reactor water level is at +45 inches and rising.

C. Reactor is at 75% power and a " Lockout" of 4160 volt bus 11 occurs.

D. Reactor is at 75% power and Condensate Pump 11 trips.

Answer:

D I

Question Number: 1-B.05.08-011 Reference (s):

1. B.05.08-01

2. B.01.04-02 K/A

Reference:

295009 Task Number: AK3.01 Rating RO/SRO: 3.2/3.3 Monticello JTA:

j Objective (s): l System Code: NA l

l I/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 19 of 102 l

Exam Question Number: 17 Point Value: 1.00 Time (Minutes):

During power operations you observe that APRM 1,2, and 3 go downscale. Which of the followir g caused this event to occur?

A. RPS MG Set No.12 breaker tripping open due to undervoltage relay failure.

B. RPS MG Set No.11 motor bearings seizing the shaft. j C. 125 VDC Div i charger output having decrease to 100 VDC.

D. 125 VDC Div ll inverter failure.

Answer:

B Question Number: 1-B.05.01.02-041 Reference (s):

1. B.05.01.02-02 K/A

Reference:

215005 Task Number: K6.01 Rating RO/SRO: 3.7/3.8 Monticello JTA:

Objective (s):

System Code: NA l/mif

1 l

l MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 20 of 102 Exam Question Number: 18 Point Value: 1.00 Time (Minutes):

During a loss of normal offsite power No.11DG has been loaded at 2750 KW for 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months . If power cannot be restored, how long can No.11 EDG continue to run under these conditions?

A. 452 hours0.00523 days 0.126 hours 7.473545e-4 weeks 1.71986e-4 months .

B. 952 hours0.011 days 0.264 hours 0.00157 weeks 3.62236e-4 months .

C. 1452 hours0.0168 days 0.403 hours 0.0024 weeks 5.52486e-4 months .

D. 1952 hours0.0226 days 0.542 hours 0.00323 weeks 7.42736e-4 months .

l Answer:

l l

Question Number: 1-B.09.08-046 Reference (s):

1. B.09.08-02 K/A

Reference:

264000 Task Number: K3.01 Rating RO/SRO: 4.2/4.4 Monticello JTA:

Objective (s):

System Code: NA I/mlf

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATICN - ANSWER KEY Page 21 of 102 Exam Question Number: 19 Point Value: 1.00 Time (Minutes):

1 You are the on duty Shift Supervisor reviewing the Core Spray System Prestart Valve Checklist just prior to initiating rod withdrawal following a refueling outage. You notice valve MO-1741 (11 l CS PUMP TORUS SUCTION) is circled in red. You must:

A. Notify the Core Spray system engineer to initiate a work order against MO-1741.

B. Understand the reason the item is circled in red and verify it does not conflict with Tech Specs.

C. Issue a 3087 (DOCUMENT CHANGE, HOLD, AND COMMENT FORM) against the i checklist to prevent future use without a revision.

D. Prevent rod withdrawal until the Plant Manager has evaluated the prestart checklist and l authorizes Reactor startup.

Answer:

B Question Number: 1-C.1-028 Reference (s):

1. C.1 K/A

Reference:

294001 Task Number: K1.01 Rating RO/SRO: /3.7 Monticello JTA: SS333.013 Objective (s): M-8108L-029, EO-1 System Code: NA l/mif

t MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0

LICENSE EXAMINATION - ANSWER KEY Page 22 of 102 Exam Question Number: 20 Point Value: 1.00 Time (Minutes):

Given: l

. Small break LOCA DW pressure 4 PSIG and increasing slowly Reactor pressure 1000 PSIG and holding steady Reactor level at +35 inches and holding steady To place the "A" loop of RHR in service for torus cooling / torus spray, the operator shall perform which of the following?

A. Place Containment Spray 2/3 Height Bypass Core switch in the MANUAL OVERRIDE position.

B. Momentarily place the Containment Spr ly/Cu ]!!ng LPCI Initiation Bypass switch in the BYPASS position.

C. Depress the LPCI Loop Select Logic Reset nushbutton.

D. Depress the Shutdown Cooling Group 11 Isola. ion Reset pushbutton.

Answer:

B Question Number: 1-B.03.04-031 Reference (s):

1. B.03.04-05 K/A

Reference:

203000 Task Number: ,

A4.05 Rating RO/SRO: /4.1 Monticello JTA:

Objective (s):

System Code: NA l/mlf

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: l 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 23 of 102 Exam Question Number: 21 Point Value: 1.d0 Time (Minutes):

Given:

Reactor water level +9 inches

. Fuel pool monitor indicates 57 mR/hr.

Reactor Building vent WRGM indicates 4700 uci/sec.

. Reactor Building vent monitor indicates 20 mr/hr.

. Drywell pressure 1.8 PSIG.

Which of the following automatic responses is correct?

A. LPCI Loop select logic has energized.

B. SBGT system has auto initiated.

C. RCIC has auto initiated.

D. Core spray pumps have auto initiated.

1 Answer:

B 1

l Question Number: 1-B.05.11-036 Reference (s):

1. B.05.11 K/A

Reference:

295023 Task Number: AK2.07 Rating RO/SRO: 3.6/3.9 Monticeito JTA:

Objective (s):

System Code: NA l/mif

4 MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 24 of 102 Exam Question Number: 22 Polnt Value: 1.00 Time (Minutes):

Temporary removal of HOLD and SECURE cards is allowed within the equipment isolation process. Which of the following describe a correct action within the temporary removal process?

A. All safety tags re-installed using the temporary removal process are required to be independently verified.

B. Eq,uipment verification is required for all safety tags which are temporarily removed, not re-installed and then given permanent removal status.

C. Authorization from the owner of a safety tag is not required when temporarily removing a safety tag.

D. All safety tags temporarily removed using the temporary removal process are required to be independently verified.

Answer:

B Ouestion Number: 1-4 awl-04-027 .

Reference (s):

1. 4 awl-04.04.01

2. 4 awl-04.04.02 K/A

Reference:

294001 Task Number: K1.02 Rating RO/SRO: /4.5 Monticello JTA:

Objective (s):

System Code: NA I/mlf

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY l Page 25 of 102 Exam Question Number: 23 Point Value: 1.00 Time (Minutes): _ l Which of the following is a refuel interlock failure? '

A. Refuel bridge over the core, mode switch in startup, reverse travel blocked.

B. Refuel bridge over the core, mode switch in refuel,1 rod at position 48, reverse travel blocked.

C. Refuel bridge over the core, fuel grapple not full up,1 control rod at position 48, reverse travel permitted.

D. Refuel bridge over the core. Mode switch in refuel, all rods at 00. Reverse travel permitted.

Answer:

C Ouestion Number: 1-B.05.05-020 Reference (s):

1. B.05.05-06 K/A

Reference:

234000 Task Number: A2.01 Rating RO/SRO: 3.3/3.7 Monticello JTA:

Objective (s):

System Code: NA l/mif

f MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 26 of 102 l l

Exam Question Number: 24 Point Value: 1.00 Time (Minutes):

Given:

. Reactor at 10% power Turbine / Generator on line i

Plant staff has decided to remove the Turbine / Generator from service to perform minor work on the exciter brushes. The Shift Supervisor directs you to place the PRO switch to OPEN. This r:sults in the...

A. bypass valves opening and removing steam load to the turbine.

B. control valves c!ccing causing a Reactor high pressure scram.

C. stop valves closing causing a Reactor high pressure scram.

D. control valves opening causing a low main steam line pressure Group I isolation.

i Answer:

D Question Number: 1-B.05.09-013 Reference (s):

1. B.05.09-02 K/A

Reference:

245000 Task Number: K6.02 Rating RO/SRO: 3.5/3.7 Monticello JTA:

Objective (s):

System Code: NA l/mif

I MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 27 of 102 l Exam Question Number: 25 Point Value: 1.00 Time (Minutes):

With the plant on line at 100% power, which of the following would NOT be the direct result of a main generator lockout (286G)?

