ML17142A427

2016 Monticello Nuclear Generating Plant Initial Licensed Operator Examination Proposed RO Written Examination

ML17142A427
Person / Time
Site:	Monticello
Issue date:	05/18/2017
From:	Reeser D W NRC/RGN-III/DRS/OLB
To:	NRC/RGN-III/DRS/OLB
Shared Package
ML15274A423	List: ML17142A415 ML17142A423 ML17142A425 ML17142A427 ML17142A429 ML17142A430 ML17156A043 ML17156A045
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Download: ML17142A427 (225)

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Monticello NRC Written Exam Page: 1 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM The reactor was operating at rated conditions when the 11 Reactor Recirc pump tripped. Three minutes later, indicated Total Core Flow on Panel C

-04 recorder is 38 Mlbm/hr.

Actual core flow is assumed to be-A. higher than indicated due to reverse flow in the idle loop.

B. lower than indicated due to reverse flow in the idle loop.

C. lower than indicated due to lower reactor power resulting in a lower core D. the same as indicated due to a subtraction circuit in the Total Core Flow summing logic.

Question 1 Points: 1.0

Monticello NRC Written Exam Page: 2 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

1 Answer: B DISTRACTOR ANALYSIS A. Incorrect, this is the opposite effect B. Correct, Total core flow is a sum of recirc loop flows. Since reverse flow may occur in the idle loop during high power/recirc pump trip conditions, this reverse flow is added to the forward flow in the running loop and makes indicated flow appear higher than actual core flow. C. Incorrect, Core flow is equally affected by core P. D. Incorrect, this logic is not installed at MNGP Tier: 1 Group: 1 K/A: 295001 Partial or Complete Loss of Forced Core Flow Circulation AA2.03 Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION: Actual core flow

Importance Rating:

3.3 10 CFR Part 55:

55.41.10 10 CFR 55.43.b

N/A K/A Match:

KA is matched by having the applicant determine the effect of a recirc pump trip on actual core flow indication SRO Justification:

N/A Technical

References:

Ops Man C.4

-B.05.01.02.A Proposed references None to be provided:

Learning Objective:

MT-ILT-AOP-003L ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 3 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

1 Cognitive Level:

Higher _ Lower X Question Source:

New _ Modified Bank

_ Bank X Question History:

MNGP 2015 ILT Audit exam Comments:

Monticello NRC Written Exam Page: 4 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM The plant is at full power when a "Station Blackout" occurs; loss of Buses 11 through 16 are indicated. 13 Diesel Generator is available but only supplying power to LC

-107 and LC

-108. Entry conditions for EOP C.5

-1200, Primary Containment Control, are present and the CRS directs you to perform each of the following EOP actions.

Which one of the following actions can be accomplished AND the system perform its intended function as directed by the CRS? (Assume manual operation of MOTOR OPERATED valves is performed when required.)

A. Perform C.5

-3402, Draining Torus Water to Radwaste, to lower Torus water level.

B. Perform C.5

-3501, H 2/O 2 Analyzer Operation, to establish H 2 and O 2 sampling of the Drywell. C. Perform C.5

-3502, Containment Spray, to initiate Torus and Drywell sprays to reduce Torus and Drywell pressure.

D. Perform C.5

-3503, Defeat Drywell Cooler Trips, to reduce Drywell air temperature.

Question 2 Points: 1.0

Monticello NRC Written Exam Page: 5 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

2 Proposed Answer: C DISTRACTOR ANALYSIS A. Incorrect: a prerequisite to perform C.5

-3402, Draining Torus Water to Radwaste, is having RHR available for service; however, with a SBO, and only the non

-essential 13 Diesel Generator available and only powering to LC

-107 and LC

-108, RHR is NOT available. B. Incorrect: H2/O2 Analyzers are NOT available as they are powered from MCC

-133A and MCC-143A (LC-103 and LC

-104) via Power Panels P

-73A and P-73B. C. Correct: per EOP C.5

-3502, IF a RHR pump is not available, THEN several options (PARTs) to spray containment are available, but, given the conditions, PART H of C.5

-3502, USE FIRE WATER SYSTEM FOR CONTAINMENT SPRAY is the only viable option. All MOVs are in the Reactor Building and are accessible for manual operation.

D. Incorrect: DW Cooling Fans are NOT available as they are powered from MC

-133A and MCC-143A (LC-103 and LC

-104)

Tier: 1 Group: 1 K/A: (295003 Partial or Complete Loss of AC / 6) Generic 2.4.6 Knowledge of EOP mitigation strategies. (CFR: 41.10 / 43.5 / 45.13)

Importance Rating:

3.7 10 CFR Part 55:

41.10 10 CFR 55.43.b

N/A K/A Match:

K/A is matched by testing the applicants' knowledge of the EOP mitigating strategies available when the plant experiences a loss of AC SRO Justification:

N/A Technical

References:

Ops Man C.4

-B.09.02.A, EOP C.5-1200 and -3502, M-8107L-023 (RHR System) Rev. 20, M

-8107L-106 (E-Manual) Rev. 6, M

-8107L-040 (480 Volt System) Rev. 14, M

-8107L-089 (No. 13 Diesel Generator) Rev. 8 ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 6 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

2 Proposed references to be provided:

None Learning Objective:

5.k of M-8107L-023 (RHR System) Rev. 20 Cognitive Level:

Higher X Lower _ Question Source:

New _ Modified Bank

_ Bank X Question History:

Question 1952 from the Exam BANK Comments:

Monticello NRC Written Exam Page: 7 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM On a loss of 125 VDC Bus A, which one of the following will occur?

A. Main generator lockout relay trips are non

-functional B. Turbine controls vacuum trip is non

-functional C. Recirculation MG Set No. 12 protective trip circuits are non

-functi onal D. HPCI remote turbine trip function is non

-functional Question 3 Points: 1.0

Monticello NRC Written Exam Page: 8 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

3 Answer: A DISTRACTOR ANALYSIS A. Correct. B. Incorrect, Turbine controls vacuum trip is non

-functional on a loss of 125 VDC Bus B C. Incorrect, Recirculation MG Set No. 12 protective trip circuits are non

-functional on a loss of 125 VDC Bus B D. HPCI remote turbine trip function is non

-functional on a loss of 125 VDC Bus B Tier: 1 Group: 1 K/A: 295004 Partial or Total Loss of DC Pwr / 6

. AK1.05 Knowledge of the operational implications of the following concepts as they apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER :

Loss of breaker protection

Importance Rating:

3.3 10 CFR Part 55:

55.41.8 to 41.10 10 CFR 55.43.b

N/A K/A Match:

KA is matched by having the applicant determine that the main generator lockout relay trips are non

-functional. The lockout relay trips are part of the breaker protection relaying for the 8N7 and 8N8 breakers that provide connection for the main transformer to the Xcel 345kV system.

SRO Justification:

N/A Technical

References:

Abnormal Procedures: LOSS OF A 125 V DC BUS Ops Man C.4

-B.09.10.A Revision 14.

M-81 07L-036 (345 kV, 230 kV & 115 kV Substation) Rev. 20 M-8107L-039 (4.16 kV And 13.8 kV Station Auxiliary Systems) Rev. 21 Proposed references to be provided:

None ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 9 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

3 Learning Objective:

M-81 07L-036 (345 kV, 230 kV & 115 kV Substation) Rev. 20

5. Describe the functional and component relationships between the 345 kV, 230 kV, and 115 kV Substation and the following:

a. 125 Vdc Distribution System Cognitive Level:

Higher _ Lower X Question Source:

New X Modified Bank

_ Bank _ Question History:

New Comments:

Monticello NRC Written Exam Page: 10 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM A plant shutdown is in progress.

Reactor power is 25%

5-B-37 (TURBINE PRESS GEN REJECTION BYPASS) is in alarm T he channel 'A' Pressure Bypass Load Reject & Stop Valve relay is energized.

The channel 'B', 'C', and 'D' Pressure Bypass Load Reject &

Stop Valve relays are de-energized Given the above conditions, if the Main Turbine is tripped, what would be the effect on RPS?

A. No RPS actuation B. Half Scram on RPS Channel A C. Half Scram on RPS Channel B D. Full Scram Question 4 Points: 1.0

Monticello NRC Written Exam Page: 11 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

4 Proposed Answer: D DISTRACTOR ANALYSIS A, B, and C are incorrect but plausible interpretations of the effects on RPS.

D is correct

Applicant should know what the current status of the Pressure Bypass Load Reject & Stop Valve relays are indicative of

- only one bypass relay is currently energized (5A

-K9A on Panel C-15). In accordance with B.05.06

-02, to provide a bypass for the stop valve and control valve closures while at low

-power, four non

-indicating pressure switches are used to monitor the first stage turbine pressure and will provide a bypass for the scram trips when first stage pressure is below 30% of its rated full power pressure.

Correspondingly, according to ARP 5

-B-37 and Form 2204, alarm 5

-B-37 is designed to alarm below 25% reactor power AND the alarm is actuated if ANY turbine first stage pressure switch reaches that pressure equivalent. In this case, since 3 relays are still de

-energized (RPS Channels A2, B1, and B2), the RPS trip from the turbine trip would NOT be bypassed and a scram would result.

Tier: 1 Group: 1 K/A: (295005 Main Turbine Generator Trip / 3) AK2.01 Knowledge of the interrelations between MAIN TURBINE GENERATOR TRIP and the following: (CFR: 41.7 / 45.8) RPS Importance Rating:

3.8 10 CFR Part 55:

41.7 10 CFR 55.43.b:

N/A K/A Match:

K/A is matched by testing the applicants' knowledge of the association between the main turbine generator trip and RPS SRO Justification:

N/A ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 12 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

4 Technical

References:

Ops Man B.05.06

-02 and -06, ARP 5-B-37, Form 2204, NX

-7834-67-9(10), M-8107L-072 (Reactor Protection System) Rev. 16, M

-8107L-013 (Main Turbine) Rev. 16 Proposed references to be provided:

None Learning Objective:

4.c of M-8107L-072 (Reactor Protection System) Rev. 16 Cognitive Level:

Higher _ Lower X Question Source:

New _ Modified Bank

_ Bank X Question History:

Question 1245 from the MNGP Exam BANK Comments: Bank question provides reference; editorial changes were made so that reference is not needed.

Monticello NRC Written Exam Page: 13 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Complete the following statement describing the immediate reactor level response to a manual scram from rated conditions AND the reason?

Reactor level will...

A. lower due to the Recirc pump runback.

B. rise due to delay in Bypass Valves opening.

C. lower due to collapsing voids in the core region.

D. rise due to rapid closure of the Turbine Control Valves.

Question 5 Points: 1.0

Monticello NRC Written Exam Page: 14 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Answer: C DISTRACTOR ANALYSIS A. Incorrect, Recirc pumps should runback to 30% but this tends to raise reactor level.

B. Incorrect, Bypass valves opening will raise water level but since reactor pressure also lowers on a scram these valves would not be expected to open immediately.

C. Correct D. The turbine control valves will close but this would cause level to lower.

Tier: 1 Group: 1 K/A: 295006 SCRAM / 1 AK3.01 Knowledge of the reasons for the following responses as they apply to SCRAM : Reactor water level response...

Importance Rating:

3.8 10 CFR Part 55:

55.41.5 10 CFR 55.43.b

N/A K/A Match: On a manual scram from rated conditions, the sudden decrease in thermal power causes the voids in the core to collapse. This causes the indicated level to lower.

SRO Justification:

N/A Technical

References:

C.4-A Bases Proposed references None to be provided:

Learning Objective:

MT-ILT-AOP-001L ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 15 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

5 Cognitive Level:

Higher _ Lower X Question Source:

New _ Modified Bank

_ Bank X Question History:

NRC 2010 exam MNGP Comments:

Monticello NRC Written Exam Page: 16 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM The plant was operating at rated conditions when an event occurred that required Control Room evacuation.

An emergency depressurization was performed to restore RPV water level.

RPV pressure is 70 psig and lowering.

Alternate Shutdown System (ASDS) Fuel Zone RPV water level indicator reading is as shown:

Based on the given conditions, complete the following statement concerning RPV water level and why? Actual RPV water level is- A. lower than indicated because this instrument is calibrated at 0 psig. B. lower than indicated because this instrument is calibrated at 1000 psig. C. higher than indicated because this instrument is calibrated at 0 psig. D. higher than indicated because this instrument is calibrated at 1000 psig. Question 6 Points: 1.0

Monticello NRC Written Exam Page: 17 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

6 Proposed Answer: B DISTRACTOR ANALYSIS A, C, and D are incorrect but plausible misconceptions of water level indications during off

-normal conditions. According to Ops Man B.01.01

-01, Level transmitter LT 3-61, which is located on C

-55 and used for flooding the vessel during shutdown from outside the Control Room, is the only level transmitter that is calibrated for COLD conditions (0 psig).

B is correct

The examinee must understand that the Fuel Zone level indicator on the ASDS panel C-292, LI-4108, is calibrated for 1000 psig (HOT). With RPV pressure at 70 psig, cold conditions are established. The colder water requires less inventory to provide the same level indication. Therefore, actual water level is lower. As plotted on Figure 29 of B.01.01

-06 actual water level is approximately

-65 inches.

The fuel zone level instrumentation will NOT be reliable during the depressurization phase of a LOCA.

Tier: 1 Group: 1 K/A: (295016 Control Room Abandonment / 7) AA1.06 Ability to operate and/or monitor the following as they apply to CONTROL ROOM ABANDONMENT: (CFR: 41.7 / 45.6) Reactor water level Importance Rating:

4.0 10 CFR Part 55:

41.7 10 CFR 55.43.b

N/A K/A Match:

K/A is matched by testing the applicants' ability to accurately monitor the reactor water level when outside the control room.

SRO Justification:

N/A Technical

References:

Ops Man B.01.01

-01, -03, and -06, C.4-C, and M-8107L-083 (Alternate Shutdown System) Rev. 9 Proposed references to be provided:

None ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 18 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

6 Learning Objective:

Cognitive Level:

Higher X Lower _ Question Source:

New _ Modified Bank

_ Bank X Question History:

Question 1870 from the Exam BANK Comments: The question stem has been slightly modified from the original BANK question in order to improve presentation.

Monticello NRC Written Exam Page: 19 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM At 0900 today the plant was operating at rated conditions with the following RBCCW System status:

At 1000 power was momentarily interrupted to P

-6B and then restored.

At 1100 Annunciator 6

-B-32 (RBCCW LOW DISCH PRESS) alarmed and the RBCCW System status indicated the following:

Given the above sequence and indications displayed above, which one of the following completes the statements below?

P-6A is (may have) __(1)__ and P

-6B __(2)__ start automatically.

A. (1) operating normally (2) will B. (1) operating normally (2) will NOT C. (1) experienced a sheared shaft (2) will D. (1) experienced a sheared shaft (2) will NOT Question 7 Points: 1.0

Monticello NRC Written Exam Page: 20 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

7 Answer D DISTRACTOR ANALYSIS The P-6A shaft shear will result in a low discharge header condition alarm at 30 psig and the pump motor could be still running as indicated by the red indicating lamp. The momentary loss of control power to the standby pump has caused the drop out the set up feature (white indicating lamp not illuminated), the standby pump will not auto start A. (1) Incorrect (2) Incorrect B. (1) Incorrect (2) Correct C. (1) Correct (2) Incorrect D. (1)Correct (2) Correct Tier: 1 Group: 1 K/A: 295018 Partial or Total Loss of CCW / 8 AA2.03 Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER : Cause for partial or complete loss...

Importance Rating:

3.2 10 CFR Part 55:

55.41.10 10 CFR 55.43.b

N/A K/A Match:

KA is matched by having the applicant determine that the setup feature of the standby RBCCW pump is lost when power is temporarily removed and upon the loss of power to the running pump. The applicant is asked the low discharge header pressure that would result in a standby pump start if in setup and identify the status of the standby pump.

ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 21 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

7 SRO Justification:

N/A Technical

References:

B.02.05-02 C-4-B.02.05.A ARP 6-B-32 Proposed references None to be provided:

Learning Objective:

M-8107L-026 LO 7 Cognitive Level:

Higher X Lower _ Question Source:

New _ Modified Bank X Bank _ Question History:

Modified from 2015 MNGP ILT NRC question 7 Comments:

Monticello NRC Written Exam Page: 22 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM The plant is operating at rated conditions when an event occurs that results in the Air Header Pressure (PI

-1476) decreasing slowly.

Assuming the Air Header Pressure continues to slowly decrease, which one of the following alarms would be (1) the first to alarm and (2) require entry into an AOP (Abnormal Operating Procedure)

?

A. ROD DRIFT (5-A-27) B. INST AIR HEADER LOW PRESS (6

-B-34) C. SERVICE AIR HEADER LOW PRESS (6-B-35) D. SCRAM PILOT HEADER HI/LO PRESS (5-B-22) Question 8 Points: 1.0

Monticello NRC Written Exam Page: 23 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

8 Proposed Answer: B DISTRACTOR ANALYSIS A. Incorrect: at <60 psig

, the control rods will start to drift and the reactor must be manually scrammed; but AOP shall be entered prior to.

B. Correct: when Air Header Pressure reaches 85 psig

, annunciator 6

-B-34 (INST AIR HEADER LOW PRESS) will alarm. ARP 6-B-34 directs AOP C.4-B.08.04.01 entry. Per AOP C.4

-B.08.04.01, Table 1, if the IA pressure is reduced to 85 psig this is the first time operator AOP action will be required.

C. Incorrect: at 82 psig , Annunciator 6

-B-35 (SERVICE AIR HEADER LOW PRESS) alarms and CV

-1474, Serv Air Isol CV valve, closes; AOP entry is not directly required. D. Incorrect: Annunciator 5

-B-22 (SCRAM PILOT HEADER HI/LO PRESS) alarms at 60 psig. EOP entry would not be required until control rods start to drift.

Tier: 1 Group: 1 K/A: (295019 Partial or Total Loss of Inst. Air / 8) 2.4.4 Ability to recognize abnormal indications for system operating parameters that are entry

-level conditions for emergency and abnormal operating procedures. (CFR: 41.10 / 43.2 / 45.6)

Importance Rating:

4.5 10 CFR Part 55:

41.10 10 CFR 55.43.b:

N/A K/A Match:

K/A is matched by testing the applicants' ability to recognize Instrument Air pressure has reduced to an AOP entry level condition SRO Justification:

N/A Technical

References:

AOP C.4-B.08.04.01.A, ARPs 6

-B-34, 6-B-35 and 5-B-22, and M-8107L-024 (Instrument and Service Air Alternate Nitrogen and Instrument Nitrogen Systems) Rev. 24 Proposed references to be provided:

None ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 24 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

8 Learning Objective:

7 of M-8107L-024 (Instrument and Service Air Alternate Nitrogen and Instrument Nitrogen Systems) Rev. 24 Cognitive Level:

Higher _ Lower X Question Source:

New X Modified Bank

_ Bank _ Question History:

NEW - Question 78 from 2013 MNGP ILT NRC exam used as a starting point but converted from SRO to RO question Comments:

Monticello NRC Written Exam Page: 25 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM The following conditions exist with plant startup activities being performed IAW procedure 2167 (Plant Startup

): RPV water level was being maintained between +30 to +35 inches RHR SDC is in service

Subsequently, a loss of offsite power occurs.

Given the above conditions, which ONE of the following completes the statements below?

RHR SDC will __(1)__.

Maintaining RPV water level in the above band __(2)__ natural circulation between the inside and outside of the core shroud could occur.

A. (1) remain in service (2) ensures B. (1) remain in service (2) does NOT ensure C. (1) be lost (2) ensures D. (1) be lost (2) does NOT ensure Question 9 Points: 1.0

Monticello NRC Written Exam Page: 26 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

9 Answer: D DISTRACTOR ANALYSIS A. (1) Incorrect, A Group 2 PCT isolation logic will occur due to the loss of normal offsite power, this results in a loss of SDC (2) Incorrect, Maintaining a reactor water level of +55' or greater ensures that circulation can occur between the inside and outside of the core shroud B. (1) Incorrect, Maintaining a reactor water level of +55' or greater ensures that circulation can occur between the inside and outside of the core shroud.

(2) Correct C. (1) Correct (2) Incorrect, Maintaining a reactor water level of +55' or greater ensures that circulation can occur between the inside and outside of the core shroud D. Correct Tier: 1 Group: 1 K/A: 295021 Loss of Shutdown Cooling / 4

. AK1.04 Knowledge of the operational implications of the following concepts as they apply to LOSS OF SHUTDOWN COOLING :

Natural circulation-Importance Rating:

3.6 10 CFR Part 55:

55.41.8 to 41.10 10 CFR 55.43.b

N/A K/A Match:

Plant startup requires a RPV level band of +30" to +35", SDC or a recirc pump is required to be in service during this Condition, a loss of normal offsite power will result in a loss of both and the RPV level will not support natural circulation

SRO Justification:

N/A ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 27 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

9 Technical

References:

Shutdown Procedure, Ops Man C.3 Revision 79

LOSS OF NORMAL SHUTDOWN COOLING, Ops Man C.4

-B.03.04.A; 2167 Plant Startup

Proposed references to be provided:

None Learning Objective:

Cognitive Level:

Higher X Lower _ Question Source:

New X Modified Bank

_ Bank _ Question History:

New Comments:

Monticello NRC Written Exam Page: 28 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM The plant is operating in MODE 1 with fuel bundles being shuffled in the Spent Fuel Pool. An event occurs resulting in the following conditions:

4-A-1 (REFUELING FL AREA HI RADIATION) is in alarm ARM A-1 (1027 RB NORTH EAST L OW) is in alarm ARM A-2 (1027 RB NORTH HIGH) is in alarm ARM A-3 (1027 RB WEST STAIRWA Y) is in alarm Refuel Bridge radiation monitor is in alarm RM-17-453A (Fuel Pool Monitor Channel A) is 30 mr/hr and slowly rising RM-17-453B (Fuel Pool Monitor Channel B) is 25 mr/hr and slowly rising

Which one of the following is the correct response to these conditions?

A. Evacuate the Refuel Floor ONLY.

B. Verify automatic initiation of SBGT ONLY.

C. Evacuate the Reactor Building AND the Refuel Floor.

D. Verify automatic initiation of SBGT and CRV

-EFT (High Radiation Mode).

Question 1 0 Points: 1.0

Monticello NRC Written Exam Page: 29 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

10 Proposed Answer: C DISTRACTOR ANALYSIS A. Incorrect: The RB should also be evacuated in accordance with Ops Manual D.2

-05. If only the Refuel Bridge radiation alarm sounds, RB evacuation is not required.

B. Incorrect: SBGT would not be initiated automatically until RM 453A or B reached 50 mr/hr.

C. Correct: When 4-A-1 alarms due to ARM A

-1, A-2, and/or A

-3 on C-11, the ARM indicators should be checked and it shall be determined the affected area and radiation level. According to Ops Man B.05.12

-03, ONLY ARM A

-1 and A-3 also have a local range indication at the sensor with an upscale trip light and horn to indicate an alarm condition.

Since BOTH RB and Refuel Bridge radiation alarms are sounded, according to Ops Man D.2-05 and ARP 4

-A-1, all personnel in the RB and Refuel Floor Area shall evacuate.

D. Incorrect: See 'B' above.

Tier: 1 Group: 1 K/A: (295023 Refueling Acc / 8) AK2.03 Knowledge of the interrelations between REFUELING ACCIDENTS and the following: (CFR: 41.7 / 45.8) Radiation monitoring equipment Importance Rating:

3.4 10 CFR Part 55:

41.7 10 CFR 55.43.b:

N/A K/A Match:

K/A is matched by testing the applicants' knowledge of the association between refueling accidents and radiation monitoring equipment SRO Justification:

N/A Technical

References:

Ops Man B.05.12

-01 and -03, ARP 4-A-1, Ops Man D.2

-05, M-8107L-019 (Fuel Handling) Rev. 14, M

-8107L-077 (Process Radiation Monitoring And Area Radiation Monitors) Rev. 15 Proposed references to be provided:

None ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 30 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

10 Learning Objective:

Cognitive Level:

Higher X Lower _ Question Source:

New _ Modified Bank X Bank _ Question History:

Question 10 from the 2010 Audit Exam Comments: Minor editorial changes were made and distracter 'D' reworded slightly.

Monticello NRC Written Exam Page: 31 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM The plant was at rated conditions when a plant transient occurred.

Drywell pressure is 30 psig, rising at a rate of approximately 1 psig/minute, and approaching the Pressure Suppression Pressure Limit.

Neither Drywell Spray train is currently available, but maintenance personnel have reported that they can have one of the trains restored within the next half hour.

RPV injection is limited and RPV level is approaching TAF.

Based on the above conditions, Containment Venting -.

A. is immediately required to protect the containment integrity B. must wait until DW Press exceeds the Pressure Suppression Limit C. may be initiated in anticipation core uncovering and the resulting fuel damage D. must wait until it has been determined that DW Sprays will be unable to Maintain the DW Pressure below the DW Design Pressure Question 1 1 Points: 1.0

Monticello NRC Written Exam Page: 32 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

11 Answer:

C DISTRACTOR ANALYSIS The maximum pressure of drywell and pressure suppression chamber is 62 psig (USAR

-05.02) In general, primary containment venting should be considered as a last resort, performed only if primary containment pressure cannot be controlled using sprays and limited to the volume required to maintain pressure below the DW Pressure Limit (Fig D). In extreme cases, however, such as an extended station blackout beyond the plant design basis in which power is not restored, earlier or more extensive primary containment pressure reductions may be appropriate to restore and maintain adequate core cooling or limit the total radioactivity release. Venting to maintain primary containment pressure below the DW Pressure Limit is addressed in PART Q. The need for venting at lower pressures to restore and maintain adequate core cooling or limit the total radioactivity release is evaluated in the PART N override.

A. Incorrect; based on the rate of pressure rise, DW pressure will not exceed Primary Containment Pressure Limit for over 30 minutes.

B. Incorrect; per the global override at the top of the DW/Torus Pressure leg, earlier venting is permitted to restore and maintain adequate core cooling or limit the total radioactivity release. C. CORRECT D. Incorrect; per the global override at the top of the DW/Torus Pressure leg, earlier venting is permitted to restore and maintain adequate core cooling or limit the total radioactivity release. Tier: 1 Group: 1 K/A: 295024 High Drywell Pressure / 5.

EK3.07 Knowledge of the reasons for the following responses as they apply to HIGH DRYWELL PRESSURE : Drywell venting Importance Rating: 3.5 10 CFR Part 55:

41.5 10 CFR 55.43.b

N/A ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 33 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

11 K/A Match:

The K/A is matched as the applicant must evaluate primary containment conditions against the design basis and evaluate the mitigate strategy, such that venting the drywell is permitted to be performed prior to spraying the drywell to reduce total dose.

SRO Justification:

N/A Technical

References:

USAR-05.02 C.5.1-1200 C.5-1200 Proposed references to be provided:

None Learning Objective:

M-8107L-044 LO 9,11 Cognitive Level:

Higher X Lower _ Question Source:

New X Modified Bank

_ Bank _ Question History:

New Comments:

Monticello NRC Written Exam Page: 34 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM The plant was at 100% power when a transient occurred resulting in a reactor scram and an increase in Reactor pressure which indicated a C.4

-1100 (RPV Control) entry condition.

The CRS directs manual RPV pressure control with SRV(s).

The SRV F handswitch is taken to OPEN, but its amber light does NOT illuminate. Which one of the following actions should be taken next?

A. Place SRV F hand

-switch in CLOSE and then any other SRV hand

-switch to OPEN.

B. Cycle SRV F hand

-switch to CLOSE and immediately back to OPEN.

C. Monitor RPV pressure and SRV tailpipe temperature to determine if SRV F is open.

D. Place SRV hand

-switches in OPEN following the preferred sequence until at least one SRV amber light illuminates.

Question 1 2 Points: 1.0

Monticello NRC Written Exam Page: 35 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

12 Proposed Answer: C DISTRACTOR ANALYSIS A. Incorrect: according to B.03.03

-05.H, SRV B is NOT the next preferred sequence after SRV F - SRV C is B. Incorrect: Procedurally incorrect: According to B.03.03

-05.H, Once a relief valve has been closed, it should NOT be reopened for at least 10 seconds (in the case of SRV E, G, and H, reopening is blocked for 10 seconds after alarm clears) or discharge piping and containment damage may result C. Correct: In this condition, a reactor scram has occurred, the main turbine has tripped (reactor is isolated) and Reactor pressure is increasing

- and the CRS directs use of the SRV(s) as an alternate pressure control system (per C.5

-1100, RPV Control). The pressure switch within the SRV F tailpipe has failed or is not responding properly (the amber light is not lit) so the operator must use other means to verify the SRV has actuated besides the amber light. SRV tailpipe temperature changes and a decrease in Reactor pressure are both means to monitor SRVs and they should be reviewed prior to opening the next SRV in the sequence (a sequence is identified in Ops Man B.03.03

-05.H that shall be employed to spread the heat around the Torus and will open the SRV's with a lower number of life cycles first).

D. Incorrect: Procedurally not the preferred approach; it may take some time for the amber light to illuminate and there are indications that should be reviewed before another SRV is opened to minimize pressure transients.

Tier: 1 Group: 1 K/A: (295025 High Reactor Pressure / 3) EA1.03 Ability to operate and/or monitor the following as they apply to HIGH REACTOR PRESSURE: (CFR: 41.7 / 45.6) Safety/relief valves: Plant

-Specific Importance Rating:

4.4 10 CFR Part 55:

41.7 10 CFR 55.43.b:

N/A K/A Match:

K/A is matched by testing the applicants' ability to operate the SRV(s) according to procedure when a high reactor pressure condition exists AND accordingly be able to monitor the SRV(s) status. The applicant shall understand what indications actually represent

- the amber lights do NOT indicate actual SRV position.

ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 36 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

12 SRO Justification:

N/A Technical

References:

Ops Man B.03.03

-01 and -05, EOPs C.5

-1100 and -3302, ARP 5

-A-46, M-8107L-025 (Reactor Pressure Relief) Rev. 23 Proposed references to be provided:

None Learning Objective:

7 of M-8107L-025 (Reactor Pressure Relief) Rev. 23 Cognitive Level:

Higher X Lower _ Question Source:

New _ Modified Bank

_ Bank X Question History:

Question 549 of Exam BANK

- with the question stem and distractors modified in an attempt to strengthen question and more

-appropriately match K/A Comments:

Monticello NRC Written Exam Page: 37 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM The plant was operating at rated conditions when a station blackout occurred. Following an assessment of the ability to restore AC sources, the Shift manager declared an Extended Loss of AC Power (ELAP) event. Plant conditions cannot be maintained below the heat capacity temperature limit

. Given the above conditions, Pressure reductions of the RPV are prioritized to __(1)__ .

The RPV is required to be __(2)__.

A. (1) maintain core cooling

(2) fully depressurized B. (1) maintain core cooling

(2) depressurized to not less than 150 psig C. (1) mitigate primary containment challenges (2) fully depressurized D. (1) mitigate primary containment challenges (2) depressurized to not less than 150 psig Question 1 3 Points: 1.0

Monticello NRC Written Exam Page: 38 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

13 Answer: B DISTRACTOR ANALYSIS The Heat Capacity Limit is a function of RPV pressure. If torus temperature approaches the limit, additional operating margin can be gained by reducing RPV pressure. Such pressure reductions are appropriate, however, only if the core will remain adequately cooled: Since RPV depressurization may result in loss of steam

-driven injection systems, pressure reductions to mitigate primary containment challenges must be coordinated with core cooling strategies. Full depressurization is appropriate only if adequate core cooling will not be sacrificed as a result. Loss of adequate core cooling would compound containment challenges and increase any resulting radioactivity release. Core cooling is thus prioritized over other EOP objectives A. (1) Correct (2) Incorrect, RCIC and HPCI are the only available injections sources, 150 psig is required in the RPV to ensure adequate injection source B. Correct C. (1) Incorrect, core cooling is prioritized over other EOP objectives (2) Incorrect, RCIC and HPCI are the only available injections sources, 150 psig is required in the RPV to ensure adequate injection source D. (1) Incorrect, core cooling is prioritized over other EOP objectives (2) Correct Tier: 1 Group: 1 K/A: 295026 Suppression Pool High Water Temp.

EA2.03 Ability to determine and/or interpret the following as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE : Reactor pressure Importance Rating:

3.9 10 CFR Part 55:

41.10 10 CFR 55.43.b:

N/A K/A Match:

The applicant must determine that given station station blackout conditions only RCIC/HPCI are available injection sources and that a complete RPV depressurization is not the correct mitigation strategy as core cooling is prioritized over containment integrity.

ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 39 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

13 SRO Justification:

N/A Technical

References:

C.5-1200 C.5.1-1200 C.4-B.09.02.A Proposed references to be provided:

None Learning Objective:

Cognitive Level:

Higher X Lower _ Question Source:

New X Modified Bank

_ Bank _ Question History:

New Comments:

Monticello NRC Written Exam Page: 40 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM The plant was operating in MODE 1

, in a normal full power lineup with no equipment out of service, when a loss of offsite power occurred. All plant systems responded as expected. The CRS has entered and is implementing C.5

-1100 RPV Control and C.5

-1200 Primary Containment Control.

RPV Water Level is being maintained between 9 and 48 inches with RCIC; supplemented by HPCI as needed RPV Pressure is being maintained 600 and 800 psig with HPCI in the pressure control mode; supplemented by SRVs as needed.

Both RHR loops are aligned for Torus Cooling Torus Temperature is 135F and slowly lowering Current Drywell atmospheric conditions:

o Drywell Temperature is 135F and slowly rising o Drywell Pressure 1.6 psig and slowly rising Given the above conditions, which one of the following summarizes the operator actions (if any) that are necessary to place all available Drywell Cooling is service?

A. No operator actions are required; all available Drywell Cooling is already in service.

B. Verify ALL DW Cooling Fans are running; Open associated DW Cooling Fan Discharge Dampers.

C. Place ALL DW Cooling Fan control switches to OFF; Verify Fan Inlet Damper control switches in AUTO; Place ALL DW Cooling Fan control switches to ON; Open associated DW Cooling Fan Discharge Dampers D. Verify DW Cooling Fans 2, 3, and 4 are running and associated Fan Inlet Dampers are OPEN (AUTO);

Open associated DW Cooling Fan Discharge Dampers; Start DW Cooling Fan 1; Open the associated Fan Inlet Damper; Open associated DW Cooling Fan Discharge Damper.

Question 1 4 Points: 1.0

Monticello NRC Written Exam Page: 41 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

14 Answer:

D DISTRACTOR ANALYSIS A. Incorrect; DW Cooling Fans will restart following restoration of AC power by the EDGs, but fan discharge dampers have to be manually opened.

B. Incorrect; DW Cooling Fan 1 was in Standby prior to the power loss and therefore does not restart. C. Incorrect; DW Cooling Fans 2, 3, and 4 will already be running therefore stopping the fans, then restarting is unnecessary. DW Cooling Fan 1 is in Standby and starting the fan does not require placing the control switch to OFF and then to ON.

D. Correct; DW Cooling Fans 2, 3, and 4 will be running, but discharge dampers must be opened. DW Cooling Fan 1 must be started and then its discharge damper opened.

Tier: 1 Group: 1 K/A: (295028 High Drywell Temperature / 5) 2.2.44 Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.

(CFR: 41.5 / 43.5 / 45.12)

Importance Rating:

4.2 10 CFR Part 55:

41.10 10 CFR 55.43.b:

N/A K/A Match:

Applicant must evaluate given plant conditions to determine DAC system status and then determine the actions necessary to ensure all available Drywell Cooling is in service.

ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 42 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

14 SRO Justification:

N/A Technical

References:

C.5-1100 and C.5-1200, and M

-8107L-044 (Primary Containment) Rev. 19 Proposed references to be provided:

None Learning Objective:

Cognitive Level:

Higher X Lower _ Question Source:

New X Modified Bank

_ Bank _ Question History:

Comments:

Monticello NRC Written Exam Page: 43 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM The plant was preparing to shutdown due to low torus water level from a leak that has been isolated. While still at rated conditions a reactor scram occurred due to an inadvertent Group I isolation. Control rods FAILED to insert and the following plant conditions now exist:

Reactor power is 10% and slowly lowering due to SBLC injection Torus water temperature is 160°F ALL available torus cooling is in service Torus water level is

-2 ft. Drywell pressure is 3.5 psig Which of the following states the correct adjustment, if any, to torus cooling necessary to maintain maximum available torus cooling and stay within pump operating limits?

A. No adjustment required B. Reduce flow in each RHR loop to 4000 gpm C. Reduce flow in each RHR loop to 6000 gpm D. Reduce flow in each RHR loop to 7500 gpm Question 1 5 Points: 1.0

Monticello NRC Written Exam Page: 44 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

15 Answer C DISTRACTOR ANALYSIS C is correct as torus overpressure is calculated to be approximately 7.10 psig. If possible the RHR pumps should always be operated within the NPSH limits. RHR flow should be operated at the maximum flow rate possible to reduce torus temperature.

A. Incorrect, this is too much flow and will jeopardize adequate NPSH, but is plausible if the examinee misinterprets Figure F or miscalculates Overpressure protection B. Incorrect; it is under the 2 pumps curve but but does not maximize available Torus Cooling.

C. Correct D. Incorrect, this it is too much flow, but is plausible since flow corresponds to limit for 1 pump Tier: 1 Group: 1 K/A: 295030 Low Suppression Pool Wtr Lvl EK1.02 Knowledge of the operational implications of the following concepts as they apply to LOW SUPPRESSION POOL WATER LEVEL: Pump NPSH Importance Rating:

3.5 10 CFR Part 55:

55.41.8 to 10

10 CFR 55.43.b:

N/A K/A Match:

KA is matched by having the applicant determine the required action to maintain the RHR system operation within NPSH requirements.

SRO Justification:

N/A Technical

References:

C.5-1200 Figure F, C.5.1-1200, C.5-1200 ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 45 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

15 Proposed references to be provided:

C.5-1200 Figure F (inserted with question Learning Objective:

M-8107L-044, LO 8 &10 Cognitive Level:

Higher X Lower _ Question Source:

New _ Modified Bank X Bank _ Question History:

Modified NRC exam 2015 Q 13, changes to stem to address low torus water level and 0 psi overpressure.

Comments:

Monticello NRC Written Exam Page: 46 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Which of the following completes the statement below.

The Reactor Protection System reactor low water level signal is received by __(1)__ level transmitters AND will send a SCRAM input __(2)__ time delay if the +9 inch setpoint is indicated.

(1) (2) A. 4 independent WITHOUT a B. 4 independent WITH a 7.3 second C. 2 independent and 1 Safeguard WITHOUT a D. 2 independent and 1 Safeguard WITH a 7.3 second Question 1 6 Points: 1.0

Monticello NRC Written Exam Page: 47 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

16 Proposed Answer: D DISTRACTOR ANALYSIS A. Correct: The applicant must have knowledge of the reactor water low level inputs to the RPS logic. Per B.05.06

-02, for the RPS, Reactor vessel level is sensed by four level transmitters, LT 3-57A, LT-2-3-57B, LT-2-3-58A and LT 3-58B. The reactor low water level scram setpoint for RPS is +9 inches. The same level transmitters are used for the Low-Low Water Level Primary Containment Isolation system to isolate Group I and III valves at

-47 inches. For the ATWS system, Level is sensed by four different level transmitters (LT 3-180A, LT-2-3-180B, LT-2-3-180C, and LT 3-180 D). An ATWS system trip is initiated at

-47 inches. To prevent the ATWS trip on low

-low water level from affecting the ECCS system performance, a 7.3

-second time delay is provided for this trip. If the low-low level condition clears before the time delay relay times out, the relay will reset and the ATWS trip will not occur. Per B.05.07

-02, for Reactor Level Control, Reactor Water level is measured by two independent level transmitters (LT 52A and LT-6-52B) and a third level input is obtained from the B Safeguards level transmitter LT 3-85A. B. Incorrect: The ATWS trip system employs a 7.3 second time delay so ECCS system performance is not affected. Plausible the applicant confuses the ATWS and RPS logic.

C. Incorrect: Per M

-8107L-046 (Reactor Level Control) Rev. 12, Reactor Level Control level instrumentation includes 2 independent level transmitters (LT 52A and B) and a third level input is received from Safeguards transmitter (LT 3-85A). Plausible the applicant confuses the LT from Reactor Level Control and RPS.

D. Incorrect: plausible the applicant confuses RPS level input characteristics with the ATWS and Reactor Level Control systems.

ANSWER EXPLANATION

Monticello NRC Written Exam Page: 48 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

16 Tier: 1 Group: 1 K/A: (295031 Reactor Low Water Level / 2) EK2.11 Knowledge of the interrelations between REACTOR LOW WATER LEVEL and the following: (CFR: 41.7 / 45.8) Reactor protection system Importance Rating:

4.4 10 CFR Part 55:

41.7 10 CFR 55.43.b: N/A K/A Match:

K/A is matched by testing the applicants' knowledge of the interrelations between Reactor Low Water Level and the Reactor Protection System; specifically testing the applicant's knowledge of the low water level inputs to RPS. SRO Justification:

N/A Technical

References:

Ops Man B.05.06

-02 and -03, B.05.07

-02, ARP 5-B-19, M-8107L-072 (Reactor Protection System) Rev. 16 and M

-8107L-046 (Reactor Level Control) Rev. 12 Proposed references to be provided:

None Learning Objective: 6 of M-8107L-072 (Reactor Protection System) Rev. 16 Cognitive Level:

Higher _ Lower X Question Source:

New X Modified Bank

_ Bank _ Question History:

Used Questions 875 and 1227 from BANK as starting points but this question is significantly different Comments: QUESTION BACKGROUND

Monticello NRC Written Exam Page: 49 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM An ATWS has occurred with the following conditions Boron was injected using SBLC C.5-2002 (Emergency RPV Depressurization) was required to be entered 2 SRVs were able to be opened Depressurization is continuing using Alternate Depressurization Systems per C.5

-3303 (Alternate Depressurization).

Which One of the following completes the statement below?

______ mode(s) of RWCU may be used to depressurize the reactor.

A. NEITHER the normal nor dump B. ONLY the normal C. ONLY the dump D. BOTH the Normal and Dump

Question 1 7 Points: 1.0

Monticello NRC Written Exam Page: 50 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

17 Answer: B DISTRACTOR ANALYSIS With ATWS conditions and boron injected into the RPV the alternate depressurization systems allows use of the RWCU normal mode as it is OK to defeat isolations including SBLC. The RWCU dump mode is not allowed with boron injected into the core as this would result in the loss of boron from the RPV.

A. Incorrect, as stated above the normal mode is allowed B. Correct, the normal mode is allowed C. Incorrect, the dump mode would result in loss of boron from the RPV D. Incorrect, the dump mode would result in loss of boron from the RPV Tier: 1 Group: 1 K/A: 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown.

EK1.05 Knowledge of the operational implications of the following concepts as they apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN : Cold shutdown boron weight: Plant

-Specifi c Importance Rating:

3.4 10 CFR Part 55:

55.41.8 to 10 10 CFR 55.43.b:

N/A K/A Match:

KA is matched by having the applicant identify that alternate depressurization is not permitted with the RWCU dump mode, as this would result in the loss of boron fro m the RPV. SRO Justification:

N/A Technical

References:

C.5-2002 Ops Man C.5.1

-2002 ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 51 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

17 Proposed references to be provided:

None Learning Objective:

Cognitive Level:

Higher _ Lower X Question Source:

New _ Modified Bank X Bank _ Question History:

MNGP Bank question 2002 Comments:

Monticello NRC Written Exam Page: 52 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM The plant was operating at rated conditions when an event occurred that resulted in a high off

-site release rate and the initiation of Standby Gas Treatment System.

Given the above conditions, what is the response to the exhaust and supply fans in:

(1) Reactor Building (2) Turbine Building (3) Main Plenum Room A. (1) Exhaust fans TRIP (2) Supply fans TRIP (3) Exhaust fans TRIP B. (1) Exhaust and Supply fans TRIP (2) Supply fans TRIP (3) Exhaust fans TRIP C. (1) Exhaust and supply fans TRIP (2) Exhaust fans TRIP (3) Exhaust fans TRIP D. (1) Exhaust and supply fans TRIP (2) Exhaust and supply fans TRIP (3) Exhaust and supply fans TRIP Question 1 8 Points: 1.0

Monticello NRC Written Exam Page: 53 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

18 Proposed Answer: B DISTRACTOR ANALYSIS A, C, and D are incorrect: plausible interpretations of the plant ventilation systems' response to high off-site release rate and corresponding SBGT initiation. The applicant could confuse Buildings and/or the intent of the ventilation systems during accident conditions.

B is correct: When a high Off

-site release exists, all primary systems discharging outside primary and secondary containments should be isolated except systems needed for Reactor shutdown, core cooling, and primary containment venting. As such, the plant ventilation systems will operate quite differently during normal operation than during a high off

-site release. Given the above conditions, SBGT initiation will trip an assortment of exhaust and supply fans. Per B.08.07

-02 and B.04.02-01, when the SBGT system initiates, the Reactor Building supply and exhaust fans trip (V-EF-10, -24A/B, -28, and V-AC-10A/B and V

-AH-4A/B), the Turbine Building supply fans trip (V-MZ-1, -4, -5, and -6, and V-AH-1 and -2), and main plenum room exhaust fans trip (V-EF-20, -21, and -22). The Main Plenum Room exhaust fans are tripped to eliminate a potential bypass leakage path into the Main Plenum Room from SCTMT. The Turbine Building supply fans are tripped to prevent pressuring the Turbine Building when the Main Plenum exhaust fans are tripped.

Tier: 1 Group: 1 K/A: (295038 High Off

-site Release Rate / 9) EK2.03 Knowledge of the interrelations between HIGH OFF

-SITE RELEASE RATE and the following: (CFR: 41.7 / 45.8) Plant ventilation systems Importance Rating:

3.6 10 CFR Part 55:

41.7 10 CFR 55.43.b:

N/A K/A Match:

K/A is matched by testing the applicants' knowledge of the interrelations between high off

-site release rate and plant ventilation systems; specifically testing the applicant's knowledge of non

-Control Room ventilation systems' response to an accident condition.

ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 54 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

18 SRO Justification:

N/A Technical

References:

Ops Man B.08.07

-01 and -02, Ops Man B.04.02

-01, EOP C.5-1400, A.2-204, P&ID NH-36267, and M

-8107L-027 (HVAC) Rev. 20 Proposed references to be provided:

None Learning Objective:

5.l of M-8107L-027 (HVAC) Rev. 20 Cognitive Level:

Higher X Lower _ Question Source:

New X Modified Bank

_ Bank _ Question History:

None Comments:

Monticello NRC Written Exam Page: 55 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM The plant was operating at 100% with the electric fire pump on clearance for maintenance. A fire started in the #11 EDG Room that resulted in the actuation of the EDG room sprinkler system.

Which ONE of the following completes the statement below?

IAW C.4-B.08.05.A [Plant Fire], local manual operator action _____________.

A. is required, to isolate flow to the screen wash header to ensure adequate flow for fire water header.

B. is required, to ensure that two fire pumps are in operation since some of the flow from the Screen Wash/Fire Pump (P

-104) will be diverted to the Screen Wash header.

C. is not required, since both the Diesel Fire Pump (P

-105) AND the Screen Wash/Fire Pump (P

-104) will automatically start to provide the required flow to the fire water header.