A. 8N4 and 8NS (main generator breakers) trip and lockout.

B. A reactor scram.

C. Generator field breaker trip and lockout.

D. Turbine trip and lockout (286T).

Answer:

B i

Question Number: 1-B.09.02-025 Reference (s):

1. B.09.02-02 K/A

Reference:

295005 Task Number: AK3.04 Rating RO/SRO: /3.2 Monticello JTA:

Objective (s):

System Code: NA I/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 l LICENSE EXAMINATION - ANSWER KEY Page 28 of 102 i \

Exam Question Number: 26 Point Value: 1.00 Time (Minutes):

Prior to placing HPCI in service, the operator is directed to place torus cooling in service if time parmits. The reason for this procedural requirement is to...

J A. ensure that torus temperature will remain below 90 degrees F. i B. prevent localized torus temperature transients. :

1 l C. prevent chugging in the HPCI turbine exhaust piping. l

) D. ensure that a steam environment cannot exist in the torus air space.

4 Answer: l

B l 1

Question Number: 1-B.03.02-022 4

Reference (s):

1. B.03.02-05 K/A

Reference:

295013 l

Task Number: AA2.02

Rating RO/SRO: 3.2/4.0 1

Monticello JTA:

Objective (s):

System Code: NA l

J 1/mlf

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION- ANSWER KEY Page.?9 of 102 l Exam Question Number: 27 Point Value: 1.00 Time (Minutes):

Which of the following is the maximum temperature at which the Shift Supervisor would direct 3 ADS valves open to ensure drywell temperature limits are not exceeded in accordance with C.5-1200.

A. 270 degrees F and temporature stable.

B. 280 degrees F and temperature increasing.

C. 290 degrees F and temperature stable D. 300 degrees F and temperature increasing Answer:

B Question Number: 1-C.5.1-1000-002 Reference (s):

1. C.S.1-1200 K/A

Reference:

295027 Task Number: EK3.01 Rating RO/SRO: /3.8 Monticello JTA:

Objective (s):

System Code: NA 1/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0

LICENSE EXAMINATION - ANSWER KEY Page 38 of 102 Exam Question Number: 36 Point Value: 1.00 Time (Minutes):

Using the RWCU pump room figure, where shall you spend your time if you are in the RWCU

room and waiting for someone to bring you tools?

A. A B. B

C. C D. D i

4 Answer:

A Question Number: 1-awl-08-011 Reference (s):

j

1. 4 AWi-08.04.01 K/A

Reference:

294001 Task Number: K1.04 Rating RO/SRO: /3.6 I Monticello JTA:

Objective (s):

System Code: NA I/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601

TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 39 of 102

~

Exam Question Number: 37 Point Value: 1.00 Time (Minutes):

Given:

. 1R transformer out of service

. 1 AR transformer supplied from 1 ARS 1

+ 2R transformer supplying plant load l

A reactor startup is about to begin Which of the following is the correct response? I A. Continue with reactor startup since you have two transmission lines that are fully operable.

i B. Continue with reactor startup but do not place the mode switch in RUN until both

~

Emergency Diesels have been proven operable. )

C. Transfer the supply for 1 AR to 10 transformer and continue with the reactor startup.

D. Continue with the reactor startup but do not place the mode switch to RUN until the 1 R is returned to service.

l Answer:

l C

l 1

Question Number: 1-TS-041 Rsference(s):

1. Tech Spec 3.9.A.1 K/A

Reference:

295003 Task Number: SG 03 l

Rating RO/SRO: /4.2 Monticello JTA:

Objective (s):

System Code: NA I/mlf

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 40 of 102 Exam Question Number: 38 Point Value: 1.00 lime (Minutes):

Which of the following set of conditions is a valid level reading with a main steam line leak in l primary containment?

Condition A Condition B

Safeguard level indicators read -35"

Vessel flood indication reads -5"

RPV pressure is 200 PSIG RPV pressure 100 PSIG

Average DW temp is 350*F Average DW temp is 330*F

Secondary Containment temp is 210 F = Secondary Containment temp is 70*F Condition C Condition D

~

Fuel zone level indicator reads -130" Feedwater levelindicator reads +9"

RPV pressure is 150 PSIG

RPV pressure is 15 PSIG

Average DW temp is 390 F

Average DW temp is 290*F

Secondary Containment temp is 450*F Secondary Containment temp is 100*F Answer:

A Question Number: 1-C.5-1000-070 Rsference(s):

1. C.5-1100, Detail A, Figures B and C K/A

Reference:

295032 Task Number: EK2.08 Rating RO/SRO: 3.8/3.9 Monticello JTA:

Objective (s):

System Code: NA I/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 41 of 102 l Exam Question Number: 39 Point Value: 1.00 Time (Minutes):

Given:

A Reactor startup is in progress.

Reactor pressure is approximately 500 PSIG.

The Pressure Regulator Override (PRO) is maintaining No.1 Turbine bypass valve 10-15% open.

Mechanical Pressure Regulator (MPR) is in standby with the setpoint 50 PSIG above reactor pressure.

Which of the following describes the Turbine Bypass valve response given a Turbine Vacuum Trip 2? Turbine Bypass valves will...

A. not change position. Turbine Vacuum Trip 2 generates a Turbine trip and will close only the Turbine Stop and Control valves.

B. initially close. Reactor pressure will increase to the MPR setpoint at which time the Turbine Bypass valves will open to control reactor pressure at the higher value.

C. close and remain closed until the Turbine Vacuum Trip 2 is reset.

D. open to control reactor pressure as a result of the closing of the Turbine Stop and Control valve drains.

6nswer:

C Question Number: 1-B.06.01-049 R ference(s):

1. B.06.01 K/A

Reference:

295002 Task Number: AK3.04' Rating RO/SRO: 3.4/3.6 Monticello JTA:

Objective (s):

System Code: NA I/mlf

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 42 of 102 Exam Question Number: 40 Point Value: 1.00 Tme (Minutes):

Given:

- Reactor power 43%

Core flow 25 mlb/hr The C-05 operator is adjusting recirc flow to exit the exclusion area of the power to flow map.

If reactor power as indicated by the APRMs begins to slowly increase and decrease with an increasing magnitude the immeidate operator action (s) is/are to...

A. notify the nuclear engineer.

B. enter rapid power reduction and reduce power with control rods until APRM traces are steady.

3 C. manually scram the reactor.

D. place the MPR in service to stop control valve hunting.

1 Answer:

f C

1 4

Question Number: 1-C.4-B.05-006 Reference (s):

1. C.4-B.05.01.02.A K/A

Reference:

216000 Task Number: SG 15 Rating RO/SRO: 4.1/4.4 Monticello JTA:

Objective (s):

System Code: NA I/mlf

l l

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 I LICENSE EXAMINATION - ANSWER KEY Page 43 of 102 Exam Question Number: 41 Point Value: 1.00 Time (Minutes): i Which of the following is an acceptable value concerning the recirc system and core flow or loop flow?

A. A core plate DP of 3 and 60% core flow.

B. A 50% loop flow and No.11 recirc pump at 50% speed.

C. A 40% loop flow and No.12 recirc pump at 40% speed.

' D. 25,000 GPM loop flow and No.11 recirc pump at 80% speed. l Answer:

I D

l Question Number: 1-B.01.04-056 Reference (s):

1. B.01.04-06.02, Fig 1,2,3 and 4 K/A

Reference:

202001 Task Number: A1.03 Rating RO/SRO: 3.6/3.6 Monticello JTA:

Objective (s):

System Code: NA I/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 44 of 102 Exam Question Number: 42 Point Value: 1.00 Time (Minutes):

With the plant at full power an automatic 2R to 1 R transfer occurs. No abnormalities exist. Which of the following identify the status of the Reactor Feed Pumps (RFP)?

A. Both 11 and 12 RFPs are operating.

B. 11 RFP is operating,12 RFP breaker is closed but 12 bus is de-energized.

C. 12 RFP is operating,11 RFP breaker is closed but 11 bus is de-energized.

D. Both 11 and 12 RFP have tripped on undervoltage. ,

Answer:

B 1

1 Question Number: 1-B.09.06-035 Reference (s): l

1. B.09.06 K/A

Reference:

295003 Task Number: AK3.03 Rating RO/SRO: 3.5/3.6 Monticello JTA:

Objective (s):

System Code: NA l/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR _ Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 45 of 102 Exam Question Number: 43 Point Value: 1.00 Time (Minutes):

Which of the following describe how the Condensate and Feedwater system will react to a complete loss of 480 Volt AC Uninterruptible Power Supply Y-917 A. The controllers for the feedpump recirc valves will lose power and the feedpump recirc i

valves will fail in the closed position. Position indication will remain available from C-06.

B. The condensate recirc valves will lose power and the condensate recirc valves will fail open. Position indication is not available from C-06.

C. The backup power supply for the Feedwater Digital Control system process modules will lose power. Computer alarm 5-B 47 (FW CONTROL HARDWARE TROUBLE) will annunciate.

D. Feedwater heater dump valves will fail open and the feedwater heater drain valves will fail closed upon lose of power. Position indication is not available from C-20.

Answer:

A Question Number: 1-B.06.05-018 Reference (s):

1. B.06.05-05 K/A

Reference:

259001 Task Number: SG 07 Rating RO/SRO: 3.5/3.5 Monticello JTA:

Objective (s):

System Code: NA I/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 46 of 102

=,=--

Exam Question Number; 44 Point Value: 1.00 mme (Minutes):

Plant staff has determined that an entry into the waste collector tank is required to remove sludge buildup. Which of the following is correct concerning entry into the waste collector tank?

A. A confined space entry permit is required and is issued by the safety administrator.

B. If the Initial oxygen concentration is approximately 21% no ventilation or continuous monitoring is required.

C. A job specific emergency rescue plan is not required if the tank contents are non-flammable.

D. A confined space entry permit is not required if the entrance to the tank will last less than

0 minutes.

Answer:

A Question Number: 1-NSPSM-006 R:ference(s):

1. Safety Manual Lesson Plan SM-23.01 K/A

Reference:

294001 Task Number: K1.14 Rating RO/SRO: 3.2/3.4 Monticello JTA:

Objective (s):

System Code: NA I/mif

i MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 \

TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 47 of 102 l Exam Question Number: 45 Point Value: 1.00 Time (Minutes):

A leak in the drywell while at power has just occurred. Which of the following concerning leakcge to the drywell sumps is correct?

A. A 2 GPM increase in unidentified leakage within any 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months period requires cold shutdown conditions within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

B. Unidentified leakage greater than 10 GPM requires cold shutdown conditions within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

C. Identified leakage of 10 GPM requires cold shutdown conditions within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

D. Identified leakage of greater than 20 GPM requires cold shutdown conditions within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

I Answer:

D l 1

I l

Question Number: 1-TS-032 Rsference(s):

1. Tech Specs 3.6 K/A

Reference:

268000 Task Number: A4.01 Rating RO/SRO: 3.4/3.6 Monticello JTA:

Objective (s):

System Code: NA I/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 l LICENSE EXAMINATION - ANSWER KEY Page 48 of 102

. EmTestion Number: 46 Point Value: 1.00 Time (Minutes):

In order to place RHR in shutdown cooling, annunciator 3-B-45 (RHR HIGH REACTOR I PRESSURE) must be clear. The minimum pressure to clear the alarm is... !

A. 60 PSIG at RHR pump suction. I B. 75 PSIG at RHR pump suction.

C. 85 PSIG at RHR pump suction.

D. 100 PSIG at RHR pump suction.

Answer:

1 B l l

l l

Question Number: 1-C.6-001 Reference (s):

1. C.6 ARP K/A

Reference:

295007 Task Number: AK2.05 Rating RO/SRO: /3.1 Monticello JTA:

Objective (s):

System Code: NA I/mif

1 1

l MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 49 of 102 Exam Question Number: 47 Point Value: 1.00 Time'ihlinutes):

While performing the quarterly RCIC operability tests, A-16 (RCIC ROOM RAD MONITOR) reaches the alarm setpoint. The Reactor Building Operator has reported a steam environment exists in the RCIO pump room. As the reactor operator you want to isolate steam flow to the ,

RCIC room. l Which of the following by procedure is the correct action (s)?

A. Depress the RCIC turbine trip button.

B. Close MO-2078 (STEAM ADMISSION VALVE). l C. Close MO-2075 and MO-2076 (RCIC STEAM ISOLATION VALVES).

D. Manually scram the reactor.

I Answer:

C l l

l l

Question Number: B.02.03-018 Reference (s):

1. B.02.03-018 l

2. EOP 1300 K/A

Reference:

295033 Task Number: EK3.03 Rating RO/SRO: 3.8/3.9 Monticello JTA:

Objective (s):

System Code: NA 1/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 50 of 102 Exam Question Number: 48 Point Value: 1.00 Time (Minutes):

Upon an automatic initiation signal to Standby Gas Treatment (SBGT) with normal AC power available Train A can only maintain a flow of 2000 SCFM. Which of the following describe how I tho SBGT system would respond?

A. If flow on Train A is not above 3000 SCFM within 30 seconds Train B flow control valve will open to achieve the desired flow.

B. If flow on Train A is not above 2800 SCFM within 10 seconds Train B will auto start to achieve the desired flow.

C. Train B immediately received an auto start signal and will operate in parallel with Train A until manually secured by an operator.

D. Initially TrWn A Mi receive a start and 5 seconds later Train B will receive an auto start. l Low flow of GOOD SCFM on Train A will annunciate the low flow alarm on C-24. Train B will l maintain the desired fiow l

Answer:

B Question Number: 1-B.04.02-024 Reference (s):

1. B.04.02-01 K/A

Reference:

295034 Task Number: EA1.04 Rating RO/SRO: 4.1/4.2 Monticello JTA:

Objective (s):

System Code: NA I;mlf

_MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 51 of 102 Exam Question Number: 49 Point Value: 1.00 Time (Minutes):

The Monticello plant is in the initial stages of a reactor startup when a small LOCA occurs. The following conditions are currently present:

Core flooding instruments indicate -130 inches Drywell temperature 110 degrees F

. Reactor pressure 620 PSIG .

1 The Shift Supervisor is concerned that the fuel is uncovered and asks you to determine what actual water level is. Actual water level is...

i

< A. -120 inches B. -130 inches i C. -140 inches D. -160 inches

~

Answer:

C i

Question Number: 1-B.01.01-031 Reference (s):

1. B.01.01-06.02 K/A

Reference:

216000 Task Number: A3.01 Rating RO/SRO: 3.4/3.4 Monticello JTA:

Objective (s):

System Code: NA I/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 52 of 102 Exam Question Number: 50 Point Value: 1.00 Time (Minutes):

The on duty reactor operator was reviewing the computer point RPV 506 (10 Minute Average Core Thermal Power) which was indicating 1671 MWth. By procedure, which of the following is the correct operator response?

A. Verify that the daily average for core thermal power has been less than 1670 MWth.

B. No action needs to be taken provided hourly MWth average is less than 1670 MWth.

C. Take action to reduce core thermal power to less than1670 MWth.

D. No action needs to be taken. There is a 1% deviation allowed to the 1670 MWth limit.

Answer:

C Ouestion Number: l-C.2-014 Reference (s):

1. C.2-01 K/A

Reference:

294001 Task Number: A1.15 Rating RO/SRO: 3.2/3.4 Monticello JTA:

Objective (s): I System Code: NA l

l l

i I/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 53 of 102 Exam Question Number: 51 Point Value: 1.00 Time (Minutes):

Given:

- Multiple stuck rods at position 48

Torus temperature 110 degrees F SBLC is required to... !

A. prevent exceeding the torus heat capacity limit. I B. prevent exceeding the ECCS vortex limit.

C. ensure secondary containment is maintained.

D. ensure a return to criticality from a positive temperature coefficient does not occur.

Answer:

Question Number: 1-C.S.1-2000-001 Reference (s):

1. C.S.1-2007, Part S and T K/A

Reference:

295026 Task Number: EK3.04 Rating RO/SRO: /4.1 Monticello JTA:

Objective (s):

1 System Code: NA 1/mit ,

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 54 of 102 Exam Question Number: 52 Point Value: 1.00 Ime (Minutes):

l Given:

> . Normal shutdown cooling unavailable

. No recirc pumps are running Reactor water level +65 inches Reactor water temperature 160 degrees F and increasing Which of the following is the correct operator action to place the RWCU system into the heat .

r:Jection mode?