D. is not required, since the automatic start of either the Diesel Fire Pump (P-105) OR the Screen Wash/Fire Pump (P

-104) alone will provide the required flow to the fire water header.

Question 1 9 Points: 1.0

Monticello NRC Written Exam Page: 56 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

19 Answer: C DISTRACTOR ANALYSIS A. Correct; with the electric fire pump on clearance the plant fire procedure requires manual action to ensure flow is not diverted away from the sprinklers. The screen wash header control valve will automatically close if P

-104 auto starts, but the procedure requires that the header be manually isolated.

B. Incorrect; while two pumps are required to be in operation, flow to the Screen wash header must be isolated. The screen wash header control valve will automatically close if P

-104 auto starts, but the procedure requires that the header be manually isolated.

C. Incorrect; even if both pumps automatically start, manual action is required by the procedure to ensure that the screen wash header is isolate

d. D. Incorrect; both pumps are required to be in operation and even if both pumps automatically start, manual action is required by the procedure to ensure that the screen wash header is isolated Tier: 1 Group: 1 K/A: 600000 Plant Fire On Site AK3.04 Knowledge of the reasons for the following responses as they apply to PLANT FIRE ON SITE: Actions contained in the abnormal procedure for plant fire on site Importance Rating:

2.8 10 CFR Part 55:

55.41.10 10 CFR 55.43.b

N/A K/A Match:

KA is matched by having the applicant determine that the plant fire procedure requires operator action to ensure the screen wash/fire pump is not diverted from the sprinkler system when required as one of two available fire pumps.

SRO Justification:

N/A Technical

References:

Ops Man C.4

-B.08.05.A Ops Man B.08.05

-01 ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 57 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

19 Proposed references None to be provided:

Learning Objective:

M-8107L-010, LO 7, 9 Cognitive Level:

Higher X Lower _ Question Source:

New X Modified Bank

_ Bank _ Question History:

Comments:

Monticello NRC Written Exam Page: 58 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM The plant is operating at rated conditions with the Automatic Voltage Regulator (AVR) in AUTOMATIC when a grid electrical disturbance resulted in a variance in grid voltage and frequency and an entry into C.4

-F (RAPID POWER REDUCTION). The following conditions now exist: Main Generator is ON

-LINE with the following parameters:

o 450 MWe o 250 MVAR o H 2 pressure 30 psig o frequency steady at 59.6 Hz Annunciator 8

-A-34 (1-BUS 345 KV LOW FREQ) is in alarm (Alarm response procedure attached).

The Transmission System Operator (TSO) requests that MNGP raise their output to help improve grid stability. Which one of the following represents the highest load increase that is within the limits of the attached Reactive Capability vs. Megawatt Load curves?

A. Load cannot be increased; an immediate reactor shutdown and turbine trip is required.

B. Raise Generator output to 600 MWe Maintain Generator VAR Load at 250 MVAR C. Raise Generator output to 600 MWe Lower Generator VAR load to 150 MVAR D. Raise Generator output to 700 MWE Lower Generator VAR Load to 150 MVAR Question 20 Points: 1.0

Monticello NRC Written Exam Page: 59 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

20 Proposed Answer: C DISTRACTOR ANALYSIS Grid disturbances can affect the nominal generator frequency of 60 Hz. Annunciator 8

-A-34 will alarm at 59.8 Hz. Applicant must understand the nominal characteristics of generator operation and the generator set points. Applicant should recognize that the above initial conditions are within operating limits and do not require any immediate actions. ARP 8-A-34 directs raising generator load as directed by the TSO as long as the generator is operated within limits.

A. Incorrect; per ARP 8-A-34 (1-BUS 345 KV LOW FREQ) the generator may run indefinitely at this frequency and the current load is within the limits for generator gas pressure of 30 psig.

B. Incorrect; MW and MVAR are outside the limits for generator gas pressure of 30 psig; plausible because load is within the limits for 45 psig.

C. Correct; MW and MVAR are within the limits for generator gas pressure of 30 psig.

D. Incorrect; MW and MVAR are outside the limits for generator gas pressure of 30 psig; plausible because load is within the limits for 45 psig.

Tier: 1 Group: 1 K/A: (700000 Generator Voltage and Electric Grid Disturbances / 6) AA1.01 Ability to operate and/or monitor the following as they apply to GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES: (CFR: 41.5 and 41.10 / 45.5, 45.7, and 45.8) Grid frequency and voltage Importance Rating:

3.6 10 CFR Part 55:

41.5 and 41.10

10 CFR 55.43.b:

N/A K/A Match:

K/A is matched by testing the applicants' ability to respond to a grid disturbance and their knowledge of the normal and abnormal operating characteristics of the generator and associated equipment, specifically frequency and voltage ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 60 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

20 SRO Justification:

N/A Technical

References:

Ops Man B.09.02

-02, -05, and -06, ARP 8-A-34, 8-A-11, 8-11-31, M-8107L-034 (Generation) Rev. 17 Proposed references to be provided:

Figure 2 of Ops Man B.09.02

-02 Learning Objective:

LO 8.c of M

-8107L-034 (Generation) Rev. 17 Cognitive Level:

Higher X Lower _

Question Source:

New X Modified Bank _ Bank _ Question History:

Comments: Question developed from MNGP 2009 NRC Exam Question 20 and MNGP Exam BANK Question 716

.

Monticello NRC Written Exam Page: 61 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM At 1400 the plant was operating at rated conditions when the following annunciators alarmed. OFF GAS HI RADIATION (4

-A-12) OFF-GAS TIMER ACTUATED (4

-A-2) Which ONE of the following completes the statements below?

The earliest time off

-gas flow will be automatically terminated is __(1)__

Assuming no operator actions the reactor will automatically scram __(2)__ the turbine trip on low condenser vacuum trip signals.

A. (1) 1415 (2) before B. (1) 1415 (2) after C. (1) 1430 (2) before D. (1) 1430 (2) after Question 2 1 Points: 1.0

Monticello NRC Written Exam Page: 62 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

21 Answer: C DISTRACTOR ANALYSIS The off-gas isolation occurs after 30 minutes. The reactor scram setpoint is 22.3" Hg Vac, the turbine trip setpoint is 20" Hg Vac A. (1) Incorrect (2) Correct B. (1) Incorrect (2) Incorrect C. (1) Correct (2) Correct D. (1) Correct (2) Incorrect Tier: 1 Group: 2 K/A: 295002 Loss of Main Condenser Vac AA2.02 Ability to determine and/or interpret the following as they apply to LOSS OF MAIN CONDENSER VACUUM : Reactor power: Plant

-Specific Importance Rating:

3.2 10 CFR Part 55:

41.10 10 CFR 55.43.b:

N/A K/A Match:

KA is matched by having the applicant determine that the alarm condition will result in automatic isolation of the offgas system following a 30 minute time delay, and once offgas is isolated the condenser vacuum will degrade to the reactor auto scram setpoint which occurs at higher vacuum then the turbine trip. ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 63 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

21 SRO Justification:

N/A Technical

References:

Ops Man C.4

-B.06.03.A C.6-004-A-02 Proposed references None to be provided: Learning Objective:

Cognitive Level:

Higher _ Lower X Question Source:

New _ Modified Bank X Bank _ Question History:

MNGP exam bank 1366

Comments:

Monticello NRC Written Exam Page: 64 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM The plant is operating in MODE 1 when a small break LOCA concurrent with a Loss of Offsite Power occurs. Given the following current conditions:

Control rods are fully inserted Both EDGs are operating and supplying their respective busses.

The only system injecting to the vessel is CRD Reactor pressure is 550 psig and lowering at 10 psig/min DW pressure is 0.6 psig and rising at 0.05 psi/min RPV level is

-47 inches and lowering at 0.5 inches per minute What is the status of the Core Spray system 17 minutes later?

A. Core Spray pumps are not running.

B. Core Spray pumps are running and injecting to the RPV C. Core Spray pumps are running but the injection valves have not opened.

D. Core Spray pumps are running injection valves are open, but no injection is occurring. Question 22 Points: 1.0

Monticello NRC Written Exam Page: 65 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

22 Proposed Answer: B DISTRACTOR ANALYSIS A. Incorrect; CS will start and injection valves open when RPV pressure is <420 psig (at T+13 min). [Outboard injection valves are normally open, inboard injection valves are normally closed , and open when Reactor pressure is below valve pressure interlock setpoint.]

B. Correct; CS will start and injection valves open when RPV pressure is <420 psig (at T+13 min). ADS will actuate when approximately two minutes later (T=15 minutes). Injection will occur a short time later when RPV press falls below the discharge head of the pump, less static head and dynamic head losses

- approximately 310 psig. Specifically, an automatic initiation signal along with <420 psig Rx pressure for CS injection to occur.

Core Spray is initiated when ONE of the following conditions has been met:

a. High drywell pressure (>1.84 psig)

OR b. Reactor low

-low water level AND

1) Reactor pressure < 420 psig

OR 2) RPV level <

-47" for 15 minutes In addition, the Inboard and Outboard Isolation/Injection valves (MO

-1753 or MO

-1754 and MO-1751 or MO

-1752) also receive an open demand at <420 psig (assuming one of the above conditions are met).

C. Incorrect; See 'B' above.

D. Incorrect; See 'B'; plausible if examinee does not recognize that ADS actuation will also occur. Tier: 1 Group: 2 K/A: (295007 High Reactor Pressure / 3) AK2.04 Knowledge of the interrelations between HIGH REACTOR PRESSURE and the following: (CFR: 41.7 / 45.8)

LPCS Importance Rating:

3.2 10 CFR Part 55:

41.7 10 CFR 55.43.b:

N/A ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 66 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

22 K/A Match:

K/A is matched by testing the applicants' knowledge of the Low Pressure Core Spray System's inability to inject at high reactor pressure; the LPCS pumps will only inject once reactor pressure drops below a certain threshold and auto initiation signals are met. SRO Justification:

N/A Technical

References:

Ops Man B.03.01

-01 and -02, B.03.03

-01 and -02, and M-8107L-005 (Core Spray) Rev. 18 Proposed references to be provided:

None Learning Objective:

5.d of M-8107L-005 (Core Spray) Rev. 18 Cognitive Level:

Higher X Lower _ Question Source:

New _ Modified Bank X Bank _ Question History:

Modified from MNGP Exam BANK Question 138 (M8107L-005 7)

Comments:

Monticello NRC Written Exam Page: 67 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM The plant was at rated conditions when a transient resulted in the following conditions:

Bus 15 is unavailable Bus 16 is being supplied by 12 EDG Torus water temperature is 112°F and rising Torus Cooling is in service using 12 & 14 RHR pumps and 14 RHRSW pump A RHR system flow is 0 gpm.

B RHR system flow is 8000 gpm.

B RHRSW system flow is 3500 gpm.

By procedure, which of the following actions would be allowed to be performed to increase the heat removed from the torus?

A. Start #12 RHRSW pump.

B. Throttle OPEN MO

-2003 (HX Bypass).

C. Throttle OPEN CV-1729 (RHR HX SW Outlet).

D. Throttle OPEN MO

-2009 (Torus Cooling Inj/Test Inboard).

Question 23 Points: 1.0

Monticello NRC Written Exam Page: 68 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

23 Answer: C DISTRACTOR ANALYSIS IAW Operations Manual B.03.04

-05: THROTTLE OPEN MO

-2009, to provide 4000 gpm per pump OR Adjust flow for approximately 3500 gpm per pump using CV

-1729 OR CLOSE MO

-2003 HX Bypass. CAUTION Due to Emergency Diesel Generator transient loading capability, a single EDG may only provi de power to three large motors (RHRSW, Core Spray, or RHR) at one time.

In accordance with Operations Manual B.08.01.03

-05: If emergency or abnormal conditions require, a single RHRSW pump may operate at flow rates up to 6000 gpm. Operation at flows greater than this may result in damage to the pump thrust bearing A. Incorrect, three large pumps are already running on the EDG.

B. Incorrect, opening the heat exchanger bypass valve reduce cooling of the torus water C. Correct, a single RHRSW pump may operate at up to 6000 gpm during abnormal or emergency conditions D. Incorrect, the RHR is at the pump limit of 4000 gpm per pump

Tier: 1 Group: 2 K/A: 295013 High Suppression Pool Temp.

AA1.01 Ability to operate and/or monitor the following as they apply to HIGH SUPPRESSION POOL TEMPERATURE : Suppression pool cooling...

Importance Rating:

3.9 10 CFR Part 55:

41.10 10 CFR 55.43.b:

N/A K/A Match:

KA is matched by having the applicant determine a method of increasing cooling to the torus water that is permitted by procedures given a set of plant conditions.

ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 69 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

23 SRO Justification:

N/A Technical

References:

Operations Manual B.03.04-05 Operations Manual B.08.01.03

-05 Proposed references None to be provided:

Learning Objective:

M-8107L-023 LO 9 Cognitive Level:

Higher X Lower _ Question Source:

New _ Modified Bank X Bank _ Question History:

MNGP exam bank 466

Comments:

Monticello NRC Written Exam Page: 70 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM The reactor was operating at rated conditions when an event occurred. Torus level is reported by the BOP operator to be +4.0 feet.

Complete the following statement concerning the current torus water level?

At this torus water level-

A. HPCI operation is not permitted.

B. SBGT cannot be used to vent non

-condensable from the torus airspace.

C. SRV operation could cause SRV tail pipe damage resulting in containment failure.

D. Vacuum Breakers will not function to relieve non-condensable from the torus to the drywell Question 24 Points: 1.0

Monticello NRC Written Exam Page: 71 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

24 Proposed Answer: C DISTRACTOR ANALYSIS A, B, and D are incorrect but plausible variations since each system deals with pressure relief/suppression pool level control. Per C.5.1

-1200, A. Incorrect: HPCI is a concern for lower suppression pool level (not high); if suppression pool level falls to

-3.7 feet, then the HPCI exhaust will uncover but operation can still be permitted under extreme conditions.

B. Incorrect: SBGT can be used to vent the torus at levels up to 11.3 ft.

C. Correct: A torus water level of 3.7 feet corresponds to the Maximum Pressure Suppression Primary Containment Water Level, which bounds both the Pressure Suppression Pressure and the SRV Tail Pipe Level Limit. SRV operation with torus water level above the SRV Tail Pipe Level Limit could damage the SRV discharge lines. This, in turn, could lead to containment failure from direct pressurization and damage to equipment inside the containment from pipe

-whip and jet

-impingement loads. At Monticello, the SRV Tail Pipe Level Limit is bounded by the Maximum Pressure Suppression Primary Containment Water Level for all RPV pressures below approximately 1150 psig D. Incorrect: Vacuum Breakers will operate under high suppression level up to +4.2 feet; above

+4.2 feet the Vacuum Breakers may not function as designed.

Tier: 1 Group: 2 K/A: (295029 High Suppression Pool Wtr Lvl / 5) EK1.01 Knowledge of the operational implications of the following concepts as they apply to HIGH SUPPRESSION POOL WATER LEVEL: (CFR: 41.8 to 41.10) Containment integrity Importance Ratin g: 3.4 10 CFR Part 55:

41.8 to 41.10 10 CFR 55.43.b:

N/A K/A Match:

K/A is matched by testing the applicants' knowledge of the high suppression pool water level's operational impact on the primary containment's structural integrity.

ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 72 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

24 SRO Justification:

N/A Technical

References:

EOP C.5-1200, C.5.1

-1200 Proposed references to be provided:

None Learning Objective:

Cognitive Level:

Higher _ Lower X Question Source:

New _ Modified Bank

_ Bank X Question History: Question 26 from 2010 MNGP ILT NRC Comments:

Monticello NRC Written Exam Page: 73 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM The plant was operating at rated conditions when a transient occurred.

The following conditions are now present:

RWCU area temperature is 175°F HPCI area temperature is 185°F Based on the above indications

An automatic isolation of the __(1)__ system has occurred. The safety function of the associated isolation valves is to __(2)__.

A. (1) HPCI (2) minimize the loss of reactor coolant inventory ONLY B. (1) RWCU (2) minimize the loss of reactor coolant inventory ONLY C. (1) HPCI (2) minimize the loss of reactor coolant inventory AND establish the primary containment boundary D. (1) RWCU (2) minimize the loss of reactor coolant inventory AND establish the primary containment boundary Question 25 Points: 1.0

Monticello NRC Written Exam Page: 74 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

25 Answer: C DISTRACTOR ANALYSIS

A. (1) Correct (2) Incorrect, minimizing the loss of reactor coolant inventory is also a function B. (1) Incorrect, An isolation of the RWCU system is generated when room temperature exceeds 187.5°F (2) Incorrect, minimizing the loss of reactor coolant inventory is also a function C. (1) Correct (2) Correct D. (1) Incorrect, An isolation of the RWCU system is generated when room temperature exceeds 187.5°F (2) Correct Tier: 1 Group: 2 K/A: 295032 High Secondary Containment Area Temperature EK3.03 Knowledge of the reasons for the following responses as they apply to HIGH SECONDARY CONTAINMENT AREA TEMPERATURE : Isolating affected systems...

Importance Rating:

3.8 10 CFR Part 55:

41.5 10 CFR 55.43.b:

N/A K/A Match:

KA is matched by having the applicant determine based on plant conditions the correct PCIS isolation and why the system is required to be isolated.

ANSWER EXPLANATION s QUESTION BACKGROUND

Monticello NRC Written Exam Page: 75 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

25 SRO Justification:

N/A Technical

References:

Ops Man B.05.06

-02 Ops Man B.03.02

-01 Tech Spec Bases, LCO 3.6.1.3

Proposed references None to be provided:

Learning Objective: M-8107L-023 LO 9 Cognitive Level:

Higher _ Lower X Question Source:

New X Modified Bank

_ Bank _ Question History:

Comments:

Monticello NRC Written Exam Page: 76 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Which one of the following choices describes the related systems' responses to an UPSCALE trip of a single Reactor Building Exhaust Plenum radiation monitor?

The trip circuit will-

. 1) isolate the normal Reactor Building ventilation exhaust path

2) initiate operation of the Standby Gas Treatment System

3) close the primary containment purge and ventilation valves

4) NOT alter the related systems' status A. (1) ONLY B. (1) AND (2) ONLY C. (1) AND (2) AND (3)

D. (4) Question 26 Points: 1.0

Monticello NRC Written Exam Page: 77 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

26 Proposed Answer: C DISTRACTOR ANALYSIS A, B, and D are incorrect but plausible variations of the actions of the Reactor Building Ventilation system upon receiving a high radiation (upscale signal). The applicant must first recognize that a single upscale in the Reactor Building exhaust plenum (or the fuel pool monitors) trip will satisfy the trip circuit logic (one upscale or TWO downscale satisfy the circuit)

- thus "D" is plausible since the applicant may believe more than 1 upscale is required. In addition, the applicant must know the actions when the trip circuit is satisfied.

C is correct

In accordance with Ops Manual B.05.11

-02, there are two Reactor Building exhaust vent plenum monitors (RM 452A and RM 452B), and one upscale or two downscale will initiate the following:

a. Reactor Building Ventilation System shutdown

b. Standby Gas Treatment System initiation

c. Primary Containment purge and ventilation valves closure (select Group II Primary Containment valves) Annunciator B 55 (Reactor Building Exhaust High Rad) will alarm when output of either channel exceeds 20 mrem/hr.

ANSWER EXPLANATION

Monticello NRC Written Exam Page: 78 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

26 Tier: 1 Group: 2 K/A: (295034 Secondary Containment Ventilation High Radiation / 9) 2.1.28 Knowledge of the purpose and function of major system components and controls. (CFR: 41.7)

Importance Rating:

4.1 10 CFR Part 55:

41.7 10 CFR 55.43.b:

N/A K/A Match:

K/A is matched by testing the applicants' knowledge of the function of the major components within Secondary Containment Ventilation associated with a high radiation signal.

SRO Justification:

N/A Technical

References:

Ops Manual B.05.11

-01 and -02, and M-8107L-077 (Process Radiation Monitoring and Area Radiation Monitors) Rev. 15 Proposed references to be provided:

None Learning Objective:

2.j of M-8107L-077 (Process Radiation Monitoring and Area Radiation Monitors) Rev. 15 Cognitive Level:

Higher _ Lower X Question Source:

New X Modified Bank

_ Bank _ Question History:

N/A Comments: QUESTION BACKGROUND

Monticello NRC Written Exam Page: 79 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM The plant was operating at rated power when HPCI area water level was rising. The CRS directed entry into C.5-1300 [Secondary Containment Control]. The operating crew was NOT able to isolate the source of the discharge.

Which one of the following completes the statement below?

IAW C.5-1300 if the source of the discharge is from the CST, a __(1)__ is required, when __(2)__ area(s) water level is/are above max safe value(s) .

A. (1) normal reactor shut down (2) one B. (1) normal reactor shut down (2) 2 or more C. (1) SCRAM (2) one D. (1) SCRAM (2) 2 or more Question 27 Points: 1.0

Monticello NRC Written Exam Page: 80 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

27 Answer:

B DISTRACTOR ANALYSIS The CST is not a source of primary water discharging into the reactor building so the operator will not be directed to shut down until 2 or more areas are above max safe values for the same parameter. If the discharge was from a primary system the operator would SCRAM before any one water level reached max safe value IAW C.5

-1300. A. (1) Correct (2) Incorrect B. (1) Correct (2) Correct C. (1) Incorrect (2) Incorrect D. (1) Incorrect (2) Correct Tier: 1 Group: 2 K/A: 295036 Secondary Containment High Sump/Area Water Level

2.4.6 Knowledge

of EOP mitigation strategies.

Importance Rating:

3.7 10 CFR Part 55:

41.10 10 CFR 55.43.b:

N/A K/A Match:

KA is matched by having the applicant determine if the plant conditions require EOP mitigate action in the water levels leg. The required action to mitigate the transient is dependent on the source of discharge to the area and the number of parameters that are exceeded.

QUESTION BACKGROUND ANSWER EXPLANATION s

Monticello NRC Written Exam Page: 81 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

27 SRO Justification:

N/A Technical

References:

Ops Man C.5-1300, Secondary Containment Control Ops Man C.5.1

-1300, Secondary Containment Control Proposed references to be provided:

None Learning Objective:

M-8107L-023 LO 9 Cognitive Level:

Higher _ Lower X Question Source: New X Modified Bank

_ Bank _ Question History:

Comments:

Monticello NRC Written Exam Page: 82 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM A small break LOCA has occurred in the drywell and the following annunciator alarms are observed: 3-B-53 (DRYWELL HI PRESS) 5-B-24 (REACTOR WATER LEVEL HI/LO)

Based only on these valid annunciator alarms , what is the expected status of the RHR system?

A. A LPCI initiation signal is present AND RHR pumps are injecting into the RPV B. A LPCI initiation signal is present but water is NOT injecting into the RPV because the LPCI OUTBOARD injection valves are still closed C. A LPCI initiation signal is present but water is NOT injecting into the RPV because the LPCI INBOARD injection valves are still closed.

D. A LPCI initiation signal is NOT present therefore RHR pumps are NOT injecting water into the RPV. Question 28 Points: 1.0

Monticello NRC Written Exam Page: 83 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

28 Proposed Answer: C DISTRACTOR ANALYSIS A, B, and D are incorrect but plausible variations of a LPCI initiation signal and injection: The applicant must have knowledge of the set-points associated with the listed annunciators and how they correspond to LPCI injection. A LPCI initiation signal AND RPV pressure below 420 psig must be present before the Inboard and/or Outboard Injection valves will open automatically. A LPCI Initiation Signal is present as indicated by Annunciator 3

-B-53 (High DW Pressure). Annunciator 5

-B-24 may be associated with RPV water level being below normal (less than +30"), but since annunciator 3-A-38 (Low-Low Level) is not active, the LPCI Initiation signal on low

-low RPV water level is not present. Annunciator 3

-A-30 (Reactor Low Pressure (420 psig)) is not active, therefore the permissive to open the injection valves is not met and neither LPCI loop will be injecting.