A. Maximize RBCCW flow through the non-regenative heat exchanger.

B. Minimize RWCU flow through the clean-up system non-regenative heat exchanger. I C. Line up RWCU to dump to the condenser.

D. Maximize RBCCW flow through the regenative heat exchanger.

l Answer:

A Question Number: 1-C.4-B.03-009 R;ference(s):

1

1. C.4-8.03.04.A j K/A

Reference:

295021 l Task Number: AA1.01 i Rating RO/SRO: 3.4/3.4 Monticello JTA: l Objective (s):

System Code: NA l/mif

1 1

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0

! LICENSE EXAMINATION - ANSWER KEY Page 55 of 102 i ~'

l Exam Question Number: 53 Point Value: 1.00 Time (Minutes):

l The maximum design pressure limit for the drywell at Monticello is:

A. 65 PSIG B. 56 PSIG

! C. 60 PSIG l D. 58 PSIG l

Answer:

8 Question Number: 1 B.04.01-019 Rsference(s):

1. B.04.01-02.01 K/A

Reference:

295024 Task Number: EK1.01 Rating RO/SRO: 4.1/4.2 Monticello JTA:

Objective (s):

System Code: NA 1

1/mtf

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 56 of 102 Exam Question Number: 54 Point Value: 1.00 Time (Minutes):

During 100% aower operation, alarm 5-A-46 (SRV OPEN) is received. The amber light is on for SRV A. Whic1 of the following is the immediate operator action per C.4-B.3.3.A (STUCK OPEN !

RELIEF VALVE)?

A. Scram the Reactor; enter C.4-A (REACTOR SCRAM); and execute concurrently with this procedure.

B. Place Div ll Lo-Lo Set Logic switch on Control Room Panel C-253D in BYPASS (HS-S3B).

C. Place the handswitch for the affected SRV to the OPEN position and then return it to the l normal position.

D. Execute C.4-F (RAPID POWER REDUCTION) concurrently and CLOSE the MSIVs to l control reactor cooldown.

Answer:

C l Question Number: 1-C.4-B.03-010 !

Reference (s):

1. C.4-B.03.03.A K/A

Reference:

239002 Task Number: SG 14 Rating RO/SRO: 4.1/3.9 Monticello JTA:

Objective (s):

System Code: NA I/mit

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 57 of 102 Exain Question Number: 55 Point Value: 1.00 Time (Minutes):

Given:

A trip of a reactor feedpump Reactor water level decreases to 0 inches The reactor scrammed All control rods inserted Remaining feed pump restored level to +35 inches The recirc sample line isolation valves (CV-2790 & CV-2791) are closed due to:

A. a Group I isolation.

B. a Group ll isolation.

C. a Group 111 isolation.

D. a Group IV isolation. ,

l Answen C

Ouestion Number: 1-TS-034 Reference (s):

1. Tech Spec 3.7.2 K/A

Reference:

223002 Task Number: A1.01 Rating RO/SRO: 3.5/3.4 Monticello JTA:

Objective (s):

System Code: NA l/mit

1 1

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 58 of 102 l

Exam Question Number: 56 Point Value: 1.00 Eme (Minutes):

^

The plant has experienced a small LOCA and the following plant conditions exist:

. Reactor pressure 700 PSIG

- Reactor level 35 inches

. Drywell pressure 3 PSIG i

. Torus water temperature 82 degrees F Which EOPs should be entered?

A. 1200 and 1300 B. 1205 and 1100 C. 1100 and 1300 D. 1100 and 1200

)

i Answer:

D i

Question Number: 1-C.5-1000-073 Reference (s):

1. C.5-1100

2. C.5-1200 4

K/A

Reference:

295010 Task Number: SG 11 Rating RO/SRO: 4.2/4.5 Monticello JTA:

Objective (s):

System Code: NA 1/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 59 of 102 Exam Question Number: 57 Point Value: 1.00 Time (Minutes):

Given:

l

. Torus level 3 feet

. Drywell pressure 2.8 PSIG

= Reactor water level- Normal i

. 3 ADS valves open l . Drywell H2concentration 7.5%

. Drywell O2concentration 8%

. Torus pressure 1.8 PSIG Which of the following shall be implemented?

A. Start Torus spray.

B. Vent and purge primary containment.

C. Start CGCS.

D. Spray drywell.

j Answer:

B I

Question Number: 1-C.5-1000-081 Reference (s):

1. C.5-1205 Flow Chart

. K/A

Reference:

295037 Task Number: SG 12 Rating RO/SRO: /4.6 Monticello JTA:

Objective (s):

System Code: NA l/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 60 of 102 Exam Question Number: 58 Point Value: 1.00 Time (Minutes):

i Given:

o 1,000 GPM leak from recirc o No RHR pumps available o No.11 and No.12 core spray pumps running o ADS timer reads 100 sec. and is timing down Which of the following will prevent the ADS relief valvec from opening?

A. Placing the ADS relief valve hand switches in the CLOSED position.

B. Removing both core spray pumps from service.

C. Decrease drywell pressure to 1.7 PS!G.

D. Resetting reactor scram. '

Answer:

B Question Number: l-B.03.03-016 Rsference(s):

1. B.03.03-01 K/A

Reference:

209001 Task Number: K3.02 Rating RO/SRO: 3.8/3.9 Monticello JTA:

Objective (s):

System Code: NA i

1 1/mlf j l

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 61 of 102 l

, Exam Question Number: 59 Point Value: 1.00 Time (Minutes):

An event resulted in an automatic initiation of the HPCI system. Reactor water level was restored to greater than +48 inches. Drywell pressure currently reads 2.5 PSIG. Which of the following automatically restarts the HPCI system?

A. Reactor water level drops below -48 inches.

B. Reactor water level drops below +48 inches.

C. Reactor water level drops below +9 inches.

D. The reactor operator depresses the GROUP IV ISOLATION RESET pushbutton.

l Answer:

A 4

Question Number: l-B.03.02-023 Reference (s):

1. B.03.02 K/A

Reference:

206000 Task Number: K6.12 Rating RO/SRO: 4.2/4.3 Monticello JTA:

Objective (s):

System Code: NA I

I/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0

) LICENSE EXAMINATION - ANSWER KEY Page 62 of 102 Exam Question Number: 60 Eoint Value: 1.00 Ime (Minutes):

Given:

. Drywell pressure 13.4 PSIG

All Drywell cooling fans in service per C.5-3503

. Torus level +3.5 feet I a Torus spray in service Which of the following shall be implemented?

A. Blowdown the reactor.

. B. Place Drywell cooling fan switches to OFF.

C. Stop Torus spray.

l D. Vent Primary Containment.

i an3W911 B

Question Number: 1-C.5-1000-077 RSference(s):

1. EOP 1200 K/A

Reference:

295010 Task Number: AA1.01 Rating RO/SRO: /3.5 Monticello JTA:

Objective (s):

System Code: NA

/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 63 of 102 Exam Question Number: 61 Point Value: 1.00 Time (Minutes):

Given:

. Drywell temperature 145 degrees F.

. Drywell pressure 1.5 PSIG.

. Torus temperature 85 degrees F.

Torus water level +3.5 inches.

. Reactor level +20 inches.

. Reactor pressure 900 PSIG.

Which EOP should be entered:

A. C.5-1100 B. C.5-1200 C. C.5-1205 D. C.5-1300 Answer:

B Ouestion Number: 1-C.5-1000-072 R:ference(s):

1. C.5-1100, Fig F K/A

Reference:

219000 Task Number: A1.04 Rating RO/SRO: 3.2/3.2 Monticello JTA:

Objective (s):

System Code: NA l/mlf

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 64 of 102 Exam Question Number: 62 Point Vape: 1.00 Time (Minutes):

Given:

Reactor water level +35 inches and stable.

. Dryweel pressure 1.8 PSIG.

Torus Pressure 1.6 PSIG.

A loop of RHR in service spraying the drywell.

B loop of RHR in service on torus cooling.

. Torus temperature is 85 degrees F.