A. Incorrect; A LPCI Injection signal is present, but RPV pressure is above 420 psig as is evident by the absence of annunciator 3

-A-30. The Inboard Injection valves will not be open. B. Incorrect; A LPCI Injection signal is present, but RPV pressure is above 420 psig as is evident by the absence of annunciator 3

-A-30. The Inboard Injection valves will not be open. The Outboard Injection valves are NORMALLY ope

n. C. Correct: A LPCI Injection signal is present, but RPV pressure is above 420 psig as is evident by the absence of annunciator 3

-A-30. The Inboard Injection valves will not be open. The Outboard Injection valves are NORMALLY open.

D. Incorrect; A LPCI Injection signal is present as evidenced by active Annunciator 3

-B-53 (High DW Pressure

) ANSWER EXPLANATION

Monticello NRC Written Exam Page: 84 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

28 Tier: 1 Group: 2 K/A: (203000 RHR/LPCI: Injection Mode) 2.4.31 Knowledge of annunciator alarms, indications, or response procedures. (CFR: 41.10 / 45.3)

Importance Rating:

4.2 10 CFR Part 55:

41.10 / 45.3

10 CFR 55.43.b:

N/A K/A Match:

K/A is matched by testing the applicants' knowledge of the annunciator alarms, and their corresponding setpoints, associated with the RHR/LPCI injection mode SRO Justification:

N/A Technical

References:

Ops Man B.03.04

-01 and -03, and M-8107L-023 (RHR System) Rev. 20 Proposed references to be provided:

None Learning Objective:

7 of M-8107L-023 (RHR System) Rev. 20 Cognitive Level:

Higher _ Lower X Question Source:

New _ Modified Bank X Bank _ Question History:

Question 502 from BANK and Question 56 of 2003 MNGP ILT

- modified question stem with the replacement of metric with annunciators in order to match K/A and changed a distractor Comments: This question has ties to Question 502 in the exam bank, but the question stem has been modified significantly and 1 distractor has been changed so it likely qualifies as a significantly modified BANK question QUESTION BACKGROUND

Monticello NRC Written Exam Page: 85 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM The plant was operating in Mode 2 with a startup in progress. A reactor coolant leak develop ed in the Reactor Vessel Bottom Head and following parameters were recorded at the indicated times

TIME Reactor Level Reactor Pressure Drywell pressure 00:00:00 +30 inches 900 psig 0.5 psig 00:05:00 +8 inches 850 psig 0.7 psig 00:10:00 -15 inches 750 psig 1.1 psig 00:20:00 -48 inches 600 psig 1.9 psig 00:30:00 +30 inches 400 psig 2.4 psig Based on the above timeline, which of the following is correct?

A. ONLY a Partial Group 2 Isolation signal has occurred by 00:05:00. B. All Main Steam Isolation Valves are closed at 00:10:00.

C. Division 1 RHR was selected for LPCI Loop injection path by 00:20:00. D. Division 2 RHR LPCI injection valves have received an open signal by 00:30:00.

Question 29 Points: 1.0

Monticello NRC Written Exam Page: 86 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

29 ANSWER D DISTRACTOR ANALYSIS A. Incorrect: A Full Group 2 Isolation would occur at this time.

B. Incorrect: With the plant in Mode 2 the Mode Switch would be in STARTUP. Therefore the <840 psig in RUN Group 1 isolation will be bypassed.

C. Incorrect: Plausible as LPCI loop selection takes place at

-47" and 1.84 psig, Division 2 is the default loop for LPCI injection and since the leak is in the bottom head, Division 1 would NOT be selected.

D. Correct: LPCI loop selection takes place at

-47" and 1.84 psig, division 2 is the default loop for LPCI injection and since RCS pressure is <420 psig and drywell pressure is >1.84 psig the division 2 RHR injection valves will be demanded open.

Tier: 2 Group: 1 K/A: 203000 RHR/LPCI: Injection Mode A4.08 Ability to manually operate and/or monitor in the control room: Reactor pressure Importance Rating:

4.3 10 CFR Part 55: 41.7 10 CFR 55.43.b:

N/A K/A Match:

The applicant is given parameters that would be monitored in the control room that affect the RHR system lineup to LPCI. Based on the plant parameters LPCI injection via the Division 2 RHR system would occur since RCS pressure has dropped low enough to allow the injection valves to open.

SRO Justification:

N/A ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 87 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

29 Technical

References:

B.03.04-01, B.03.04-02 Proposed references to be provided: None Learning Objective:

M-81 07L-023, RHR System, 7. Describe the RHR system operation, controls, automatic functions, alarms, setpoints, and or interlocks.

Cognitive Level:

Higher X Lower _ Question Source:

New _ Modified Bank X Bank _ Question History:

Significantly modified from MNGP NRC Exam 2015, Q 11 Comments:

Monticello NRC Written Exam Page: 88 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM The plant is in MODE 4 with the 12 RHR Pump is operating in a Normal Shutdown Cooling Mode.

The desired RCS temperature control band is 120

-140 F. Neither Reactor Recirculation pump is in operation.

The CRD and RWCU systems are shutdown.

12 RHR Pump flow is 3900 gpm 12 RHRSW Pump flow is 2200 gpm 12 RHR HX dP is 50 psid Time RR Loop A Suction Temperature RR Loop B Suction Temperature 12 RHR HX Inlet Temperature RWCU Inlet Temperature 0900 141 139 140 139 0915 140 139 138 140 0930 140 138 137 139 0945 139 139 135 139 1000 138 138 134 140 Give the above information, what is the RCS Heatup/Cooldown rate.

A. Cooling down at 3F/hr B. Cooling down at 1F/hr C. Cooling down at 6F/hr D. Heating up at 1F/hr Question 30 Points: 1.0

Monticello NRC Written Exam Page: 89 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

3 0 Proposed Answer: C DISTRACTOR ANALYSIS A, B, and D are incorrect but plausible variations of actions in order to decrease the recirculation loop temperature at a slower rate (i.e., decrease cooldown rate).

A. Incorrect: There may be some back

-flow through the 11 RR Loop, but the temperature of the loop will not be representative of the RCS temperature.

B. Incorrect:

With the 12 RR Loop suction or discharge valve shut there will be no flow through the loop and the indicated temperature will not be representative of the RCS temperature.

C. Correct: The coolant flowing throught the in

-service RHR train will be representative of the RCS temperature.

D. Incorrect:

With the RWCU system shutdown there will be no flow through the system and the indicated temperatue will not be representative of the RCS temperature

.

Tier: 1 Group: 2 K/A: (205000 Shutdown Cooling) K1.03 Knowledge of the physical connections and/or cause

-effect relationships between SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) and the following:

Recirculation loop temperature

Importance Rating:

3.4 10 CFR Part 55:

CFR: 41.2 to 41.9 / 45.7 to 45.8 10 CFR 55.43.b:

N/A K/A Match:

K/A is matched by testing the applicants' knowledge of the cause

-effect relationships between the SDC system and the recirculation loop temperature, specifically focusing on how altering SDC components effect recirculation loop temperature SRO Justification:

N/A Answer Explanation Question Background

Monticello NRC Written Exam Page: 90 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

30 Technical

References:

Ops Man B.03.04

-01 and -02, Startup Procedure B.03.04

-05.D.2, and M

-8107L-023 (RHR System) Rev. 20 Proposed references to be provided: None Learning Objective:

7 of M-8107L-023 (RHR System) Rev. 20

Cognitive Level:

Higher X Lower _ Question Source:

New _ Modified Bank X Bank _ Question History:

Question 29 of 2010 MNGP ILT

- significantly modified to match K/A Comments: This question has ties to Question 29 from the 2010 MNGP ILT, but it has been modified significantly; thus it may qualify as a NEW question.

Also, the question could be potentially be strengthened by including more information in the question stem (i.e., including a list of times and temperatures, like what is done in Question 514 in the Exam BANK

- see the comments in the top of this document).

Monticello NRC Written Exam Page: 91 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM The reactor was at 100% power and offsite power was in a normal lineup when a loss of Division 2, 125 VDC occurred.

Which of the following statements correctly describes the effect this will have on the plant?

A. The 12 EDG will NOT be able to start automatically.

B. The 12 EDG will be able to automatically start and flash the field.

C. HPCI will NOT be able to start automatically.

D. HPCI Steam Line Isolation Valve [MO

-2034] is unable to be manually closed from the control room

. Question 31 Points: 1.0

Monticello NRC Written Exam Page: 92 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

31 Answer: C DISTRACTOR ANALYSIS The EDG will auto start from the fast start relay for the 11 EDG which is powered from division 1 125 VDC. The field flash circuitry, however, is not cross connected and would require jumpers to accomplish this function. Division 2, 125 VDC powers D21, Circuit 15 (via C39) supplies HPCI logic power (for initiation, trip, and Group IV isolation).

A. Incorrect, see above. B. Incorrect, see above.

C. Correct, see above.

D. Incorrect, Control power for the only AC

-powered HPCI valve (MO

-2034) is 120 Vac supplied directly from the control power transformer in that MCC breaker (MCC

-143). Tier: 1 Group: 1 K/A: 206000 HPCI K2.03 Knowledge of electrical power supplies to the following: Initiation logic: BWR

-2,3,4 Importance Rating:

2.8 10 CFR Part 55:

41.7 10 CFR 55.43.b:

N/A K/A Match:

The power supply to the initiation logic is lost, the applicant is asked what effect this will have on the plant.

SRO Justification:

N/A Technical

References:

Ops Man B.03.02

-02 NX-8292012-5 ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 93 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

31 Proposed references to be provided

None Learning Objective:

M-8107L-002 LO 8e Cognitive Level:

Higher _ Lower X Question Source:

New _ Modified Bank X Bank _ Question History:

Significantly modified MNGP bank question 796 (M8107L-042 4) Comments:

Monticello NRC Written Exam Page: 94 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM The plant is in MODE 1 when a Small Break LOCA occurs. The following is observed:

Bus 15 is locked

-out HPCI tripped and is not available ADS has automatically initiated RPV pressure is 200 psig and lowering CS Pump B is operating and injecting into the RPV Division 2 RHR pumps are running and aligned for torus cooling RPV water level is

-55 inches and rising slowly

Given the stated conditions, complete the following statement that describes the effect on the ADS System if off

-site power is lost to Bus 16:

Automatic Depressurization of the Reactor...

A. continues even if EDG 12 fails to start.

B. will cease, then re

-initiate immediately upon restart of the Core Spray pump following restoration of power to Bus 16 from EDG 12.

C. will cease, then re-initiate 107 seconds after a Core Spray pump is restarted following restoration of power to Bus 16 from EDG 12.

D. will cease, then after power is restored to Bus 16 from EDG 12, BOTH inhibit switches A and B must be placed in INHIBIT and back to AUTO to re

-establish depressurization Question 32 Points: 1.0

Monticello NRC Written Exam Page: 95 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

32 Proposed Answer: C DISTRACTOR ANALYSIS A. Incorrect: ADS will cease since AC interlock logic (K10A and K12A) will de

-energize breaking the seal-in (no pumps running).

B. Incorrect: ADS will cease since AC interlock logic (K10A and K12A) will de

-energized breaking the seal-in (no pumps running), but the timer will reset and delay initiation for 107 seconds following restart of the CS pump.

C. Correct: When the RHR and CS pumps trip/lose power, relays K10A and K12A are de

-energized, which open up the K10A and K12A contacts to de

-energize the 107 second timer, closing the valves. If the pumps are restarted, contacts K10A and K12A close to start the107 second timer again.

D. Incorrec t: plausible interpretations of how INHIBIT logic works; resetting using inhibit switch is unnecessary.

Tier: 2 Group: 1 K/A: (209001 LPCS) K3.02 Knowledge of the effect that a loss or malfunction of the LOW PRESSURE CORE SPRAY SYSTEM will have on following: (CFR: 41.7 / 45.4) ADS logic Importance Rating:

3.8 10 CFR Part 55:

41.7 10 CFR 55.43.b:

N/A K/A Match:

K/A is matched by testing the applicants' knowledge of what effect the loss of the CS pumps will have on ADS logic SRO Justification:

N/A QUESTION BACKGROUND ANSWER EXPLANATION

Monticello NRC Written Exam Page: 96 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

32 Technical

References:

Ops Man B.03.03-01, B.03.03

-06 Figure 5, M

-8107L-025 (Reactor Pressure Relief) Rev. 23, M

-8107L-005 (Core Spray) Rev. 18 Proposed references to be provided:

None Learning Objective:

7 from M-8107L-025 (Reactor Pressure Relief) Rev. 23

Cognitive Level:

Higher X Lower _ Question Source:

New _ Modified Bank X Bank _ Question History:

Question 43 of 2015 MNGP ILT NRC Written Exam Comments: Potential cueing concern in distractors, as proposed correct answer is the only option that states ADS will continue.

Monticello NRC Written Exam Page: 97 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Due to the failure of the RPS to complete a reactor shutdown, the Unit Supervisor has directed the Reactor Operator to manually initiate Standby Liquid Control System [SBLC]. The Reactor operator has unlocked SBLC System Selector Switch and turned the handle to SYS 1.

Which One of the following completes the statements below?

Forced Circulation is __(1)__ to ensure adequate dispersion of the solution into the core.

RWCU pumps __(2)__ receive an automatic trip signal A. (1) required (2) will B. (1) required (2) will NOT C. (1) NOT required (2) will D. (1) NOT required (2) will NOT Question 33 Points: 1.0

Monticello NRC Written Exam Page: 98 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

33 Answer C DISTRACTOR ANALYSIS A. (1) Incorrect, without a recirculation pump running, natural circulation provides adequate dispersion of the solution into the core (2) Correct B. (1) Incorrect, without a recirculation pump running, natural circulation provides adequate dispersion of the solution into the core (2) Incorrect, RWCU pumps trip on SBLC system actuation unless the isolation interlocks are bypassed per the EOP C. Correct D. (1) Correct (2) Incorrect, RWCU pumps trip on SBLC system actuation unless the isolation interlocks are bypassed per the EOP Tier: 2 Group: 1 K/A: 211000 SLC K4.05 Knowledge of STANDBY LIQUID CONTROL SYSTEM design feature(s) and/or interlocks which provide for the following: Dispersal of boron upon injection into the vessel Importance Rating:

3.4 10 CFR Part 55:

41.7 10 CFR 55.43.b:

N/A K/A Match:

The SBLC system is designed to shutdown the reactor from all conditions at any time in core life, normal mixing via recirculation pumps is not required to ensure borated solution will disperse into the core region, natural circulation is sufficient. The SBLC system provides enough boron solution to meet the shutdown requirements with normal water level including water volume in the RHR shutdown cooling piping and the recirculation loops. Isolation of RWCU and tripping of the pumps is a start interlock with the actuation of SBLC to ensure borated solution is contained within the RCS volume as described.

ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 99 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

33 SRO Justification:

N/A Technical

References:

Ops Man B.03.05

-05 Proposed references to be provided:

None Learning Objective:

Cognitive Level:

Higher X Lower _ Question Source:

New X Modified Bank

_ Bank _ Question History:

New Comments:

Monticello NRC Written Exam Page: 100 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM The reactor was operating at rated conditions when the following occurred:

BOTH manual scram push buttons were depressed then released.

Reactor pressure is 750 psig and slowly decreasing.

The OATC has placed the SCRAM DISCHARGE VOLUME HIGH WATER LEVEL BYPASS switches in BYPASS.

Given the above conditions, which of the following mode switch positions will allow the scram to be reset?

A. SHUTDOWN ONLY B. SHUTDOWN OR REFUEL ONLY C. SHUTDOWN OR START & HOT STBY ONLY D. SHUTDOWN OR REFUEL OR START & HOT STBY ONLY Question 34 Points: 1.0

Monticello NRC Written Exam Page: 101 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

34 Proposed Answer: B DISTRACTOR ANALYSIS A, C, and D are incorrect but plausible interpretations of this RPS logic arrangement: Per the RPS Logic Diagram, although Low Condenser Vacuum / MSIV Closure scram signal can be bypassed in Shutdown OR Refuel OR Start & Hot Stby, Start & Hot Stby is NOT a condition for BYPASS of SDV High Level trip, thus the MS can only be switched to Shutdown OR Refuel to clear ALL the parameters.

B is correct

Reset is possible ONLY if ALL the conditions that caused the trip or scram have been cleared. Per the RPS logic diagram, this can only be accomplished for this RPS logic arrangement if the mode switch is in either SHUTDOWN or REFUEL, Reactor Pressure is <600 psig, AND the SDV high level scram signal key switch is placed in BYPASS (key switch only works with BOTH RPS buses powered) (the latter two conditions are said to apply). In these conditions relays are energized which bypasses the low condenser vacuum, MSIV closure, and SDV Level inputs to RPS. Tier: 2 Group: 1 K/A: (212000 RPS) K5.02 Knowledge of the operational implications of the following concepts as they apply to REACTOR PROTECTION SYSTEM: (CFR: 41.5 / 45.3) Specific Logic arrangements Importance Rating:

3.3 10 CFR Part 55:

41.5 10 CFR 55.43.b

N/A K/A Match:

K/A is matched by testing the applicants' knowledge of the logic arrangements of the Reactor Protection System ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 102 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

3 4 SRO Justification:

N/A Technical

References:

Ops Man B.05.06-06, Figure 6, NX

-7834-67-09, (-10), (-11), M-8107L-072 (Reactor Protection System) Rev. 16 Proposed references to be provided:

NONE Learning Objective:

6 from M-8107L-072 (Reactor Protection System) Rev. 16 Cognitive Level:

Higher X Lower _ Question Source:

New _ Modified Bank X Bank _ Question History: Question 35 of 2009 MNGP Audit Written Exam Comments:

Monticello NRC Written Exam Page: 103 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM IRM 15 is on range 3 reading 110, subsequently the high voltage power supply fails low.

Which IRM trip unit(s) would be actuated by this condition?

1) IRM HI HI

2) IRM INOP 3) IRM DOWNSCALE A. 1 only B. 3 only C. 1 & 2 only D. 2 & 3 only Question 35 Points: 1.0

Monticello NRC Written Exam Page: 104 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

35 Answer D DISTRACTOR ANALYSIS A. Incorrect, for IRM HI HI the output of the detector would have to be 119.375 units or more on 0 to 125 unit, a failure of the high voltage supply would cause the output to lower, this is the opposite effect of the malfunction presented B. Incorrect, the IRM downscale is expected for this condition but so is the IRM INOP as presented in answer D.

C. Incorrect, IRM INOP is expected but the IRM HI HI is incorrect as discussed in A.

D. Correct, IRM INOP and IRM DOWNSCALE are expected for High voltage power supply failure Tier: 2 Group: 1 K/A: 215003 IRM K6.04 Knowledge of the effect that a loss or malfunction of the following will have on the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM : Detectors

Importance Rating:

3.0 10 CFR Part 55:

41.7 10 CFR 55.43.b

N/A K/A Match:

The applicant is asked to determine the effect on IRM system (trip units) when the detector fails due to a loss of high voltage to the detector SRO Justification:

N/A Technical

References:

ARP 5-A-5 ARP 5-A-29 ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 105 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

35 Proposed references to be provided:

None Learning Objective:

M8107L-064, LO 6 Cognitive Level:

Higher _ Lower X Question Source:

New X Modified Bank

_ Bank _ Question History:

Comments:

Monticello NRC Written Exam Page: 106 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM A reactor startup is in progress with the Source Range Monitors (SRMs) and Intermediate Range Monitors (IRMs) in service as described below.

The Rod Worth Minimizer is in service.

NO SRMs or IRMs are BYPASSED All IRMs are downscale on Range 1 SRM Drives shows NEITHER "IN" NOR "OUT" illuminated for SRM CH 22 and 23 SRM Drives shows "IN" illuminated for SRM CH 21 and 24 SRM CH 21 reads 8.9 x 10 4 cps and a 29 second period SRM CH 22 reads 2.9 x 10 2 cps and a 10 second period SRM CH 23 reads 9.4 x 10 1 cps and a 34 second period SRM CH 24 reads 6.8 x 10 0 cps and a 55 second period BYPASSING which of the following will remove the Control Rod withdraw block?

A. SRM CH 21 B. SRM CH 22 C. SRM CH 23 D. SRM CH 24 Question 36 Points: 1.0

Monticello NRC Written Exam Page: 107 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

36 Proposed Answer: C DISTRACTOR ANALYSIS

A. Incorrect: plausible to think the applicant doesn't know the UPSCALE setpoint.

B. Incorrect: plausible to think the applicant doesn't know the Retract Not Permitted setpoint. Also, plausible the applicant thinks a particular period setpoint causes a control rod withdraw block C. Correct: The following SRM trips initiate Control Rod Withdrawal Blocks in the Refuel or Startup Modes/ These rod blocks hold true for each SRM unless it is bypassed. Only one (1) SRM can be bypassed.

These are:

UPSCALE (>9.07x10 4 cps (Nominal 1x10 5 cps)) (bypassed on IRM Range 8 or above) (5

-A-12), -A-4), RETRACT NOT PERMITTED (Detector Not Full In and Channel is <100 cps) (bypassed on IRM Range 3 or above) (5

-A-28) Thus, since SRM CH 23 reads < 100 cps and is NOT FULL IN, a withdrawal rod block is in place for this SRM D. Incorrect: plausible to think the applicant doesn't know the DOWNSCALE setpoint Tier: 2 Group: 1 K/A: (215004 Source Range Monitor) A1.05 Ability to predict and/or monitor changes in parameters associated with operating the SOURCE RANGE MONITOR (SRM) SYSTEM controls including: (CFR: 41.5 / 45.5) SCRAM, rod block, and period alarm trip setpoints Importance Rating:

3.6 10 CFR Part 55:

41.5 10 CFR 55.43.b:

N/A ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 108 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

36 K/A Match:

K/A is matched by testing the applicants' ability to predict what changes to the SRM system controls would relieve a rod block SRO Justification:

N/A Technical

References:

Ops Man B.05.01.01

-03, M-8107L-054 (Source Range Monitors) Rev. 10 Proposed references to be provided:

None Learning Objective:

6 from M-8107L-054 (Source Range Monitors) Rev. 10

Cognitive Level: Higher X Lower _ Question Source:

New X Modified Bank

_ Bank _ Question History:

N/A Comments:

Monticello NRC Written Exam Page: 109 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM A reactor startup is in progress with all IRMs on range 6. The following annunciators are in alarm:

ROD WITHDRAW BLOCK APRM FLOW BIAS OFF NORMAL Based on the above conditions, which one of the following completes the statements below

?

A condition resulting in a(an) __(1)__ is preventing control rods from being withdrawn.

Bypassing the associated RBM/APRM channel __(2)__ allow control rods to be withdrawn.

A. (1) RBM Flow Comparison Alarm (2) WILL B. (1) RBM Flow Comparison Alarm (2) WILL NOT C. (1) APRM Flow Upscale Alarm (2) WILL D. (1) APRM Flow Upscale Alarm (2) WILL NOT Question 37 Points: 1.0

Monticello NRC Written Exam Page: 110 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

37 Answer D DISTRACTOR ANALYSIS With IRMs greater than range 2 the SRM DOWNSCALE rod block is bypassed, the APRM Flow UPSCALE will cause a rod block for the given conditions. A single trip input from a given unbypassed APRM generates a "half

-vote" in each of the four voters; no 1/2 SCRAM occurs.

1/2 SCRAM is a plausible condition as a loss of either RPS A/B would result in this condition A. (1) Incorrect (2) Incorrect B. (1) Incorrect (2) Correct C. (1) Correct (2) Incorrect D. (1) Correct (2) Correct Tier: 2 Group: 1 K/A: 215005 APRM / LPRM A2.06 Ability to (a) predict the impacts of the following on the AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Recirculation flow channels upscale

Importance Rating:

3.4 10 CFR Part 55:

41.5 10 CFR 55.43.b:

N/A ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 111 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

37 K/A Match:

The applicant is given indications of a recirculation flow channel upscale failure and asked to evaluate the effect on interrelated systems. The condition is bypassed by the ARP which mitigates a full scram if another input is received.