As the shift supervisor your next required action is:

A. Remove drywell sprays from service.

l B. Place all available torus cooling in service.

C. Align all RHR flow to the reactor vessel.

b. Align RHR for torus sprays.

Answer:

1 A Question Number: 1-C.5-1000-083 Reference (s):

1. C.S.1-1200 K/A

Reference:

230000 Task Number: A3.01 Rating RO/SRO: 3.4/3.3

~

Monticello JTA:

Objective (s):

System Code: NA l/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 65 of 102 Exam Question Number: 63 Point Value: 1.00 Time (Minutes): l 1 You are on duty in the control room when you receive annunciator 5-B-31 (LOSS OF CONTINUITY TO SQUlB VALVE). While investigating you notice that both white squib valve !

ready indicating lights are de-energized. Which of the following actions shall the operator l perform?

A. Check the computer alarm typer in the control room to identify which valve is reading low milliamps.

B. Read the values on the meter relays 11-67-A/B (behind C-05) to determine which valve indication initiated the alarm.

C. Read the values on the squib valve indicators located in the cable spreading room to determine which valve indication initiated the alarm.

D. Read the values on the indicators located at the squib valves to determine which valve circuit initiated the alarrn.

Answer:

B Question Number: 1-B.03.05-022 Reference (s):

1. B.03.05-02 K/A

Reference:

211000 Task Number: K4.04 Rating RO/SRO: 3.8/3.9 Monticello JTA:

Objective (s):

System Code: NA I/mif

1 MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 66 of 102 l Exam Question Number: 64 Point Value: 1.00 Time (Minutes): i A Reactor scram signal has been generated and ALL control rods fail to insert. The shift i supervisor gives the order to initiate SBLC. Which of the following describe the effect on the l RWCU system due to the initiation of SBLC7 A. MO-2397, MO-2399, MO-2404 and MO-2405 receive a close signal. The RWCU pumps trip from the subsequent valve closure.

B. MO-2397, MO-2398 and MO-2399 receive a close signal. The RWCU pumps trip directly from the SBLC rignal.

C. MO-2397, MO 2398 and MO-2399 receive a close signal. The RWCU pumps trip from the subsequent valve closure. I

D. MO-2397, MO-2399, MO-2404 and MO-2405 receive a close signal. The RWCU pumps trip directly from the SBLC signal.

1 Answer:

1 O

l Question Number: 1-B.03.05-023 l

Reference (s):

1. B.03.05 K/A

Reference:

211000 Task Number: A3.06 Rating RO/SRO: 4.0/4.1 Monticello JTA:

Objective (s):

System Code: NA l/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 i

LICENSE EXAMINATION - ANSWER KEY Page 67 of 102

. Exam Question Number: 65 Point Value: 1.00 Time (Minutes):

Given:

Multiple stuck control rods at position 48.

Reactor water level is being maintained between -150 and -120". l

. Reactor power <3%

Hot shutdown boron weight has been injected. ,

Which of the following actions shall be taken when restoring Reactor water level, you observe the SRMs indicating a positive period with increasing reactor power?

A. Wait until cold shutdown boron weight has been injected.

l B. Continue to inject until level covers the top of active fuel.

C. Stop all injection except boron and CRD.

D. Maintain Reactor level above -126 and reactor power <3% or enter 2002 and blowdown.

1 .

Answer:

C Question Number: 1-C.5-2000-013 Rsference(s):

1. C.5-2007 K/A

Reference:

295014 Task Number: AA2.02 Rating RO/SRO: /3.9 Monticello JTA:

Objective (s):

System Code: NA I/mlf

l MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 68 of 102 Exam Question Number: 66 Point Value: 1.00 mme (Minutes):

l The 115% TRIP SET indicating light is illuminated on the RBM 7 cabinet. This light indicates that ;

ths... 1 A. RBM output signal is above the trip reference level and a rod block trip has occurred. !

B. power biased rod block trip is set to the intermediate power level.

)

C. APRM/RBM TRIP LEVEL pushbutton on C-05 has been depressed to determine the RBM trip setpoint in effect.

D. reference APRM output signal is above the trip reference level.

1 Answer:

B Question Number: 1-B.05.01.02-042 R ference(s):

1. B.05.01.02-03 K/A

Reference:

201005 Task Number: K5.09 Rating RO/SRO: 3.5/3.5 Monticello JTA:

Objective (s):

System Code: NA I

1/mif

i MONTICELLO NUCLEAR GENERATING PLANT M81000-9601

TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 69 of 102 Exam Question Number: 67 Point Value: 1.00 Time (Minutes): '

Reactor recirc pump speeds became mismatched with reactor power at 75%. Which one of the following states the reason for maintaining the speed of the faster recire pump within 130% of the speed of the slower pump?

A. To enhance the capability of the LPCI loop select logic ability to select the broken loop.

B. Prevent jet pump cavitation.

C. Prevent stub tube vibration in the lower core area.

! D. Prevent impro aer mixing in the lower core which could result in thermal stress of the lower stub tube welc s.

4 Answer:

A '

l Question Number: 1-B.01.04-054 Reference (s):

1. B.1.4-05.01 j K/A

Reference:

202002 Task Number: A2.04 Rating RO/SRO: 3.0/3.0 Monticello JTA:

Objective (s):

System Code: NA i

I/mif

i 1

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 1 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 70 of 102 Exam Question Number: 68 Point Value: 1.0 Time (Minutes):

A LPCI initiation signal occurs due to low-low water level for 20 minutes. Which of the following is correct if Loop "B" RHR is selected by LPCI Loop select logic? (Assume Reactor pressure 900 ESIG).

A. The RHR injection (inboard and outboard) valves on the non-selected loop will close and remain closed. The outboard injection valve on the selected 1003 will remain open, the inboard injection valve will open when Reactor pressure is less 11an 460 PSIG.

B. The RHR injection (inboard and outboard) valves on both loops will remain open until Reactor pressure decreases to 460 PSIG. The non-selected loop outboard injection valve I will then close and the selected loop outboard injection valves will open. I C. The RHR injection (inboard and outboard) valves all close until Reactor pressure is less than 460 PSIG, then the selected loop injection valves open.

1 D. The RHR injection (inboard and outboard) valves on the selected loop open at 460 PSIG and remain open for 5 minutes and then auto close. The non-selected loop (inboard and outboard) injection valves close and remain closed due to the initiation signal.

Answer:

A Question Number: 1-B.03.04-004 Reference (s):

1. B.03.04-02 K/A

Reference:

295031 Task Number: EA1.01 Rating RO/SRO: 4.4/4.4 Monticello JTA: 2050080101 Objective (s): M-8107L-023, EO-7 System Code: RHR 1/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 71 of 102 Exam Question Number: 69 Point Value: 1.00 Time (Minutes):

The main function of the Rod Worth Minimizer is:

A. To provide a continuous update of current rod position to the operator during rod manipulation.

B. Act as an operational aid to prevent violation of the fuel integrity safety criteria during 4 withdrawal of a single control rod.

C. To provide a local relative power signal for operator evaluation during control rod movement.

D. To limit rod motion such that high worth rods are not created, thereby limiting the maximum reactivity increase due to a control rod drop accident.

Answer:

D Question Number: 1-B.05.02-036 Reference (s):

1. B.05.02-01 K/A

Reference:

295014 Task Number: AK1.05 Rating RO/SRO: /4.2 Monticello JTA:

Objective (s):

System Code: NA I/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 l LICENSE EXAMINATION - ANSWER KEY Page 72 of 102 Exam Question Number: 70 Point Value: 1.00 Ime (Minutes):

1 During the fire system operability test, flow rate for the diesel driven fire pump was measured to be 1250 GPM. Which of the following actions is correct?

A. E'itr a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months LCO.

B. Enter a 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months LCO.

C. Enter a 7 day LCO.

D. Enter a 14 day LCO.

Answer:

C 4

Question Number: 1-TS-036 Reference (s):

1. Tech Spec 3.13.B.1.A K/A

Reference:

286000 Task Number: A4.06 Rating RO/SRO: /3.4 Monticello JTA:

Objective (s):

System Code: NA i

1/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 73 of 102 Exam Question Number: 71 Point Value: 1.00 Time (Minutes): l While testing No.14 ESW pump, it trips and is declared inoperable. As the Shift Supervisor you id:ntify that the loss of No.14 ESW pump requires declaring...

A. No.11 EDG inoperable, j B. V-EAC-14A ("A" EFT) inoperable.

C. No.12 EDG inoperable.

D. "B" RHR pumps inoperable if No.14 ESW cannot be restored within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

Answer:

D Question Number: 1-B.03.04-030 Reference (s):

1. B.03.04-05 l K/A

Reference:

205000 Task Number: K6.05 Rating RO/SRO: /3.3 Monticello JTA:

Objective (s):

System Code: NA I/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 74 of 102 Exam Question Number: 72 Point Value: 1.00 Time (Minutes):

.Following a reactor scram all scram signals are clear except the scram discharge volume high level. Subsequent operator actions in C.4-A (REACTOR SCRAM) direct the operator to reset the scram as soon as possible. The reason is to reduce...

A. DP across the CRD piston and to reduce thermal stress on the CRD stub tubes.

B. CRD flow to the vessel and to reduce thermal stress on the feedwater inlet nozzles.

C. DP across the CRD flow control valve and to ensure cooling water header is not i overpressurized.

D. cold water injection into the RPV and to minimize stratification in the lower head. 1 Answer: l l

D Question Number: 1-C.4-A-019 R:ference(s):

1. C.4-A K/A

Reference:

295006 Task Number: AA1.06 Rating RO/SRO: 3.5/3.6 Monticello JTA:

Objective (s):

System Code: NA l/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 75 of 102 Exam Question Number: 73 Point Value: 1.00 Time (Minctes):

While on duty in the control room you receive annunciator 3-B-25 (UNDERVOLTAGE HPCI DC MCC). Which of the following caused this event to occur?

A. 250 VDC Division I had a battery cell short to ground.

B. 250 VDC Division ll distribution panel D-100 circuit breaker 11 tripped on high voltage.

C. 125 VDC Division l Charger output having decreased to 100 VDC.

D. 125 VDC Division ll inverter failure.

Answer:

B Ouestion Number: 1-B.09.09-007 Reference (s):

1. B.09.09-01 K/A

Reference:

263000 i

Task Number: K2.01 Rating RO/SRO: 3.1/3.4 Monticello JTA:

Objective (s):

System Code: NA I/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 l LICENSE EXAMINATION - ANSWER KEY Page 76 of 102 Exam Question Number: 74 Point Value: 1.00 Time (Minutes):

Which of the following concerning core orificing is correct?

A. The larger diameter orifices are placed in the outer regions of the core.

B. The orifices are located inside the nose cone of the fuel bundle.

C. Core orificing is used to ensure the higher power region of the core is not starved of coolant due to the increased DP across the fuel bundle.

D. Core orificing is used to maintain an equal flow rate across the core, ensuring a uniform flux distribution is achieved in the high power region of the core.

Answer: '

C l

Question Number: 1-B.01.01-033 R3ference(s):

1. B.01.01 -01 K/A

Reference:

290002 ,

l Task Number: K4.03 Rating RO/SRO: /3.3 Monticello JTA:

Objective (s):

System Code: NA I

i I/mlf

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 :

4 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 77 of 102 Exam Question Number: 75 Point Value: 1.00 Time (Minutes):

While on duty in the control room you receive annunciator 8-B-31 (NO.101480V LD CTR MCC FEEDER TRIP). Investigation indicates that the supply breaker to MCC-111 has tripped. 30 minutes after the loss of MCC-111 all procedural follow-up is completed. MCC-111 has not been returned to service. The status of RPS is:

A. 1/2 scram on B RPS.

B. Both RPS busses reset with B RPS being supplied by alternate source C. 1/2 scram on A RPS.

D. Both RPS busses reset with A RPS being supplied by alternate source.

l Answer:

C 1 I

Question Number: 1-B.09.12-008 Reference (s):

1. B.09.12-02 K/A

Reference:

212000 Task Number: K2.01 Rating RO/SRO: 3.2/3.3 Monticello JTA:

Objective (s):

System Code: NA I/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 78 of 102 Exam Question Number: 76 Point Value: 1.00 Time (Minutes):

Which of the following is correct concerning 4160 Bus 157

^

A. 152-308 (bus tie breaker) must be open to allow the 1 AR to close in on the bus.

B. 152-408 (bus tie breaker) must be open to allow No.11 EDG to close in on the bus.

C. Placing 15 bus setup / lockout key switch to lockout will prevent 152-308 from opening on an auto bus transfer.

D. No.11 EDG will initiate a make-before-break transfer if 152-308 is closed. l Answer:

A Question Number: 1-B.09.06-039 Reference (s):

1. B.09.06-01 K/A

Reference:

262001 Task Number: K4.03 Rating RO/SRO: /3.4 Monticello JTA:

Objective (s):

System Code: NA I/mif

)

MONTICELLO NUCLEAR GENERATING PLANT l M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 795102 Exam Question Number: 77 Point Value: 1.00 Time (Minutes):

During your shift the plant experiences a total loss of instrument air. Reactor feedwater flow will...

A. decrease to 0 GPM.

B. remain the same.

C. Increase.

D. decrease to 3300 GPM.

Answer:

C Question Number: 1-B.05.07-013 R ference(s):

1. B.05.07-01

2. C.4-B.08.04.01 K/A

Reference:

295019 Task Number: AK2.03 Rating RO/SRO: /3.3 Monticello JTA:

Objective (s):

System Code: NA I/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 80 of 102 Exam Question Number: 78 Point Value: 1.00 Time (Minutes):

l Which of the following explains why the logic for the Reactor Protection System is normally l j cnergized? l A. A two-out-of-four logic can only be accomplished with a system logic that is normally

, energized.

B. This results in a fail safe condition if power to the reactor protection system logic were to be completely lost.

C. Power from the RPS logic must always be available in order to supply the IRM and SRM neutron detectors.

D. In the event that all power to the RPS logic was lost, the reactor could still be manually scrammed.

l Answer: :

1 8

4 Question Number: 1-B.05.06-011 Reference (s):

1. B.05.06-01 K/A

Reference:

212000 Task Number: K3.05 Rating RO/SRO: 3.7/3.8 Monticello JTA: 2120050101 Objective (s): M-8107L-072 System Code: PPS 1/mif

i MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 j

LICENSE EXAMINATION - ANSWER KEY Page 81 of 102 Exam Question Number: 79 Point Value: 1.00 Time (Minutes):

Given:

o Reactor water level-55 inches o Drywell pressure 7.5 PSIG o Station power from 1 AR o RCIC steam line pressure is 100 PSIG 1

o RCIC Room temperature is 160 degrees F o RCIC steam flow 40,000 LB/Hr Which of the following is correct? RCIC will...

A. continue injecting to the reactor vessel.

B. auto isolate due to a valid Group 5 signal from low steam line pressure.

C. auto isolate due to a valid Group 5 signal from high area temperature.

D. auto isolate in 5 seconds from steam line flow if signal is still present.

1 Answer:

A Question Number: 1-B.02.03-017 !

Reference (s):

1. B.02.03-01 1

. K/A

Reference:

217000 l 1

Task Number: A2.02 Rating RO/SRO: 3.8/3.7 Monticello JTA: j Objective (s)- !

l System Code: NA l l

I/mif

1

, MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 82 of 102 Exam Question Number: 80 Point Value: 1.00 Time (Minutes):

V-EF-18A stack dilution fan has been declared inoperable. V-EF-18B stack dilution fan is in service. What is the status of SBGT?

A. "A" and "B" SBGT are inoperable.

l B. "A" SBGT train is inoperable, i C. As long as V-EF-188 is operable, there are no operational concerns.

l D. "B" SBGT train is inoperable.

1 Answer:

B i

I l

l Question Number: 1-B.04.02-022 l Rsference(s):

1. B.04.02-05

2. Tech Spec 3.7 K/A

Reference:

261000 Task Number: SG 11 Rating RO/SRO: 3.3/4.2 Monticello JTA:

Objective (s):

System Code: NA I/mlf

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 83 of 102 Exam Question Number: 81 Point Value: 1.00 Time (Minutes):

A small leak in containment has developed causing drywell pressure to increase to 2.5 PSIG.