SRO Justification:

N/A Technical

References:

C.6-005-A-30, C.6-005-A-4, C.6-005-A-22 B.05.01.02

-01 , B.05.05-02 Proposed references to be provided:

None Learning Objective

M-8107L-066 LO 5a, 7, 8 Cognitive Level:

Higher X Lower _ Question Source:

New X Modified Bank

_ Bank _ Question History:

Comments:

Monticello NRC Written Exam Page: 112 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM The plant is operating in Mode 1 when a loss of #11 Recirc pump occurs. ALL APRMs are adjusted for single loop operation (SLO). Given the following:

Operating BELOW the MELLA+ region APRM 2/4 ODA indicates Total Recirc flow is 41%

Which one on the following approximates the current STP SCRAM Setpoint?

A. 72.2% B. 78.2% C. 81.6% D. 90.2% Question 38 Points: 1.0

Monticello NRC Written Exam Page: 113 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

38 Proposed Answer: B DISTRACTOR ANALYSIS A. Incorrect: This number represents the APRM STP UPSCALE Alarm/Rod Block single loop operation (SLO) flow

-biased setpoint using the equation 0.55W+49.6% for 41% flow. (55*0.41)+49.6=72.15%

B. Correct: With one recirculation pump running the single loop equation (SLO) must be used to determine the STP Flow Biased setpoints. For the UPSCALE TRIP/SCRAM setpoint this equation is 0.55W+55.6%. W is equal to percent total recirc flow which in this case is 41%. (55*0.41)+55.6 = 78.15%.

C. Incorrect: This number represents the OLD APRM STP UPSCALE TRIP/SCRAM SLO flow biased setpoint. According to the RPS (1) Diagram (Big Notes) dated 03/20/2012 shown in M

-8107L-072 (Reactor Protection System), Rev. 16, the old equation was 0.66(W

-7.6) +59.6 (SLO). (66*(0.41

-0.076))+59.6=81.64%

D. Incorrect: This number represents the APRM STP UPSCALE TRIP/SCRAM Two Loop Operation (TLO) flow

-biased setpoint using the equation 0.61W+65.2% for 41% flow. (61*0.41)+65.2=90.21%

Tier: 2 Group: 1 K/A: (215005 APRM / LPRM) A1.04 Ability to predict and/or monitor changes in parameters associated with operating the AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM controls including: (CFR: 41.5 / 45.5) SCRAM and rod block trip setpoints Importance Rating:

4.1 10 CFR Part 55: 41.5 10 CFR 55.43.b

N/A K/A Match:

K/A is matched by testing the applicants' ability to predict how the current conditions will affect the APRM SCRAM setpoints SRO Justification:

N/A ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 114 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

38 Technical

References:

Ops Man ARP 5-A-22, B.05.01.02, B.05.06

-02, M-8107L-066 (Power Range Neutron Monitoring System) Rev. 10, M

-8107L-072 (Reactor Protection System), Rev. 16 Proposed references to be provided:

None Learning Objective:

7 from M-8107L-066 (Power Range Neutron Monitoring System) Rev. 10 Cognitive Level:

Higher X Lower _ Question Source:

New _ Modified Bank X Bank _ Question History:

Question 1 of 2010 MNGP ILT NRC Written Exam, and Question 34 of 2013 MNGP ILT NRC Written Exam Comments:

Monticello NRC Written Exam Page: 115 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM The plant was operating at rated conditions with HPCI out of service when a Group I Isolation Occurred. Given the following:

RCIC received an auto initiation signal on RPV Low

-Low Level 5 minutes later:

The RCIC pump flow signal input to the flow controller failed HIGH Assuming that no operator action has been, or will be taken, complete the following statement describing the RCIC system response.

The RCIC turbine speed will....

A. remain relatively constant B. decrease to approximately 2000 rpm C. increase to approximately 4500 rpm and the turbine will subsequently trip on high RPV water level D. increase until the mechanical overspeed trips the turbine Question 39 Points: 1.0

Monticello NRC Written Exam Page: 116 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

39 ANSWER B DISTRACTOR ANALYSIS In automatic flow control mode, the RCIC system flow controller compares the pump flow with the controller

-setpoint and generates a signal proportional to the difference. Controller output of 4 mA to 20 mA corresponds to turbine speeds of 2000 rpm to 4500 rpm, respectively. In this condition, the RCIC turbine speed would decrease due to the high flow signal and continue to operate at 2000 rpm. The mechanical overspeed would not be reached (5625 RPM). High water level would not be reached because the RCIC turbine is operating at minimum speed A. Incorrect, plausible if the applicant believes the controller is normally in manual B. Correct C. Incorrect, this would occur if the signal failed low D. Incorrect, rpm is limited to 4500 by the governor, which did not fail. Tier: 2 Group: 1 K/A: 217000 RCIC A3.04 Ability to monitor automatic operations of the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) including: System flow Importance Rating:

3.6 10 CFR Part 55:

41.7 10 CFR 55.43.b: N/A K/A Match:

The applicant is asked to evaluate how the RCIC system responds to a failure of the flow signal to the controller.

SRO Justification:

N/A ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 117 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

39 Technical

References:

B.02.03-01, B.02.03

-02 Proposed references None to be provided:

Learning Objective:

M-8107L-003, Rev. 18, learning objective 7.

Cognitive Level:

Higher X Lower _ Question Source:

New _ Modified Bank X Bank _ Question History:

ILT Bank - 2013 NRC Exam, question 38 Comments:

Monticello NRC Written Exam Page: 118 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM The plant is operating at 80% power and a RCIC Full Flow Test is being conducted with the following valve line

-up: MO-2075 (RCIC STEAM LINE ISOLATION INBOARD)

OPEN MO-2076 (RCIC STEAM LINE ISOLATION OUTBOARD)

OPEN MO-2106 (RCIC PUMP DISCHARGE OUTBOARD)

OPEN MO-2107 (RCIC PUMP DISCHARGE INBOARD)

CLOSED MO-2110 (RCIC TEST FLOW ISOLATION)

OPEN MO-3502 (RCIC TEST RETURN FLOW)

OPEN During performance of the RCIC Full Flow test, a complete loss of the D

-31 (Division I 125/250 VDC Distribution Panel), coincident with a loss of Feedwater

, occurs. Which one of the following describes: (1) the impact that the loss of D31 will have on RCIC operation; and (2) the operator action that can be taken to mitigate the impact?

A. (1) MO-2110 and MO

-3502 will automatically close and MO

-2107 will automatically open to provide injection into the RPV; RCIC Flow Controller output will fail to minimum.

(2) Place the RCIC Flow Controller in MANUAL and adjust speed as necessary to control flow in order to maintain RPV level in the required band.

B. (1) The RCIC system will continue to operate in the full

-flow test lineup, RCIC injection to the RPV CANNOT be established, but the system may be operated in the full

-flow test lineup for pressure control; RCIC flow control is unaffected.

(2) Monitor RPV pressure and adjust the flow controller output as necessary to control pressure.

C. (1) The RCIC system will continue to operate in the full

-flow test lineup; RCIC flow control is unaffected.

(2) Establish injection into the RPV by dispatching one or more equipment operators to manually close MO

-2110 and MO

-3502, then manually open MO

-2107. D. (1) The RCIC turbine will trip as a direct result of the loss of DC power.

(2) Dispatch one or more equipment operators to locally isolate the discharge flow

-path by manual closure of MO

-2110 and MO

-3502. Question 40 Points: 1.0

Monticello NRC Written Exam Page: 119 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

40 Proposed Answer: C DISTRACTOR ANALYSIS A, B, and D are incorrect: plausible but incorrect interpretations of the RCIC system with loss of DC power: it is plausible that the applicant doesn't know (1) D

-31 Division I 125/250 VDC Distribution Panel powers RCIC; (2); RCIC will NOT auto initiate on loss of FW (3) that the DC

-powered valves remain "as is" due to loss of DC; or (4) what the appropriate next step to take is in C.4

-B.09.09.A (LOSS OF A 250 VDC BUS).

C is correct: Abnormal Procedure C.4

-B.09.09.A shall be entered when D31 is lost and since RCIC is supplied by MCC D311 via D31, the DC valves remain "as is" in the full flow test line

-up due to loss of power.

Tier: 2 Group: 1 K/A: (217000 RCIC) A2.05 Ability to (a) predict the impacts of the following on the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: (CFR: 41.5 / 45.6) D.C. power loss Importance Rating:

3.3 10 CFR Part 55:

41.5 10 CFR 55.43.b:

N/A K/A Match:

K/A is matched by testing the applicants' ability to predict the impact a loss of D.C. power will have on the RCIC system and based on those predictions use procedures to mitigate the consequences of the loss of D.C. power

SRO Justification:

N/A Technical

References:

Ops Man B.02.03-01 and -05, C.4-B.09.09.A, NH

-36251, NH-36252, M-8107L-003 (RCIC) Rev. 18, M

-8107L-041 (Station Battery Systems) Rev. 14 ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 120 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

40 Proposed references to be provided:

None Learning Objective:

8.g from M

-8107L-003 (RCIC) Rev. 18 Cognitive Level:

Higher X Lower _ Question Source:

New _ Modified Bank X Bank _ Question History:

N/A Comments: Although the base of this question comes from Question 69 in the Exam BANK, it has been significantly modified.

Monticello NRC Written Exam Page: 121 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM The plant was operating at 100% power when an LOCA occurred with the following timeline of indications:

TIME Drywell pressure Reactor Level 02:00 0.5 psig 30 inches 02:10 1.9 psig -20 inches 02:20 3.5 psig -60 inches 02:30 5.5 psig -80 inches 02:40 6.5 psig -50 inches 02:50 7.0 psig -40 inches Which ONE of the following completes the statements below? The MINIMUM operator action(s) required to reset and close the ADS SRVs is to take __(1)__ to INHIBIT and then back to AUTO; and given the above time line, the EARLIEST this can occur without reinitiating the ADS initiation logic is __(2)__.

A. (1) EITHER the A or B INHIBIT switch (2) 02:40 B. (1) EITHER the A or B INHIBIT switch (2) 02:50 C. (1) BOTH the A and B INHIBIT switches (2) 02:40 D. (1) BOTH the A and B INHIBIT switches (2) 02:50 Question 41 Points: 1.0

Monticello NRC Written Exam Page: 122 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

41 Answer: D DISTRACTOR ANALYSIS A. (1) Incorrect, Either channel is capable of actuating automatic blowdown, but both must be reset to close the ADS SRVs (2) Incorrect, the low

-low level signal is still present so the ADS initiation timer would start B. (1) Incorrect, Either channel is capable of actuating automatic blowdown, but both must be reset to close the ADS SRVs (2) Correct, the low

-low level signal would be cleared C. (1) Correct, Both channels must be reset for the ADS SRVs to close (2) Incorrect, the low

-low level signal is still present so the ADS initiation timer would start D. (1) Correct, Both channels must be reset for the ADS SRVs to close (2) Correct, the low

-low level signal would be cleared Tier: 2 Group: 1 K/A: 218000 ADS A4.03 Ability to manually operate and/or monitor in the control room:

ADS logic reset Importance Rating:

4.2 10 CFR Part 55:

55.41.7 10 CFR 55.43.b:

N/A K/A Match:

KA is matched by having the applicant determine the minimum action required to reset the ADS logic which results in the closure of ADS SRVs that would be aligned to auto, and to determine that the initiating signal of low

-low reactor water level must be cleared.

SRO Justification:

N/A ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 123 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

41 Technical

References:

OPS MAN B.03.03-01 OPS MAN B.03.03

-05 Proposed references to be provided:

None Learning Objective:

M-8107L-005 LO 7 Cognitive Level:

Higher X Lower _ Question Source:

New X Modified Bank

_ Bank _ Question History:

New Comments:

Monticello NRC Written Exam Page: 124 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Complete the following statement:

The purpose of the Primary Containment Isolation System (PCIS) is to isolate the process lines that penetrate the Primary Containment, thus preventing the release of radioactive materials, from a postulated reactor accident, in excess of that which would result in a _________________

.

A. whole body dose of 25 Rem to an individual located at the exclusion area boundary the postulated duration of the accident.

B. whole body dose of 25 Rem to an individual located at the exclusion area boundary for two hours from the onset of the accident.

C. maximum whole body dose rate of 25 Rem/hour to an individual located at the exclusion area boundary from the onset of the accident.

D. maximum whole body dose rate of 25 Rem/hour to an individual located at the exclusion area boundary for two hours from the onset of the accident.

Question 42 Points: 1.0

Monticello NRC Written Exam Page: 125 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

42 Proposed Answer: B DISTRACTOR ANALYSIS A. is correct: The purpose of the PCIS is to prevent the release of radioactive materials in excess of 10CFR50.67 (Accident Source Term), which is 25 rem within a 2

-hour period during an accident.

B. Is incorrect: plausible interpretations of the purpose of the PCIS: 10CFR20.1301 applies to dose limits for individual members of the public due to licensed operations (not accidents), which is 100 mrem in a year C. Is incorrect: 10CFR50.46 applies to acceptance criteria for emergency core cooling systems (ECCS) for light

-water nuclear power reactors, which is to provide adequate cooling to the fuel. D. Is incorrect: 10CFR50.67 applies to the Accident Source Term for PCIS, not ECCS Tier: 2 Group: 1 K/A: (223002 PCIS/Nuclear Steam Supply Shutoff) 2.1.27 Knowledge of system purpose and/or function Importance Rating:

3.9 10 CFR Part 55:

41.5 10 CFR 55.43.b:

N/A K/A Match:

K/A is matched by testing the applicants' knowledge of the PCIS purpose SRO Justification:

N/A Technical

References:

Ops Man B.05.06-01, M-8107L-070 (Primary Containment Isolation System) Rev. 12 Proposed references to be provided:

None ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 126 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

42 Learning Objective:

1 and 11 from M

-8107L-070 (Primary Containment Isolation System) Rev. 12 Cognitive Level:

Higher _ Lower X Question Source: New X Modified Bank

_ Bank _ Question History:

N/A Comments:

Monticello NRC Written Exam Page: 127 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Given the following conditions:

A loss of Reactor feed has occurred.

RPV water level lowered to

-49 inches and is recovering with HPCI and RCIC.

Reactor pressure is 900 psig.

The CRS has directed you to verify expected initiations and isolations.

Which ONE of the following valves is out of position for the given plant conditions AND should be repositioned?

A. MO-2013 (RHR DIV 2 LPCI INJ OTBD) is OPEN. B. MO-1753 (11 CS INJECTION INBOARD) is CLOSED.

C. MO-2107 (RCIC PUMP DISCHARGE INBOARD) is OPEN.

D. MO-2373 (MAIN STEAM LINE DRAIN INBOARD) is OPEN.

Question 43 Points: 1.0

Monticello NRC Written Exam Page: 128 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

4 3 Answer D DISTRACTOR ANALYSIS A. Incorrect, M0-2013 is normally open, remains open because LPCI Loop Select chose "B" Loop to inject into.

B. Incorrect, MO

-1753 is normally closed and would not open until reactor pressure was <420 psig with an ECCS signal present C. Incorrect, MO

-2107 is open because it auto opened on Low Low RPV water level.

D. Correct, MO-2373 should have closed on the Group I isolation signal of Low Low RPV Water Level.

Tier: 2 Group: 1 K/A: 223002 PCIS/Nuclear Steam Supply Shutoff K1.01 Knowledge of the physical connections and/or cause effect relationships between PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT

-OFF and the following: Main steam system Importance Rating:

3.8 10 CFR Part 55:

55.41.2 to 41.9

10 CFR 55.43.b

N/A K/A Match:

KA is matched by having the applicant determine that plant conditions have warranted a group 1 isolation, and the effect of this is that auto closure of the main steam drain isolation valves should have occurred.

SRO Justification:

N/A Technical

References:

Plant Protection System, Ops Man B.05.06-01 Core Spray Cooling System, Ops Man B.03.01

-01 Residual Heat Removal System, Ops Man B.03.04-02 Reactor Core Isolation Cooling, Ops Man B.02.03-02 ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 129 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

4 3 Proposed references None to be provided:

Learning Objective:

M8107L-070 24 Cognitive Level:

Higher X Lower _ Question Source:

New _ Modified Bank

_ Bank X Question History:

MNGP Bank question 1198 Comments:

Monticello NRC Written Exam Page: 130 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Complete the following statement:

SRVs __(1)__ are assigned to the Automatic Depressurization System (ADS) Logic Channel A and SRVs __(2)__ are assigned to ADS Logic Channel B.

A. (1) A, C, and D (2) E, G, and H B. (1) E, G, and H (2) A, B, and C C. (1) A, C, and D (2) A, C, and D D. (1) E, G, and H (2) E, G, and H Question 44 Points: 1.0

Monticello NRC Written Exam Page: 131 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

44 Proposed Answer: C DISTRACTOR ANALYSIS A, B and D are incorrect: Three SRVs are required for the ADS function. Choices are plausible if the candidate believes that each logic channel operates different valves and/or the candidate confuses the ADS assigned valves with the Low

-Low-Set assigned valves. C is correct: There are eight (8) safety/relief valves (SRV) located on the main steam lines within the drywell between the reactor vessel and the first main steam isolation valves (MSIV).. Three of the SRVs (RV 71A, C & D) are assigned to the Automatic Depressurization System (ADS) and the valves are operated by either or both logic channels.

Tier: 2 Group: 1 K/A: (239002 SRVs) K1.08 Knowledge of the physical connections and/or cause effect relationships between RELIEF/SAFETY VALVES and the following: (CFR: 41.2 to 41.9 / 45.7 to 45.8) Automatic depressurization system Importance Rating:

4.0*

10 CFR Part 55:

41.2 to 41.9 10 CFR 55.43.b:

N/A K/A Match:

K/A is matched by testing the applicants' knowledge of which SRVs are assigned to the Automatic Depressurization System function.

SRO Justification:

N/A Technical

References:

Ops Man B.03.03-01, NH-36241-1, M-8107L-025 (Reactor Pressure Relief) Rev. 23 Proposed references to be provided:

None ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 132 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Numbe r: 44 Learning Objective:

5 and 6 from M-8107L-025 (Reactor Pressure Relief) Rev. 23

Cognitive Level:

Higher _ Lower X Question Source:

New X Modified Bank

_ Bank _ Question History:

N/A Comments:

Monticello NRC Written Exam Page: 133 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Given the following conditions:

3 days ago the plant was at 40% of rated power RPV water level was stable at 37 inches The Digital Feedwater Level Control System (DFCS) was in AUTO with 3

-element control selected.

Today The plant was at rated power The "B" Feedwater Flow loop input to DFCS instantaneously failed FULLY DOWNSCALE Following the transient, which ONE of the following completes the statements below?

RPV water level will be controlled at __(1)__ 3 days ago.

RPV water level control will be in __(2)__ control.

A. (1) the same level as (2) single-element B. (1) the same level as (2) 3-element C. (1) a lower level than (2) single-element D. (1) a lower level than (2) 3-element Question 45 Points: 1.0

Monticello NRC Written Exam Page: 134 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Answer C DISTRACTOR ANALYSIS Programmed RPV level is designed to lower indicated level by 3 inches from 10% to 100% reactor power to prevent carryover and carryunder, operations is able to defeat the level programmer to maintain a steady RPV water level as power increases. Proper operation of the three element control mode is dependent upon valid steam and feedwater flow signals. The level control system monitors the quality of these signals and will automatically switch to single element control (where these signals are not required) if a failure is detected

.

A. (1) Incorrect, level programmer is in service and reactor power has increased 60% of rated power (2) Correct B. (1) Incorrect, level programmer is in service and reactor power has increased 60% of rated power (2) Incorrect, a failure has occurred and the system would automatically switch to single element C. (1) Correct (2) Correct D. (1) Correct (2) Incorrect, a failure has occurred and the system would automatically switch to single element Tier: 2 Group: 1 K/A: 259002 Reactor Water Level Control System A3.05 Ability to monitor automatic operations of the Reactor Water Level Control System including: Changes in reactor power Importance Rating:

3.4 10 CFR Part 55:

41.5 10 CFR 55.43.b

N/A K/A Match:

KA is matched by first having the applicant evaluate the change in programmed level as a function of reactor power. The second half of the question relates to monitoring automatic operations with the failure of feed water flow indication to the control system.

ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 135 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

45 SRO Justification:

N/A Technical

References:

Ops Man B.05.07

-02 Proposed references None to be provided:

Learning Objective:

M-8107L-046 LO 6, 7 Cognitive Level:

Higher X Lower _ Question Source: New X Modified Bank

_ Bank _ Question History:

Comments:

Monticello NRC Written Exam Page: 136 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM The plant was operating at full power with Standby Gas Treatment (SBGT) System Train "B" out of service (isolated) for maintenance.

A design basis loss of coolant accident occurred. All automatic actuations/isolations occurred as expected, EXCEPT that SBGT System Train "A" failed to start and cannot be started.

As a result, without further operator action, the Secondary Containment differential pressure is expected to __(1)__ and any release from the Secondary Containment to the environment will be __(2)__. (1) (2) A. decrease but remain negative filtered and elevated B. decrease and then go negative filtered and elevated C. decrease but remain positive unfiltered but elevated D. decrease and then go positive unfiltered and at ground level Question 46 Points: 1.0

Monticello NRC Written Exam Page: 137 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

46 Proposed Answer:

D DISTRACTOR ANALYSIS D is correct:

In the event of an accident, which requires that SCT integrity be established, the SBGT system SHALL establish a sub atmospheric pressure in SCT and provide a filtered SCT exhaust flow path to the Off

-Gas Stack; however SBGT is INOP so unfiltered air will remain in the SCT and a negative pressure CANNOT be maintained (differential pressure between the RB and atmosphere will increase as the pressure builds within the RB). As a result, the SCT is not expected to minimize ground level escape of airborne radioactivity.

A, B, and C are incorrect: plausible interpretations of what effects a loss of the SBGT will have: with both trains of the SBGT system INOP, the SCT differential pressure will decrease and go positive.

With normal ventilation trains shutdown and/or isolated air is expected to leak from the SCT at ground level.

Tier: 2 Group: 1 K/A: (261000 SGTS) K3.01 Knowledge of the effect that a loss or malfunction of the STANDBY GAS TREATMENT SYSTEM will have on following: (CFR: 41.7 /45.6) Secondary containment and environment differential pressure Importance Rating:

3.3 10 CFR Part 55:

41.7 10 CFR 55.43.b:

N/A K/A Match:

K/A is matched by testing the applicants' knowledge of the effect a loss of the Standby Gas Treatment System will have on the Secondary Containment and environment differential pressurize (pressure across the RB) SRO Justification:

N/A ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 138 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

46 Technical

References:

Ops Man B.04.02-01, M-8107L-008 (Standby Gas Treatment and Secondary Containment Systems) Rev. 19 Proposed references to be provided:

None Learning Objective:

8.a.vii from M

-8107L-008 (Standby Gas Treatment and Secondary Containment Systems) Rev. 19 Cognitive Level:

Higher _ Lower X Question Source:

New X Modified Bank

_ Bank _ Question History:

N/A Comments:

Monticello NRC Written Exam Page: 139 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM The plant is operating at 100% power when a sudden pressure fault condition occurred in the generator main transformer [relay SPR

-63 actuates]

Which ONE of the following completes the statements below?

This condition DIRECTLY actuates the __(1)__.

The field breaker trips open __(2)__.

A. (1) turbine lockout relay (286/T)

(2) immediately B. (1) turbine lockout relay (286/T)

(2) once 8N7 and 8N8 are sensed open C. (1) generator lockout relay (286/G)

(2) immediately D. (1) generator lockout relay (286/G)

(2) once 8N7 and 8N8 are sensed open Question 47 Points: 1.0

Monticello NRC Written Exam Page: 140 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

47 Answer C DISTRACTOR ANALYSIS A. (1) Incorrect, the turbine lockout relay 286/T is actuated by the generator lockout relay 286/G (2) Correct, generator lockout relay 286/G trips and locks out the field breaker B. (1) Incorrect, the turbine lockout relay 286/T is actuated by the generator lockout relay 286/G when (2) Incorrect, generator lockout relay 286/G trips and locks out the field breaker.

Would be correct for any turbine trip not caused by a generator lockout.

C. (1) Correct, SPR

-63; Generator transformer sudden pressure will operate for fault in the generator transformer and operation of this relay will cause the generator lockout relay 286/G to trip (2) Correct, generator lockout relay 286/G trips and locks out the field breaker D. (1) Correct, SPR

-63; Generator transformer sudden pressure will operate for fault in the generator transformer and operation of this relay will cause the generator lockout relay 286/G to trip (2) Incorrect, generator lockout relay 286/G trips and locks out the field breaker.

Would be correct for any turbine trip not caused by a generator lockout.

Tier: 2 Group: 1 K/A: 262001 AC Electrical Distribution K4.02 Knowledge of A.C. ELECTRICAL DISTRIBUTION design feature(s) and/or interlocks which provide for the following: Circuit breaker automatic trips

Importance Rating:

2.9 10 CFR Part 55:

55.41.7 10 CFR 55.43.b:

N/A K/A Match:

KA is matched by having the applicant determine that a sudden overpressure condition in the main transformer will result in generator lockout trip and that the field breaker is immediately opened on that trip condition.

ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 141 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

47 SRO Justification:

N/A Technical

References:

Ops Man B.09.02

-02, Generation Proposed references to be provided:

None Learning Objective:

M-8107L-036 LO7 Cognitive Level:

Higher X Lower _

Question Source:

New X Modified Bank

_ Bank Question History:

Comments:

Monticello NRC Written Exam Page: 142 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM While the plant is operating in MODE 1, annunciator 8

-A-29 (Div II Inverter Y

-81 Trouble) is received in the Main Control Room. An equipment operator sent to investigate, reports that the FUSE BLOWN indicator is illuminated on UPS Inverter Panel Y

-81. The equipment operator is directed transfer distribution panels Y

-30 and Y-80 to the Maintenance Bypass source in preparation for shutdown of the inverter.

Which one of the following choices describes:

(1) the effect(s), if any, this malfunction will have on the power supplied to distribution panels Y-30 and Y-80; and (2) how that effect will impact components associated with the Containment Isolation System.?

A. (1) A loss of sync between the INVERTER and ALTERNATE SOURCE will result in the Static Switch auto

-transfer being blocked, causing a complete loss of power to the distribution panels. Power will be restored to the distribution panels when the Maintenance Bypass Switch is placed in BYPASS.

(2) Automatic isolation of the RWCU System on High Filter/Demineralizer Inlet Temperature will be blocked.

B. (1) Initially there is NO loss of power to the distribution panels since the Static Switch will auto-transfer to ALTERNATE SOURCE. There will be a momentary loss of power when the Maintenance Bypass Switch on Y

-83 is positioned to the BYPASS position.

(2) A partial RWCU system isolation will occur when the Maintenance Bypass Switch on Y-83 is positioned to the BYPASS position.

C. (1) A momentary loss of power to the distribution panels will occur due to initiation of a "crash" transfer of the INVERTER upon loss of sync between INVERTER and ALTERNATE SOURCE. There will be NO loss of power when the Maintenance Bypass Switch on Y

-83 is positioned to the BYPASS position.

(2) The SBGT System will start and the Secondary Containment will isolate.

D. (1) There will be NO loss of power to the distribution panels since the Static Switch will auto-transfer to ALTERNATE SOURCE. Additionally there will be NO loss of power when the Maintenance Bypass Switch on Y

-83 is repositioned to the BYPASS position. (2) The will be NO change in status for any component associated with the Containment Isolation System.

Question 48 Points: 1.0

Monticello NRC Written Exam Page: 143 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

48 Proposed Answer: D DISTRACTOR ANALYSIS A. Incorrect: (1) the inverters will transfer to the alternate source automatically and power to the distribution panels will not be lost; (2) if power were to be lost to Y

-30, automatic isolation of the RWCU System on High Filter/Demineralizer Inlet Temperature will be blocked due to loss of power to logic relay.

B. Incorrect: (1) The manual bypass switch (MBS) provides "make

-before-break" switching to the alternate AC when taking the inverter/static switch unit out of service for maintenance or a malfunction. (2) If power were to lost to Y

-80, a partial RWCU system isolation would occur.

C. Incorrect: (1) There is no loss of sync and the inverters will transfer to the alternate source automatically and power to the distribution panels will not be lost; (2) If power were to lost to Y-80, the SBGT System would start and the Secondary Containment would isolate.

D. Correct: (1) The inverters will transfer to the alternate source automatically and power to the distribution panels will not be lost. The manual bypass switch (MBS) provides "make

-before-break" switching to the alternate AC when taking the inverter/static switch unit out of service for maintenance or a malfunction. (2) Since power is not lost to the distribution panels, components associated with the Containment Isolation System will NOT be effected.

Tier: 2 Group: 1 K/A: K3.10 Knowledge of the effect that a loss or malfunction of the UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) will have on following: (CFR: 41.7 / 45.4) Containment isolation: Plant

-Specific Importance Rating:

2.7 10 CFR Part 55:

41.7 10 CFR 55.43.b

N/A K/A Match: K/A is matched by testing the applicants' knowledge of the effects that a loss or malfunction of UPS (Y

-81) will have on containment isolation ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 144 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

48 SRO Justification:

N/A Technical

References:

Ops Man B B.09.13-01 and -06, B.02.04-05, 8-A-29, M-8107L-063 (Uninterruptable Power Supply and Instrument AC) Rev 12, M

-8107L-070 (Primary Containment Isolation System) Rev. 12

Proposed references to be provided:

None Learning Objective:

7.b and 8.a from M

-8107L-063 (Uninterruptable Power Supply and Instrument AC) Rev 12

Cognitive Level:

Higher X Lower _ Question Source:

New _ Modified Bank X Bank _ Question History:

N/A Comments: Question has been significantly modified from Question 1065 from Exam BANK. One of the distractors may need some work.

Monticello NRC Written Exam Page: 145 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM The plant is operating at 100% power when the following timeline of events occurred:

TIME 16:00 ALL AC power is lost to LC

-108 16:10 ALL AC power is lost to LC

-107 At 16:05 power will be available to DC Distribution Panel D71 from __(1)__.

With no operator action, Y91 will supply all Y94 loads for __(2)__ minutes.

A. (1) battery #17 ONLY (2) 30 B. (1) battery #17 ONLY (2) 60 C. (1) Battery #17 AND Y-91 (2) 30 D. (1) Battery #17 AND Y

-91 (2) 60 Question 49 Points: 1.0

Monticello NRC Written Exam Page: 146 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

49 Answer A DISTRACTOR ANALYSIS A. (1) Correct (2) Correct B. (1) Correct (2) Incorrect, on a loss of AC power to Y

-91, the process computer panel supplies are automatically shed after 30 minutes to extend the availability of 250 VDC Battery 17.

C. (1) Incorrect, The AC source that supplies the battery is from LC

-108 to Y-91, LC-107 it the alternate supply to Y

-91s output to Y

-94 (2) Correct D. (1) Incorrect, The AC source that supplies the battery is from LC

-108 to Y-91, LC-107 it the alternate supply to Y

-91s output to Y

-94 (2) Incorrect, on a loss of AC power to Y

-91, the process computer panel supplies are automatically shed after 30 minutes to extend the availability of 250 VDC Battery 17.

Tier: 2 Group: 1 K/A: 263000 DC Electrical Distribution K6.01 Knowledge of the effect that a loss or malfunction of the following will have on the D.C. ELECTRICAL DISTRIBUTION: A.C. electrical distribution Importance Rating:

3.2 10 CFR Part 55:

55.41.7 10 CFR 55.43.b:

N/A K/A Match:

KA is matched by having the applicant determine that the normal AC power supply to Y-91 is lost. The charger for battery 17 and its associated bus have lost powe r from the output of Y

-91 will only have battery power. Subsequently the alternate power supply to Y

-94 is lost and the effects of this are there is not power to the plant computer since greater than 30 minutes have elapsed since the normal power supply to Y-91 was lost.

ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 147 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

49 SRO Justification:

N/A Technical

References:

Ops Man B.09.13

-02 Ops Man B.09.13

-01 Proposed references to be provided:

None Learning Objective:

M-8107L-063 Cognitive Level:

Higher X Lower _ Question Source:

New X Modified Bank

_ Bank _ Question History:

Comments:

Monticello NRC Written Exam Page: 148 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM The plant is at rated conditions with the 1AR Transformer ISOLATED for modifications. A loss of normal off

-site power (LONOP) then occurs coincident with an ECCS initiation signal. Complete the following statement for the above conditions.

Nominally, #13 and #14 RHR Pumps will auto start _________ after the LONOP.

A. 10 seconds B. 15 seconds C. 20 seconds D. 25 seconds Question 50 Points: 1.0

Monticello NRC Written Exam Page: 149 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

50 Proposed Answer: C DISTRACTOR ANALYSIS A. incorrect: Plausible time for the EDG start time B. incorrect: Plausible start time for 11 and 12 RHR pumps C. correct: If normal auxiliary electrical power is not available at the time of an ECCS automatic initiation, a 10 second delay is added to allow the two EDG to start, come up to speed and for their respective breakers to CLOSE. This will be followed by a 10 second delay before starting 13 & 14 RHR Pumps. A total of 20 seconds will lapse before 13 and 14 RHR pumps start.

According to B.03.04

-02, Electrical Power Interlocks:

If normal auxiliary electrical power is available at the time of an ECCS automatic initiation, the starting of the RHR and Core Spray pumps will be delayed to limit the maximum motor starting load. The time delays employed are as follows:

Time Essential Bus 15 Essential Bus 16 5 seconds 11 RHR Pump 12 RHR Pump 10 seconds 13 RHR Pump 14 RHR Pump 15 seconds 11 Core Spray Pump 12 Core Spray Pump D. incorrect: Plausible start times for Core Spray pumps based on the power loss.

Tier: 2 Group: 1 K/A: (264000 EDGs) K5.06 Knowledge of the operational implications of the following concepts as they apply to EMERGENCY GENERATORS (DIESEL/JET): (CFR: 41.5 / 45.3) Load sequencing Importance Rating:

3.4 10 CFR Part 55:

41.5 10 CFR 55.43.b:

N/A ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 150 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

50 K/A Match:

K/A is matched by testing the applicants' knowledge of the load sequencing following Emergency Diesel Generator initiation SRO Justification:

N/A Technical

References:

Ops Man B.03.04-02, B.09.08-01, M-8107L-042 (Diesel Generator System) Rev. 19 Proposed references to be provided:

None Learning Objective:

8 from M-8107L-042 (Diesel Generator System), Rev. 19

Cognitive Level:

Higher _ Lower X Question Source:

New _ Modified Bank

_ Bank X Question History:

Question 49 of the 2013 MNGP ILT NRC Written Exam Comments:

Monticello NRC Written Exam Page: 151 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Given the following plant conditions Instrument Air system pressure on PR

-1176 is 102 psig 6-B-20 (15 AIR DRYER S

-121 TROUBLE) is in alarm Local operator reports that S

-121 drying mode is fixed and dew point is 10°F Which ONE of the following completes the statements below?

The dryer will automatically cycle between chambers based on __(1)__.

The air compressor/dryer train should __(2)__.

A. (1) the level of moisture in the chamber (2) be removed from lead (priority 1) operation.

B. (1) the level of moisture in the chamber (2) remain in lead (priority 1) operation until dew point is < 0°F C. (1) a fixed time interval (2) be removed from lead (priority 1) operation.

D. (1) a fixed time interval (2) remain in lead (priority 1) operation until dew point is <

0°F Question 51 Points: 1.0

Monticello NRC Written Exam Page: 152 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

51 Answer C DISTRACTOR ANALYSIS A. (1) Incorrect, AMLOC Mode [NORMAL] dryer will automatically cycle between chambers based on the level of moisture in the chamber as sensed on the AMLOC (2) Correct, if the from lead (priority 1) operation B. (1) Incorrect, AMLOC Mode [NORMAL] dryer will automatically cycle between chambers based on the level of moisture in the chamber as sensed on the AMLO C (2) Incorrect, from lead (priority 1) operation C. (1) Correct, The dryer will still switch back and forth between chambers on a fixed timer, and it will purge and recharge each time (2) Correctfrom lead (priority 1) operation D. (1) Correct, The dryer will still switch back and forth between chambers on a fixed timer, and it will purge and recharge each time (2) Incorrect, from lead (priority 1) operation Tier: 2 Group: 1 K/A: 300000 Instrument Air A2.01 Ability to (a) predict the impacts of the following on the INSTRUMENT AIR SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation: Air dryer and filter malfunctions Importance Rating:

2.9 10 CFR Part 55:

55.41.5 10 CFR 55.43.b:

N/A K/A Match:

The applicant is given indications of an air dryer malfunction and asked what affects that may have on the regeneration cycle and if the dew point of the dryer outlet is acceptable for continued lead operation.

ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 153 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number: 51 SRO Justification:

N/A Technical

References:

Ops Man B.08.04.01

-05 Ops Man B.08.04.01

-01 Proposed references to be provided:

None Learning Objective:

Cognitive Level:

Higher X Lower _ Question Source:

New X Modified Bank

_ Bank _ Question History:

Comments:

Monticello NRC Written Exam Page: 154 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM The plant is operating in MODE 1. Due to fouling of the in

-service RBCCW Heat Exchanger tubes, the Service Water inlet and outlet valves to the heat exchanger are now full open and Service Water flow has gradually lowered.

If the declining trend in Service Water flow through the RBCCW Heat Exchangers (HX) continues, which one of the following describes how the RWCU system will be affected?

A. RWCU Pump Room temperatures will rise, eventually causing RWCU to isolate and the RWCU pumps to trip.

B. The RWCU System temperature at discharge of the RWCU pumps will rise, eventually causing RWCU to isolate and the RWCU pumps to trip.

C. Upon receipt of a High RBCCW HX Outlet temperature signal, the RWCU Filter Demineralizers will automatically go into hold and RWCU system flow will bypass the Filter Demineralizers using MO

-2400 (Filter/Demineralizer Bypass).

D. RBCCW System Flow through the RWCU NRHX will automatically increase in response to the rising RWCU system temperature.

Question 52 Points: 1.0

Monticello NRC Written Exam Page: 155 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

52 Proposed Answer: B DISTRACTOR ANALYSIS A. Incorrect: Neither RBCCW nor Service Water supply the area room coolers.

B. Correct: If RBCCW temperature rises (system is nominally maintained <95F), the RWCU water temperature will also rise and Inlet Filter Demineralizer water temperature will eventually be > 140

°F, causing a HI

-HI Demin water temperature condition to alarm (4

-B-31) and stopping RWCU water flow by closing valves MO-2399 (per B.02.02

-01). C. Incorrect: There are no automatic control features associated with MO

-2400. D. Incorrect: There are no automatic temperature/flow control valves on the RBCCW outlet of the RWCU NRHS.

Tier: 2 Group: 1 K/A: (400000 Component Cooling Water) A1.02 Ability to predict and / or monitor changes in parameters associated with operating the CCWS controls including: (CFR: 41.5 / 45.5) CCW temperature Importance Rating:

2.8 10 CFR Part 55:

41.5 10 CFR 55.43.b : N/A K/A Match:

K/A is matched by testing the applicants' ability to monitor the CCW temperature and predict the changes an altering temperature will have on the operating CCWS

SRO Justification:

N/A Technical

References:

Ops Man B.02.05.01, B.02.02-01 , 4-B-31, M-8107L-026 (RBCCW) Rev. 14, M-8107L-030 (Reactor Water Cleanup System) Rev. 18 Proposed references to be provided:

None ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 156 of 2 25 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

52 Learning Objective:

5.g from M-8107L-026 (RBCCW) Rev. 14

Cognitive Level:

Higher X Lower _ Question Source:

New _ Modified Bank X Bank _ Question History:

Question 687 from the Exam BANK Comments: From Question 687 of the Exam BANK, the distractors have been slightly altered and Distractor "D" has been replaced.

Monticello NRC Written Exam Page: 157 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM The plant was in Mode 1 when annunciator 6

-B-32 (RBCCW LOW DISCH PRESS) was received. The alarm cleared several seconds later.

Which ONE of the following events would cause the above sequence?

A. Loss of all offsite power B. Loss of the 2R Transformer C. Loss of the 1AR Transformer D. Loss of the 1R Transformer Question 53 Points: 1.0

Monticello NRC Written Exam Page: 158 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

53 Answer A DISTRACTOR ANALYSIS A. Correct; one or both RBCCW pumps will start after the EDGs connect to their respective busses. B. Incorrect; if the 11 RBCCW pump was running, it will be lost and the 12 RBCCW pump will auto start on low system pressure; if the 12 RBCCW pump was running, it will remain running and the alarm would not be received.

C. Incorrect; the running pump should remain running and the alarm would not be received.

D. Incorrect; if the 12 RBCCW pump was running, it will be lost and the 11 RBCCW pump will auto start on low system pressure; if the 11 RBCCW pump was running, it will remain running and the alarm would not be received.

Tier: 2 Group: 1 K/A: 400000 Component Cooling Water K6.05 Knowledge of the effect that a loss or malfunction of the following will have on the CCWS: Motors Importance Rating:

2.8 10 CFR Part 55:

55.41.7 10 CFR 55.43.b:

N/A K/A Match:

KA is matched by having the applicant identify the power supply to the RBCCW pumps and to recognize the difference in impact between the loss of one offsite power source and loss of all offsite power sources.

SRO Justification:

N/A ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 159 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

53 Technical

References:

Ops Man C.4

-B.02.05.A Proposed references None to be provided:

Learning Objective:

M-8107L-026 LO 4, 7 Cognitive Level:

Higher _ Lower X Question Source:

New _ Modified Bank X Bank _ Question History:

MNGP Bank 584 Comments:

Monticello NRC Written Exam Page: 160 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Which of the following causes the Scram Discharge Volume (SDV) Vent and Drain valves to close during a reactor scram?

A. Energizing SDV pilot solenoid valves from the 125 VDC batteries.

B. De-energizing SDV pilot solenoid valves from the 125 VDC batteries.

C. De-energizing SDV Pilot solenoid valves from the Reactor Protection System bus.

D. Energizing Backup Scram solenoid valves from the Reactor Protection System bus.

Question 54 Points: 1.0

Monticello NRC Written Exam Page: 161 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

54 Proposed Answer: C DISTRACTOR ANALYSIS A, B, and D are incorrect but plausible interpretations of the power supply and functioning of the SDV vent and drain valve solenoids during a scram

125 VDC batteries power the backup scram pilot valves and are energized during scram.

C is correct: During normal operation the pilot valves for the SDV vent and drain valves are energized. Upon the initiation of a Reactor scram, both Reactor Protection System logic channels are de-energized and BOTH pilot valves (in both sets) open, venting control air from the vent and drain valve operators and permitting these valves to close.

Tier: 2 Group: 2 K/A: (201001 CRD Hydraulic) K2.04 Knowledge of electrical power supplies to the following: (CFR: 41.7) Scram discharge volume vent and drain valve solenoids Importance Rating:

3.2 10 CFR Part 55:

41.7 10 CFR 55.43.b

N/A K/A Match:

K/A is matched by testing the applicants' knowledge of the power supplies to the scram discharge volume vent and drain valve solenoids SRO Justification:

N/A Technical

References:

Ops Man B.01.03-01, M-8107L-020 (CRD Hydraulics) Rev. 17 Proposed references to be provided:

None Learning Objective:

4 from M-8107L-020 (CRD Hydraulics) Rev. 17 ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 162 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

54 Cognitive Level:

Higher _ Lower X Question Source:

New _ Modified Bank

_ Bank X Question History:

Question 379 from the Exam BANK Comments:

Monticello NRC Written Exam Page: 163 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM A plant startup is in progress in accordance with procedure Ops Man C.1

Which ONE of the following completes the statements below?

After reaching the POAH, a subcritical Reactor is indicated by __(1)__

In this condition

, control rods should be inserted __(2)__ A. (1) a decreasing reactor coolant temperature.

(2) until all control rods are fully inserted

. B. (1) the need to down

-range IRMs by more than one range.

(2) until all control rods are fully inserted

. C. (1) a decreasing reactor coolant temperature.

(2) to the subcritical hold point on the "Predicted Critical for Plant Startup" form

. D. (1) the need to down

-range IRMs by more than one range.

(2) to the subcritical hold point on the "Predicted Critical for Plant Startup" form

. Question 55 Points: 1.0

Monticello NRC Written Exam Page: 164 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

55 Answer B DISTRACTOR ANALYSIS After reaching the POAH, a subcritical reactor is indicated by multiple IRMs have been down ranged through at least 2 ranges. Ops Man C.1 part III.F (Operator Response to Subcriticality

) states: If subcriticality occurs, Operator action SHALL be taken to prevent an unintentional re

-criticality in the event Reactor water temperature decreases.

In this condition sufficient rod notches should be inserted to maintain the Reactor subcritical (i.e. all IRMs on Range 1). Control rods should be inserted until the subcritical hold point noted on Form 2159.

The SRMs SHALL be fully inserted to permit full range neutron flux level monitoring.

A. (1) Incorrect (2) Incorrect B. (1) Correct (2) Incorrect C. (1) Incorrect (2) Correct D. (1) Correct (2) Correct Tier: 2 Group: 2 K/A: 201003 Control Rod and Drive Mechanism K5.03 Knowledge of the operational implications of the following concepts as they apply to CONTROL ROD AND DRIVE MECHANISM : Reactor power control

Importance Rating:

3.3 10 CFR Part 55:

41.7 10 CFR 55.43.b:

N/A ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 165 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

55 K/A Match:

KA is matched by placing the applicant in a startup condition with the control rods responsible for reactor power control. The applicant must remember that an indication of a subcritical reactor when in the intermediate range is multiple IRMs have been down ranged through at least 2 ranges. The applicant must then state the requirement to prevent inadvertent recriticality given applicable conditions.

SRO Justification:

N/A Technical

References:

OPS MAN C.1 Proposed references to be provided:

None Learning Objective:

M-8107L-021 LO 8 Cognitive Level:

Higher _ Lower X Question Source: New X Modified Bank

_ Bank _ Question History:

Comments:

Monticello NRC Written Exam Page: 166 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Reactor startup is in progress. Control rod withdrawal has commenced. When selecting a control rod for withdrawal a transient occurs with the following observed:

Control rods able to be selected.

ROD SELECT pushbutton indicating light and the associated indicating light on the full core display for the selected rod are ON Unable to move control rods.

The following annunciators in ALARM:

o 5-A-35 (RWM ROD BLOCK) o 5-B-52 (TORUS WTR HI TEMP SPOTMOS TROUBLE)

Which of the following would cause the above conditions?

A. Loss of power to Panel Y10 B. Loss of power to Panel Y70 C. RPIS Master Clock malfunction D. Steam Flow sensors failing HIGH Question 56 Points: 1.0

Monticello NRC Written Exam Page: 167 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

56 Proposed Answer: B DISTRACTOR ANALYSIS A. Incorrect: Panel Y10 supplies the RPIS, not RWM. Per AOP C.4

-B.09.13.A, Loss of Y10 will result in the inability to select control rods and indicating white select light on the full core display will be lost.