The feedwater system has held level constant at +35". Assuming no operator action since the start of the leak, what is the status of HPCl?

A. In service supplying water to the reactor vessel.

B. In service with outboard discharge valve closed and minimum flow valve open.

C. In standby.

D. In service with flow on test return to CSTs.

Answer:

A Question Number: 1-B.03.02-021 Reference (s):

1. B.03.02-01 K/A

Reference:

295024 Task Number: EK2.01 Rating RO/SRO: 3.9/4.0 Monticello JTA:

Objective (s):

System Code: NA I/mif

A MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 84 of 102 i

Exam Question Number: 82 Point Value: 1.00 Eme (Minutes):

1 Which of the following describes the flow path of the Standby Gas Treatment System (SBGT) when it initiates on high drywell pressure? Draws air from the...

A. Drywell and exhausts to the off-gas stack.

B. Reactor Building and exhausts to the off-gas stack.

C. Drywell and exhausts to the Reactor Building Plenum.

D. Reactor Building and exhausts to the Reactor Building Plenum.

i i

Answer:

B l Question Number: 1-B.04.02-023 Rsference(s):

1. B.04.02 K/A

Reference:

288000 i

Task Number: K1.03 Rating RO/SRO: 3.7/3.7 Monticello JTA:

Objective (s):

System Code: NA 1/mif

/

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 ,

TITLE: 1996 NRC SENIOR REACTOR OPERATOR - Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 85 of 102 Exam Question Number: 83 Point Value: 1.00 Time (Minutes): I Given:

o Reactor ressure 650 PSIG I o Steam line break in drywell, i o Drywell pressure 2.3 PSIG and slowly increasing. 1 o Reactor water level normal.

Assuming normal plant configuration and no operator actions, which of the following is correct concerning the core spray system operation?

! A. Core spray pumps running. Outboard valves closed and inboard valves open.

J B. Core spray pumps not running. Auto start at low reactor pressure.

C. Core spray pumps not running. Auto start at low low level.

D. Core spray pumps running. Outboard valves open and inboard valves closed.

Answer:

D A

Question Number: 1-B.03.01-072

Rsference(s):

1. B.03.01-01

) K/A

Reference:

209001 Task Number: A1.08 Rating RO/SRO: 3.3/3.3 Monticello JTA:

Objective (s):

System Code: NA i

1/mif

1

l MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 86 of 102 Exam Question Number: 84 Point Value: 1.00 Tme (Minutes):

While operating at 100% power a Group I auto isolation occurs and the reactor scrams. Low low set actuates to control pressure. How many safety / relief valves will be open when reactor pressure reaches 975 PSIG?

A. 3 B. 2 C. 1 D. O Answer; C

Question Number: 1-B.03.03-017 RIference(s):

1. B.03.03-01 K/A

Reference:

295025 Task Number: EK3.09 Rating RO/SRO: 3.7/3.7 Monticello JTA:

Objective (s):

System Code: NA I/mif

l MONTICELLO NUCLEAR GENERATING PLANT l M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 87 of 102 Exam Question Number: 85 Point Value: 1.00 Time (Minutes):

The plant is o perating at 100% power. The shift chemist informs you that his most recent reactor coolant sample indicates reactor coolant contains 1.0 ppm of chloride ions. As the Shift Supervisor your action is to...

A. Initiate an orderly shutdown and have the reactor in a cold shutdown condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

B. Increase RWCU flow to 85 GPM for each filter to facilitate removal of chlorides.

2 C. place the plant in hot shutdown within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

D. order the chemist to sample reactor coolant nourly until chlorides are reduced.

Answer:

A Question Number: 1-TS-040 ,

Reference (s):

1. Tech Spec 3.6 K/A

Reference:

294001 Task Number: A1.14 Rating RO/SRO: /3.4 Monticello JTA:

Objective (s):

System Code: NA I/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 88 of 102 Exam Question Number: 86 Point Value: 1.00 Time (Minutes):

The reactor is at 50% power whea you lose all drywell cooling fans. Drywell pressure and t mperature will:

A. increase causing a reactor scram at 150 degrees F drywell temperature.

B. Increase causing a RCIC initiation at 2 PSIG drywell pressure.

C. Increase causing a reactor scram at 2 PSIG drywell pressure.

D. will remain constant due to the continuous cooling provided by the N2 atmosphere.

Answer:

C l

Question Number: 1-B.04.01-019 Rsference(s):

1. B.04.01 -01 K/A

Reference:

295012 Task Number: AA2.02 Rating RO/SRO: 3.9/4.1 Monticello JTA:

Objective (s):

System Code: NA I/mif

MONTICELLO NUCLEAR GENERATits0 PLANT M81000-9601 4

TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 89 of 102 Exam Question Number: 87 Point Value: 1.00 Time (Minutes):

Given:

Loss of 125 VDC Bus A 3-A-25 (AC INTERLOCK ALARM) ON Reactor water level -30" and decreasing

Reactor pressure 900 PSIG Assuming reactor water level continues to decrease to -60 inches, which of the following is correct?

A. ADS valves E, G, H will open.

B. ADS valves A, C, D will open.

l C. ADS will not auto initiate due to loss of 125 VAC Bus A.

D. ADS valves E, F, G will open.

Answer:

B Ouestion Number: 1-B.03.03-018 Reference (s):

1. B.03.03-02 K/A

Reference:

218000 Task Number: K5.01 Rating RO/SRO: 3.8/3.'8 Monticello JTA:

Objective (s):

System Code: NA l/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 90 of 102 Exam Question Number: 88 Point Value: 1.00 Time (Minutes): l While performing an annunciator check at the start of a shift, the operator identifies that only the ennunciators for panel C-06, C-07 and C-08 failed to respond. Which of the following would be a possible reason for the faliure?

A. Inverter failure in the 250VDC system.

B. 24 VDC charger output for 24VDC reads 20VDC.

C. Y-20 fuse disconnect failed in Y-20.

D. A 125 VDC cell in the 125 VDC battery bank shorted to ground.

1 Answer:

D Question Number: 1-C.4-B.09-009 R ference(s):

1. C.4-B.9.10.A K/A

Reference:

295004 Task Number: AA2.02 Rating RO/SRO: 3.5/3.9 Monticello JTA:

Objective (s):

System Code: NA I/mlf

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 91 of 102 Exam Question Number: 89 Point Value: 1.00 Time (Minutes):

A reactor startup and heatup is in progress. Reactor pressure is 900 PSIG. Which of the following actions must be taken if ALL CRD flow is lost and two (2) CRD accumulators low pressure alarms come in?

A. Hold at present power level until you recharge the accumulators then proceed with startup.

B. Restore CRD flow within two hours and if unsuccessful, perform a reactor scram.

C. Manually scram the reactor.

D. Manually scram the reactor when any CRD drive high temperature alarm is received.

Answer:

C Question Number: 1-C.4-B.01-019 Reference (s): ,

1. C.4-B.01.03.A K/A

Reference:

295022 Task Number: AA1.02 Rating RO/SRO: 3.6/3.6 Monticello JTA:

Objective (s):

System Code: NA l/rnif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 92 of 102 l Exam' Question Number: 90 Point Value: 1.00 Time (Minutes):

A truck roll over has left the Monticello site in a chlorine environment. Which of the following concerning Control Room ventilation is correct?

A. The Emergency Filtration Training (EFT) system will auto initiate in the chemical mode at 2 PPB chlonne.

B. Manually place the Emergency Filtration Train (EFT) system in the Recirc Mode.

1 C. Manually place the Emergency Filtration Train (EFT) system in the High Rad Emergency mode.

D. The Emergency Filtration Train (EFT) system will auto initiate in the High Rad Mode at 2 PPB chlonne.

Answer:

8 Question Number: 1 B.08.13-015 Reference (s):

1. B.08.13-01 K/A

Reference:

294001 Task Number: K1.11 Rating RO/SRO: /3.3 Monticello JTA:

Objective (s):

System Code: NA l/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 93 of 102 3 Exam Question Number: 91 Point Value: 1.00 Time (Minutes):

Which of the following is a function of the fuel pool skimmer surge tanks?