B. Correct: Per AOP C.4

-B.09.13.F, Loss of Y70 will result in the following: unable to move control rods (RWM inputs to RMCS so insert and withdrawal rod blocks will result); the following annunciators will ALARM: 5

-A-35 (RWM ROD BLOCK) and 5

-B-52 (TORUS WTR HI TEMP SPOTMOS TROUBLE); and controls to RWM will be lost.

C. Incorrect: A Master Clock malfunction causes RPIS to be inoperative. However, with the RPIS INOP, the control rods would not able to be selected.

D. Incorrect: RWM uses steam flow sensors from the digital feedwater system; however a HIGH reading will NOT cause a rod block (RWM not enforcing with Rx Power >20%); conversely, a LOSS of steam flow signal would enforce an insert and withdrawal rod block

Tier: 2 Group: 2 K/A: (201006 RWM) K6.01 Knowledge of the effect that a loss or malfunction of the following will have on the ROD WORTH MINIMIZER SYSTEM (RWM): (CFR: 41.7 / 45.7) RWM power supply: P

-Spec (Not-BWR6) Importance Rating:

2.8 10 CFR Part 55:

41.7 10 CFR 55.43.b:

N/A K/A Match:

K/A is matched by testing the applicants' knowledge of the power supply to the Rod Worth Minimizer and the operational implications when that power supply is lost ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 168 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

56 SRO Justification:

N/A Technical

References:

Ops Man B.05.02-03, C.4-B.09.13.F, C.4

-B.09.13.A , M-8107L-001 (Rod Worth Minimizer) Rev. 12 Proposed references to be provided:

None Learning Objective:

4.e from M-8107L-001 (Rod Worth Minimizer) Rev. 12 Cognitive Level:

Higher _ Lower X Question Source: New X Modified Bank X Bank _ Question History:

Question 1032 of the Exam BANK Comments: Question has been significantly modified from Question 1032 of the Exam BANK, could be considered a NEW question.

Monticello NRC Written Exam Page: 169 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM The plant is operating at 60% rated power with power ascension in progress. The #11 Recirc Pump speed control is placed in the raise position.

Which ONE of the following completes the statements below?

The maximum speed change with the PLC control signal on is __(1)__.

If the tachometer output signal fails high, __(2)__.

A. (1) 2%/second (2) a Scoop Tube Lock will occur.

B. (1) 2.5%/second (2) a Scoop Tube Lock will occur.

C. (1) 2%/second (2) recirc pump speed will lower to approximately 50% speed D. (1) 2.5%/second (2) recirc pump speed will lower to approximately 50% speed Question 57 Points: 1.0

Monticello NRC Written Exam Page: 170 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

57 Answer A DISTRACTOR ANALYSIS The speed signal from the Flow Control System limits the time rate of change in speed demand to 2.5%/second in the decreasing direction and 2%/second in the increasing direction. Protective logic functions monitor the flow control loop and lock the actuator in position if abnormal conditions exist. This protective circuit will generate a scoop tube lock upon sensing a change in MG set actuator position or MG set speed which was not called for by the control room operator. This failure is MNGP site specific OE (AR 01008012).

A. (1) Correct (2) Correct B. (1) Incorrect (2) Correct C. (1) Correct (2) Incorrect D. (1) Incorrect (2) Incorrect Tier: 2 Group: 2 K/A: 202001 Recirculation A3.05 Ability to monitor automatic operations of the RECIRCULATION SYSTEM including: Pump speed: Plant

-Specific Importance Rating:

2.9 10 CFR Part 55:

41.7 10 CFR 55.43.b:

N/A K/A Match:

KA is matched by having the applicant monitor for proper automatic response of the system given an operator initiated demand to raise speed. The system limits the rate speed increase and prevents speed changes is the speed signal from the tachometer is abnormal.

ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 171 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

57 SRO Justification:

N/A Technical

References:

Ops Man B.01.04

-01 AR 01008012 Proposed references to be provided:

None Learning Objective:

M-8107L-047 LO 7, 8 Cognitive Level:

Higher _ Lower X Question Source:

New _ Modified Bank X Bank _ Question History:

MNGP bank 915

Comments:

Monticello NRC Written Exam Page: 172 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Following startup, power is at 55% and rising as the crew brings the plant to full load.

Just as the operator is about to withdraw the selected control rod, APRM 2 fails and is indicating a constant 10% power.

Which one of the following identifies expected system response and why?

A. RBM B WILL NOT enforce rod blocks.

RBM trip outputs are automatically bypassed when the "reference" channel input drops below the LPSP.

B. RBM B WILL enforce rod blocks.

When APRM 2 failed downscale, APRM 4 was automatically selected as the "reference" channel input to RBM B.

C. RBM B WILL enforce rod blocks.

RBM B generates an INOP rod block when the "reference" channel input drops below the LPSP. D. RBM B WILL enforce rod blocks.

RBM B generates an INOP rod block when the "reference" channel input fails downscale.

Question 58 Points: 1.0

Monticello NRC Written Exam Page: 173 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

58 Proposed Answer: A DISTRACTOR ANALYSIS A. Correct: When the APRM 2 dropped to 10%, the RBM will automatically bypass itself since the reference APRM STP power level is below the LOW POWER SETPOINT (reactor power is less than 25.9%). The reference reactor power level signal for RBM Channel B is normally obtained from APRM Channel 2, or alternatively from APRM Channel 4 when Channel 2 is bypassed.

B. Incorrect: No rod blocks will be enforced; the reference APRM is <25.9%, so auto bypassed. APRM 4 is selected as the "reference" channel input only after APRM 2 is bypassed. C. Incorrect: see A D. Incorrect: No rod blocks will be enforced; the reference APRM is <25.9% (see A) but is above the "downscale" trip setpoint..

Tier: 2 Group: 2 K/A: (215002 RBM) K1.01 Knowledge of the physical connections and/or cause

-effect relationships between ROD BLOCK MONITOR SYSTEM and the following: (CFR: 41.2 to 41.9 / 45.7 to 45.8) APRM: BWR

-3, 4, 5 Importance Rating:

2.9 10 CFR Part 55:

41.2 to 41.9

10 CFR 55.43.b

N/A K/A Match:

K/A is matched by testing the applicants' knowledge of the connection between the APRMs and the RBMs, and the cause-effects if an APRM malfunctions SRO Justification:

N/A ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 174 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

58 Technical

References:

Ops Man B.05.01.02

-01, ARP 5-A-51, M-8107L-066 (Power Range Neutron Monitoring System) Rev. 10 Proposed references to be provided:

None Learning Objective:

5 from M-8107L-066 (Power Range Neutron Monitoring System) Rev. 10 Cognitive Level:

Higher _ Lower X Question Source:

New _ Modified Bank X Bank _ Question History:

Question 1124 of the Exam BANK Comments:

Monticello NRC Written Exam Page: 175 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM The plant was at rated power when a reactor scram occurred due to a steam leak inside containment. The following plant conditions now exist:

RPV Level is (-) 57 inches and slowly rising Reactor Pressure is 580 psig and slowly lowering Drywell Pressure is 10 psig Drywell Temperature is 265 °F The Control Room Supervisor has directed initiation of Drywell Spays, using RHR Loop A, to cool the Drywell .

Which set, of the following three conditions, listed below is required (logically) to initiate Drywell Spray to cool the Drywell?

1. Annunciator Window 3

-B-54, "CONTAINMENT SPRAY PERMISSIVE," in ALARM status

2. RHR Div 1 Containment Spray/Cooling LPCI Initiation

Bypass switch in BYPASS 3. RHR Div 1 Containment Spray 2/3 Core Height Bypa ss key-lock switch in MAN OVERRIDE A. 1 only B. 1 AND 2 only C. 1 AND 3 only D. 1 AND 2 AND 3 Question 59 Points: 1.0

Monticello NRC Written Exam Page: 176 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

59 Answer B DISTRACTOR ANALYSIS Containment Spray Isolation Valves (Drywell and Torus) MO

-2010, MO-2020, MO-2022, MO-2011, MO-2021 and MO

-2023 are all interlocked to be automatically closed when a LPCI automatic initiation signal is received. These valves cannot be opened when a LPCI initiation signal is present except under the following conditions: a) reactor water level is greater than 2/3 core height [interlock can be bypassed], b) drywell pressure greater than 1 psig, and c) the associated Containment Spray/Cooling LPCI Initiation Bypass switch in BYPASS. The LPCI initiation signal is from PS-10-101A-D and the drywell permissive for core spray originates from PS 119A-D. A. Incorrect, a LPCI initiation signal is present and must be bypassed.

B. Correct, Drywell pressure is greater than 1 psig and a valid actuation of LPCI has been received and must be bypassed C. Incorrect, a valid actuation of LPCI has been received and must be bypassed; RPV water level is above 2/3 core height, therefore bypassing the interlock is not required logically (bypass is procedurally required).

D. Incorrect, a valid actuation of LPCI has been received and must be bypassed; RPV water level is above 2/3 core height, therefore bypassing the interlock is not required logically (bypass is procedurally required).

Tier: 2 Group: 2 K/A: 226001 RHR/LPCI: CTMT Spray Mode K3.02 Knowledge of the effect that a loss or malfunction of the RHR/LPCI: CONTAINMENT SPRAY SYSTEM MODE will have on following: Containment/drywell/suppression chamber temperature Importance Rating:

3.5 10 CFR Part 55:

41.7 10 CFR 55.43.b:

N/A ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 177 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

59 K/A Match:

KA is matched by having the applicant evaluate a set of plant conditions that are associated with LOCA conditions and determining if RHR system operation responds correctly. For the given conditions LPCI actuated but is not able to be aligned to containment spray due to the malfunction of the containment spray permissive which cannot be bypassed.

SRO Justification:

N/A Technical Referen ces: Ops Man C.5

-3502 Ops Man B.03.04

-01 Ops Man B.03.04

-02 Proposed references to be provided:

None Learning Objective:

M-8107L-023 LO 7 Cognitive Level:

Higher X Lower _ Question Source:

New _ Modified Bank X Bank _ Question History: BFN 2015-301 NRC exam Q 58 Comments:

Monticello NRC Written Exam Page: 178 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM The reactor is operating in MODE 1 when the following is observed:

Annunciator 3

-B-56 (HIGH AREA TEMP STEAM LEAK) alarms Temperatures in the main steam line chase are slowly rising at approximately 1F/minute, as indicated on TR

-4926 on Panel C

-21. Reactor water level is +36 inches and oscillating minimally due to the change in steam flow, although still in the analyzed region of the power

-flow map Given the above observations, which one of the following choices:

(1) Correctly characterizes the size and location of the leak; and (2) Identifies the expected operator response?

A. (1) a steam leak outside the primary containment but a Group 1 Isolation is NOT imminent.

(2) Evacuate personnel from the affected area and attempt to identify and isolate the source of the leakage.

B. (1) a steam leak outside the primary containment and a Group 1 Isolation is imminent.

(2) SCRAM the reactor and ensure the MSIVs are closed.

C. (1) a steam leak inside the primary containment but a Group 1 Isolation is NOT imminent.

(2) Attempt to identify and isolate the source of the leakage.

D. (1) a steam leak inside the primary containment and a Group 1 Isolation is imminent.

(2) SCRAM the reactor and ensure the MSIVs are closed.

Question 60 Points: 1.0

Monticello NRC Written Exam Page: 179 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

60 Proposed Answer: A DISTRACTOR ANALYSIS A is correct

A main steam line chase temperature of 165°F will sound a HIGH AREA TEMP STEAM LEAK alarm (3

-B-56) on Panel C

-03 and will help to determine if a steam leak exists outside of Primary Containment. If temperature continues to rise it will give a Group 1 isolation at 195 to 200F; however, the provided trend information indicates that a Group 1 isolation is not expected for approximately 30 minutes. Per ARP 3

-B-56, at this point the abnormal procedure C.4

-B.02.04.A (Steam Leaks Outside Primary Containment) shall be referred to, which states to evacuate personnel and isolate the leak.

B, C, and D are incorrect but plausible interpretations of the 3

-B-56 annunciator received and the plant's response to slowly rising main steam line chase temperature. It's plausible that the applicant doesn't know the 3

-B-56 alarm applies to the 165F temperature setpoints in the Main Steam areas located outside the Primary Containment. The 3

-B-56 alarm is the first indicator of a problem in the steam chase and the setpoint is low enough it could be indicative of a small steam leak (5

-10 gpm) in the MSL outside primary containment. The provided trend information indicates that a Group 1 isolation (195

-200F) is not expected for approximately 30 minutes. Also, alarms that are more indicative of a LARGE leak/break have not occurred: low pressure and high flow alarms, 5

-B-32 (MSL Leakage), and 4

-A-11 (RB High Rad). As stated in ARP 3

-B-56, AOP C.4

-B.02.04.A should be referred to, which states personnel should be evacuated from the affected areas AND the leak should be isolated. C.5

-1300 would also be entered but a reactor shutdown is not required until the same parameter in two areas exceed the Max Safe value or it is determined that the leak cannot be isolated.

Tier: 2 Group: 2 K/A: (239001 Main and Reheat Steam) A2.07 Ability to (a) predict the impacts of the following on the MAIN AND REHEAT STEAM SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: (CFR: 41.5 / 45.6) Main steam area high temperature or differential temperature high

Importance Rating:

3.8 10 CFR Part 55:

41.5 10 CFR 55.43.b:

N/A ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 180 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

60 K/A Match:

K/A is matched by testing the applicants' ability to determine the impacts a rise in the Main Steam area temperature will have on the Main and Reheat Steam System, and what procedural steps to take to mitigate the consequences of this rising temperature SRO Justification:

N/A Technical

References:

Ops Man B.02.04-01, ARP 3-B-56, Abnormal Procedure C.4

-B.02.04.A, ARP 5-A-17/18, Abnormal Procedure C.4

-B.04.01.A, and Emergency Procedure C.5

-1300, M-8107L-007 (Main Steam) Rev. 20, M

-8107L-070 (Primary Containment Isolation System) Rev. 12 Proposed references to be provided:

Learning Objective:

7 from M-8107L-007 (Main Steam), Rev. 20

Cognitive Level:

Higher X Lower _ Question Source:

New X Modified Bank

_ Bank _ Question History:

Comments:

Monticello NRC Written Exam Page: 181 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM The plant is in MODE 1 with the reactor at full rated power. The Electrical Pressure Regulator (EPR) is in service. Given the following:

The Electrical Pressure Regulator (EPR) Control Position is set at 910 PSI The Mechanical Pressure Regulator (MPR) Handwheel Position indicates 920 PSI An overcurrent condition has caused the running EPR oil pump supply breaker to trip open and the Standby EPR oil pump failed to start.

Given the above information, which of the following is correct?

A. Control valves will open, Main Steam pressure will lower, and a reactor scram will occur.

B. Control valve closure will result in a reactor scram.

C. Control valves will initially throttle close, then throttle open to a slightly higher steady state value. D. Control valves will initially throttle open, then throttle close to a slightly lower steady state value. Question 61 Points: 1.0

Monticello NRC Written Exam Page: 182 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

61 Answer C DISTRACTOR ANALYSIS General precautions; during power operation, changing the controlling pressure regulator setpoint will have a small but noticeable effect on core thermal power (approximately 3MWt per 10 psig change). Both EPR oil pumps A & B are powered by MCC

-142A, so loss will cause the MPR to be in control, reactor pressure will rise and reactor power would be expected to increase ~ 3 MWt, resulting in increased steam flow to the turbine.

A. Incorrect; plausible it examinee believes that the pressure set point fails to 0 psi upon loss of the EPR oil pumps; set point fails high on loss the oil pumps.

B. Incorrect; Plausible if the applicant believes that the EPR remains in control; MPR takes control when EPR output falls below MPR output.

C. Correct D. Incorrect; this is the opposite effect of the correct answer and is plausible if examinee believes that the pressure set point fails to a slightly lower value (e.g. failed to 900 psi).

Tier: 2 Group: 2 K/A: 241000 Reactor/Turbine Pressure Regulator K3.05 Knowledge of the effect that a loss or malfunction of the REACTOR/TURBINE PRESSURE REGULATING SYSTEM will have on following: Main Turbine Steam Flow Importance Rating:

3.7 10 CFR Part 55:

41.7 10 CFR 55.43.b

N/A K/A Match:

The applicant is asked to identify the plant response to a failure of the EPR pumps. The plant responds by increasing pressure and steam flow to the main turbine as control changes to the MPR. Turbine steam flow is directly proportional to TCV position. ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 183 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

61 SRO Justification:

N/A Technical

References:

Ops Man B.05.09

-05 Proposed references to be provided:

None Learning Objective:

M-8107L-048 LO 9 Cognitive Level:

Higher X Lower _ Question Source:

New _ Modified Bank X Bank _ Question History:

MNGP 2010 Audit Q 60 Comments:

Monticello NRC Written Exam Page: 184 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Plant startup is continuing in MODE 1 following completion of Turbine

-Generator roll to 1800 rpm. Prior to Turbine

-Generator synchronization, the turbine speed decreased to 1550 rpm and is held constant.

Without further operator action what is an anticipated response, if any?

A. Annunciator 7

-B-33 (TURBINE VIBRATION HI GH) alarms. B. Auxiliary Oil Pump auto starts.

C. No response, this is an expected operating characteristic D. Annunciator(s) 7

-B-31/32 (TURB DIFF EXPANSION LONG/SHORT ROTOR) alarm.

Question 62 Points: 1.0

Monticello NRC Written Exam Page: 185 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number: 62 Proposed Answer: B DISTRACTOR ANALYSIS A. Incorrect: this is not considered a vibration

-sensitive speed; continuous operation near the turbine's critical speeds of 1150, 1200 and 1400 rpm is not permitted (acceleration should be constant in these regions), as vibrations are expected to be a concern B. Correct: The turbine is designed for 1800 rpm. If turbine speed is less than 1600 rpm the Main Shaft Oil Pump will be ineffective and cannot supply the proper oil requirements so the Auxiliary Oil Pump will start at this time (AOP is placed in AUTO during startup when shaft speed gets above 1600 rpm).

C. Incorrect: decreasing to 1550 rpm is NOT an expected operational occurrence, the normal operation of the turbine is 1800 rpm.

D. Incorrect: a DECREASE in the turbine speed should NOT affect the general precaution temperature limit (HP turbine first stage bowl temperature rate of change should NOT exceed 150°F/hr) so differential expansion is not a concern; differential expansion is more of a concern during startup, Tier: 2 Group: 2 K/A: (245000 Main Turbine Gen. / Aux.) A1.02 Ability to predict and/or monitor changes in parameters associated with operating the MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS controls including: (CFR: 41.5 / 45.5) Turbine speed Importance Rating:

2.6 10 CFR Part 55:

41.5 10 CFR 55.43.b:

N/A K/A Match:

K/A is matched by testing the applicants' ability to monitor turbine speed and predict the impacts a decrease in turbine speed will have on the Main Turbine Generator and Auxiliary Systems ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 186 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

62 SRO Justification:

N/A Technical

References:

Ops Man B.06.01-02 and -05, M-8107L-013 (Main Turbine) Rev. 16, M-81 07L-087 (Turbine Auxiliaries) Rev. 10 Proposed references to be provided:

None Learning Objective:

9 from M-81 07L-087 (Turbine Auxiliaries) Rev. 10 Cognitive Level:

Higher _ Lower X Question Source:

New X Modified Bank

_ Bank _ Question History:

Comments:

Monticello NRC Written Exam Page: 187 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM The plant was operating at rated conditions when a station power transfer occurred from the 2R to the 1R transformer. A reactor scram was inserted and all systems responded as expected.

Which one of the following actions must be taken next to control Reactor Feedwater IAW procedure C.4

-A (REACTOR SCRAM)?

A. Prepare and restart #11 Reactor Feed Pump.

B. Prepare and restart #12 Reactor Feed Pump.

C. Control RPV water level using HPCI and/or RCIC.

D. Control RPV water level with the Low Flow Reg valve.

Question 63 Points: 1.0

Monticello NRC Written Exam Page: 188 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

63 Answer D DISTRACTOR ANALYSIS On a station power transfer, all plant busses will transfer to the 1R transformer with the exception of 12 bus. This is to prevent a second feed pump from starting and complicating the electrical situation. 12 Reactor Feed pump is powered from 12 bus so it will not be running. 11 Reactor Feed pump will remain running and will be sufficient to maintain level post scram. Therefore RPV level will be maintained on the low flow feedwater regulating valve.

A. Incorrect, assuming the power transfer occurs correctly, 11 RFP will remain running.

B. Incorrect, this pump can not be used as 12 Bus will be de

-energized. If 11 Bus didn't re

-power correctly then 12 Bus would get re

-powered and 12 RFP would start.

C. Incorrect, C.4

-A action to take if the RFPs aren't available.

D. Correct Tier: 2 Group: 2 K/A: 259001 Reactor Feedwater A4.01 Ability to manually operate and/or monitor in the control room: System flow Importance Rating:

3.6 10 CFR Part 55:

41.7 10 CFR 55.43.b

N/A K/A Match:

KA is matched by having the applicant evaluate a plant transient that results the need for the operator to take manual control of system flow.

SRO Justification:

N/A ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 189 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

63 Technical

References:

Ops Man B.09.06-01, C.4-A Proposed references None to be provided:

Learning Objective:

MT-ILT-AOP-001L LO 8 Cognitive Level:

Higher X Lower _ Question Source:

New _ Modified Bank _

Bank X Question History:

2013 MNGP NRC exam Q 61 Comments:

Monticello NRC Written Exam Page: 190 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM The plant is operating at 100% power when the 4

-A-12 (OFF GAS HI RADIATION) and 4

-A-2 (OFF-GAS TIMER ACTUATED) annunciators alarm on Panel C04

-A. Investigation reveals valid A & B Offgas Pretreatment Radiation Monitors UPSCALE.

Which one of the following correctly identifies: a) the required AOP/EOP to be implemented to mitigate the above condition, b) the required operator action, and 3) the reason for entering the procedure and initiating the specified operator action?

A. Immediately initiate a Manual Reactor SCRAM, using C.4

-K (Immediate Reactor Shutdown), because the off

-site release rate has exceeded the limits of C.5

-1400 (Radioactive Release Control).

B. Reduce Reactor Recirculation System flow to minimum then initiate a Manual Reactor SCRAM, in accordance with C.4

-K (Immediate Reactor Shutdown), because the Off

-Gas system has isolated and Main Condenser vacuum is degrading.

C. Reduce power, in accordance with C.4

-F (Rapid Power Reduction), to attempt to bring the gross gamma activity rate within limits.

D. Reduce reactor power, in accordance with C.4

-F (Rapid Power Reduction), because the Off-Gas system has isolated and Main Condenser vacuum is degrading.

Question 64 Points: 1.0

Monticello NRC Written Exam Page: 191 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

64 Proposed Answer: C DISTRACTOR ANALYSIS A. Incorrect: the signal is VALID and UPSCALE but is well below EOP C.5

-1400 entry condition. See C B. Incorrect: the reactor should only be shutdown AFTER the 30

-minute timer times out; C.4

-K (Immediate Reactor Shutdown) is NOT the first abnormal procedure to enter, C.4

-K entry is a secondary entry if the 30

-minute timer times out OR activity remains high after the C.4

-F (Rapid Power Reduction) procedure; Main Condenser vacuum will not degrade until the timer timers out resulting in recombiner trains trip.

C. Correct: Off-Gas Pretreatment Rad Monitors monitor the short

-lived radioisotopes, thus there is 30

-minute time delay to validate the condition and before a reactor scram shall occur. Per ARP 4

-A-2, if Off-Gas Pretreatment Radiation Monitors indicate a valid UPSCALE, check the MSL rad monitors, notify shift supervisor, and reduce power before 30 minutes elapses using Rapid Power Reduction (C.4

-F). When the 30

-minute timer times out the recombiner trains trips, which leads to the offgas isolation and eventually to main condenser vacuum degrading.