A. To prevent uncovering of stored fuelin the event of a fuel pool rupture.

B. Provide a means to monitor system make-up requirements.

C. Provides for cooling of fuel pool water.

D. Provides natural circulation in the event both fuel pool cooling pumps are unavailable.

Answer:

B Ouestion Number: 1 B.02.01-013 R@ference(s):

1. B.02.01-01 K/A

Reference:

233000 Task Number: SG 7 Rating RO/SRO: 3.2/3.3 Monticello JTA:

Objective (s):

System Code: NA 1/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 94 of 102 Exam Question Number: 92 Point Value: 1.00 Time (Minutes):

While startincI RCIC the operator observes turbine RPM increasin to 5700 then dropping to zero.

MO-2080 ind cates closed and the amber mechanical overspeed ht is ON. Which of the following operator actions will restore the RCIC system to operatio ?

A. Take the handswitch for MO-2080 located on C-04 to the CLOSE position and then to the OPEN position.

B. You must send an operator to reset the trip throttle valve locally.

C. Use the pushbuttons on C-296 located in the RCIO room to CLOSE and then re-open the valve.

D. Take the handswitch for MO-2080 located on C-04 to the OPEN position.

J i

Answer:

B Ouestion Number: 1-A.4-003 Rsference(s):

1. B.2.3-02 K/A

Reference:

217000 Task Number: A4.02 Rating RO/SRO: 3.9/3.9 Monticello JTA:

Objective (s):

System Code: NA i

I/mlf

1 MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 )

LICENSE EXAMINATION - ANSWER KEY Page 95 of 102 Exam Question Number: 93 Point Value: 1.00 Time (Minutes):

The radiation protection department has determined entrance into an area of the plant cou!d result in personnel receiving 1200 mr/hr,30 centimeters from the radiation source. Which one of tha following is the required posting for the area?

A. High Radiation Area B. Locked High Radiation Area C. Strange Area D. Locked High High Radiation Area l

Answer:

B Question Number: 1-4 awl-08-009 Reference (s):

1. 4 AWi-08.04.01 K/A

Reference:

294001 Task Number: K1.03 Rating RO/SRO: 3.3/3.8 Monticello JTA:

Objective (s):

System Code:

NA I/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 96 of 102 Exam Question Number: 94 Point Value: 1.00 Time (Minutes):

Initial Conditions:

Reactor power 100%

. HPCI testing in progress

Torus temperature 92*F

All available torus cooling in service.

An inadvertent Group I atuo isolation occurs causing a reactor scram. Five (5) control rods r: main at position 48. Which of the following EOPs have an entry condition present?

A. 1100,1300 B. 1200,1300 C. 1200,1400 D. 1100,1200

)

i i

I Answer: !

D l

Question Number: l-C.5-1000-068 R::ference(s):

1. C.5-1100,1200 K/A

Reference:

295037 Task Number: SG 11 Rating RO/SRO: 4.4/4.7 Monticello JTA:

Objective (s):

System Code: NA l/mit

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 97 of 102 l Exam Question Number: 95 Point Value: 1.00 Time (Minutes):

Given: '

=

Off-site release rate above Alert level

- Reactor Building DP .5 inches l

- Exhaust plenum radiation 10 mR/hr Which one of the following EOPs shall be entered?

A. C.5-1400 B. C.5-1300 C. C.5-1200 D. C.5-1100 Answer:

A Question Number: 1-C.5-1000-082 Reference (s):

1. C.5-1400 K/A

Reference:

295038 Task Number: EK1.02 Rating RO/SRO: 4.2/4.4 Monticello JTA:

Objective (s):

System Code: NA I/mif

l MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 ;

LICENSE EXAMINATION- ANSWER KEY Page 98 of 102 l Exam Question Number: 96 Point Value: 1.00 Time (Minutes): 1 1

The procedure for station blackout gives a reactor water level band of -126" to +48". This band...

A. Maximizes the heat removing capacity of the water injected into the vessel by HPCI or li RCIC.

B. Minimizes the chance of a HPCI or RCIC turbine trip from repeated starting and stopping.

C. Maximizes the battery capacity for HPCI or RCIC operation.

D. Reduces the heating loads in HPCI and RCIC rooms due to reduced HPCI and RCIC '

operating times.

l Answer: j l

Question Number: l-C.4-B.09-012 Reference (s):

1. C.4-B.09.02.A K/A

Reference:

295003 Task Number: AA2.03 Rating RO/SRO: 3.5/3.5 Monticello JTA:

Objective (s):

System Code: NA 1/mif

MONTICELLO NUCLEAR GENERATING PLANT M8100b-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR '

Revision 0 i LICENSE EXAMINATION - ANSWER KEY Page 99 of 102 l Exam Question Number: 97 Point Value: 1.00 Ime (Minutes):

4 During your shift, Division I of the 125 VDC system is declared inoperable. Per Tech Specs you must:

A. Initiate an orderly shutdown of the reactor and be less than than 212'F within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

B. Initiate an orderly shutdown of the reactor and be in the shutdown within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

i C. Restore the inoperable division of 125 VDC within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or be less than 212*F within 36

hours.

D. Immediately verify operability of Division ll 125 VDC. If Division 11 is operable, reactor operation may continue for 7 days.

Answer:

A Question Number: 1-TS-039 Reference (s):

1. Tech Spec 3.9 K/A

Reference:

295004 Task Number: SG3 Rating RO/SRO: /4.1 Monticello JTA:

Objective (s):

l System Code: NA I/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 100 of 102 ,

Exam Question Number: 98 Point Value: 1.00 Time (Minutes): ,

1 You are on duty in the Control Room when annunciators are received that indicate a loss of Y-30.

Which of the following is/are the required immediate operator action (s)?

A. Determine status of fused disconnect Y-84.

B. Take manual control of CV-3-19A or CV-3-198 to maintain proper CRD flow.

C. Maintain both SJAE steam pressures at 125 PSIG by throttling the respective pressure control outlet valve (MS-23-1 and MS-23-2).

D. Execute C.4-B.05.07.A (LOSS OF REACTOR WATER LEVEL CONTROL) concurrently.

Answer: i D

Question Number: 1-C.4-B.09-011 Reference (s):

1. C.4-B.09.13.E K/A

Reference:

262002 Task Number: SG 14 Rating RO/SRO: 3.3/3.4 Monticello JTA:

Objective (s):

System Code: NA l/mif

MONTICELLO NUCLEAR GENERATING PLANT M81000 9601

TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 101 of 102 Exam Question Number: 99 Point Value: 100 Time (Minutes):

Using the attached portion of a P&lD, determine the T(PE and POSITION of the circled valve (SW-112-2).

A. Normally OPEN globe valve.

B. Normally CLOSED gate valve.

C. Normally OPEN gate valve.

D. Normally CLOSED globe valve. 1 1

J Answer:

i C - _

] Question Number: 1-P&lD-001 Rnference(s):

1. P&lD 294001 K/A

Reference:

i Task Number: A1.07 Rating RO/SRO: /3.7 Monticello JTA: '

Objective (s):

System Code: NA l

I/mlf

l MONTICELLO NUCLEAR GENERATING PLANT M81000-9601 TITLE: 1996 NRC SENIOR REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 102 of.102 Exam Question Number: 100 Point Value: 1.00 Ime (Minutes):

While on duty in the Control Room, annunciator C05-A-49 (RADWASTE TROUBLE) alarms.

Further investigation indicates annunciator C84-A-9 (REACTOR BLDG FLOOR DRAIN SUMP HI LEVEL) in radwaste is in alarm. Your next action shall be to...

A. isolate all discharges into area except systems needed for reactor shutdown, core cooling, fire fighting and primary containment venting.

B. attempt to maintain water level below maximum safe level.

C. wait until two or more areas are above maximum safe values.

D. attempt to maintain water level below maximum normal level.

Answer:

D Question Number: 1-C.5-1000-080 Reference (s):

1. C.5-1300 K/A

Reference:

295036 Task Number: SG 12 Rating RO/SRO: /4.1 Monticello JTA:

Objective (s):

System Code: NA 1/mif

ML20134H382

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