D. Incorrect: wrong reason; the power should be reduced, but main condenser vacuum does NOT degrade until after the 30

-minute timer times out and sometime after offgas recombiner trains trip.

Tier: 2 Group: 2 K/A: (271000 Offgas) 2.4.4 Ability to recognize abnormal indications for system operating parameters that are entry

-level conditions for emergency and abnormal operating procedures.

Importance Rating:

4.5 10 CFR Part 55:

41.10 10 CFR 55.43.b

N/A ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 192 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

64 K/A Match:

K/A is matched by testing the applicants' ability to recognize abnormal indications and annunicator alarms associated with the Offgas System that are entry conditions for abnormal operating procedure, Ops Man C.4

-F SRO Justification:

N/A Technical

References:

Ops Man B.05.11-01 and -02, ARP 4-A-2 and 4-A-12, M-8107L-091 (Off-Gas Recombiners) Rev. 11, M-8107L-077 (Process Radiation Monitoring and Area Radiation Monitors) Rev. 15 Proposed references to be provided:

None Learning Objective:

2.d and 7 of M

-8107L-077 (Process Radiation Monitoring And Area Radiation Monitors) Rev. 15 and 7 of M-8107L-091 (Off-Gas Recombiners) Rev. 11 Cognitive Level:

Higher X Lower _ Question Source:

New X Modified Bank

_ Bank _ Question History:

Comments:

Monticello NRC Written Exam Page: 193 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM The plant is at rated conditions with the following conditions:

RM-17-452A [Reactor Building exhaust vent plenum monitor] reads 30 mrem/hr RM-17-453A [Refueling floor process monitor] reads 33 mrem/hr Which one of the following is correct concerning the "A" SBGT system?

A. NEITHER RM 452A nor RM 453A have generated a high signal; therefore "A" SBGT remains in Standby.

B. ONLY RM-17-452A has generated a high signal; therefore "A" SBGT starts.

C. ONLY RM-17-453A has generated a high signal; therefore "A" SBGT starts.

D. BOTH RM-17-452A and RM 453A have generated a high signal, EITHER of which starts the "A" SBGT.

Question 65 Points: 1.0

Monticello NRC Written Exam Page: 194 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

65 Answer B DISTRACTOR ANALYSIS SBGT initiation is provided automatically when the following parameters exceed preset limits:

1) Reactor Building ventilation plenum high radiation, one high (26 mrem/hr) or two downscale trips of the two Reactor Building exhaust vent plenum monitors (RM 452A and RM 452B), or 2) Refueling floor radiation, one high (50 mrem/hr) or two downscale trips of the two refueling floor process monitors (RM 453A and RM 453B) A. Incorrect, start logic is met due to RM 452A B. Correct C. Incorrect, setpoint is not met for RM 453A D. Incorrect, setpoint is not met for RM 453A Tier: 2 Group: 2 K/A: 288000 Plant Ventilation K4.01 Knowledge of PLANT VENTILATION SYSTEMS design feature(s) and/or interlocks which provide for the following: Automatic initiation of standby gas treatment system Importance Rating:

3.7 10 CFR Part 55:

41.7 10 CFR 55.43.b:

N/A K/A Match:

KA is matched by giving the applicant a set of plant conditions and asking if the "A" SBGT system status has changed and the reason for the change, if any.

ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 195 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

65 SRO Justification:

N/A Technical

References:

Ops Man B.05.11

-02 Proposed references to be provided:

None Learning Objective:

M-8107L-008 LO 7 Cognitive Level:

Higher _ Lower X Question Source:

New X Modified Bank _

Bank _ Question History:

Comments:

Monticello NRC Written Exam Page: 196 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM A licensed reactor operator last completed their 10 CFR 55.53 required medical examination on September 15, 2016. Which one of the following is the latest date that they may complete their next medical examination and still meet the requirements of 10 CFR 55.53?

A. September 15, 2017 B. September 15, 2018 C. September 30, 2018 D. December 31, 2018 Question 66 Points: 1.0

Monticello NRC Written Exam Page: 197 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

66 Proposed Answer: C DISTRACTOR ANALYSIS A, B, and D are incorrect; plausible interpretations of 10 CFR 55. Medical physicals are typically recommended yearly in a personal instance, but licensees are required to take physicals every 2 years. In addition, the notification timeline to the Commission for many licensee actions/events varies from minutes to multiple months (e.g., per 10 CFR 50.73, a LER is required to be submitted within 60 days).

C is correct

As stated in 10 CFR 55, Subpart C

- Medical Requirements, "A licensee shall have a medical examination by a physician every two years" and in Subpart F, § 55.53(i) "The licensee shall have a biennial medical examination. NUREG 1021 clarifies the "biennial" requirement to be on the last day of anniversary month in the second year.

Tier: 3 Group: 1 K/A: Generic 2.1.4, Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, "no

-solo" operation, maintenance of active license status, 10CFR55, etc. (CFR: 41.10 / 43.2)

Importance Rating:

3.3 10 CFR Part 55:

41.10 10 CFR 55.43.b:

N/A K/A Match:

K/A is matched by testing the applicants' knowledge of the licensee's responsibilities related to 10 CFR 55 medical requirements.

SRO Justification:

N/A Technical

References:

10 CFR 55.53 (2016); NUREG 1021 (Rev 10); OWI-01.08 (Rev 22)

Proposed references to be provided:

None ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 198 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

66 Learning Objective:

N/A Cognitive Level:

Higher _ Lower X Question Source:

New X Modified Bank _ Bank _ Question History:

Comments:

Monticello NRC Written Exam Page: 199 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM The plant is at rated power and a DANGER card is being placed on a safety related component. IAW 4 AWI-04.04.02 [equipment positioning, independent and concurrent verification methods] the MINIMUM permission required to perform a concurrent verification instead of an independent verification is provided by who?

A. Control Room Supervisor B. Shift Manager C. Assistant Operations Manager D. Operations Manager Question 67 Points: 1.0

Monticello NRC Written Exam Page: 200 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

67 Answer D DISTRACTOR ANALYSIS 4 AWI-04.04.02 [equipment positioning, independent and concurrent verification methods] states that independent verification of equipment isolation SHALL be performed for proper component position upon installation of all DANGER cards, The Operations Managers permission is required to perform a concurrent verification for an independent verification when hanging Danger Cards.

D is correct A, B and C are incorrect: Plausible misconceptions on authority Tier: Group: K/A: Conduct of Operations 2.1.29 Knowledge of how to conduct system lineups, such as valves, breakers, switches, etc.

Importance Rating:

4.1 10 CFR Part 55:

41.10 10 CFR 55.43.b:

N/A K/A Match:

The KA is matched by having the applicant evaluate whose authority is required to deviate from the requirements of independent verification given a specific scenario.

SRO Justification:

N/A Technical

References:

4 AWI-04.04.02 Proposed references to be provided:

None ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 201 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

67 Learning Objective:

Cognitive Level: Higher _ Lower X Question Source:

New X Modified Bank _

Bank _ Question History:

Comments:

Monticello NRC Written Exam Page: 202 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM A Breaker and Relay Technician called the Control Room to request that Operations cycle a 4160 VAC breaker for testing using the control switch in the Control Room. Prior to cycling the breaker, the operator finds both a BREAKER/RELAY TEST STATUS card and a Danger tag on the breaker hand-switch. Which one of the following CORRECTLY identifies the correct operator action(s) for this situation?

A. Obtain verbal assurance from the Breaker and Relay Technician that the breaker is in the test position, then cycle the breaker.

B. Inform the Breaker and Relay Technician that the breaker cannot be cycled until the Danger tag is cleared from the hand-switch. C. Temporarily remove the Danger tag after receiving verbal authorization from the CRS, cycle the breaker, then replace the Danger tag.

D. Cycle the breaker per the Breaker and Relay Technician's request since the BREAKER/RELAY TEST STATUS card overrides the Danger tag

. Question 68 Points: 1.0

Monticello NRC Written Exam Page: 203 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

68 Answer: B DISTRACTOR ANALYSIS FP-OP-TAG-01, section 4.15

- Danger Tags are used to provide worker protection. At no times may a Danger Tagged component be operated except for component position verification by the independent verifier.

In accordance with 4 AWI

-04.04.09: Section 4.1.2.B.3 If a Danger or Caution tag and a BREAKER/RELAY TEST STATUS card are placed on the same control switch, the Danger or Caution tag SHALL take precedence and operation of the control switch is prohibited until the Danger or Caution tag is removed.

A. Incorrect; Danger tag must be cleared IAW the tagging procedure before the breaker can be cycled.

B. Correct; Danger tag must be cleared IAW the tagging procedure before the breaker can be cycled. C. Incorrect; Danger tag must be cleared IAW the tagging procedure. D. Incorrect; the Danger Tag takes precedence over the test tag.

Tier: 3 Group: 1 K/A: Generic 2.1.26 Knowledge of industrial safety procedures (such as rotating equipment, electrical, high temperature, high pressure, caustic, chlorine, oxygen and hydrogen). (CFR: 41.10 / 45.12)

Importance Rating:

3.4 10 CFR Part 55:

41.10 10 CFR 55.43.b

N/A K/A Match:

SRO Justification:

N/A ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 204 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

68 Technical

References:

FP-OP-TAG-01, section 4.15; 4 AWI-04.04.09: Section 4.1.2.B.3 Proposed references to be provided:

None Learning Objective:

M8108L-039 Cognitive Level:

Higher _ Lower X Question Source:

New _ Modified Bank X Bank _ Question History:

Modified from MNGP Exam Bank Question 1551 (M8108L-039 50) Comments:

Monticello NRC Written Exam Page: 205 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM The reactor is shutdown for a scheduled refueling outage. The following conditions exist:

RPV water level is 57 inches Reactor Coolant Temperature is 149°F The Reactor Mode switch is in SHUTDOWN ALL Reactor Vessel Head closure bolts are detensioned Division 2 RHR/RHRSW pumps are in Shutdown Cooling (SDC)

Division 1 AC Busses are deenergized for a scheduled maintenance window

Maintenance personnel assigned to work on EDG 11, have instead pumped down the lube oil sump for EDG 12.

Which one of the following Technical Specification LCOs would be NOT MET?

A. LCO 3.4.8 (RHR Shutdown Cooling System

- Cold Shutdown).

B. LCO 3.8.2 (AC Sources

- Shutdown).

C. LCO 3.8.8 (Distribution Systems

- Shutdown) D. LCO 3.9.8 (RHR

- Low Water Level).

Question 69 Points: 1.0

Monticello NRC Written Exam Page: 206 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

69 Answer D DISTRACTOR ANALYSIS The maintenance activity has resulted in EDG 12 being inoperable. The unavailability of EDG 12 along with the Division 1 maintenance window, the examinee must determine that no EDGs are operable and LCO 3.8.2 is not satisfied. Then the examinee must also recognize that the plant is in Mode 5.

A. Incorrect, bus 16 remains energize from offsite power and the requirements for LCO 3.4.8 are met. B. Correct; EDG 12 is no longer available to supply Bus 16.

C. Incorrect; the required distribution system is unaffected and remains energized from offsite power. D. Incorrect; Bus 16 remains energize from offsite power and the requirements for LCO 3.9.8 are met. Tier: 3 Group: K/A: Equipment Control 2.2.36 Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operations.

Importance Rating:

3.1 10 CFR Part 55:

41.10 10 CFR 55.43.b:

N/A K/A Match:

The KA is matched SRO Justification:

N/A ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 207 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

69 Technical

References:

TS Table 1.1

-1 TS 3.9.8 Proposed references to be provided:

None Learning Objective:

Cognitive Level:

Higher X Lower _ Question Source:

New _ Modified Bank X Bank _ Question History:

MNGP 2013 NRC exam question 9 Comments:

Monticello NRC Written Exam Page: 208 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM While verifying control switch tags in the Main Control Room, the independent verifier discovered that a control switch was in a different position than that specified on the tag.

Which one of the following action(s) is required to be done FIRST?

A. Initiate an Action Request.

B. Stop and notify the Control Room Supervisor.

C. Verify the required position in the Clearance Order.

D. Reposition the control switch to match the tagged position.

Question 70 Points: 1.0

Monticello NRC Written Exam Page: 209 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

70 Proposed Answer: B DISTRACTOR ANALYSIS A and C are incorrect: These would be plausible actions after the CRS is notified.

B is correct: The individual performing the independent verification or concurrent verification check SHALL NOT physically reposition the component. If the component is not found in the specified condition, the individual SHALL notify the CRS for corrective action.

D is incorrect: This action is specifically not allowed initially.

Tier: 3 Group: 2 K/A: Generic 2.2.13, Knowledge of tagging and clearance procedures. (CFR: 41.10 / 45.13) Importance Rating:

4.1 10 CFR Part 55:

41.10 10 CFR 55.43.b

N/A K/A Match:

K/A is matched by testing the applicants' knowledge of tagging (control switch tags).

SRO Justification:

N/A Technical

References:

AWI-04.04-02 section 4.3.6, Proposed references to be provided:

None ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 210 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

70 Learning Objective:

2 from M8108L

-039 Cognitive Level:

Higher _ Lower X Question Source:

New _ Modified Bank

_ Bank X Question History:

2009 MNGP Audit Written Exam

- Question 70 Comments:

Monticello NRC Written Exam Page: 211 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM The on duty RO is performing 0000

-A [operations daily log

- part a]. Given the following:

S

• STEP 2 If in MODES 1, 2, or 3, Then OBTAIN and RECORD-With the plant at rated power the S

• indicates the procedure step shall be completed satisfactorily to meet surveillance requirements from which, if any, of the following?

Technical Specifications Technical Requirements Manual A. NOT required NOT Required B. NOT required Required C. Required NOT Required D. Required Required Question 71 Points: 1.0

Monticello NRC Written Exam Page: 212 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

71 Answer C DISTRACTOR ANALYSIS The plant is in a mode of applicability for the step and the following precautions apply:

1. Procedure steps identified with an asterisk (*) SHALL be completed satisfactorily to meet Technical Specification requirements. If any one of these steps or substeps can NOT be satisfactorily completed, then notify the Shift Supervision immediately.

2. Procedure steps identified with a "#" SHALL be satisfactorily completed to meet TRM requirements. If any one of these steps can NOT be completed satisfactorily, immediately notify Shift Supervision.

3. Regardless of the steps initiating conditional statement, steps identified with an "S" SHALL be performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before (based on expectation) establishing Plant conditions requiring operability of the associated system or component in or to satisfy Tech Spec SR 3.0.2 or TSR 3.0.2.

A. Incorrect, plausible miss application of the precautions B. Incorrect, plausible miss application of the precautions C. Correct D. Incorrect, plausible miss application of the precautions Tier: 3 Group: K/A: Equipment Control 2.2.12 Knowledge of surveillance procedures.

Importance Rating:

3.7 10 CFR Part 55:

41.10 10 CFR 55.43.b

N/A K/A Match:

The KA is matched by having the applicant evaluate a step in the daily log and determine if they support license requirements in a mode of applicability.

ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 213 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

71 SRO Justification:

N/A Technical

References:

0000-A, B, D, E, H [OPERATIONS DAILY LOG

- PARTS A, B, D, E, H]

Technical Specifications Proposed references to be provided:

None Learning Objective:

Cognitive Level:

Higher _ Lower X Question Source:

New X Modified Bank _

Bank _ Question History:

Comments:

Monticello NRC Written Exam Page: 214 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM The plant is operating at full power with the following conditions:

Annunciator 4

-A-11, REACTOR BUILDING HI RADIATION, is in alarm.

Area Radiation Monitor, RCIC EQUIPMENT AREA (896), amber HI light is lit.

Annunciator 259

-A-6, RBV EFFLUENT HIGH RADIATION, is in alarm.

The mid-range detector for Reactor Building Vent WRGM is now providing the input for calculating effluent release.

Which of the following actions is immediately required by procedure for the stated conditions?

A. SCRAM the Reactor, per C.4-A (Reactor Scram)

. B. Commence a normal Reactor shutdown, per C.4-K (Immediate Reactor Shutdown)

. C. Evacuate all personnel from the Reactor Building.

D. Dispatch the Reactor Building operator to investigate.

Question 72 Points: 1.0

Monticello NRC Written Exam Page: 215 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

72 Proposed Answer: C DISTRACTOR ANALYSIS A & B are incorrect but plausible interpretations of immediate required actions as they are contingent steps later in the AOPs.

C is correct: With the above stated conditions a steam leak exists in the Reactor Building (Secondary Containment). The immediate action of AOP C.4

-B.02.04.A (STEAM LEAKS OUTSIDE PRIMARY CONTAINMENT) is to evacuate all unnecessary personnel from the Reactor Building.

D is incorrect: plausible since Annunciator 4

-A-11 requires that RP personnel permission is required for entry into the Reactor Building.

Tier: 3 Group: 3 K/A: Generic 2.3.13 Knowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high

-radiation areas, aligning filters, etc. (CFR: 41.12 / 43.4 / 45.9 / 45.10)

Importance Rating:

3.4 10 CFR Part 55:

41.12 10 CFR 55.43.b:

N/A K/A Match:

K/A is matched by testing the applicants' knowledge of the response to radiation monitor alarms SRO Justification:

N/A ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 216 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

72 Technical

References:

AOP B.02.04.A, ARP 4

-A-11, AWI-08.04.02 Proposed references to be provided:

None Learning Objective:

MT-ILT-AOP-005L 2 Cognitive Level:

Higher X Lower _ Question Source:

New _ Modified Bank

_ Bank X Question History:

Question 1751 of Exam BANK Comments:

Monticello NRC Written Exam Page: 217 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM The control room has been notified of two unconscious individuals in a locked high

-radiation area [LHRA] / highly contaminated area [HCA] in the Reactor Building. The fire brigade has been assembled and is responding to this serious injury involving the potential loss of life.

Which one of the following completes the statements below?

One member of the fire brigade has lost dosimetry in route to the radiologically controlled area [RCA], IAW A.5

-100 [on-site medical emergencies] the member __(1)__ enter the RCA and respond to victims location within the LHRA / HCA.

IAW A.5-100 the __(2)__ is responsible for contamination control at the accident scene.

A. (1) may (2) radiation protection/chemical technician B. (1) may (2) fire brigade leader C. (1) may not (2) radiation protection/chemical technician D. (1) may not (2) fire brigade leader Question 73 Points: 1.0

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73 Answer A DISTRACTOR ANALYSIS In all cases the health and safety of the injured person(s) is the primary concern. Prompt medical treatment takes precedence over radiological decontamination, radiological monitoring or contamination control methods when serious injury involving the potential loss of life or limb has occurred. Radiation Protection/Chemical Technicians are responsible for contamination control at the accident scene and radiological monitoring of the victim and emergency response personnel.

A. (1) correct, in this circumstance prompt treatment takes precedence over radiological monitoring (2) correct, the rad pro / chem tech has responsibility for contamination control B. (1) correct, in this circumstance prompt treatment takes precedence over radiological monitoring (2) incorrect, if this was a plant fire the fire brigade leader would be responsible for giving the brigade instructions as to any radiation and/or contamination problems.

C. (1) incorrect, in this circumstance prompt treatment takes precedence over radiological monitoring (2) correct, the rad pro / chem tech has responsibility for contamination control D. (1) incorrect, in this circumstance prompt treatment takes precedence over radiological monitoring (2) incorrect, if this was a plant fire the fire brigade leader would be responsible for giving the brigade instructions as to any radiation and/or contamination problems.

Tier: 3 Group: K/A: Radiation Control 2.3.12 Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high

-radiation areas, aligning filters, etc.

Importance Rating:

3.2 ANSWER

EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 219 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

73 10 CFR Part 55:

41.12 10 CFR 55.43.b:

N/A K/A Match:

The KA is matched having the applicant evaluate a scenario where a plant medical emergency is taking place, during this event normal radiological requirements are suspended if there is a potential for loss of life, the licensed operator has a responsibility as a fire brigade chief to understand the responsibilities of that position as they apply to radiological conditions.

SRO Justification:

N/A Technical

References:

A.5-100 [on-site medical emergencies]

Proposed references to be provided:

None Learning Objective:

Cognitive Level:

Higher _ Lower X Question Source:

New X Modified Bank _ Bank _ Question History:

Comments:

Monticello NRC Written Exam Page: 220 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Which of the following requires the assigned individual(s) to be respirator qualified?

1. Serving as a Fire Brigade member

2. Manning the Control Room during a Toxic Gas event 3. Manning the ASDS Panel for Shutdown Outside the Control Room

4. Manning the Control Room during ALL Emergency Plan implementations

A. 1 AND 2 ONLY B. 1, 2, AND 3 ONLY C. 1, 2, AND 4 ONLY D. 1, 2, 3, AND 4 Question 74 Points: 1.0

Monticello NRC Written Exam Page: 221 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

74 Proposed Answer: A DISTRACTOR ANALYSIS A is correct: Fire Brigade and Toxic gas events are on

-shift collateral duties that require respirator qualifications B, C, and D are incorrect: 3 and 4 are not required; however they are both plausible due to some overlapping responsibilities between the four choices.

Tier: 3 Group: 4 K/A: Generic 2.4.12 Knowledge of general operating crew responsibilities during emergency operations. (CFR: 41.10 / 45.12)

Importance Rating:

4.0 10 CFR Part 55:

41.10 10 CFR 55.43.b:

N/A K/A Match:

K/A is matched by testing the applicants' knowledge of the operating crew responsibility during emergency operations, particularly related to an required emergency devices in different circumstances/locations SRO Justification:

N/A Technical

References:

Operations Work Instruction OWI-01-06 (Rev 53)

Proposed references to be provided:

NONE ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 222 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

74 Learning Objective:

Cognitive Level:

Higher _ Lower X Question Source:

New _ Modified Bank

_ Bank X Question History:

Question 74 from 2009 MNGP ILT Exam

Comments: The first two randomly selected K/As for this question were rejected.

Monticello NRC Written Exam Page: 223 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM If entry conditions for both C.5

-1100 [RPV Control] and C.4-B.03.04.A [Loss of Normal Shutdown Cooling] are met, in what MODES does C.5

-1100 have precedence?

A. 1 and 2 ONLY B. 1, 2 and 3 ONLY C. 1, 2 ,3 and 4 ONLY D. 1, 2, 3, 4 and 5 ONLY Question 75 Points: 1.0

Monticello NRC Written Exam Page: 224 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

75 Answer B DISTRACTOR ANALYSIS The EOPs need not be entered during cold shutdown or outage conditions. During these conditions, many of the objectives of the EOPs are not applicable. For example, if all fuel is removed from the vessel, the objectives of C.5

-1100 (RPV CONTROL) are no longer relevant or operationally significant. Other plant operating procedures and administrative controls provide appropriate guidance for minimizing risk and responding to transients and accidents during shutdown and refueling conditions. However, Operators may refer to the EOPs during these conditions if desired.

A. Incorrect, the EOPs are also required in mode 3 B. Correct C. Incorrect, not required to be entered in mode 4 D. Incorrect, not required to be entered in mode 4 or 5

Tier: 3 Group:

K/A: Emergency Procedures / Plan

2.4.8 Knowledge

of how abnormal operating procedures are used in conjunction with EOPs Importance Rating:

3.8 10 CFR Part 55:

41.12 10 CFR 55.43.b:

N/A K/A Match:

The KA is matched by having the applicant recall when EOPs are required to be used and relate that to when AOPs are lower priority procedures.

SRO Justification:

N/A ANSWER EXPLANATION QUESTION BACKGROUND

Monticello NRC Written Exam Page: 225 of 225 2016 EXAMINATION ANSWER KEY ILT NRC RO WRITTEN EXAM Question Number:

75 Technical

References:

Ops Man C.5.1

-1000 Proposed references to be provided:

None Learning Objective:

Cognitive Level:

Higher _ Lower X Question Source:

New X Modified Bank _

Bank _ Question History:

Comments: