ML17230A322
| ML17230A322 | |
| Person / Time | |
|---|---|
| Site: | Three Mile Island  |
| Issue date: | 07/03/2017 |
| From: | Exelon Generation Co |
| To: | D'Antonio J Operations Branch I |
| References | |
| CAC U01944 | |
| Download: ML17230A322 (425) | |
Text
{{#Wiki_filter:EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 1 ID: 1685138 Points: 1.00 Plant Conditions:
- 100% power with ICS in full auto.
EVENT:
- Reactor Trip due to low condenser vacuum*
- Condenser vacuum is 22 in Hg mercury and slowly lowering
- OTSG 'A' is at 98% in the operating range and slowly rising
- OTSG 'B' is at 25" in the startup range and steady What actions will the operating crew take to stabilize the plant?
A 1) Trip 'A' Main Feed Pump
- 2) Stabilize OTSG pressure with the MS-V-3's (Turbine Bypass Valves)
B. 1) Trip both Main Feed Pumps
- 2) Stabilize OTSG pressure with the MS-V-4's (Atmospheric Dump Valves)
C. 1) Trip 'A' Main Feed Pump
- 2) Stabilize OTSG pressure with the MS-V-4's (Atmospheric Dump Valves)
D. 1) Trip both Main Feed Pumps
- 2) Stabilize OTSG pressure with the MS-V-3's (Turbine Bypass Valves)
Answer: B [Answer Explanation TMI OPS IL T EXAM Page: 1 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Explanation: To answer this question correctly the examinee must know: (1) on a low condenser vacuum, the MS-V-3's close and latch shut (2) at that point the MS-V-4's become the controlling valves to stabilize OTSG pressure at the MS-V-3 setpoint (3) the step to stabilize pressure is Step 3.10, which sends the operator to OP-TM-EOP-010, Guide 6 which directs the operator to MAINTAIN OTSG pressures below 1020 psig (4) due to the 'A' OTSG being greater than 97.5%, both of the Main Feed Pumps must be tripped, IAW OP-TM-EOP-001, step 3.6 RNO verifying BOTH OTSG levels below 97.5 % in the operating range, the RNO directs the operator ENSURE FW-P-lA and FW-P-lB (the Man Feed Pumps) are tripped. A. 1) Trip 'A' Main Feed Pump Plausible because the 'A' OTSG is the only OTSG with a high level, but
- 2) Stabilize OTSG pressure due to the Main Feedwater System being cross-connected, both with the MS-V-3's (Turbine Main Feedwater Pumps must be tripped. In addition, if the Bypass Valves) examinee does not know that a main condenser vacuum< 23 in HG will close and latch the MS-V~3's (Turbine Bypass Valves) the examinee could choose this answer.
B. 1) Trip both Main Feed Correct Answer Pumps
- 2) Stabilize OTSG pressure with the MS-V-4's (Atmospheric Dump Valves)
- c. 1) Trip 'A' Main Feed Pump Plausible because the 'A' OTSG is the only OTSG with a high level, but
- 2) Stabilize OTSG pressure due to the Main Feedwater System being cross-connected, both with the MS-V-4's Main Feedwater Pumps must be tripped.
!(Atmospheric Dump Valves)
D. 1) Trip both Main Feed If the examinee does not know that a main condenser vacuum< 23 Pumps in HG will close and latch the MS-V-3's (Turbine Bypass Valves) the
- 2) Stabilize OTSG pressure examinee could choose this answer.
with the MS-V-3's (Turbine Bypass Valves) Examination Outline Cross-reference: Level RO SRO Tier# 1 Group# K/A# E02 2.1.20 Importance Rating 4.6 4.6 K/A: Ability to interpret and execute procedure steps. Proposed Question: RO Question 1 Technical Reference(s): OP-TM-EOP-001, Rev 16 OP-TM-411-000, Rev 21 OP-TM-EOP-010, Rev 19 TMI OPS ILT EXAM Page: 2 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Proposed References to be provided to applicants during examination: None Learning Objective: EOP DBIG PC0-1 Question Source: Bank # Modified Bank# New x Question History: N/A Last NRC Exam: N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 10 55.43 Comments: KIA Match: This question matches the KA because the examinee will have to interpret that the
'A' OTSG level is high, and that the procedurally driven action to execute is to trip both Main Feedpumps.
In addition, Guide 6, which is a required for plant stabilization, is required. The examinee will have to diagnose that the MS-V-3's (Turbine Bypass Valves) are closed and latched, and the the MS-V-4's (Atmospheric Dump Valves) are required to be utilized to stabilize the plant. High Cog: This question is High Cog because the examinee must understand that when condenser vacuum lowers to < 22 in Hg, the plant response is that of cooldown to atmosphere and not the condenser. The MS-V-3 valves will latch closed, and transfer their setpoint to the MS-V-4 valves. TMI OPS ILT EXAM Page: 3 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS ILT EXAM Page: 4 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRG EXAM SUBMITTAL 2 ID: 1737142 Points: 1.00 Plant Conditions:
- 100% power with JCS in full auto.
Event:
- A Small Break LOCA has occurred inside containment.
- The leak is estimated at 25 gpm.
- Reactor Building pressure is 0.5 psig and rising at approximately 0.1 psig every two hours.
- Reactor Building temperature above 320' elevation is 120°F and rising at approximately 2°F every hour.
OTSG Startup level indicates (1) than actual based on elevated Reactor Building (2) A. (1) lower (2) pressure B. (1) higher (2) pressure C. (1) lower (2) temperature D. (1) higher (2) temperature Answer: D
!Answer Explanation TMI OPS ILT EXAM Page: 5 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL
<<Explanation: To answer this question correctly the examinee must know: (1) The Startup Range Reference legs for OTSG level control are closed cell, wet reference legs; (2) Because of this, Reactor Building pressure will have no effect on the Startup Level indication, but Reactor Building temperature will; (3) As Reactor Building temperature rises, the water in the reference leg will become less dense; (4)
When the water becomes less dense, the pressure on the High Pressure side of the D/P cell will lower, which lowers the D/P felt by the system; (5) The lower D/P results in a HIGHER than actual level. A. (1) lower INCORRECT: Reactor Building pressure will have no effect on the (2) pressure Startup Range level indication. Plausible because Reactor Building pressure is a parameter that is rising in the above scenario. B. (1) higher INCORRECT: Reactor Building pressure will have no effect on the (2) pressure Startup Range level indication. Plausible because Reactor Building pressure is a parameter that is rising in the above scenario.
- c. (1) lower INCORRECT: Indicated level will appear higher than actual level.
(2) temperature Plausible because the D/P cell fells a lower pressure on the High Pressure side. D. (1) higher CORRECT: See above. (2) temperature Examination Outline Cross-reference: Level RO SRO Tier# 1 Group# KIA# 009 EK2.03 Importance Rating 3.0 3.3 KIA: Small Break LOCA: Knowledge of the interrelationship between the small break LOCA and the following: S/Gs Proposed Question: RO Question #2 Technical Reference(s): TQ-TM-104-411-C001, Rev 8 OS-24, Rev 28 Proposed References to be provided tq applicants during examination: None Learning Objective: 411-GL0-2 Question Source: Bank# 375108 Modified Bank # New Question History: Sim Exam 5 Last NRC Exam: N/A Question Cognitive Level: Memory or Fundamental Knowledge TMI OPS ILT EXAM Page: 6 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 7 55.43 Comments: KA Match; This question matches the KA because the examinee must determine the level error in an OTSG caused by a small break LOCA. High Cog: The examinee must analyze the effects of a temperature rise on the OTSG level detectors. TMI OPS ILT EXAM Page: 7 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS ILT EXAM Page: 8 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 3 ID: 1685156 Points: 1.00 Plant Conditions:
- Reactor is a 70% power
- All ICS stations are in HAND EVENT:
- RC-P-1 B trips Tcold on the 'A' RCS loop will _ _ _ and the operator will have to _ _ _ 'A' feedwater flow to maintain a o°F ~Tc.
A. rise raise B. rise lower C. lower lower D. lower raise Answer: C
~nswer Explanation TMI OPS ILT EXAM Page: 9 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL
<<Explanation: To answer this question correctly, the examinee will have to know: (1) RC-P-lB is in the
'A' RCS loop (2) because ALL ICS stations are in hand, the plant will respond to the loss of 'A' loop RCS flow, but the control system will keep the other parameters (i.e. Feedwater flow, Control Rod Position, etc) steady, (3) !\..Tc is calculated by taking Tcold A - Tcold B, therefore with the loss of flow in the
'A' loop, the /'I.Tc will become negative, (4) to make the /'I.Tc become less negative, the operator will have to lower on 'A' feedwater flow.
A. rise This is plausible if a reactor coolant pump in the 'B' loop were raise secured, and the question still asked how to make /'I.Tc by controllinQ the 'A' feedwater loop. B. rise This is plausible if the examinee misunderstands the direction lower Tcold will go when an 'A' loop Reactor Coolant Pump is secured.
- c. lower Correct Answer lower D. lower This is plausible if the student does not understand how to raise correct the !\..Tc situation by with 'A' feedwater flow.
Examination Outline Cross-reference: Level RO SRO Tier# 1 Group# KIA# 015 AA1.09 Importance Rating 3.1 3.2 KIA: Ability to operate and I or monitor the following as they apply to the Loss of Reactor Coolant Pump Malfunction (Loss of RC Flow): RCS temperature detection system. Proposed Question: RO Question #3 Technical Reference(s): TQ-TM-104-621-C001, Rev 10 Proposed References to be provided to applicants during examination: None Learning Objective: 621-GL0-11 Question Source: Bank# 858178 Modified Bank # New Question History: N/A Last NRC Exam: N/A Question Cognitive Level: Memory or Fundamental Knowledge TMI OPS IL T EXAM Page: 10 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 7 55.43 Comments: (KA Match and why high cog) KIA Match: This matches the KIA because the examinee will have to describe what they expect RCS Tcold to do upon securing a reactor cooling pump.. In addition, the question requires the operator to know how to operate the FW control station associated with level in the OTSG in which the reactor coolant pump was secured. The RCS temperature detection subsystem in the question is the ~Tc ICS circuit which monitors the 'A' and 'B' RCS cold leg temperatures. When in automatic, this ICS circuit uses FW demand and ~Tc to maintain a near zero cold leg temperature. If the system were in automatic, when a reactor coolant pump is secured, the system will automatically re-ratio feedwater to maintain a near zero ~Tc. High Cog: This question is high cog because the examinee will have understand the what the impact of securing a reactor coolant pump has to analyze how the RCS parameters will change, and how to manipulate controls to return those parameters to normal. TMI OPS ILT EXAM Page: 11 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS IL T EXAM Page: 12 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 4 ID: 1685199 Points: 1.00 Plant Conditions:
- 100% power with ICS in full auto.
Event:
- MU-P-1 B trips on overload.
- MAP G-2-5 PZR LEVEL HI-LO annunciator has alarmed.
- Pressurizer level is 196 inches and slowly lowering.
Which one of the following identifies actions that the operator must take while restoring a Makeup Pump to operation? A De-energize all Pzr Heaters; AND CLOSE MU-V-33A-D, Control Bleed Off Valves. B. CLOSE MU-V-3, Letdown Isolation Valve; AND CLOSE MU-V-33A-D, Control Bleed Off Valves. C. De-energize all Pzr Heaters; AND Take MU-V-17, Makeup Flow Control Valve, and MU-V-32, Seal Injection Valve, to HAND and CLOSE the valves. D. CLOSE MU-V-3, Letdown Isolation Valve; AND Take MU-V-17, Makeup Flow Control Valve, and MU-V-32, Seal Injection Valve, to HAND and CLOSE the valves. Answer: D
!Answer Explanation TMI OPS ILT EXAM Page: 13 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL
<<Explanation: To answer this question correctly the examinee must know: (1) Since there is no makeup flow, the inventory will begin to lower. Pressurizer level will lower due to the normal letdown and CBO flow of the the reactor coolant pumps. (2) The crew will enter OP-TM-AOP-041 for a loss of Seal Injection (due to the MU-P-lB trip), which directs MU-V-32 to be closed in step 3.3 and MU-V-3 and MU-V-17 to be closed in step 3.5 RNO.
A. De-energize all Pzr Heaters; This is plausible because the operator may incorrectly believe that AND the heaters will need to be deenergized due to low pressurizer level; CLOSE MU-V-33A-D,Control and because the operator may incorrectly believe that procedures Bleed Off Valves. direct the closure of MU-V-33A-D to save RCS inventory from being lost. B. CLOSE MU-V-3, Letdown This is plausible because the operator may incorrectly believe that Isolation Valve; AND procedures direct the closure of MU-V-33A-D to save RCS inventory CLOSE MU-V-33A-D, Control from being lost. Closing MU-V-3 would save inventory, but incorrect Bleed Off Valves. due to MU-V-33's are not required to be closed. C. De-energize all Pzr Heaters; This is plausible because the operator may incorrectly believe that AND that the heaters will need to be deenergized due to low pressurizer Take MU-V-17, Makeup Flow level. According to OP-TM-MAP-G0305, at 80 inches in the Pzr the Control Valve, and MU-V-32, Pzr Heaters will automatically trip. However, this level has not been Seal Injection Valve, to HAND reached, and the need to de-energize the Pzr heaters is not and CLOSE the valves. identified in either EOP-10 Guide 9, or AOP-041. D. CLOSE MU-V-3, Letdown Correct Answer Isolation Valve; AND Take MU-V-17, Makeup Flow Control Valve, and MU-V-32, Seal Injection Valve, to HAND and CLOSE the valves. Examination Outline Cross-reference: Level RO SRO Tier# 1 Group# 1 K/A# 022 AKl.03 Importance Rating 3.0 3.4 K/A: Knowledge of the operational implications of the following concepts as they apply to the Loss of Reactor Coolant Makeup: Relationship between charging flow and PZR level. Proposed Question: RO Question #4 Technical Reference(s): OP-TM-AOP-041, Rev 8 Proposed References to be provided to applicants during examination: None Learning Objective: AOP-041-PC0-1 TMI OPS ILT EXAM Page: 14 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Question Source: Bank# 719461 Modified Bank# New Question History: Sim Exam 7 Last NRC Exam: Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 55.41 8 55.43 Comments: K/ A Match: The KA is matched because the operator must demonstrate knowledge (i.e. what actions must be taken) of the operational implications (i.e. RCS Inventory is being lost, and action that are needed to start MU Pump restart) of the concept of the relationship between charging flow and Pzr level as it applies to the Loss of Reactor Coolant Pump Makeup. Due to the loss of the charging flow, pressurizer level will lower, so letdown is isolated by closing MU-V-3 to minimize the less of inventory from the pressurizer. MU-V-17(Pressurizer level control valve) and MU-V-32 (Seal Injection Valve) are closed in hand for a controlled restoration of makeup and seal injection upon the restoration of a makeup pump. TMI OPS ILT EXAM Page: 15 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS IL T EXAM Page: 16 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 5 ID: 1737146 Points: 1.00 Plant Conditions:
- 100% power with ICS in full auto.
EVENT:
- All available Nuclear River water pumps trip, and cannot be restarted.
- OP-TM-AOP-031, LOSS OF NUCLEAR SERVICES COMPONENT COOLING is entered.
Which one of the following describes the strategy and basis for Reactor Coolant Pump (RCP) operation? A. The RCPs must be secured due to the loss of labyrinth cooling to each RCP. B. The RCPs must be secured to eliminate heat load from the NSCCW System. C. The RCPs may remain in operation provided seal injection flow is greater than 22 gpm. D. The RCPs may remain in operation provided the SR-NR cross tie is performed prior to reaching the Hl-2 alarm setpoint for the RCPs. Answer: B
!Answer Explanation TMI OPS IL T EXAM Page: 17 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL
<<Explanation: To answer this question correctly, the examinee must know: (1) After the Reactor is tripped in OP-TM-AOP-031, the next step the operating crew must do is trip all four Reactor Coolant Pumps; (2) According the the basis, this is to eliminate heat load from the Nuclear Services system.
A. The RCPs must be secured Incorrect: Plausible because Intermediate Closed Cooling Water due to the loss of labyrinth (which is cooled by Nuclear River Water) does cool the thermal cooling to each RCP. barrier on the reactor coolant pumps. Incorrect because the seal injection cools the labyrinth seal. B. The RCPs must be secured Correct Answer: See above. to eliminate heat load from the NSCCW System.
- c. The RCPs may remain in Incorrect: Plausible because Intermediate Closed Cooling does cool operation provided seal the thermal barrier of the Reactor Coolant Pump, and there is an injection flow is greater than interlock with ICCW and SI. Incorrect because the Reactor Coolant 22 gpm. Pumps must be secured because of the lack of cooling to the RCP motors and the heat load on the NSCCW system.
D. The RCPs may remain in INCORRECT: Plausible because a cross connect does exist between operation provided the Secondary River and Nuclear River water. The systems are cross SR-NR cross tie is connected in OP-TM-AOP-031. Incorrect because the Reactor performed prior to reaching Coolant Pumps are a major heat load on the system and must be the Hl-2 alarm setpoint for secured prior to cross connecting. the RCPs. Examination Outline Cross-reference: Level RO SRO Tier# 1 Group# KIA# 026 AK3.03 Importance Rating 4.0 4.2 KJA: Loss of Component Cooling Water: Knowledge of the reasons for the following responses as they apply to Loss of Component Cooling Water: Guidance actions contained in EOP for Loss of CCW. Proposed Question: RO Question #5 Technical Reference(s): OP-TM-AOP-031, Rev 6 OP-TM-AOP-031, Rev 2 Proposed References to be provided to applicants during examination: None Learning Objective: AOP-031-PC0-4 Question Source: Bank # 634661 Modified Bank # New TMI OPS ILT EXAM Page: 18 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Question History: Sim Exam 6 Last NRC Exam: N/A Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 b.7 55.43 Comments: KIA Match: This question matches the KA because the examinee must have knowledge of an action contained in the AOP for Loss of Nuclear Services Component Cooling. TMI OPS ILT EXAM Page: 19 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS ILT EXAM Page: 20 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 6 ID: 1685231 Points: 1.00 Plant Conditions:
- 100% power with ICS in full auto.
EVENT:
- The PORV fails partially open.
- Efforts to close the PORV Block valve have failed.
Current Plant Conditions:
- The plant is being shutdown.
- RCS Pressure is 2050 psig and slowly lowering.
- Pressurizer level is 250 inches and slowly rising.
In accordance with OP-TM-AOP-043, LOSS OF PRESSURIZER, what guidance will be given regarding Subcooling Margin? Place MU-V-17 in hand and raise makeup flow to maintain _ __ A. > 25°F SCM B. > 40°F SCM C. > 45°F SCM D. > 70°F SCM Answer: B [Answer Explanation
- TMI OPS IL T EXAM Page: 21 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL
<<Explanation: To answer this question correctly, the examinee must know: (1) The plant is being shutdown because there is inadequate heater capacity to maintain RCS pressure; (2) To maintain RCS pressure high enough to complete the shutdown, the steam bubble in the pressurizer will have to be squeezed, and pressurizer level will go up; (3) With current plant conditions, there is adequate pressurizer level indication and there the plant is not solid; (4) To use a steam table to calculate SCM is<
401'!JF SCM, when the guidance is applicable. A. > 25F SCM. Plausible because 25F SCM is a limit for entry into OP-TM-EOP-002 when the plant is shutdown. B. > 40F SCM. Correct Answer. C. > 45F SCM. Plausible because this guidance would be applicable if the plant had a loss of all pressurizer level indication. D. > 70F SCM. Plausible if the operating crew was performing a solid plant shutdown and cooldown. Pressurizer level is at 250 inches so solid plant operations are not applicable at this time. Examination Outline Cross-reference: Level RO SRO Tier# 1 Group# 1 K/A# 027 AA2.12 Importance Rating 3.7 3.8 K/A: Ability to determine and interpret the following as they apply to Pressurizer Pressure Control Malfunctions: PZR Level Proposed Question: RO Question #6 Technical Reference(s): OP-TM-AOP-043, Rev 6 Steam Tables Proposed References to be provided to applicants during examination: Steam Tables Learning Objective: AOP-043-PC0-4 Question Source: Bank# Modified Bank# New x Question History: N/A Last NRC Exam: N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x TMI OPS ILT EXAM Page: 22 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 10 CFR Part 55 Content: 55.41 5 55.43 Comments: K/ A Match: This is a K/A match because the PORV is part of the Pressurizer Pressure Control system, in that it receives an input from a narrow range pressure detector and opens when a setpoint is reached. Due to the PORV being open far enough to effectively lower pressure beyond the capacity of the pressurizer heaters, a shutdown must commence. To effectively ensure we have time to shutdown before tripping on a low pressure signal, the Pressurizer Level Control Valve, MU-V-17 is taken to HAND, and flow is raised to squeeze the bubble in the pressurizer. The operator will control pressurizer level to maintain a subcooling margin > 40F which the examinee can determine with the steam tables. High Cog: This question is high cog because the examinee will have to analyze the current plant parameters and determine which subcooling margin guidance is applicable. TMI OPS IL T EXAM Page: 23 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS ILT EXAM Page: 24 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 7 ID: 1685342 Points: 1.00 Event:
- Loss of offsite power.
- Emergency Diesel Generator, EG-Y-1A fails to start.
- Emergency Diesel Generator, EG-Y-1 B trips after starting.
Based on these conditions, which of the following control room extension controls or instruments remain operable? A. RM-A-2 Sample Pump. B. Motor Driven Fire Pump FS-P-2. C. 1SB-D2, 1B Auxiliary Transformer feeder breaker to 1D 4KV Switchgear. D. RR-Pl-225, RB Emergency Cooling Outlet Cooler 1B pressure instrument. Answer: C
~nswer Explanation TMI OPS ILT EXAM Page: 25 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL Explanation: To answer this question correctly, the examinee must know: (1) the DC electrical system is used to supply ES breaker control power and protective relaying. A. RM-A-2 Sample Pump. Plausible because this is safety related equipment, but RM-A-2 sample pump is powered from lA ES 480V MCC and uses 120V control power transformer housed in the breaker cubicle. B. Motor Driven Fire Pump Plausible because it is safety related equipment, but employs AC FS-P-2. control power.
- c. 1SB-02, 1B Auxiliary Correct Answer.
Transformer feeder breaker to 1D 4KV Switchgear. D. RR-Pl-225, RB Emergency Plausible because this is is an ES pressure indicator, but due to lack Cooling Outlet Cooler 1B of power to TRB none of the RB Emergency Cooler outlet pressure pressure instrument. instruments are available. Examination Outline Cross-reference: Level RO SRO Tier# 1 Group# KIA# 055 EA2.04 Importance Rating 3.7 KIA: Ability to determine or interpret the following as they apply to a Station Blackout: Instruments and controls operable with only de battery power available. Proposed Question: RO Question #7 Technical Reference(s): 1107-5, Rev 151 TQ-TM-1 04-740-COO1, REV 7 Proposed References to be provided to applicants during examination: None Learning Objective: AOP-020-PC0-2 Question Source: Bank # Modified Bank # 363906 New Question History: Sim Exam 8 Last NRC Exam: Question Cognitive Level: Memory or Fundamental Knowledge x TMI OPS ILT EXAM Page: 26 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 5 Comments: KIA Match: This matches the KIA because the examinee must know what controls are DC power (which would make them available during a station blackout) in the control room to answer the question correctly. The question choices are a mixture of instrument and controls. Modified Bank Question: This question was modified by changing the failure of EG-Y-B to trip after starting, and replacing MU-V-16C with an instrument (RR-Pl-225). This replacement was performed to better match the KIA. Event:
- Loss of offsite power.
- Emergency Diesel Generators EG-Y-1 A and EG-Y-1 B both failed to start.
Based on these conditions, identify the ONE statement below that describes control room extension controls that remain operable. A. RM-A-2 Sample Pump. B. Motor Driven Fire Pump FS-P-2. C. High Pressure Injection valve MU-V-16C. D. 1SB-D2, 1B Auxiliary Transformer feeder breaker to 1D 4KV Switchgear. Answer: D TMI OPS IL T EXAM Page: 27 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS ILT EXAM Page: 28 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 8 ID: 1685400 Points: 1.00 Plant Conditions:
- 100% power with ICS in full auto.
- Station Blackout Diesel Generator, EG-Y-4 is unavailable due to an outage.
EVENT:
- Loss of Offsite power.
- Emergency Diesel Generator, EG-Y-1 B has started and is powering 'E' 4kV Bus.
- Emergency Diesel Generator, EG-Y-1A has tripped on overspeed.
What action per OP-TM-AOP-020, Loss of Station Power, will be taken to prevent the loss of plant control and provide additional time to restore AC power? A. Secure Emergency DC Seal Oil Pump GN-P-2. B. Initiate OP-TM-732-901, Energize 1P 480V Bus using the ES Bus Cross Tie. C. Initiate OP-TM-732-902, Energize 1S 480V Bus using the ES Bus Cross Tie. D. Ensure Turning Gear Oil Pump LO-P-5 is running, then secure Emergency Bearing Oil Pump LO-P-6. Answer: B [Answer Explanation TMI OPS IL T EXAM Page: 29 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL lro answer this question, the examinee must know (1) EG-Y-1A powers the 'D' 4kV bus (2) since EG-Y-1A and EG-Y-4 are unavailable, the 'D' 4kV bus has no power supply (3) 1P480V Bus is downstream of the 'D' 4kV bus and has no power (4) the ES busses can be crosstied with the reactor is not critical IA. "Secure Emergency DC Seal Oil Pump." - Incorrect - Plausible since this equipment is identified in step 3.15 as "verify operating" in this AOP procedure not securing the pump. B. "Initiate OP-TM-732-901, Energize 1P 480V Bus using the ES Bus Cross Tie .. " - Correct - This is step 3.21. This energizes the battery chargers for the "A" station battery. In accordance with OP-TM-AOP-0201, Loss of Station Power basis document, if AC is only available to one train, the 480V ES busses will be crosstied and large DC loads will be minimized. This will allow for additional time to restore an AC power source. The procedures to crosstie the ES busses can be l,f)erformed without jeopardizing the reliability of the available AC supply and will prevent the loss of plant control caused by loss of DC power and two vital busses. C. "Initiate OP-TM-732-902, Energize 1S 480V Bus using the ES Bus Cross Tie."- Correct
!Answer - Plausible because this is a step in the procedure, however it is for when the 1E 4kV is de-energized not the situation given in the stem.
D. "Ensure Turning Gear Oil Pump LO-P-5 is running, then secure Emergency Bearing Oil Pump LO-P-6." - Incorrect - Plausible, since LO-P-6 is powered from "A" DC and will be running. LO-P-5 is powered from 1P 480V and will not be running. Step 3.13 directs the examinee to ensure LO-P-5 or LO-P-6 is running. Once that is verified, the examinee would move to the next step with no action taken. Examination Outline Cross-reference: Level RO SRO Tier# 1 Group# KJA# 056 AK3.02 Importance Rating 4.4 KJA: Knowledge of the reasons for the responses as they apply to the Loss of Offsite Power: Actions contained in the EOP for loss of offsite power. Proposed Question: RO question #8 Technical Reference(s): OP-TM-AOP-020, Rev 24 Proposed References to be provided to applicants during examination: None Learning Objective: AOP020-PC0-4 Question Source: Bank # Modified Bank # 1244855 TMI OPS ILT EXAM Page: 30 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL New Question History: N/A Last NRC Exam: N/A Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 7 55.43 Comments: This is a KA match because contains actions in our loss of offsite power AOP. The loss of offsite power AOP for TMI is essentially an EOP in broad terms. The loss of offsite power EOP for TMI deals the an extended loss of offsite power. Original Question: Plant Conditions:
- Plant is at 100% power
- EG-Y-4 is unavailable due to an outage.
Event:
- Loss of Offsite power.
- Emergency Diesel Generator, EG-Y-1A has started and is powering 'D' 4kV Bus
- EG-Y-1 B has tripped on overspeed.
What action per OP-TM-AOP-020, Loss of Station Power, will be taken to prevent the loss of plant control and provide additional time to restore AC power? A. Secure Emergency DC Seal Oil Pump GN-P-2. B. Initiate OP-TM-732-901 Energize 1P 480V Bus using the ES Bus Cross Tie. C. Initiate OP-TM-732-902 Energize 1S 480V Bus using the ES Bus Cross Tie. D. Ensure Turning Gear Oil Pump LO-P-5 is running, then secure Emergency Bearing Oil Pump LO-P-6. Answer: C TMI OPS ILT EXAM Page: 31 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL TMI OPS ILT EXAM Page: 32 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 9 ID: 1685632 Points: 1.00 Plant Conditions:
- Plant Cooldown is in progress per 1102-11, Plant Cooldown.
- Current Cooldown rate is 85°F/HR.
- Current RCS temperature is 359°F and RCS Pressure is 600 psig.
EVENT:
- Channel 1 of B train ES indicates actuated.
- Nl-5 loses indication on console center.
- MU-V-2A/2B Letdown Cooler Outlet Valves close.
(1) Which one of the following describes the action required if RCS temperature lowers below 313°F? (2) What is the reason for the action taken? A. (1) Open RC-RV-2 (PORV) until RCS pressure is below 540 psig. (2) The NOTT interlock has lost power. B. (1) Open RC-V-1 (RCS Spray Valve) until RCS pressure is below 540 psig. (2) The PORV and the NOTT interlock have lost power. C. (1) Open RC-RV-2 (PORV) until RCS pressure is below 540 psig. (2) RC-V-1 and the NOTT Interlock have lost power.
- 0. (1) Open RC-V-1 (RCS Spray Valve) until RCS pressure is below 540 psig.
(2) The NOTT interlock has lost power. Answer: A
!Answer Explanation TMI OPS IL T EXAM Page: 33 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Explanation: To answer this question correctly, the examinee must know: (1) Channel 1 of B train ES appearing actuated, Nl-5 losing indication on console center, and MU-V-2A/2B letdown cooler outlet valves closing are all indications that Vital Bus A is lost; (2) the reason the stem indicates that on Channel 1 of B train ES appears actuated vice Channel 1 of A and B train ES appears actuated is because the A train ES lights are powered from Vital Bus A, and this information would not be apparent to the operator until the ES Status Light Power Supply Select Switch is positioned to the BUS-B position; (3) The operating crew would enter OP-TM-AOP-015, LOSS OF VBA, which would direct the operating crew to open RC-RV-2 if RCS pressure were> 590 psig when RCS temperature is< 313°F due to NOTT interlock not being operable. A. (1) Open RC-RV-2 (PORV) Correct Answer until RCS pressure is below 540 psig. (2) The NOTT interlock has lost power. B. (1) Open RC-V-1 (RCS INCORRECT: Plausible because RC-V-1 (RCS Spray Valve) is usually Spray Valve) until RCS used to lower RCS pressure. At this temperature and pressure, the pressure is below 540 psig. PORV is used due to NOTT concerns. In addition, the PORV did not (2) The PORV and the lose power. NOTT interlock have lost power.
- c. 1) Open RC-RV-2 (PORV) INCORRECT: Plausible because RC-RV-2 is what the operators would until RCS pressure is below use to lower pressure in this case. Incorrect because RC-V-1 did not 540 psig. lose power (lA ES MCC).
(2) RC-V-1 and the NOTT Interlock has lost power.
- o. (1) Open RC-V-1 (RCS Plausible because RC-V-1 (RCS Spray Valve) is usually used to lower Spray Valve) until RCS RCS pressure. At this temperature and pressure, the PORV is used pressure is below 540 psig. due to NOTT concerns.
(2) The NOTT interlock has lost power. Examination Outline Cross-reference: Level RO SRO Tier# 1 Group# KIA# 057 AK3.01 Importance Rating 4.1 4.1 KIA: Knowledge of the reasons for the following responses as they apply to the Loss of Vital AC Instrument Bus: Actions contained in EOP for loss of vital ac electrical instrument bus. Proposed Question: RO Question #9 Technical Reference(s): OP-TM-AOP-015, Rev 10 OP-TM-AOP-0151, Rev 7 Proposed References to be provided to applicants during examination: None TMI OPS ILT EXAM Page: 34 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Learning Objective: AOP-015-PC0-4 Question Source: Bank # Modified Bank # 606540 New Question History: Sim Exam 5 Last NRC Exam: N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 10 55.43 Comments: (KA Match and why high cog) KIA Match: This matches the KA because the examinee can determine that the PORV is used to lower pressure due to NOTT concerns (vice the spray valve). Loss of a vital bus is an AOP at this facility. The examinee must determine which AOP is entered and the action within. High Cog: This question is high cog because the examinee will have to analyze plant conditions and determine which vital bus was lost. Plant Conditions:
- Plant Cooldown is in progress per 1102-11, Plant Cooldown.
- Current Cooldown rate is 85°F/HR.
- Current RCS temperature is 359°F and RCS Pressure is 600 psig.
Sequence of Events:
* "A" inverter fails and VBA is lost.
- OP-TM-AOP-015, Loss of VBA is entered.
- 15 minutes into the casualty the Unit Reactor Operator reports "RCS Temperature is 312°F and RCS Pressure is 595 psig.
Based on the report, _(1)_ should be opened and should remain open until RCS pressure is less than the procedurally required value of_(2)_ psig. A. (1) RC-RV-2 (PORV) (2) 540 B. (1) RC-RV-2 (PORV) (2) 500 TMI OPS IL T EXAM Page: 35 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL C. (1) RC-V-1 (RCS Spray Valve) (2) 540 D. (1) RC-V-1 (RCS Spray Valve) (2) 500 Answer: A TMI OPS ILT EXAM Page: 36 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS ILT EXAM Page: 37 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 10 ID: 1699640 Points: 1.00 Plant Conditions:
- 100% power with ICS in full auto.
- Operating crew is performing Emergency Diesel Generator, EG-Y-1A, 24 hour endurance run in accordance with 1107-3.
- Currently EG-Y-1A is operating in parallel with the grid.
EVENT: The following alarms are received simultaneously:
- Battery 1A Discharging, A-1-7.
- Battery Charger 1N1 C/1 E Trouble, A-2-7.
- Inverter 1N1 C/1 E System Trouble, A-3-7.
- CROM Breaker Test Trouble, PRF 1-1-1.
- 230 KVolt Substation Trouble, NN-3-1.
- 7 KVolt Bus Trouble, AA-3-2.
- 4 KVolt BOP Bus Trouble, AA-3-3.
- 480 Volt BOP Bus Trouble, AA-3-5.
In order to protect EG-Y-1A the operating crew must: G 1-02 = EG-Y-1 A Diesel output breaker to 1D 4160V Bus EG-V-15A =Air Start Header Isolation Valve to EG-Y-15A A. Close EG-V-15A, only. B. Close EG-V-15A and trip EG-Y-1A fuel rack. C. Open breaker G1-02 from the control room and close EG-V-15A. D. Open breaker G1-02 using the local OPEN pushbutton and close EG-V-15A. Answer: D
!Answer Explanation TMI OPS ILT EXAM Page: 38 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL
<<Explanation: To answer this question correctly, the examinee must know: (1) With the alarms present, there is a complete loss of 'A' DC; (2) when DC power is lost, EG-Y-lA loses its excitation field, in addition the ability to operate breakers associated with the 1D 4160V bus is lost (3) when DC is lost to EG-Y-lA with the generator breaker closed (parallel with the grid) the diesel will act as an inductive load and damage will occur (TQ-TM-104-861-COOl); (4) in addition, the air start solenoid will open which results in the air start distributor staying engaged, resulting in damage to the distributor.
A. Close EG-V-15A, only. Plausible because if the examinee determines that a complete loss of
'A' DC occurred without regard to the current status of the diesel (which is parallel to the grid), then this would be the correct answer.
B. Close EG-V-15A and trip Plausible because these actions are in OP-TM-AOP-023, which would EG-Y-1A fuel rack. be entered when 'A' DC was lost. Tripping the fuel racks is to shutdown the diesel, not for diesel protection. In addition, performing these steps would not open the diesel output breaker Gl-02 which is causing the diesel to become an inductive motor.
- c. Open breaker G1-02 from Plausible because these actions would protect the diesel. Incorrect the control room and close because Gl-02 must be opened locally at the breaker because 'A' DC EG-V-15A. control power was lost, and the control room extension control will not work.
D. Open breaker G1-02 using Correct answer - OP-TM-AOP-023 (step 4.15) directs the crew to the local OPEN pushbutton close EG-V-lSA. 1107-3 (Limit and Precaution 2.1.2) directs the and close EG-V-15A. breaker to be opened locally with the manual plunger. Examination Outline Cross-reference: Level RO SRO Tier# 1 Group# KIA# 058 AK3.01 Importance Rating 3.4 3.7 KIA: Knowledge of the reasons for the following responses as they apply to the Loss of DC Power: Use of de control power by the D/Gs. Proposed Question: RO Question #10 Technical Reference(s): 1107-3, Rev 146 OP-TM-AOP-023, Rev 7 Proposed References to be provided to applicants during examination: None Learning Objective: 861-GL0-11 Question Source: Bank# Modified Bank # New x TMI OPS IL T EXAM Page: 39 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Question History: NIA Last NRC Exam: N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 b.5 55.43 Comments: KIA Match: The question matches the KIA because the examinee will have to know what the effect of a loss of DC has on a running/paralleled diesel generator. The examinee will have to know that it effects the control power to the diesel generator breaker, in addition to the effects on the starting air solenoid. High Cog: The examinee will have to analyze the alarms present, and the present condition of the diesel (paralleled with the grid) to determine the steps needed to protect the diesel generator. TMI OPS IL T EXAM Page: 40 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS ILT EXAM Page: 41 of425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 11 ID: 1699734 Points: 1.00 Plant Conditions:
- 100% power with ICS in full auto.
- NR-P-1 C is out of service for maintenance.
- NR-P-1A is ES selected and running on 1R 480v bus.
- NR-P-1 Bis ES selected and running on 1T 480v bus.
EVENT:
- Loss of Offsite Power occurs.
- RCS pressure lowered to 1575 psig and is now rising slowly.
- RB pressure is 1.5 psig and relatively steady.
EVENT + 10 seconds:
- The Diesel Generators have started and are powering the ES Buses.
Which one of the following identifies the Nuclear River Water pump(s) that are running, if any, 1 minute after the re-energization of the ES Buses? A. NR-P-1A ONLY. B. NR-P-1 B ONLY. C. NR-P-1A and NR-P-1 B. D. No NR pump is running. Answer: C
!Answer Explanation TMI OPS ILT EXAM Page: 42 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL
<<Explanation: To answer this question correctly, the examinee must know: (1) When an loss of of offsite power occurs, all nuclear river water pumps shut off; (2) At an RCS pressure less than 1600 psig, and ES signal is generated; (3) When the diesels start and power the ES busses, and with an ES signal present, the remaining two Nuclear River Water pumps will start on Block 3.
A. NR-P-1A ONLY. Plausible if the student believes a pump will start on standby. NR-P-lA would receive a start signal first if NR-P-lC tripped. B. NR-P-1 B ONLY. Plausible because had the plant been in a normal lineup with NR-P-lA and NR-P-lC ES selected and running, then NR-P-lB would be the only running Nuclear River Water Pump after a loss of offsite power event (with no ES). C. NR-P-1A and NR-P-1 B. Correct Answer D. No NR pump is running. Plausible because in this lineup, if no ES signal were present, then no NR pumps would be running. Examination Outline Cross-reference: Level RO SRO Tier# Group# KIA# 062 AK302 Importance Rating 3.6 3.9 KIA: Knowledge of the reasons for the following responses as they apply to the Loss of Nuclear Service Water: The automatic actions (alignments) within the nuclear service water resulting from the actuation of ESFAS.
- Proposed Question: RO Question #11 Technical Reference(s): TQ-TM-104-531-C001, Rev 9 TQ-TM-104-740-C001, Rev 7 Proposed References to be provided to applicants during examination: None Learning Objective: 740-GL0-10 Question Source: Bank# 298156 Modified Bank #
New Question History: System Exam 6 Last NRC Exam: Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 4 TMI OPS ILT EXAM Page: 43 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 55.43 Comments: K/A Match: This matches the K/A because the examinee has to understand what happens to the Nuclear River Water pumps on an Loss of Offsite power in conjunction with an ES actuation signal. The Nuclear River Water pumps are part of the Nuclear Service Water system, they provide cooling to the Nuclear Service Water Coolers. High Cog: The examinee will have to analyze the current plant conditions: Only 2 nuclear river water pumps are available, and they that they are ES selected, that we have an Loss of Offsite power and that RCS pressure is 1575 psig, and understand that when RCS pressure is below 1600 psig, that an ES signal is present. Both nuclear service river water pumps trip when offsite power is lost and, both start on Block 3 ES after power is restored. TMI OPS ILT EXAM Page: 44 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS ILT EXAM Page: 45 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 12 ID: 1700681 Points: 1.00
<<REFERENCE PROVIDED Plant Conditions
- Reactor power is 75% with ICS in auto.
EVENT:
- Nl-5 power starts to slowly lower causing a SASS Mismatch.
- FW-V-17A, Main Feedwater Control Valve, starts to fail closed, causing a Feedwater to Reactor Cross Limit.
Neutron Error is at -1.5% on console center. Based on the above plant conditions, control rods will _.._(1,_,.)_ due to _ .(2)__. {) s
*Ui PERCErJT ICS25 A. (1) insert (2) Nl-5 failing B. (1) insert (2) Feedwater to Reactor Cross Limits C. (1) withdraw (2) Nl-5 failing D. (1) withdraw (2) Feedwater to Reactor Cross Limits Answer: C
!Answer Explanation TMI OPS ILT EXAM Page: 46 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL
<<Explanation: To answer this question correctly, the examinee must know: (1) NEGATIVE indicated neutron error results in control rod withdraw (Neutron Error= Reactor Demand - Actual Power); (2) Nl-5 power drifting low causes a positive neutron error which is displayed on the console as a negative neutron error; (3) A SASS MISMATCH alarm prevents Nl-5 from automatically swapping to the good instrument (Nl-6); (4) Nl-5 is the normally selected power range detector, with a SASS MISMATCH in, Nl-5 will continue to be the controlling nuclear instrument, even though it is failing low; (5) The result is a situation where control rods will withdrawal to attempt to zero out neutron error, but as long as Nl-5 continues to fail low, the negative neutron error will demand that control rod withdrawal; (6) Feedwater to Reactor Cross Limits cannot raise Reactor Power, therefore will not cause control rods to withdrawal.
A. (1) insert INCORRECT: Nl-5 failure LOW would create a neutron error to the (2) Nl-5 failing CRD System, while this error is positive (with respect to ICS actual power vs demanded power) the operator would see an inverted signal in which neutron error would appear negative and demand a control rod withdrawal. Rods inserting is plausible because this negative indication may cause the examiner to believe the control rods should be inserting. B. (1) insert INCORRECT: Control Rods would withdraw. The examinee may (2) Feedwater to Reactor reason control rods would be inserting. Rods inserting is plausible Cross Limits because this negative indication may cause the examiner to believe the control rods should be inserting.
- c. (1) withdraw CORRECT Answer: Indicated Neutron Error on console indication is (2) Nl-5 failing reversed polarity to the actual neutron error going to the CRD System AND FW Cross Limits can only LOWER Reactor power, i.e.
drive Control Rods IN. D. (1) withdrawal INCORRECT: Feedwater Cross Limits cannot raise Reactor Power, (2) Feedwater to Reactor however with the indicated neutron error the operator may reason Cross Limits the Cross Limit is inducing this error. Examination Outline Cross-reference: Level RO SRO Tier# 1 Group# 2 KIA# 001 AA2.05 Importance Rating 4.4 4.6 KIA: Continuous Rod Withdrawal Ability to determine and interpret the following as they apply to Continuous Rod Withdrawal: Uncontrolled rod withdrawal, from available indication Proposed Question: RO Question #12 Technical Reference(s): ICS Analog Print: 0553732 TQ-TM-104-621-C001, Rev 10 Proposed References to be provided to applicants during 0553732 examination: Learning Objective: 621-GL0-11 Question Source: Bank # TMI OPS ILT EXAM Page: 47 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Modified Bank# New x Question History: N/A Last NRC Exam: N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 b.7 55.43 Comments: KIA Match: The conditions given in the question result in a Continuous Rod Withdrawal: indication of Nl-5 failing low and Neutron Error. The operator must understand the indication and the final result of the multiple indications. High Cog: The operator must understand the relationship between neutron error and the signal sent to the CRD System. While a negative error may imply Control Rods would insert, the ICS Signal would be positive and rods would withdraw. With a Feedwater to Reactor Cross Limit in effect the operator must understand the ICS does not allow this cross limit to raise reactor demand, only allows reactor demand to be lowered. TMI OPS ILT EXAM Page: 48 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS ILT EXAM Page: 49 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 13 ID: 1700738 Points: 1.00 Plant Conditions:
- 100% power with ICS in full auto.
- Pressurizer Level LT-1 is selected as the controlling channel.
EVENT:
- A leak develops on the reference leg of LT-1.
Following the event, indicated (LT-1) Pressurizer level will _(1)_ and actual Pressurizer level will _(2)_. A. (1) rise (2) lower B. (1) rise (2) remain the same C. (1) lower (2) rise D. (1) lower (2) remain the same Answer: A
!Answer Explanation TMI OPS ILT EXAM Page: 50 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL
<<Explanation: To answer this question correctly, the examinee must know: (1) The pressurizer uses a wet reference leg, which means a O DP when the pressurizer is full; (2) Normal Level setpoint is 220 inches; (3) As the reference leg loses water, the DP would lower which would be seen as a pressurizer level rise on the PZR Level indication; (4) Since indicated pressurizer level is rising, MU-V-17, Pressurizer Level Control valve, will close to maintain level at setpoint of 220 inches; (S) Actual pressurizer would lower due to letdown flow remaining constant and makeup flow lowering due to MU-V-17 closing.
A. (1) rise Correct. Pressurizer level instruments RC LT-1 and LT-3, are (2) lower manually selected on RC-1 LR recorder on CC. The level transmitters use a wet reference leg such that a full pressurizer has O" DP, and an empty pressurizer has 400" DP. Consequently, a leak in the reference leg will reduce the differential pressure between the reference and the variable leg. As the differential pressure is reduced, indicated level will rise. Pressurizer level is maintained at 220" when the plant is operating at 100% full power. The level is sensed and applied to a level control circuit. The level control circuit when in the automatic mode will control the position of the normal makeup valve (MU-V-17). If the level drops below 220" the circuit will open the normal makeup valve until the levels returns to normal, and vice-versa. Consequently, when the reference leg leak occurs, the indicated level will start to rise, causing MU-V-17 to close. Since there is less makeup flow, pressurizer level will actually lower. B. (1) rise Incorrect. This is plausible because the operator may misunderstand (2) remain the same the Pressurizer Level detector operation. If so, this is the exact opposite of what should happen. The examinee could believe that MU-V-17 would still maintain a pressurizer level of 220", which is not the case since it is receiving a signal to close due leaking reference leg. C. (1) lower Incorrect. This is plausible because the operator may incorrectly (2) rise believe that when the leak is sensed that the level control will automatically shift to LT-3 similar to the SASS protected instrumentation. In a(!dition, the examinee could believe that a leaking reference leg would make indicated pressurizer level to lower, which would cause MU-V-17 to open and pressurizer level to rise. D. (1) lower Incorrect. This is plausible because the operator may misunderstand (2) remain the same the Pressurizer Level detector operation, and may incorrectly believe that when the leak is sensed that the level control will automatically shift to LT-3 similar to the SASS protected instrumentation. Examination Outline Cross-reference: Level RO SRO Tier# 1 Group# 2 K/A# 028 AKl.01 Importance Rating 2.8 3.1 K/A: Knowledge of the operational implications of the following concepts as they apply to Pressurizer Level Control Malfunctions: PZR reference leg leaks. TMI OPS ILT EXAM Page: 51 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL Proposed Question: RO Question #13 Technical Reference(s): TQ-TM-104-624-COOl, Rev 4 TQ-TM-104-220-COOl, Rev 8 Proposed References to be provided to applicants during examination: None Learning Objective: 624-GL0-5 Question Source: Bank# 862259 Modified Bank# New Question History: System Exam 11 Last NRC Exam: N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 b.8 55.43 Comments: KA Match: The K/A/ is matched because the examinee must demonstrate knowledge of the operational implications of PZR reference leg leak abnormalities as they apply to Pressurizer Level Control Malfunctions. High Cog: The question is at the Comprehension/Analysis cognitive level because the examinee must demonstrate understanding of how the Pressurizer Level control system detects level, and then determine how a failure of a reference leg effects actual pressurizer level to correctly answer the question. In addition, the examinee must take into account how an erroneous pressurizer level effects the pressurizer makeup valve which would close and cause actual level to lower. TMI OPS ILT EXAM Page: 52 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS ILT EXAM Page: 53 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 14 ID: 1700748 Points: 1.00 Plant conditions:
- Plant startup is in progress.
- Source Range Channels indicate 100 cps.
- Group 5 rods are being withdrawn from 50% to 75%.
EVENT:
- Source Range Channel Nl-11 fails low.
Based on this condition, the startup _ _ _ _ _ _ _ __ A. may continue using Source Range Instrument Nl-12. B. may continue using Source Range Instrument Nl-11A. C. will be terminated AND the crew will initiate RCS Boration. D. will be terminated AND the crew will fully insert Group 5 and 4 control rods. Answer: A
!Answer Explanation TMI OPS ILT EXAM Page: 54 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL
<<Explanation: To answer this question correctly, the examinee must know: (1) There 2 independent source range channels that are part of the Reactor Protection System (Nl-11 and Nl-12); (2) These channels are required by Table 3.5-1 of Technical Specification 3.5.1.1; (3) At least one source range instrument is required to be operable until one intermediate range instrument is greater than 10~ 10 amps or 2 of 4 power range instruments are greater than 10% power; (4) If less than the required source range instruments are operable, the plant would be in a TS 3.0.1 situation.
A. may continue using Source CORRECT: Based on T.S. Requirements, Table 3.5-1 Range Instrument Nl-12. B. may continue using Source INCORRECT:Plausible if the operator has the misconception that Range Instrument Nl-llA. Nl-llA can be used in place of Nl-11. Nl-llA is not part of the RPS system and is the installed spare that only provides indication. C. will be terminated AND the INCORRECT: The startup is not required to be terminated. Plausible crew will initiate RCS Boration. because if the operator did believe the startup must be terminated, the crew could choose to borate the RCS until they are shutdown to 1% dK/K. D. will be terminated AND the INCORRECT: The startup is not required to be terminated. Plausible crew will fully insert Group 5 since if a startup were aborted for unanticipated criticality, the crew and 4 control rods. would insert the group of control rods being pulled, and one additional group (which would be group 4 control rods in this scenario). Examination Outline Cross-reference: Level RO SRO Tier# 1 Group# 2 K/A# 032 AK3.01 Importance Rating 3.2 3.6 K/A: Knowledge of the reasons for the following responses as they apply to the Loss of Source Range Nuclear Instrumentation: Startup termination on source-range loss Proposed Question: RO Question #14 Technical Reference(s): TQ-TM-104-623-COOl, Rev 5 Tech Specs Section 3.5.1.3 Proposed References to be provided to applicants during examination: None Learning Objective: 623-GL0-10 Question Source: Bank# 355941 Modified Bank# New NRC Exam 2000 Question History: Last NRC Exam: NO TMI OPS ILT EXAM Page: 55 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 b.10 55.43 Comments: KA Match: This question matches the K/ A because the examinee must know the correlation Loss of SR NI during a startup and the required actions; continue the startup or terminate the startup. High cog: The question is high cog because the examinee must know that the information in the answer explanation and analyze the event to determine the crew can still proceed with the startup. TMI OPS ILT EXAM Page: 56 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS ILT EXAM Page: 57 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 15 ID: 1737531 Points: 1.00 When required to verify a Radiation Monitoring System Setpoint, which is the PREFERRED METHOD for obtaining a Radiation Monitor's actual setpoints? A Contacting the l&C Department to verify the setpoint. B. Performing a Source Check IAW 1301-4.1, Weekly Surveillance Checks. C. Reading Alarm setpoints from the meter face by pressing the alarm pushbutton. D. Refer to the setpoints section of alarm response OP-TM-MAP-C0101, RADIATION LEVEL HI. Answer: A
\Answer Explanation TMI OPS ILT EXAM Page: 58 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL
<<Explanation: To answer this question correctly, the examinee must know: (1) 1105-8, Radiation Monitoring System a Caution states "Reading Alarm setpoints from the meter face by pressing the Alarm Pushbutton does not give an accurate indication of actual setpoint. This feature is not calibrated and should not be relied upon for accurate setpoint information". (2) Following that caution a procedure step directs setpoint verification by directing l&C department to refer to applicable sections of 1302-3.1 series procedures that govern RMS Monitors covered by Tech Specs or ODCM and IC-177, RMS Calibration for Non-Tech Monitors.
A. Contacting the l&C CORRECT ANSWER: 1105-8, Radiation Monitoring System Caution Department to verify the and procedure step setpoint. B. Performing a Source Check INCORRECT ANSWER: Plausible because performing a source check IAW 1301-4.1, Weekly will bring in the alarms. However, Tech Spec definition 1.13 defines a Surveillance Checks. source check in the following way: A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source. It does not check the actual setpoints of a radiation monitor. C. Reading Alarm setpoints from INCORRECT ANSWER: Plausible because setpoints can be observed the meter face by pressing the when using the pushbutton, however 1105-8 cautions against alarm pushbutton. relying upon it for accurate setpoint information. D. Refer to the setpoints INCORRECT ANSWER: Plausible because there is a setpoints section section of alarm response of this alarm response. Incorrect because this section has no OP-TM-MAP-C0101, setpoints listed and sends the operator to 1101-2.1, RADIATION RADIATION LEVEL HI. MONITORING SYSTEM SETPOINTS. Examination Outline Cross-reference: Level RO SRO Tier# 1 Group# 2 K/A# 061 AA2.03 Importance Rating 3.0 3.3 K/A: Ability to determine and interpret the following as they apply to the Area Radiation Monitoring (ARM) System Alarms: Setpoints for alert and high alarms Proposed Question: RO Question #15 Technical Reference(s): 1105-8, Rev 91 1302-3.1 series procedures Proposed References to be provided to applicants during examination: None Learning Objective: 661-GL0-9 Question Source: Bank# 887632 Modified Bank# TMI OPS ILT EXAM Page: 59 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL New Question History: Simulator Exam 9 Last NRC Exam: None Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 55.41 b.11 55.43 Comments: KA Match: This matches the KA because the question requires the examinee to determine the method to correctly determine the high setpoint on a radiation monitor. The setpoint on the front of the radiation monitor is not calibrated, and cannot be used to correctly verify the high setpoint. TMI OPS ILT EXAM Page: 60 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS ILT EXAM Page: 61 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 16 ID: 1700780 Points: 1.00 Plant Conditions:
- 100% power with ICS in full auto ..
EVENT:
- MAP C-1-1, RADIATION LEVEL HI alarm illuminates.
- RM-L-1-LO (RCS Letdown Rad Monitor) indicates a HIGH ALARM.
- RM-L-1-HI (RCS Letdown Rad Monitor) indicates an ALERT ALARM.
Based on the given conditions, letdown flow (1) isolated, because (2) A. (1) IS (2) RM-L-1-LO HIGH alarm closes MU-V-1A and MU-V1 B, Letdown Cooler Inlet valves B. (1) IS (2) RM-L-1-LO HIGH alarm closes MU-V-2A and MU-V-28, Letdown Cooler Outlet valves C. (1) IS NOT (2) both RM-L-1-LO AND RM-L-1-HI have to be in HIGH Alarm D. (1) IS NOT (2) RM-L 1-LO HIGH alarm does NOT close MU-V-2A and MU-V-28 Answer: D
!Answer Explanation TMI OPS ILT EXAM Page: 62 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL
<<Explanation: To answer this question correctly, the examinee must know: (1) RM-L-1-LO and RM-L-1-HI are not the same radiation monitor; (2) RM-L-1-LO has no interlocks; (3) RM-L-1-HI closes MU-V-2A/2B on a HIGH alarm, but not an ALERT alarm; (4) MU-V-lA and MU-V-lB do isolate letdown but there is no interlock between either of the RM-L-1 detectors.
A. (1) IS INCORRECT: Plausible since the HIGH alarm on some radiation (2) RM-L-1-LO HIGH closes monitors do initiate automatic interlocks, however RM-L-1-LO does MU-V-1A and MU-V1 B, NOT have any interlocks associated with its HIGH Alarm. Closing Letdown Cooler Inlet valves. MU-V-lA&lB would isolate letdown flow. However these valves are closed by other interlocks independent of RM-L-1-LO or RM-L-1-HI. B. (1) IS INCORRECT: Plausible since the High Alarm on some radiation (2) RM-L-1-LO HIGH alarm monitors do initiate Automatic Interlocks, however RM-L-1-LO does closes MU-V-2A and NOT have any interlocks associated with its HIGH Alarm. RM-L-1-HI MU-V-2B, Letdown Cooler HIGH alarm closes MU-V-2A and MU-V-2B. Outlet valves.
- c. (1) IS NOT INCORRECT: Letdown Flow is NOT isolated, BOTH RM-L-1-LO AND (2) Both RM-L-1-LO AND RM-L-1-HI do not need to be in HIGH alarm to isolate letdown, just RM-L-1-HI have to be in RM-L-1-HI needs to be in HIGH. Plausible because the examinee HIGH Alarm. MU-V-2A and could believe that a combination of alarms are required to isolate MU-V-2B letdown.
D. (1) IS NOT CORRECT: Letdown Flow IS NOT isolated because MU-V-2A and (2) RM-L 1-LO "High Alarm" MU-V-2B remain open since they do NOT close from RM-L-1-LO does NOT close MU-V-2A being in HIGH Alarm. and MU-V-2B. Examination Outline Cross-reference: Level RO SRO Tier# 1 Group# 2 KIA# 076 AA1.04 Importance Rating 3.2 3.4 KIA: High Reactor Coolant Activity: Ability to operate and I or monitor the following as they apply to the High Reactor Coolant Activity: Failed fuel-monitoring equipment Proposed Question: RO Question #16 Technical Reference(s): TQ-TM-104-661-C001 1105-8 Proposed References to be provided to applicants during examination: None Learning Objective: 661-GL0-10 Question Source: Bank # Modified Bank # New x TMI OPS ILT EXAM Page: 63 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Question History: NIA Last NRC Exam: N/A Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 b.7 55.43 Comments: KIA Match: This question matches the KA because the examinee is required to recall the interlocks of RM-L-1-Hi which is the radiation monitor that is used to detected failed fuel. RM-L-1-HI takes a stream off the letdown line, which is RCS water going to the makeup tank. TMI OPS IL T EXAM Page: 64 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS ILT EXAM Page: 65 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL 17 ID: 1720243 Points: 1.00 Plant Conditions:
- 100% power with ICS in full auto.
Event:
- The ICS Selected Feedwater Loop Temperature transmitter slowly fails high.
The Total Feedwater demand signal will _(1 )_due to _(2)_. A. (1) rise (2) BTU limits B. (1) rise (2) Feedwater Temperature Modification C. (1) lower (2) BTU limits D. (1) lower (2) Feedwater Temperature Modification Answer: B
!Answer Explanation TMI OPS ILT EXAM Page: 66 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL
<<Explanation: To answer this question correctly, the examinee must know: (!)There is NO effect on BTU Limits since the transmitter failed high; (2) The operation of the FW temperature circuit compares actual FW temperature (Failed Temperature Transmitter) to a calculated temperature based on Total FW Demand; (3) In this question the circuit would raise FW Demand since the control system thinks Actual FW Temperature is hotter than calculated thus raise FW Flow to match FW Flow heat removal capacity to match Reactor heat output.
A. (1) rise INCORRECT: Plausible since FW Temperature is an input to (2) BTU limits the BTU Limit Circuit, however, with FW temperature failing high has no effect. If FW temperature had failed low, it would reduce FW Flow. B. (1) rise CORRECT: FW temperature Modification is used to correct FW (2) Feedwater Temperature demand for a given load such that there is balance of BTU exchange Modification between the primary and secondary side of the steam generator. So, if FW temp is higher than the calculated expected average FW temp than FW demand signal will rise.
- c. (1) lower INCORRECT: Plausible since FWtemperature is an input to the (2) BTU limits BTU limit circuit and would lower FW flow on a low failure.
D. (1) lower INCORRECT: Plausible if Examinee does NOT understand how the (2) Feedwater Temperature control system process compares actual FW temperature with Modification calculated FW temperature. Examination Outline Cross-reference: Level RO SRO Tier# 1 Group# 2 KIA# A02 AK2.1 Importance Rating 3.8 4.0 KIA: Loss of NNl-X/Y: Knowledge of the interrelations between the (Loss of NNl-X) and the following: Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features. Proposed Question: RO Question # 17 Technical Reference(s): OP-TM-104-621-C001, Rev 10 ICS FW Analog & Digital Prints Proposed References to be provided to applicants during examination: NONE Learning Objective: 621-GL0-11 Question Source: Bank# 357040 Modified Bank # New Question History: System Exam 13 Last NRC Exam: N/A TMI OPS ILT EXAM Page: 67 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 b.7 55.43 Comments: KA Match: This question matches the KA because the examinee must have knowledge of how a Feedwater Temperature failure affects the ICS system for automatic control. High Cog: This question is High Cog because the examinee has to understand the control system interface, with respect to Main FW control. The examinee must know the control system compares Actual FW Temperature to Calculated Temperature and analyze the effects of a failure. TMI OPS ILT EXAM Page: 68 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS ILT EXAM Page: 69 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 18 ID: 1737211 Points: 1.00 To avoid damage due to gas in the Makeup Pumps, (1) must be closed if Makeup Tank level lowers to less than (2) inches with s_uction from LPI or the BWST. A. (1) MU-V-18, RCS Makeup Isolation Valve (2) 18 inches
- 8. (1) MU-V-12, Makeup Tank Outlet Isolation Valve (2) 18 inches C. (1) MU-V-18, RCS Makeup Isolation Valve (2) 40 inches D. (1) MU-V-12, Makeup Tank Outlet Isolation Valve (2) 40 inches Answer: B
!Answer Explanation TMI OPS IL T EXAM Page: 70 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL
<<Explanation: To answer this question correctly, the examinee must know: (1) In OP-TM-211-000 Precautions & Limitations: To avoid pump damage due to gas entrainment in the pump, MU-V-12 must be closed if MU Tank level is less than 18 inches and LPI or BWST is supplying MU Pump Suction; (2)
When a Makeup Pump is lined up for suction from LPI or the BWST, the only separation between those sources and the Makeup Tank is MU-V-112, which is a check valve; (3) The Makeup Pump source will be from the source with the highest pressure, which in some instances (based on BWST level or LPI flow) could the the Makeup Tank, which has a low inventory< 18 inches, could cause gas to be admitted to the Makeup Pump. A. (1) MU-V-18, RCS Makeup INCORRECT: Plausible if the examinee thinks it is necessary Isolation Valve to isolate other Makeup Pump flowpaths to prevent possible (2) 18 inches Makeup Pump Runout. Part 2 is correct. B. (1) MU-V-12, Makeup Tank CORRECT: See above Outlet Isolation Valve (2) 18 inches C. (1) MU-V-18, RCS Makeup INCORRECT: Plausible because the minimum level to ensure the Isolation Valve Makeup Pump has adequate NPSH when the suction source is the (2) 40 inches Makeup Tank exclusively is 40". If NPSH were a concern, the examinee could believe lowering the flow by closing MU-V-18 could fix the NPSH issue. D. (1) MU-V-12, Makeup Tank INCORRECT: Plausible since Part 1 is correct and thinks that 40" is Outlet Isolation Valve the correct setpoint. (2) 40 inches Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 1 KJA# 004 A1.06 Importance Rating 3.0 3.2 KJA: Chemical and Volume Control System: Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CVCS controls including: VCT level Proposed Question: RO Question #18 Technical Reference(s): OP-TM-211-000, Rev 33 Proposed References to be provided to applicants during examination: None Learning Objective: 211-GL0-14 Question Source: Bank # Modified Bank # New x TMI OPS ILT EXAM Page: 71 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Question History: NIA Last NRC Exam: N/A Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 b.5 55.43 Comments: KA Match: This question matches the KA because the examinee must know that the lowering level in the Makeup Tank (VCT) could exceed a design limit for the CVCS system. TMI OPS ILT EXAM Page: 72 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS ILT EXAM Page: 73 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 19 ID: 1737168 Points: 1.00 REFERENCE PROVIDED Plant Conditions:
- Plant Cooldown in Progress
- All 4 Reactor Coolant Pumps are OFF
- DH-P-1A is Operating.
- RCS Temperature 170F=
- RCS Pressure = 250 psig Curve (1) prevents exceeding LTOP limits. The temperature instrument monitored to prevent exceeding these limits is (2)
A. (1) Curve A (2) DH6-Tl-1 Decay Heat Suction Temperature B. (1) Curve B (2) DH6-Tl-1 Decay Heat Suction Temperature C. (1) Curve A (2) DH2-Tl-1 Decay Heat Cooler Outlet Temperature D. (1) Curve B (2) DH2-Tl-1 Decay Heat Cooler Outlet Temperature Answer: C
\Answer Explanation TMI OPS ILT EXAM Page: 74 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL
<<Explanation: To answer this question correctly, the examinee must know: (1) The 1102-11 Limits and Precautions directs reactor coolant temperature to be maintained within limits specified in Enclosure 4, Figure 1 and lA one of which is the LTOP and SURGE Line Limit (CURVE A); (2) The operators must ensure the pressure and temperature remain to the below and to the right of CURVE A; (3) The examinee must know the correct instruments to monitor to ensure the cooldown rate and LTOP limits are not violated, which for these plant conditions (RCPs secured, while on DHR) is DH2-Tll or 2; (4)
CURVE Bis the Spray Restriction line. A. (1) Curve A INCORRECT: Plausible since the operator may assume DH Suction (2) DH6-Tl-1 Decay Heat Temperature used during a cooldown. Incorrect because after Suction Temperature RCPs are secured DH Cooler Outlet Temp is used. Curve A is correct. B. (1) Curve B INCORRECT: Plausible since the operator may assume DH Suction (2) DH6-Tl-1 Decay Heat Temperature used during a cooldown. Incorrect because after Suction Temperature RCPs are secured DH Cooler Outlet Temp is used. Curve Bis incorrect.
- c. (1) Curve A CORRECT: See above (2) DH2-Tl-1 Decay Heat Cooler Outlet Temperature D. (1) Curve B INCORRECT: Plausible since the temperature indication is correct (2) DH2-Tl-1 Decay Heat but CURVE Bis the Spray Restriction Curve.
Cooler Outlet Temperature Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 1 K/A# 005 K5.0l Importance Rating 2.6 2.9 K/ A: Residual Heat Removal System: Knowledge of the operational implications of the following concepts as they apply the RHRS: Nil ductility transition temperature (brittle fracture) Proposed Question: RO Question #19 Technical Reference(s): TQ-TM-104-212-COOl, Rev 17 Tech Spec 3.1.2 1102-11, Rev 153B Proposed References to be provided to applicants during examination: 1102-11 Fig lA Learning Objective: 212-GL0-10 Question Source: Bank# Modified Bank# New x Question History: N/A Last NRC Exam: N/A TMI OPS ILT EXAM Page: 75 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 b.5 Comments: KA Match: This question matches the KA because the reference curves in 1102-11 are developed in ensure that NDT and cyclic stress limits are not violated. The examinee must know which instrument is used to ensure the LTOP curve A is NOT violated. TMI OPS ILT EXAM Page: 76 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS ILT EXAM Page: 77 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 20 ID: 1700999 Points: 1.00 Plant conditions:
- Plant Cooldown is in progress in accordance with 1102-11.
- RCS pressure is 60 psig and steady prior to venting.
- OP-TM-220-552, VENTING THE PRESSURIZER TO THE RCDT (WDL-T-3), has been initiated to lower pressurizer pressure.
To prevent large pressure transients during the Pressurizer venting, the operator must _ _ __ A. open RC-V-18, Manual Pzr Vent to RCDT. B. throttle open RC-V-28, Pressurizer Vent Valve, for 1 second. C. throttle open RC-V-1, Spray Valve, to help lower Pressurizer pressure. D. ensure RCDT cooling pump (WDL-P-8) is in AUTO with both ICCW Pumps running. Answer: B
!Answer Explanation TMI OPS IL T EXAM Page: 78 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL
<<Explanation: To answer this question correctly, the examinee must know: (1) During and plant cooldown, to lower RCS pressure in the latter stages, the pressurizer is vented to the RCDT; (2) To limit pressure and/or level transients, RC-V-28 is throttled open in small amounts (1 second per procedure);
(3) At 60 psig in the cooldown, no RCPs are running so spray from RC-V-1 is not available. A. open RC-V-18, Manual Pzr Vent INCORRECT: Plausible since this is a vent valve to the RCDT; however to RCDT. it is not allowed to be open when the RCS is > 45 psig to prevent overpressurizing the RCDT. B. throttle open RC-V-28, CORRECT: A CAUTION in OP-TM-220-552 says to use small taps on Pressurizer Vent Valve, for 1 RC-V-28 open pushbutton to avoid large pressure or level transients. second. The procedure step is to throttle open for 1 second. C. throttle open RC-V-1, Spray INCORRECT: Plausible since RC-V-1 is the normal spray valve; Valve, to help lower Pressurizer however the last RCP was shut down prior to the venting operation pressure. being initiated. D. ensure RCDT cooling pump INCORRECT: Plausible since two ICCW Pumps will be run if the RCS (WDL-P-8) is in AUTO with both temperature was >400°F; however WDL-P-8 will be started and run ICCW Pumps running. continuously during the venting operation and the RCS temperature cannot be> 400°F based on the given condition of 60 psig in the RCS. Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 1 K/A# 007 2.1.23 Importance Rating 4.3 4.4 K/A: Ability to perform specific system and integrated plant procedures during all modes of plant operation. Proposed Question: RO Question# 20 Technical Reference(s): OP-TM-220-000, Rev 23 OP-TM-220-552, Rev 6 Proposed References to be provided to applicants during examination: None Learning Objective: 220-GL0-10 Question Source: Bank# 8672881 Modified Bank# New Question History: N/A Last NRC Exam: N/A Question Cognitive Level: Memory or Fundamental Knowledge x TMI OPS IL T EXAM Page: 79 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Comprehension or Analysis 10 CFR Part SS Content: SS.41 b.10 SS.43 Comments: K/A Match: This question matches the KA because the examinee will have do demonstrate knowledge regarding the ability to mitigate large pressure transients during and RCS cooldown. The examinee will have to have knowledge of the procedure to vent the Pressurizer to the RCDT. TMI OPS ILT EXAM Page: 80 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS ILT EXAM Page: 81 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 21 ID: 1701024 Points: 1.00 Plant Conditions:
- 100% power with ICS in full auto.
- EFW Area Cooling Fan, AH-E-24A, is operating.
- EFW Area Cooling Fan, AH-E-248, is in standby.
- Emergency Feedwater Pump, EF-P-2A is running for an IST.
EVENT:
- Nuclear Service Closed Cooling Water Inlet Temperature Controller to AH-E-24A Coolers, TC-857, Fails LOW.
As a result of this controller failure, identify the resulting effect(s): AH-E-24A trips due to high (1) temperature, and AH-E-248 (2) A. (1) outlet (2) automatically starts B. (1) outlet (2) can be started manually C. (1) motor (2) automatically starts D. (1) motor (2) can be started manually Answer: B [Answer Explanation TMI OPS ILT EXAM Page: 82 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL
<<Explanation: To answer this question correctly, the examinee must know: (1) AH-E-24A/24B have NO autostart features; (2) Fan outlet temperature is monitored by a temperature Switch TS-766A/766B; (3)
The fan Motor does NOT have a Temperature Switch; (4) Since the NSCCW Temperature Controller failed LOW, the affect would reduce NSCCW Flow to the fan coolers resulting in fan outlet temperature rising (sensed by TS-766A); (5) At 125F the operating Fan would trip; (6) Alarm response HVA-5-8 would direct starting of the standby fan as long as there is no fire present (the stem of the question gives no indication of a fire). A. (1) outlet INCORRECT: With the NSCCW Temperature Controller failed low, (2) automatically starts NSCCW inlet valve would close which would reduce cooling flow to the Fan Cooling Coils. This would result in fan discharge temperature rising. At 125F the fan would trip. AH-E-24B does not have an autostart feature. This is plausible because many components have autostart features on temperature and/or a trip. B. (1) outlet CORRECT: With the NSCCW temperature controller failed low, (2) can be started manually NSCCW inlet valve would close which reduces cooling flow to the fan cooling coils resulting in fan discharge temperature rising. At 125F the fan would trip. AH-E-24B does not have an autostart feature and could be manually started. C. (1) motor INCORRECT: Plausible since an operator may believe that the fan (2) automatically starts would trip on high motor temperature as opposed to fan discharge temperature. Since AH-E-24B is in standby, it would have to be manually started since there is no autostart feature on these fans. D. (1) motor INCORRECT: Plausible since an operator may believe that the fan (2) can be started manually would trip on high motor temperature as opposed to fan discharge temperature. Since AH-E-24B is in standby, it could be manually started since there is no autostart feature on these fans. Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 2 K/A# 008 A4.09 Importance Rating 3.0 2.9 K/A: Component Cooling Water System: Ability to manually operate and/or monitor in the control room: CCW temperature control valve Proposed Question: RO Question# 21 Technical Reference(s): HVA-5-8 Rev 9 TQ-TM-104-821-COOl, Rev 2 Proposed References to be provided to applicants during examination: None Learning Objective: 821-GL0-010 Question Source: Bank# TMI OPS ILT EXAM Page: 83 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Modified Bank# New x Question History: N/A Last NRC Exam: N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 b.7 55.43 Comments: KA Match: This question matches the KA because the examinee will have to know that the operator has to manually operate AH-E-24B from the control room if the temperature control valve for the CCW to the AH-E-24A fan were to fail. High Cog: This question is high cog because the examinee has to identify the effect of the temperature controller failing low and the response of the associated control valve. This would result in the control valve closing, reducing cooling flow. The fan outlet temperature would rise, which is the signal monitored to for trip the operating fan. TMI OPS ILT EXAM Page: 84 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS ILT EXAM Page: 85 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL 22 ID: 1701070 Points: 1.00 Plant Conditions:
- 100% power with ICS in full auto.
EVENT:
- Pressurizer heater pressure control SETPOINT (RC3-PIC) signal fails to zero (0) psig.
What action(s) are required? A. Place the Diamond Rod Control station in manual and insert control rods. B. Place the Pressurizer Spray Valve, RC-V-1 in Manual and CLOSE RC-V-1. C. Verify all pressurizer heaters are deenergized OR manually deenergize heaters.
- 0. Adjust Heater Banks 1, 2 & 3 using RC3PIC, Pressurizer Pressure control in hand.
Answer: D
~nswer Explanation TMI OPS ILT EXAM Page: 86 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL
<<Explanation: To answer this question correctly, the examinee must know: (1) That the SETPOINT signal only affects PZR Heater Banks 1, 2, & 3 while the controller is in auto (2) the controller failing to 0 psig means heaters will not start at the desired setpoint (3) the crew can place the Pzr Controller in HAND per OS-24 and operate per OP-TM-220-503, "Manual Control of the Pzr" at that point the pressure lowering transient is concluded. Even though OP-TM-220-503 does NOT address instrument failures, control of RCS pressure is ensured more quickly and smoothly by entering and performing this procedure. (4) The mental process involved is that RCS pressure will lower if heaters are not on to account for losses.
A. Place the Diamond Rod Control INCORRECT - Plausible if the analysis of the transient were to station in manual and insert mistakenly lead to the determination that ALL the requirement for control rods. entry into OP-TM-AOP-070 were met. B. Place the Pressurizer Spray INCORRECT - Plausible if the analysis of the failure causes the Valve, RC-V-1 in Manual and examinee to believe that the spray valve could erroneously open. CLOSE RC-V-1. This could happen on other pressure instrument/controller failures. C. Verify all pressurizer heaters INCORRECT - Plausible if the analysis of the failure causes the are deenergized OR manually examinee to believe that the setpoint failing low energizes the deenergize heaters. heaters. This could happen on other pressure instrument/controller failures. D. Adjust Heater Banks 1, 2 & 3 CORRECT - See above. using RC3PIC, Pressurizer Pressure control in hand. Examination Outline Cross-reference: Level RO SRO Tier# 1 Group# 1 K/A# 027 AAl.01 Importance Rating 4.0 3.9 K/A: Pressurizer Pressure Control System Malfunction: Ability to operate and/ or monitor for the following as they apply to the Pressurizer Pressure Control Malfunctions: PZR heaters, sprays, and PO RVs Technical Reference(s): OP-TM-220-503, Rev 4 Proposed Question RO Question #22 Proposed References to be provided to applicants during examination: None Learning Objective: 220-GL0-11 Question Source: Bank# 897217 Modified Bank# New Question History: Last NRC Exam: N/A TMI OPS ILT EXAM Page: 87 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 7 55.43 Comments: KA MATCH: This is KA match because the operate will have to understand that heaters must be operated in manual with this controller failure. HIGH COG: This is High Cog because they will have to realize the heater setpoint failing to zero will only effect the pressurizer heaters and then that manual operation is required to control the plant. TMI OPS IL T EXAM Page: 88 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS IL T EXAM Page: 89 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 23 ID: 1701075 Points: 1.00 Initial plant conditions:
- Reactor trip due to LOCA.
- Containment Building pressure 5 psig, steady.
- Manual ESAS actuation signals were NOT initiated.
- Automatic ES Actuation status:
ES 8ct1Jatioo Ira..in.A Ir:ain-8 1600# Actuated (NOT Bypassed) Bypassed 500# Not Actuated Not Actuated 4# Defeated Actuated (NOT Defeated) EVENT:
- Containment Building pressure rises rapidly to 35 psig.
Based on these conditions, identify the ONE statement below that describes the response of the Reactor Building Spray System A. Only BS-P-1A starts. B. Only BS-P-1 B starts. C. Both BS-P-1A and BS-P-1 B start. D. Neither BS-P-1A nor BS-P-1 B starts. Answer: C
!Answer Explanation TMI OPS ILT EXAM Page: 90 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL
<<Explanation: To answer this question correctly, the examinee must know: (1) RB Pressure of 30 psi is ONE input to the Start Signal for a building spray pump; (2) The other requirement is a Block 4 permissive signal from any or the following ESAS Actuation signals: 1600 psig OR 500 psig OR 4 psig; (3)
While the 4 psig signal is the only signal that opens the BS valves the other signals (1600 psig & 500 psig) input to the Block 4 permissive signal; (4) The BS Pump start signal does not require the BS valves to be open for the pump to start. A. Only BS-P-lA starts. INCORRECT: Distracter is plausible because it acknowledges BS-P-lA starts due to ES Block 4 permit from 1600 psi. This distracter is based on the misconception that BS pumps require a Block 4 start permit (from 1600/500# ES actuation) in order to automatically start at 30 psig. B. Only BS-P-lB starts. INCORRECT: Distracter is plausible because it acknowledges that BS-P-lB will start. This distracter is based upon the common misconception that BS pumps require a Block 4 start permit from 4# ES actuation (opens BS valves) in order to start at 30 psig. C. Both BS-P-lA and BS-P-lB CORRECT: Both BS Pumps start since both the 1600 psi start. (Train A) and 4 psi (Train B) signals provide Block 4 permissive signals to enable the BS Pumps to start at 30 psi. D. Neither BS-P-lA and BS-P-lB INCORRECT: Plausible since Part of Train A (4 psi) is in Defeat and start. part of Train B (1600 psi) is Bypassed preventing Block 4 BS Pump Permissive Signal. Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 1 K/A# 013 Kl.01 Importance Rating 4.2 4.4 K/ A: Knowledge of the physical connections and/or cause effect relationships between the ES FAS and the following systems: Initiation signals for ESF circuit logic Proposed Question: RO Question #23 Technical Reference(s): TQ-TM-104-642-COOl, Rev 7 ESAS Electrical Prints Proposed References to be provided to applicants during examination: None Learning Objective: 642-GL0-10 Question Source: Bank# 371299 Modified Bank# New TMI OPS IL T EXAM Page: 91 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Question History: N/A Last NRC Exam: N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 b.7 55.43 Comments: (KA Match, why high cog, why SRO only) KA MATCH: This question matches the KA because the examinee must have knowledge of the initiation signals which start the Reactor Building Spray pumps, which is an ES system. HIGH COG: This question is High Cog because the examinee must analyze the reactor building conditions and the actuated/defeated ES signals to determine which (if any) reactor building spray pumps start. TMI OPS ILT EXAM Page: 92 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS ILT EXAM Page: 93 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 24 ID: 1701092 Points: 1.00 REFERENCE PROVIDED Plant Conditions:
- 100% power with ICS in full auto.
- RB Cooling Fans AH-E-1NB/C are all operating in FAST SPEED.
- Main Steam System leak inside the Containment Building.
- RB Temperature Elevation > 320 is at 132F and slowly rising.
- NN-2-7 RB AIR TEMP HI is in Alarm
- RB Pressure 2.3 psig Event:
- AH-E-1A trips due to THERMAL OVERLOAD (49F).
- Thermal overload condition has NOT been reset at AH-E-1A breaker.
Based on these conditions, AH-E-1A (1) automatically start if ES actuates and IAW OP-TM-534-901, RB Emergency Cooling Operations, AH-E-1A must be started in _(2)_ speed. A. (1) will (2) slow B. (1) will not (2) slow C. (1) will (2) fast D. (1) will not (2) fast Answer: A
!Answer Explanation TMI OPS ILT EXAM Page: 94 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Explanation: To answer this question correctly, the examinee must know: (1) Separate thermal overload contacts exist for slow and fast speed operation (see reference 208-561, 49F/S contacts in blocks B6 and BS); (2) Operation at slow speed would not be affected by the fast speed thermal overload contact tripping; (3) ES Actuation signal will start the fan in slow speed and is not effected by the fast speed thermal overload contact; (4) Since RB Pressure is> 2 psig, the procedure requires the fan be manually started in Slow Speed (6) in addition, have the ability to interpret station electrical drawings. A. (1) will CORRECT: Refer to 208-561. Two independent thermal overload (2) slow contacts, one for slow speed operation and one for fast speed operation. ES Actuation starts fans in slow speed. Starting the fan in slow speed is required per the procedure. B. (1) will not INCORRECT: Distracter is plausible because examinee may think (2) slow the thermal overload blocks the ES Actuation signal. AH-E-lA fan will auto start in slow speed if ES actuates, since they are separate thermal overload protection for the fast and slow speed motor contactors. AH-E-lA fan can be manually started in slow speed. C. (1) will INCORRECT: Plausible since the fan will auto start in slow speed if (2) fast ES actuates. Plausible if the examinee does not understand that if RB Pressure is >2 psig the procedure requires starting the fan in slow speed. D. (1) will not INCORRECT: AH-E-lA fan can be manually started in SLOW speed, (2) fast and will auto start in slow speed if ES actuates. The examinee may think the thermal overload blocks the ES Actuation. Plausible if the examinee does not understand that if RB Pressure is >2 psig the procedure requires starting the fan in slow speed .. Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 1 K/A# 022 A2.03 Importance Rating 2.6 3.0 K/A: Containment Cooling System: Ability to (a) predict the impacts of the following malfunctions or operations on the CCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Fan motor thermal overload/high-speed operation Proposed Question: RO Question #24 Technical Reference(s): Electrical Print 208-561, 208-461 MAP NN-2-7 alarm response, Rev 2 OP-TM-534-901Rev14 Electrical Prints Proposed References to be provided to applicants during examination: 208-561 208-461 Learning Objective: 824-GL0-10 TMI OPS ILT EXAM Page: 95 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL Question Source: Bank# Modified Bank# 371313 New Question History: N/A Last NRC Exam: N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 b.5 55.43 Comments: KA Match: This question matches the KA because the examinee must be able to predict the impact of an actuated thermal overload on the normal and ES operation of the RB Emergency cooling fans and identify the procedure requirement for starting the fan based on RB Pressure. HIGH COG: This question is high cog because the examinee must analyze the given station drawing to predict the impact of the actuated thermal overload and identify the procedure requirement for the given plant conditions. Plant conditions: Reactor is operating at 100% power, with JCS in full automatic. RB Cooling Fans AH-E-1A/B/C are all operating in FAST SPEED. Main Steam System leak inside the Containment Building. Event: AH-E-1A trips due to THERMAL OVERLOAD. Thermal overload condition has NOT been reset at AH-E-1A breaker. Based on these conditions, identify the ONE selection below that describes impact on AH-E-1A operations: (1) Ability to manually start AH-E-1A in SLOW speed; (2) Automatic ES operation. (3) Reason for impact. A. (1) Can be manually started in slow speed. (2) Will automatically start if ES actuates. (3) Thermal overload protection only applies to FAST speed operation. B. (1) Can be manually started in slow speed. (2) Will automatically start if ES actuates. (3) SEPARATE thermal overload protection is provided for the high and slow speed motor contactors. C. (1) CANNOT be manually started in slow speed. (2) Will automatically start if ES actuates. (3) COMMON thermal overload protection (for fast AND slow speeds) is DEFEATED by ES actuation. TMI OPS IL T EXAM Page: 96 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL D. (1) CANNOT be manually started in slow speed. (2) Will NOT automatically start if ES actuates. (3) COMMON thermal overload protection (for fast AND slow speeds) is NOT defeated by ES actuation. Answer: B TMI OPS ILT EXAM Page: 97 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL TMI OPS IL T EXAM Page: 98 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 25 ID: 1718554 Points: 1.00 Plant Conditions:
- 100% power with ICS in full auto.
- OP-TM-621-251 SASS Logic Test in Progress.
- Test 'A' on Nl-5 I Nl-6 Rx Pwr was successful, however the SASS channel FAILED to reset.
- Nl-5 is selected for control.
EVENT:
- Nl-5 upper chamber power supply fails to zero volts.
The crew (1) , because (2) A. (1) must immediately enter OP-TM-AOP-070, Primary to Secondary Heat Transfer Upset (2) reactor power would be lowering B. (1) must immediately enter OP-TM-AOP-070, Primary to Secondary Heat Transfer Upset (2) reactor power would be rising C. (1) must immediately enter OP-TM-EOP-001, Reactor Trip (2) the Nl-5 failure would cause a reactor trip D. (1) would have NO required actions (2) the SASS would automatically transfer to Nl-6 for reactor control Answer: B
!Answer Explanation TMI OPS ILT EXAM Page: 99 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL
<<Explanation: To answer this question correctly, the examinee must know: (1) When the SASS channel fails to reset, that the SASS channel would not swap to a good instrument on a failure of the controlling instrument; (2) When the Nl-5 upper chamber power supply fails to zero volts, the Nl-5 indicated power drops to 50%; (3) Because the SASS is failed, when Nl-5 fails low, the an ICS transient would occur that pulls control rods to maintain reactor power; (4) When control rods pull, reactor power would rise; (5)
Nl-5 could reach an RPS trip setpoint, but this would be the only immediate reactor trip signal; (6) To mitigate this plant transient, the crew would enter OP-TM-AOP-070 because a plant transient would be occurring requiring manual operation, and no valid ICS runback is present. A. (1) must immediately enter INCORRECT: The entry criteria for OP-TM-AOP-070 will be met, but OP-TM-AOP-070, Primary to reactor power would be rising. This is plausible if the examinee Secondary Heat Transfer Upset believes Nl-5 failing low would result in plant runback. (2) reactor power would be lowering B. (1) must immediately enter CORRECT: See above. OP-TM-AOP-070, Primary to Secondary Heat Transfer Upset (2) reactor power would be rising C. (l)must immediately enter INCORRECT: Plausible if examinee believes if the examinee believes OP-TM-EOP-001, Reactor Trip the Nl-5 failure input to RPS would initiate a reactor trip which (2) the Nl-5 failure would cause would require entry into OP-TM-EOP-001. If OP-TM-AOP-070 was a reactor trip not entered, a reactor trip could occur, but this failure in itself would not cause a reactor trip. D. (1) would have NO required INCORRECT: Plausible because this is how the system should work if actions the Nl-5 upper chamber power supply failed low. Incorrect because (2) the SASS would the SASS channel failed to reset in the stem of the question. automaticaly transfer to Nl-6 for reactor control Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 2 K/A# 015 A2.01 Importance Rating 3.5 3.9 K/A: Nuclear Instrumentation System: Ability to (a) predict the impacts of the following malfunctions or operations on the NIS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Power supply loss or erratic operation Proposed Question: RO Question # 25 Technical Reference(s): TQ-TM-104-621-COOl OP-TM-AOP-070, Rev 5 OP-TM-621-251 Rev 2 Proposed References to be provided to applicants during examination: None Learning Objective: 621-GL0-10 TMI OPS ILT EXAM Page: 100 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL Question Source: Bank# Modified Bank# New x Question History: N/A Last NRC Exam: N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 55.43 Comments: KA Match: This question matches the KA because the examinee must know the effects of a failing power supply on plant operations, and choose the procedure to mitigate the failure. High Cog: This question is high cog because the examinee must analyze the effect of the failure and determine plant response and determine that the response will meet the threshold for the entry criteria of OP-TM-AOP-070. TMI OPS ILT EXAM Page: 101 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS ILT EXAM Page: 102 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL 26 ID: 1720398 Points: 1.00 Which one of the following describes the operation of the Main Feedwater Pump Monitoring circuit that provides Emergency Feedwater with an input from the Heat Sink Protection System? EACH PUMP uses: A. Two pressure bistables to sense Main Feedwater Pump discharge pressure. B. Three pressure bistables to sense Main Feedwater Pump discharge pressure. C. Two pressure bistables to sense hydraulic oil pressure at the Main Feedwater Pump turbine stop valves. D. Three pressure bistables to sense hydraulic oil pressure at the Main Feedwater Pump turbine stop valves. Answer: C
!Answer Explanation TMI OPS ILT EXAM Page: 103 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL
<<Explanation: To answer this question correctly, the examinee must know: (1) Each HSPS train monitors one pressure bistable at each MFW pump; (2) Both pressure bistables on each MFW pump lower below the pressure setpoint for to get a signal to each HSPS train; (3) When an HSPS train sees both MFW pumps tripped, it will send an actuation signal to that trains associated EFW components.
A. Two pressure bistables to INCORRECT: This is plausible because the presence of Feed sense Main Feedwater Pump discharge pressure would be indicative of the operating Pump discharge pressure. status of the Main Feed Pump. The operator may incorrectly believe that the parameter sensed to determine that the FW Pump is operating or not is the discharge pressure. B. Three pressure bistables to INCORRECT: This is plausible because the presence of Feed sense Main Feedwater Pump discharge pressure would be indicative of the operating Pump discharge pressure. status of the Main Feed Pump. The operator may incorrectly believe that the parameter sensed to determine that the FW Pump is operatinq or not is the discharge pressure.
- c. Two pressure bistables to CORRECT: See above.
sense hydraulic oil pressure at the Main Feedwater Pump turbine stop valves. D. Three pressure bistables to INCORRECT: This is plausible because there are nine bistables sense hydraulic oil pressure per pump, three of them are associated with the Main Turbine at the Main Feedwater Pump Trip Circuit. The operator may incorrectly believe that the three turbine stop valves. bistables are associated with the HSPS as well. Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# K/A# 061 K1.02 Importance Rating 3.4 3.7 K/A: Auxiliary I Emergency Feedwater System: Knowledge of the physical connections and/or cause-effect relationship between the AFW and following systems: MFW System Proposed Question: Question 26 Technical Reference(s): TQ-TM-104-644-C001 Proposed References to be provided to applicants during examination: None Learning Objective: 644-GL0-3 Question Source: Bank# 909174 Modified Bank # New TMI OPS ILT EXAM Page: 104 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Question History: Last NRC Exam: 10-02 Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 b.7 55.43 Comments: (KA Match, why high cog, why SRO only) KA Match: This question matches the KA because the operator must demonstrate knowledge of the physical connections and/or cause-effect relationships between the EFW and the MFW System. This is accomplished by requiring that the operator identify the number of bistables used in the MFW Pump monitoring circuit, and the parameter that is sensed to determine that the MFW Pumps are tripped to automatically start the EFW Pumps. TMI OPS ILT EXAM Page: 105 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS ILT EXAM Page: 106 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 27 ID: 1737222 Points: 1.00 Plant conditions:
- Reactor critical at 1o-8 amps.
- Crew is performing a middle of cycle startup from a 3 week forced outage.
- ICS in HAND, EXCEPT for the Main & Startup Feedwater Valves and Turbine Bypass Valves.
- Power escalation is on hold; will recommence in one hour.
EVENT:
- MS-V-30, Turbine Bypass Valve fails OPEN Assume NO Operator actions.
Which statement below describes the plant response to this failure? A. RCS pressure lowers and the Reactor trips on low pressure. B. Reactor power increases to the 'Point of Adding Heat' and stabilizes at -1 %. C. Reactor power increases above the 'Point of Adding Heat' and then stabilizes at -3%. D. Reactor power increases to the 'Point of Adding Heat' and then lowers to 1o- 8 Amps in the Intermediate Range. Answer: C
!Answer Explanation TMI OPS IL T EXAM Page: 107 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL
<<Explanation: To answer this question correctly, the examinee must know: (1) With the plant stable at lOE-8 AMPS on the IR and when TBV fails open, this would induce a positive reactivity feedback due to the Moderator Temperature Coefficient; (2) Reactor Power would rise to the Point of Adding Heat and continue to rises as Tave lowers; (3) Eventually the power rise will stop and begin to lower as T-ave begins to rise; (3) Reactor power will stabilize at a lower power (-3%), based on the capacity of the TBV.
A. RCS pressure lowers and the INCORRECT: Plausible since RCS pressure will lower due to the Reactor trips on low pressure. overcooling, however, RCS pressure does NOT reach the the low pressure trip setpoint with a single TBV failing open. B. Reactor Power increases to the INCORRECT: Plausible since reactor power does rise to the Point of
'Point of Adding Heat' and Adding Heat(-1%), however it does NOT stabilize nor return to 1%.
stabilizes at -1% Reactor Power. C. Reactor power increases above CORRECT: See above the 'Point of Adding Heat' and then stabilizes at -3%. D. Reactor power increases to the INCORRECT: Plausible since reactor power does rise to the Point of
'Point of Adding Heat' and then Adding Heat(-1%) and above, and the examinee may think that lowers to 10-s Amps in the eventually Reactor Power will then start to lower and stabilize where Intermediate Range. the transient started.
Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 1 K/A# 039 KS.08 Importance Rating 3.6 3.6 K/A: Main and Reheat Steam System: Knowledge of the operational implications of the following concepts as the apply to the MRSS: Effect of steam removal on reactivity Proposed Question: RO Question# 27 Technical Reference(s): GFES: Reactor Operational Physics TQ-TM-104-411-COOl, Rev 8 Proposed References to be provided to applicants during examination: None Learning Objective: 411-GL0-10 Question Source: Bank# Modified Bank# New x Question History: N/A Last NRC Exam: N/A TMI OPS ILT EXAM Page: 108 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 b.5 55.43 Comments: KA Match: This question matches the KA because the examinee will have to know that when a turbine bypass valve opens up, when the reactor is below the POAH, that the RCS temperature will drop. The RCS temperature drop, will result in positivity reactivity addition, indicated by a +SUR on the JR Instrument. Reactor Power will rise above the Point of Adding Heat and eventually stabilize at ~3% Power on the Ni's. The Three Mile Island systems knowledge being tested is the capacity of the Turbine Bypass Valves. High Cog: This question is high cog because the examinee has to relate the component failure to the effect on RCS temperature and then the effect the change in RCS temperature has on reactivity feedback. TMI OPS ILT EXAM Page: 109 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS IL T EXAM Page: 11 O of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 28 ID: 1717325 Points: 1.00 Plant Conditions:
- 100% power with ICS in full auto.
- EF-P-2B, Motor Driven Emergency Feedwater Pump, is out of service for maintenance.
EVENT:
- All four Reactor Coolant Pumps trip.
- EF-P-1, Steam Driven Emergency Feedwater Pump, tripped on overspeed.
- 1D 4160V ES bus tripped on overcurrent.
- Subcooling margin is 35F and slowly lowering.
- lncore temperatures are rising.
- 'A' OTSG Level is at 36% Operating Range
- 'B' OTSG Level is at 30% Operating Range Based on these plant conditions, the operator is required to feed the OTSG's with (1) at a rate of_
.(2.)__ to promote (3)
A. (1) Main Feedwater (2) >1 Mlbm/hr (3) Natural Circulation B. (1) Main Feedwater (2) >1 Mlbm/hr (3) Boiler Condenser Cooling C. (1) Emergency Feedwater (2) > 215 GPM /OTSGs (3) Boiler Condenser Cooling D. (1) Emergency Feedwater (2) < 515 GPM (3) Natural Circulation Answer: A
!Answer Explanation TMI OPS IL T EXAM Page: 111 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL
<<Explanation: To answer this question correctly, the examinee must know: (1) When all four reactor coolant pumps trip, the reactor trips and enters the examinee into the EOP network; (2) Since EF-P-2B is out of service, EF-P-1 trips, and the 10 4160V bus trips on overcurrent, there are no Emergency Feedwater pumps running, but the Main Feedwater Pumps are still running; (3) After the trip OP-TM-EOP-001 directs the ARO to feed the OTSG's in accordance with OP-TM-EOP-010, Rule 4; (4)
From Rule 4, since subcooling margin is >25F, there is NO requirement to raise level to 75% to 85%; (5) But since there are no reactor coolant pumps operating and and no emergency feedwater, feed with MFW at >lMlb/hr. A. (1) Main Feedwater (2) CORRECT: See above
>lMlbm/hr (3) Natural Circulation B. (1) Main Feedwater (2) INCORRECT: Plausible because the examinee could believe that
>lMlbm/hr (3) Boiler since no reactor coolant pumps are running, that feeding the OTSGs Condenser Cooling at> lMlbm/hr is setting the plant up for boiler condenser cooling.
Incorrect because the OTSGs are being setup to promote natural circulation. C. (1) Emergency Feedwater (2) INCORRECT: Plausible because the examinee could believe that
>215 GPM /OTSGs (3) Boiler Emergency Feedwater is not lost. If Emergency Feedwater was Condenser Cooling. available, and subcooling margin were less than 25F the feedrate would be> 215 GPM/OTSG.
D. (1) Emergency Feedwater (2) < INCORRECT: Plausible because the examinee could believe that 515 GPM to both OTSGs (3) Emergency Feedwater is not lost. If Emergency Feedwater was Natural Circulation available, and only EF-P-2A or EF-P-2B were running, there would be a limit of< 515 GPM. Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 1 K/A# 061 K3.01 Importance Rating 4.4 4.6 K/A: Auxiliary/Emergency Feedwater System: Knowledge of the effect that a loss or malfunction of the AFW will have on the following: RCS Proposed Question: RO Question #28 Technical Reference(s): OP-TM-EOP-010, Rule 4, Rev 19 OP-TM-EOP-0101, Rule 4 basis, Rev 9 Proposed References to be provided to applicants during examination: None Learning Objective: 424-GL0-11 Question Source: Bank# Modified Bank# TMI OPS ILT EXAM Page: 112 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL New x Question History: N/A Last NRC Exam: N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 b.7 55.43 Comments: (KA Match, why high cog, why SRO only) KA MATCH: This question matches the KA because the AFW (EFW for TMI) malfunction results in the operator feeding the OTSGs at a different rate than if all of the EFW pumps were running. High Cog: This question is high cog because the examinee will have to analyze the event in the stem to realize that the reactor is tripped, and that there are no EFW pumps running. TMI OPS ILT EXAM Page: 113 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS ILT EXAM Page: 114 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 29 ID: 1717742 Points: 1.00 In-accordance-with 1107-2C Vital DC Electrical System, which of the following local indications will tell an operator that a battery charger is in the EQUALIZE mode? A. The AC Pilot Light is lit. B. The current flow is at least 50 amps. C. The output voltage is approximately 135 volts. D. Both the AC & DC input and output breakers are closed. Answer: C [Answer Explanation TMI OPS ILT EXAM Page: 115 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Explanation: To answer this question correctly, the examinee must know: (1) In accordance with 1107-2C, the operator observes each charger increases voltage to 135 +/- 2 volts. A. The AC Pilot Light is lit INCORRECT: Plausible if the examinee is NOT familiar with Battery Charger indication. The AC Pilot light is normally LIT. B. The current flow is at least 50 INCORRECT: Plausible since current flow indication is available on amps the Battery Charger. Also, if inverters are on the DC power supply, current could be> 50 amps even in float mode. C. The output voltage is CORRECT: 1107-2C: Observe that the voltmeter on the front of each approximately 135 volts. charger increases to 135 +/- 2 volts. D. Both the AC & DC input and INCORRECT: Plausible because both of these breakers are closed at output breakers are closed. all times of Battery Charger operation. Incorrect because these breakers being closed is not an exclusive indication that a battery charger is in the EQUALIZE mode. Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 1 K/A# 063 A3.01 Importance Rating 2.7 3.1 K/ A: D.C. Electrical Distribution: Ability to monitor automatic operation of the DC electrical system, including: Meters, annunciators, dials, recorders, and indicating lights Proposed Question: RO Question #29 Technical Reference(s): 1107-2C, Rev 12 Proposed References to be provided to applicants during examination: None Learning Objective: 734-GL0-2 Question Source: Bank# 356975 Modified Bank# New Question History: N/A Last NRC Exam: N/A Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 55.41 TMI OPS ILT EXAM Page: 116 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 55.43 Comments: (KA Match, why high cog, why SRO only) KA Match: This question matches the KA because the examinee must know which of the multiple indications listed at possible answer is correct for an equalizing charge (part of the DC distribution system). TM\ OPS ILT EXAM Page: 117 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS ILT EXAM Page: 118 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 30 ID: 1717423 Points: 1.00 Plant Conditions:
- 100% power with ICS in full auto.
- 1M DC Bus is Powered from 1A DC Distribution Panel.
EVENT:
- Steam leak in the Reactor Building.
- The Reactor is tripped.
- RB Pressure increases to 4.2 psig.
10 Minutes Later:
- Loss of Offsite Power Based on the above plant conditions:
(1) transfer capability of 1M DC Bus to its alternate power supply is blocked. This transfer capability is blocked due to the (2) signal. A. (1) Only the auto, (2) undervoltage B. (1) Only the auto, (2) Engineered Safeguards C. (1) Both the auto and manual, (2) under voltage D. (1) Both the auto and manual, (2) Engineered Safeguards Answer: D
!Answer Explanation TMI OPS ILT EXAM Page: 119 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Explanation: To answer this question correctly, the examinee must know: (1) The design is for the lM DC 480V Bus transfer to its alternate power supply when its normal power supply is lost on an undervoltage; (2) Any 1600 psig, 500 psig, or 4 psig ES signal blocks the auto and manual transfer if power were lost to lM DC. A. (1) Only the auto, INCORRECT: Plausible if the examinee has the misconception that (2) undervoltage the Loss of Offsite Power prevents the auto transfer of lM DC. Since AC power is lost, the examinee could believe that lM DC transfer is prohibited for reliability. lM DC is still able to transfer to the alternate power supply when plant conditions/procedures allow. B. (1) Only the auto, INCORRECT: Plausible if the examinee has the misconception that (2) Engineered Safeguards the only the auto transfer is blocked with an ES Actuation signal. The examinee could believe that the operators could still transfer lM manually. Incorrect because the auto and manual transfers are blocked on an ES signal. C. (1) Both the auto and manual, INCORRECT: Plausible if the examinee has the misconception that (2) under voltage the Loss of Offsite Power prevents auto transfer of lM DC. Since AC power is lost, the examinee could believe that lM DC transfer is prohibited for reliability. D. (1) Both the auto and manual, CORRECT: See above (2) Engineered Safeguards Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 1 K/A# 063 K4.02 Importance Rating 2.9 3.2 K/A: DC Electrical Distribution: Knowledge of DC electrical system design feature(s) and/ or interlock(s) which provide for the following: Breaker interlocks, permissives, bypasses and cross-ties. Proposed Question: RO Question #30 Technical Reference(s): TQ-TM-104-740-COOl, Rev 7 Electrical Print SS-209-050, Rev 3 Proposed References to be provided to applicants during examination: None Learning Objective: 642-GL0-11 Question Source: Bank# Modified Bank# 356975 New TMI OPS ILT EXAM Page: 120 of425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Question History: System Exam 12 Last NRC Exam: N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 55.43 Comments: KA Match: This question matches the KA because the examinee must know design feature of lM DC that blocks transfer on an ES. High Cog: This question is high cog because the examinee must recognize that plant conditions would initiate a 4 psi ES Actuation signal and this signal NOT only blocks auto transfer capabilities but prevents manual transfer as well. 1M DC Panel can be powered from 1A or 1B DC Distribution panel. It has both auto and manual ransfer capabilities to one of these power sources. Choose the correct letter below which makes the following statement TRUE. On a n - - - - - - - - - - - - - signal, 1M DC p a n e l - - - - - - - - - - transfer capabilities are prevented. A. under voltage, only auto B. Engineered Safeguards, only auto C. under voltage, both auto and manual D. Engineered Safeguards, both auto and manual Answer: D TMI OPS ILT EXAM Page: 121 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRG EXAM SUBMITTAL TMI OPS ILT EXAM Page: 122 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL 31 ID: 1717750 Points: 1.00 Which ONE of the following describes the electrical power supplies to the following pumps associate with Emergency Diesel Generator, EG-Y-1 B: (1) the Fuel Oil Transfer Pumps, DF-P-1 CID, AND (2) the Auxiliary Fuel Oil Pump, EG-P-1 OB A. (1) The two fuel oil transfer pumps are both AC powered. (2) The Auxiliary Fuel Oil Pump is AC powered. B. (1) The two fuel oil transfer pumps are both AC powered. (2) The Auxiliary Fuel Oil Pump is DC powered. C. (1) One fuel oil transfer pumps is AC powered, One fuel oil transfer pumps is DC powered. (2) The Auxiliary Fuel Oil Pump is AC powered. D. (1) One fuel oil transfer pumps is AC powered, One fuel oil transfer pumps is DC powered. (2) The Auxiliary Fuel Oil Pump is DC powered. Answer: D
!Answer Explanation TMI OPS IL T EXAM Page: 123 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL
<<Explanation: To answer this question correctly, the examinee must know: (1) Each emergency diesel has two fuel transfer pumps, one is AC and one is DC powered; (2) In addition,each diesel has two fuel oil pumps: One is engine driven and the aux fuel oil pump is DC powered.
A. (1) The two fuel oil transfer INCORRECT: Plausible since the examinee may believe that AC pumps are both AC powered. power is used for both fuel oil transfer pumps in addition to the (2) The Auxiliary Fuel Oil Pump Auxiliary Fuel Oil Pump. is AC powered. B. (1) The two fuel oil transfer INCORRECT: Plausible since the examinee may be believe that both pumps are both AC powered. fuel oil transfer pumps are both AC powered and the Auxiliary Fuel (2) The Auxiliary Fuel Oil Pump Oil Pump is DC powered. is DC powered. C. (1) One fuel oil transfer pumps INCORRECT: Plausible because the examinee may believe that is AC powered, One fuel oil Auxiliary Fuel Oil Pump is AC powered. transfer pumps is DC powered. (2) The Auxiliary Fuel Oil Pump is AC powered. D. (1) One fuel oil transfer pumps CORRECT: According to TQ-TM-104-861, lA(lB) ES MCC provides is AC powered, One fuel oil power to Diesel Generator A(B) AC Fuel Pump, DF-P-lA (DF-P-lC); transfer pumps is DC powered. while 125/250 VDC Distribution Panel lP (lQ) provide power to both (2) The Auxiliary Fuel Oil Pump the DC Fuel Transfer Pump, DF-P-lB (DF-P-lD), and the DC Auxiliary is DC powered. Fuel Pump (EG-P-lOA/B). Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 1 K/A# 064 K2.02 Importance Rating 2.8 3.1 K/ A: Emergency Diesel Generators: Knowledge of bus power supplies to the following: Fuel Oil Pumps Proposed Question: RO Question# 31 Technical Reference(s): 1107-5, Rev 151 Proposed References to be provided to applicants during examination: None Learning Objective: 861-GL0-4 Question Source: Bank# 860277 Modified Bank# New TMI OPS ILT EXAM Page: 124 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Question History: System Exam 9 Last NRC Exam: N/A Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 55.41 b.7 55.43 Comments: (KA Match, why high cog, why SRO only) The KA is matched because the examinee must demonstrate knowledge of bus power supplies to the Fuel oil transfer pumps and the Auxiliary Fuel Oil Pump for a given EOG. TMI OPS IL T EXAM Page: 125 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS ILT EXAM Page: 126 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 32 ID: 1718191 Points: 1.00 Plant conditions:
- Loss of Station Power
- EG-Y-1A, Emergency Diesel Generator, had to be started from the Control Room using the Manual Start Pushbutton.
- EG-Y-1A 'Ready to Load' light is DE-ENERGIZED.
- EG-Y-1A voltage is 4050 V.
- EG-Y-1A frequency is 60.5 Hz.
All control room controls associated with EG-Y-1A were in the ES STANDBY line-up when the diesel was started. From the list below, identify the ONE (1) action that would ENERGIZE the Ready to Load light under these conditions. A. Adjust the governor to lower frequency to 60.0 Hz. B. Energize the synchroscope for EG-Y-1A generator output breaker, G1-02. C. Adjust the local unit voltage rheostat to obtain an output voltage of 4100 V. D. Adjust the manual voltage controller on Console Right to obtain an output voltage of 4100 V. Answer: C
~nswer Explanation TMI OPS ILT EXAM Page: 127 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL
<<Explanation: To answer this question correctly, the examinee must know: (1) The 'Ready to Load' light energizes when the diesel is up to the correct operating bands: Voltage is 4100- 4300 volts, and frequency 60.24-61.0 Hz (OP-TM-642-231); (2) The examinee must realize that the voltage is low, but the frequency is in band; (3) The examinee must also recognize that there is only one method to return the voltage to specification, which is the local unit voltage rheostat.
A. Adjust the governor to lower INCORRECT: Plausible if the examinee believes that a frequency of frequency to 60.0 Hz. 60.5 Hz is out of tolerance for the 'Ready to Load' light. Incorrect because the 'Ready to Load' light will light at 60.24 Hz to 61.0 Hz. B. Energize the synchroscope for INCORRECT: Plausible if examinee relates a manual start in the EG-Y-lA generator output control room to a manual start when paralleling an emergency diesel breaker, Gl-02. with offsite power which requires the use of the synchroscope. When manually starting a diesel generator to parallel with offsite power, the synchroscope must be energized. For this situation, since there is no offsite power, the synchroscope does not need to be energized. C. Adjust the local unit voltage CORRECT: See above rheostat to obtain an output voltage of 4.lKV D. Adjust the manual voltage INCORRECT: Plausible because there is a rheostat for voltage control controller on Console Right to on console right. Incorrect because this would adjust voltage if the obtain an output voltage of 4.1 voltage regulator was in manual, which it is not. KV. Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 1 K/A# 064 A3.03 Importance Rating 3.4 3.3 K/A: Emergency Diesel Generators: Ability to monitor automatic operation of the ED/G system, including: Indicating Lights, meters, and recorders. Proposed Question: RO Question# 32 Technical Reference(s): TQ-TM-104-861-COOl, Rev 11 OP-TM-861-901, Rev 18 Proposed References to be provided to applicants during examination: None Learning Objective: 861-GL0-4 Question Source: Bank# 657377 Modified Bank# New TMI OPS ILT EXAM Page: 128 of425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Question History: Sim Exam 2 Last NRC Exam: N/A Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 55.41 b.7 55.43 Comments: (KA Match, why high cog, why SRO only) KA Match: This question matches the KA because the examinee must know which emergency diesel generator parameters are monitored by the 'Ready-to-Load' light. TMI OPS ILT EXAM Page: 129 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS IL T EXAM Page: 130 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 33 ID: 1718267 Points: 1.00 Plant Conditions:
- 100% power with ICS in full auto.
- OP-TM-AOP-005, RIVER WATER SYSTEM FAILURES, is entered due to reduced river water level and rising river water temperature.
EVENT:
- Auxiliary Operator report:
- ISPH Pump Bay Water Level is at 270 foot elevation.
- River Water temperature is 92 degrees F.
Based on these conditions identify the ONE selection that describes required action(s). A Initiate plant shutdown to be at CSD within the next 36 hours. B. Initiate plant shutdown to be at HSD IAW TS 3.0.1. requirements. C. Shutdown any river water pumps whose operation is not essential. D. Trip the reactor, initiate EOP-001, then trip all four Reactor Coolant Pumps. Answer: D
!Answer Explanation TMI OPS IL T EXAM Page: 131 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL
<<Explanation: To answer this question correctly, the examinee must know: (1) In OP-TM-AOP-005, for drought conditions there are separate actions taken for low river water level, high river water temperature, and no nuclear river water and secondary river water pumps operable; (2) Of the two parameters in the stem, only river water elevation is low out of specification; (3) When level was less than 274' a plant shutdown would have been performed to be in HSD (IAW TS 3.0.1); (4) At less than 271', the plant is tripped and all reactor coolant pumps are tripped.
A. Initiate plant shutdown to be INCORRECT: Plausible since this action is part of this procedure at CSD within the next 36 hours section but it is based on water temperature >95F NOT water level. B. Initiate plant shutdown to at INCORRECT: Plausible since this is a requirement if water level is HSD IAW TS 3.0.1. <274'. However with current level at 269', the operating crew would requirements trip the reactor and go to Section 4.3. In section 4.3, the procedure directs the crew to trip the reactor coolant pumps. This step would have been performed all ready. C. Shutdown any river water INCORRECT: Plausible since OP-TM-AOP-005 directs this step when pumps whose operation is not river water level is less than 277'. This step would have been essential performed already. D. Trip the reactor, initiate CORRECT: IAAT all NR and SR pumps are inoperable or ISPH EOP-001, then trip all four pump bay water level< 271', then trip the reactor and all 4 reactor Reactor Coolant Pumps. coolant pumps. Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 1 K/A# 076 A2.01 Importance Rating 3.5 3.7 K/A: Service Water System: Ability to (a) predict the impacts of the following malfunctions or operations on the SWS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of SWS Proposed Question: RO Question# 33 Technical Reference(s): OP-TM-AOP-005, Rev 12 Proposed References to be provided to applicants during examination: None Learning Objective: 211-GL0-7 Question Source: Bank# 355015 Modified Bank# New Question History: System Exam 7 Last NRC Exam: N/A TMI OPS ILT EXAM Page: 132 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 55.41 b.5 55.43 Comments: (KA Match, why high cog, why SRO only) KA Match: This question matches the KA because the examinee must know the procedure actions associated with a low river water level. TMI OPS IL T EXAM Page: 133 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS IL T EXAM Page: 134 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 34 ID: 1718269 Points: 1.00 Plant Conditions:
- 100% power with ICS in full auto.
- Main Instrument Air Compressor, IA-P-4, has been secured for repairs.
- Instrument Air Compressors, IA-P-1A and IA-P-1 B, are running as required.
EVENTS:
- LOCA
- Loss of Off-Site Power
- 1600 PSI ES Actuation 10 minutes later:
- Due to low instrument air pressure, the CRO starts IA-P-1A.
Cooling for IA-P-1A/B will be aligned to (1) due to the (2) A. (1) Fire Service Water, (2) ES Actuation Signal. B. (1) Fire Service Water, (2) Loss of Offsite Power. C. (1) Secondary Closed Cooling, (2) ES Actuation Signal. D. (1) Secondary Closed Cooling, (2) Loss of Offsite Power. Answer: B
!Answer Explanation TMI OPS ILT EXAM Page: 135 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Explanation: To answer this question correctly, the examinee must know: (1) The normal cooling water supply to the instrument air compressors is Secondary Services Closed Cooling Water system; (2) If none of the closed cooling water pumps are operating (as sensed by the SC pumps breaker position) the three way valves SC-V-57 (IA-P-lA) and SC-V-58 (IA-P-lB) will automatically position to allow Fire Service Water to cool the respective air compressor; (3) Loss of Offsite Power trips the secondary closed cooling pumps, which aligns fire service water to IA-P-lA/B (4) The ES actuation signal effects the auto start of IA-P-lA/B but not the cooling water. A. (1) Fire Service Water, (2) ES INCORRECT: Plausible since Fire Service is the alternate cooling Actuation Signal water. If the examinee believes an ES could affect the SCCW Pumps (Load Shed) then the backup cooling would be initiated. B. (1) Fire Service Water, (2) Loss CORRECT: See above of Offsite Power C. (1) Secondary Closed Cooling, INCORRECT: Plausible if the examinee thinks the backup SCCW pump (2) ES Actuation Signal would start once the emergency diesels started and loaded on their bus. Incorrect because the power supplies to the SCCW pumps are lC, lJ, and lN 480V busses. D. (1) Secondary Closed Cooling, INCORRECT: Plausible if the examinee thinks the backup SCCW (2) Loss of Offsite Power. Pump would start once the emergency diesel generators started and loaded on their bus. Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 1 K/A# 078 Kl.04 Importance Rating 2.6 2.9 K/ A: Instrument Air System: Knowledge of the physical connections and/or cause-effect relationships between the IAS and the following systems: Cooling water to compressor Proposed Question: RO Question # 34 Technical Reference(s): 1104-12, Rev 63 TQ-TM-104-850-COOl, Rev 6 Proposed References to be provided to applicants during examination: None Learning Objective: 850-GL0-10 Question Source: Bank# Modified Bank# 978699 New Question History: N/A Last NRC Exam: Unmodified on ILT 12-01 TMI OPS IL T EXAM Page: 136 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part SS Content: SS.41 b.2 SS.43 Comments: (KA Match, why high cog, why SRO only) KA Match: This question matches the KA because the examinee must know the cooling water associated with each IA-P-1, and when it each cooling water is utilized. High Cog: This question is High Cog because the examinee must analyze the events in the stem to determine the cooling water that IA-P-lA/B are utilizing. Plant Conditions: The plant is operating at 100% power. Main Instrument Air Compressor, IA-P-4, has been secured for repairs.
"A" and "B" Instrument Air Compressors, IA-P-1A and IA-P-1 B, are running as required.
Event: A loss of all Secondary Closed Cooling Water Pumps has occurred. Given the above information and two minutes after the event, the Instrument Air Compressors Will align to _(1 )_as the source of cooling due to _(2)_. A. (1) Fire Service water (2) high Instrument Air compressor temperature B. (1) Fire Service water (2) the tripping of all 3 Secondary Closed Cooling Water Pump breakers C. (1) Nuclear Service Closed Cooling Water (2) high Instrument Air compressor temperature D. (1) Nuclear Service Closed Cooling Water (2) the tripping of all 3 Secondary Closed Cooling Water Pump breakers Answer: B TMI OPS ILT EXAM Page: 137 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS ILT EXAM Page: 138 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 35 ID: 1718430 Points: 1.00 Given the following plant conditions:
- Reactor is at 52% power.
- ICS SG/RX Hand/Auto Station is in HAND.
- All other ICS stations are in AUTOMATIC.
EVENT:
- Group 7 Rod 4 in Quadrant YZ drops fully into the core.
Which of the following indicates the effect on (1) Quadrant Power Tilt in Quadrant YZ and (2) Tave parameter response? ASSUME NO OPERATOR ACTIONS. A. (1) Negative Quadrant Power Tilt. (2) Tave lowers and remains low. B. (1) Negative Quadrant Power Tilt. (2) Tave lowers and returns to setpoint. C. (1) Positive Quadrant Power Tilt. (2) Tave lowers and remains low. D. (1) Positive Quadrant Power Tilt. (2) Tave lowers and returns to setpoint. Answer: B
!Answer Explanation TMI OPS IL T EXAM Page: 139 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Explanation: To answer this question correctly, the examinee must know: (1) A dropped rod in any quadrant suppress power in that quadrant, thus creating a negative quadrant power tilt; (2) The Dropped Rod Runback is to 55% Reactor Power, so NO runback would be in effect for the given plant conditions; (3) On a Dropped Rod the CRD Out Inhibit clears when Reactor Power is <60% to allow for Automatic Tavg control; (4) In this case, the controlling ICS signal in which it bases the dropped rod runback for is Generated Megawatts, so when rods pull to maintain Tave, power will rise, but the runback will not come back in because Generated Megawatts remain constant; (4) The SG/RX Master in Hand would not effect Tavg Control. A. (1) Negative Quadrant Power INCORRECT: Plausible since part 1 is correct and Tave is low. The Tilt. CRD Control System would allow Rods to Withdraw to correct for a (2) Tave lowers and remains low Tave, even with a Dropped Rod, as long as the reactor power low. remains <60%. The examinee may think 55% Reactor Power is the max power since this is the setpoint for a dropped rod runback. (i.e., that control rods will not withdraw); (3) The examinee may assume with the SG/RX Master in Hand it would require manual operation to raise Tave. B. (1) Negative Quadrant Power CORRECT: The dropped rod would suppress flux in this quadrant Tilt. and this quadrant would be lower than the other quadrants. On a (2) Tave lowers and returns to dropped rod the CRD Out Inhibit clears when Reactor Power is <60% setpoint. to allow for Automatic Tave control. C. (1) Positive Quadrant Power INCORRECT: Plausible if the examinee is believes that a dropped Tilt. control rod will give a positive power tilt, based on the calculations. (2) Tave lowers and remains Reversing the operation in the calculation gives the same numerical low. value but will reverse the sign. The examinee may think 55% Reactor Power is the max power since this is the setpoint for a dropped rod runback so control rods could not withdraw. The examinee may assume with the SG/RX Master in Hand it would require manual operation to raise Tave. D. (1) Positive Quadrant Power INCORRECT: Plausible if the examinee is believes that a dropped Tilt. control rod will give a positive power tilt, based on the calculations. (2) Tave lowers and returns to Reversing the operation in the calculation gives the same numerical setpoint. value but will reverse the sign. On a Dropped Rod the CRD Out Inhibit clears when Reactor Power is <60% to allow for Automatic Tavg control Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 2 K/A# 001 K3.02 Importance Rating 3.4 3.5 K/A: Control Rod Drive System: Knowledge of the effect that a loss or malfunction of the CRDS will have on the following: RCS Proposed Question: RO Question # 35 Technical Reference(s): OP-TM-AOP-062, Rev 7 TQ-TM-104-621-COOl, Rev 10 TMI OPS ILT EXAM Page: 140 of425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TQ-TM-104-622-COOl, Rev 7 Proposed References to be provided to applicants during examination: None Learning Objective: AOP-062-PC0-5 Question Source: Bank# Modified Bank# 887495 New Question History: N/A Last NRC Exam: 2003 NRC Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 b.7 55.43 Comments: (KA Match, why high cog, why SRO only) KA Match: This question matches the KA because the examinee will have to know which area of the core has a negative quadrant power tilt, in addition to what Tave will do. High Cog: This question is high cog because the examinee will have to analyze he dropped ro to determine that quadrant power tilt in that region is negative. In addition, the examinee must know the ICS control on an dropped rod, and that there is no CRD out inhibit preventing ICS from maintaining Tave in the correct band. Sequence of events: Reactor power is 100%, with ICS in full automatic. Group 7 Rod #4 drops into the core, Quadrant YZ. Based on these conditions, identify the ONE statement below that describes initial plant response when the rod reaches full insertion. A. Pressurizer level rises. B. RCS pressure and temperature lower. C. Diamond rod control transfers to manual. D. Quadrant power tilt becomes more positive in Quadrant YZ. Answer: B TMI OPS ILT EXAM Page: 141 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS IL T EXAM Page: 142 of425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 36 ID: 1737551 Points: 1.00 Plant Conditions:
- 60% power with ICS in auto.
EVENT:
- Reactor Building pressure starts to rise.
- RCS pressure starts to lower.
- The reactor is tripped and the IMA's of OP-TM-EOP-001, REACTOR TRIP are performed.
POST TRIP CONDITIONS:
- Reactor Building pressure rises to 4.2 psig.
- RCS pressure lowers to 1675 psig.
Post Trip, RM-A-2, Reactor Building Atmosphere Monitor, (1) be used to determine whether the Reactor Building pressure increase is from the an reactor coolant leak because (2) A (1) can (2) there is NOT a 1600 psig ES Actuation Signal B. (1) can (2) Reactor Building Atmospheric conditions will NOT inhibit proper air flow NO/ &<.:J.. C. (1) can NOT (2) it is isolated from Containment D. (1) can NOT (2) Reactor Building Atmospheric conditions may inhibit proper air flow (I/.*- t Q. r;_,,,_
/J ,-
T' 3 11 * *1n.. Answer: c
!Answer Explanation TMI OPS ILT EXAM Page: 143 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL
<<Explanation: To answer this question correctly, the examinee must know: (1) ES Actuation signals, 1600 psig, 500 psig, and 4 psig RB pressure isolate RM-A-2 from the reactor building; (2) Since the stem never indicates that the 1600 psig was bypassed, when RCS pressure lowered below 1600 psig, RM-A-2 is isolated and cannot be used to differentiate between an RCS leak or steam leak; (3) In addition, RM-A-2 pump will de-energize when a combination of its' isolation valves close (CM-V-1, 2, 3, 4).
A. (1) can INCORRECT: Plausible if the examinee believes that only a 1600 psig (2) there is NOT a 1600 psig ES signal isolates RM-A-2. The 1600 psig signal is indicative of a ES Actuation Signal LOCA, the examinee may believe that in the case of a LOCA that RM-A-2 gets isolated. B. (1) can INCORRECT: Plausible if the examinee does not realize that a 1600 (2) Reactor Building psig signal is present and/or believes that a 4 psig ES actuation is the Atmospheric conditions will only ES signal that isolates RM-A-2. NOT block flow C. (1) can NOT CORRECT: A 1600 psig ES isolates RM-A-2 via CM-V-1,2,3,4 closing. (2) it is isolated from Also, there is an interlock which will automatically de-energize Containment RM-A-2's pump when either CM-V-1 or CM-V-2 close. D. (1) can NOT INCORRECT: Part 1 is correct but part 2 is incorrect. RM-A-2 does (2) Reactor Building have charcoal and paper filters. Plausible if the candidate recognizes Atmospheric conditions may that they could saturate if the detector was not isolated but this prevent proper air flow would not happen since it is Isolated from RB Atmospheric conditions. Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 2 K/A# 002 A3.01 Importance Rating 3.7 3.9 K/ A: Reactor Coolant System: Ability to monitor automatic operation of the RCS, including: Reactor coolant leak detection system Proposed Question: RO Question # 36 Technical Reference(s): 1105-3, Rev 053 TQ-TM-104-661-COOl, Rev 7 Proposed References to be provided to applicants during examination: None Learning Objective: 661-GL0-2 Question Source: Bank# Modified Bank# New x TMI OPS ILT EXAM Page: 144 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL Question History: N/A Last NRC Exam: N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 b.7 55.43 Comments: (KA Match, why high cog, why SRO only) KA Match: This question matches the KA because the examinee must know whether RM-A-2 is capable of being used for RCS leak detection. High Cog: This question is high cog because the examinee must determine that a 1600 psig ES signal is present. Then the examinee must determine that on a 1600 psig ES, the containment isolation valves for RM-A-2 go closed. TMI OPS ILT EXAM Page: 145 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS ILT EXAM Page: 146 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 37 ID: 1718596 Points: 1.00 Sequence of Events:
- Emergency Feedwater Pump, EF-P-2A, is OOS.
- Loss of Offsite Power (LOOP) occurred 10 minutes ago.
- A small break LOCA occurred following the loss of offsite power.
- Emergency Feedwater Pump, EF-P-28, tripped when it started automatically.
- OP-TM-EOP-001, Reactor Trip, IMAs were performed.
- OP-TM-EOP-006, LOCA Cooldown and OP-TM-AOP-020, Loss of Station Power, actions are in progress.
- 4 psig ESAS was manually actuated.
- RCS temperature is 518°F and SCM has been maintained >25°F throughout the transient.
- lncore Thermocouples are slowly rising.
- Natural Circulation cannot be verified.
Which ONE of the following is the NEXT required action? Reduce OTSG p r e s s u r e - - - - - - - - - - - - A. in both OTSGs to approximately 150 psig. B. while maintaining >750 psig to avoid feedwater isolation. C. in both OTSGs as low as possible (Atmospheric pressure or vacuum). D. so that secondary Tsat is 40 to 60°F lower than incore thermocouple temperature, while maintaining >150 psig. Answer: D
\Answer Explanation TMI OPS ILT EXAM Page: 147 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Explanation: To answer this question correctly, the examinee must know: (1) In OP-TM-EOP-006, Section 4.0, INADEQUATE RCS COOLDOWN is entered under the following conditions: Primary to secondary heat transfer cannot be established, RCS temperature is> 300F, and core cooldown rate is less than 40F/hr; (2) Due to the loss of offsite power, there are no reactor coolant pumps. In addition the stem states that natural circulation is not verified. In order to have primary to secondary heat transfer, a reactor coolant pump must be running or natural circulation must be verified; (3) In section 4, the crew will lower OTSG pressures so Tsat is 40 to 60F lower than incore thermocouple temperature in order to maintain the OTSGs as a heat sink; (3) With only the steam driven Emergency Feedwater Pump available (EF-P-1), OTSG pressure must be maintained >150 psig to ensure feed flow to the OTSGs. A. in both OTSGs to INCORRECT: Plausible since this would strengthen the heat sink. approximately 150 psig.. Incorrect because lowering OTSG pressure rapidly to 150 psig could cause the OTSGs to become uncoupled from the primary and further disrupt the attempts as establishing primary to secondary heat transfer. B. while maintaining> 750 psig to INCORRECT: Plausible since lowering OTSG is required and maintain avoid feedwater isolation. OTSG Pressure> 750 psig would prevent main Feedwater Isolation, allowing it be available if power is restored. However, the procedure directs bypassing the MFW Isolation signal prior to OTSG pressure< 750 psig. C. in both OTSGs as low as INCORRECT: Plausible because this is how the operating crew would possible (Atmospheric pressure perform a rapid RCS cooldown if SCM were lost and an RCP were still or vacuum). running. Incorrect because those symptoms to not exist. D. so that secondary Tsat is 40 to CORRECT: See above 60°F lower than incore thermocouple temperature, while maintaining >150 psig. Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 2 K/A# 035 A2.06 Importance Rating 4.5 4.6 K/A: Steam Generator System: Ability to (a) predict the impacts of the following malfunctions or operations on the SG; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Small break LOCA Proposed Question: RO Question# 37 Technical Reference(s): OP-TM-EOP-006, Rev 12 Proposed References to be provided to applicants during examination: None Learning Objective: EOP004-PC0-3 Question Source: Bank# TMI OPS IL T EXAM Page: 148 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Modified Bank# S7283S New Question History: Simulator Exam 9 Last NRC Exam: N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part SS Content: SS.41 b.S SS.43 Comments: (KA Match, why high cog, why SRO only) KA Match: This question matches the KA because the examinee must predict the impact that having only the steam drive emergency feed pump has on a LOCA Cooldown. In addition, the examinees must have knowledge of the LOCA cooldown procedure to understand the bands that the operating crew would set to establish the OTSG has a heat sink. High Cog: This question is high cog because the examinee must ascertain all the the requirements to enter section 4 of OP-TM-EOP-006 exist, and then understand steps within that section to strengthen the OTSG as a heat sink. Sequence of Events:
- Emergency Feedwater Pump, EF-P-2A, is OOS.
- Loss of Offsite Power (LOOP) occurred 10 minutes ago.
- A small break LOCA occurred following the loss of offsite power.
- Emergency Feedwater Pump, EF-P-28, tripped when it started automatically.
- OP-TM-EOP-001, Reactor Trip, IMAs were performed.
- OP-TM-EOP-006, LOCA Cooldown and OP-TM-AOP-020, Loss of Station Power, actions are in progress.
- RCS temperature is 518°F and SCM has been maintained >25°F throughout the transient.
- Cooldown rate is 5°F/hr.
- Conditions to verify Natural Circulation can not be met.
Which ONE of the following is the NEXT required action? A. Lower OTSG Pressure while maintaining > 750 psig to avoid feedwater isolation in accordance with EOP-006, LOCA Cooldown. B. Lower OTSG pressure to establish >40°F/hr cooldown rate while maintaining >150 psig for Emergency Feedwater Pump, EF-P-1, operation in accordance with EOP-006, LOCA Cooldown. C. Lower OTSG Pressure in both OTSG's as low as possible (Atmospheric pressure or vacuum) to promote primary to secondary heat transfer in accordance with EOP-006, LOCA Cooldown. TMI OPS ILT EXAM Page: 149 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL D. Lower OTSG Pressure so secondary Tsat is 40-60°F higher than incore thermocouple temperature to promote primary to secondary heat transfer in accordance with EOP-004, Lack of Primary to Secondary Heat Transfer. Answer: B TMI OPS ILT EXAM Page: 150 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS ILT EXAM Page: 151 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 38 ID: 1718720 Points: 1.00 Plant conditions:
- 100% power with ICS in full auto.
EVENT:
- Overhead alarm MAP C-1-1, "RADIATION LEVEL HI", just actuated.
- The source of the alarm is RM-A-5, CONDENSER VACUUM PUMP EXHAUST.
The MAP-5 Sampler starts to sample the: A. steam lines for only iodine when RM-A-5 reaches the ALERT setpoint. B. steam lines for iodine and tritium when RM-A-5 reaches the ALERT setpoint. C. condenser offgas for only iodine when RM-A-5 reaches the HI-ALARM setpoint. D. condenser offgas for iodine and tritium when RM-A-5 reaches the HI-ALARM setpoint. Answer: C
!Answer Explanation TMI OPS ILT EXAM Page: 152 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Explanation: To answer this question correctly, the examinee must know: (1) The initiating setpoint for starting the MAP-5 is from the HI Alarm NOT the Alert Setting; (2) Physical location of the sample line is from Condenser Offgas, NOT from the Steam Lines; (3) The MAP-5 detects Iodine NOT tritium. A. steam lines for only iodine INCORRECT: Plausible since both OTSGs have radiation monitors on when RM-A-5 reaches the the steam lines to detect for an OTSG Tube Leak. Incorrect because ALERT setpoint. this is not the location of the interface for RM-A-5. In addition, the alert alarm does NOT start the MAP-5. B. steam lines for iodine and INCORRECT: Plausible since both OTSGs have radiation monitors on tritium when RM-A-5 reaches the steam lines and there is a parallel line for a tritium sample for the ALERT setpoint. the MAP-5. In addition, the Alert Alarm does NOT start the MAP-5. C. condenser offgas for only CORRECT: See above. iodine when RM-A-5 reaches the HI-ALARM setpoint D. condenser offgas for iodine INCORRECT: Plausible since it does sample for Iodine, however the and tritium when RM-A-5 sample line for Tritium is in parallel and a manual operation not reaches the HI-ALARM associated with the MAP-5. setpoint. Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 2 K/A# 055 Kl.06 Importance Rating 2.6 2.6 K/ A: Condenser Air Removal System: Knowledge of the physical connections and/or cause/effect relationships between the CARS and the following systems: PRM System Proposed Question: RO Question # 38 Technical Reference(s): TQ-TM-104-661-COOl OP-TM-MAP-COlOl, Rev 3 Proposed References to be provided to applicants during examination: None Learning Objective: 661-GL0-9 Question Source: Bank# 575075 Modified Bank# New Question History: System Exam 11 Last NRC Exam: ILT05-1 Question Cognitive Level: Memory or Fundamental Knowledge x TMI OPS ILT EXAM Page: 153 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Comprehension or Analysis 10 CFR Part 55 Content: 55.41 b.7 55.43 Comments: (KA Match, why high cog, why SRO only) KA Match: This question matches the KA because the examinee must have knowledge of where the radiation monitor connects to the condenser air removal system. TMI OPS ILT EXAM Page: 154 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS ILT EXAM Page: 155 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 39 ID: 1718734 Points: 1.00 Plant Conditions:
- OP-TM-232-551, "Liquid Release of 'A' WECST with WDL-P-14A" is in progress.
- MAP Alarm C-1-1 Radiation Level High is received.
- RM-L-7, Plant Discharge Rad Monitor is in high alarm.
What automatic action mitigates the potential radioactive release to the environment? A. WDL-V-124, WDL-P-14A Outlet to MDCT, closes and WDL-P-14A WECST Recirc Pump will remain running. B. WDL-V-124, WDL-P-14A Outlet to MDCT, closes and WDL-P-14A WECST Recirc Pump trips. C. WDL-V-257, WDL-P-14A/B Discharge to MDCT/River, closes and WDL-P-14A WECST Recirc Pump will remain running. D. WDL-V-257, WDL-P-14A/B Discharge to MDCT/River, closes and WDL-P-14A WECST Recirc Pump trips. Answer: C
!Answer Explanation TMI OPS ILT EXAM Page: 156 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL
<<Explanation: To answer this question correctly, the examinee must know: (1) When the high alarm is reached for RM-L-7, then WDL-V-257 will close; (2) WDL-P-14A remains running on recirculation.
A. WDL-V-124, WDL-P-14A Outlet INCORRECT: Plausible since WDL-V-124 is the release flow control to MDCT, closes and valve however WDL-V-124 does not close on a high alarm from WDL-P-14A WECST Recirc RM-L-7. Pump will remain running. B. WDL-V-124, WDL-P-14A Outlet INCORRECT: Plausible since WDL-V-124 is the release flow control to MDCT, closes and valve and WDL-P-14A is the discharge pump; however neither WDL-P-14A WECST Recirc condition occurs on high radiation. Pump trips. C. WDL-V-257, WDL-P-14A/B CORRECT: High alarm on RM-L-7 will close WDL-V-257 and the tank Discharge to MDCT/River, WDL-P-14A remains running. closes and WDL-P-14A WECST Recirc Pump will remain running. D. WDL-V-257, WDL-P-14A/B INCORRECT: Plausible since WDL-V-257 will close on the high alarm Discharge to MDCT/River, signal from RM-L-7; however WDL-P-14A will not trip. closes and WDL-P-14A WECST Recirc Pump trips. Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 2 K/A# 068 A3.02 Importance Rating 3.6 3.6 K/ A: Liquid Rad waste System: Ability to monitor automatic operation of the Liquid Radwaste System including: Automatic Isolation Proposed Question: RO Question:# 39 Technical Reference(s): OP-TM-MAP-C0101, Rev 3 TQ-TM-104-232-COOl, Rev 7 Proposed References to be provided to applicants during examination: None Learning Objective: 661-GL0-2 Question Source: Bank# 679215 Modified Bank# New Question History: N/A Last NRC Exam: 08-01 NRC TMI OPS IL T EXAM Page: 157 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 55.41 b.7 55.43 Comments: KA Match: This question matches the KA because the examinee must know the radiation interlocks that cause automatic isolation on the liquid radwaste system. TMI OPS ILT EXAM Page: 158 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS IL T EXAM Page: 159 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 40 ID: 1718755 Points: 1.00 REFERENCE PROVIDED Plant conditions:
- Plant is shutting down to HOT SHUTDOWN.
- Tave is 575 deg-F.
- Pressurizer level is being maintained in accordance with 1102-10, PLANT SHUTDOWN.
Based on the above conditions, which indicated level below would be the minimum acceptable pressurizer level? A. 100". B. 185". C. 210". D. 220". Answer: B
!Answer Explanation TMI OPS ILT EXAM Page: 160 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL
<<Explanation: To answer this question correctly, the examinee must know: (1) 1102-10 Plant Shutdown pressurizer must be maintained with OP-TM-211-472 Attachment 7.2; (2) Interpret and use attachment 7.2 to determine the minimum level based on the given plant conditions with a Tave of 575 deg-Fis 185".
A. 100" INCORRECT: Plausible if the examinee believes that we should be maintaining Pressurizer level for hot shutdown. B. 185" CORRECT: See above.
- c. 210" INCORRECT: Plausible if the examinee uses the recommended vs Tave.
D. 220" INCORRECT: Plausible if the examinee believes that pressurizer level is to be maintained at 220", the normal operating pressurizer level. Examination Outline Cross-reference: Level RO SRO Tier# 3 Group# 1 K/A# 2.1.25 Importance Rating 3.9 4.2-K/A: Ability to interpret reference materials, such as graphs, curves, tables, etc. Proposed Question: RO Question # 40 Technical Reference(s): 1102-10, Rev 99 OP-TM-211-472, Rev 4 OP-TM-211-472, Attachment 7.2 Proposed References to be provided to applicants during examination: with Blacked out curve names. Learning Objective: GOP-010-PC0-1 Question Source: Bank# 371611 Modified Bank# New Question History: Sim Exam 2 Last NRC Exam: N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 b.10 TMI OPS ILT EXAM Page: 161 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL 55.43 Comments: (KA Match, why high cog, why SRO only) KA Match: This matches the KA because the examinee must be able to use a graph which operators use to cooldown the plant. High Cog: This question is high cog because the examinee must understand how to read the graph given the plant parameters. TMI OPS IL T EXAM Page: 162 of425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL TMI OPS ILT EXAM Page: 163 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL 41 ID: 1737589 Points: 1.00 Plant Conditions:
- The plant was at 100% power when a control rod in Group 7 dropped.
- During the runback two additional rods in Group 7 become stuck at 88% withdrawn.
- The ICS runback was completed in automatic.
With the above plant conditions the operating crew must _ _ _ _ _ _within one hour. A. trip the reactor B. be in HOT SHUTDOWN C. verify Axial Power Imbalance is within limits D. verify SOM ;?: 1% delta k/k or initiate boration Answer: D
!Answer Explanation TMI OPS ILT EXAM Page: 164 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL
<<Explanation: To answer this question correctly, the examinee must know: (1) A dropped rod in group 7 will cause a plant runback to less than 455 MWe (55% reactor power), this will drive in Group 7 control rods to~ 25% rod index; (2) When the dropped rod runback is complete, the crew must enter OP-TM-AOP-062, INOPERABLE ROD due to the two stuck rods being inoperable (control rods misaligned with the group by more than 9 inches); (3) When two or more rods are inoperable, OP-TM-AOP-062, Step 3.2 requires that a shutdown margin (SDM) calculation be performed to verify SDM ~ 1% delta k/k or initiate emergency boration.
A. trip the reactor INCORRECT: Plausible because operation with two or more rods inoperable is not permitted. Incorrect because a reactor trip is not required. B. be in HOT SHUTDOWN INCORRECT: Plausible because the operating crew will initiate a plant shutdown to HOT SHUTDOWN. Incorrect because the crew has 6 hours to be in HOT SHUTDOWN.
- c. verify Axial Power INCORRECT: Plausible because there are limits on Axial Power which Imbalance is within limits would require action within an hour, however there is nothing in the stem which would indicate that this limit is being violated.
D. verify SOM ~ 1% delta k/k or CORRECT: See Above. initiate boration Examination Outline Cross-reference: Level RO SRO Tier# 3 Group# 2 KIA# 2.2.39 Importance Rating 3.9 4.5 KIA: Knowledge of less than or equal to one hour Technical Specification action statements for systems. Proposed Question: RO Question #41 Technical Reference(s): OP-TM-AOP-062, Rev 7 OP-TM-MAP-H0101, Rev 2 OP-TM-AOP-0621, Rev 6 Proposed References to be provided to applicants during examination: None Learning Objective: AOP-062-PC0-4 Question Source: Bank # 1110401 Modified Bank # New Question History: Comp 2 Last NRC Exam: N/A TMI OPS ILT EXAM Page: 165 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 b.10 55.43 Comments: KA Match: This question matches the KA because the examinee must recognize a condition in which SOM must be verified within an hour. This is an operational 1 hour technical specification. High Cog: This question is high cog because the examinee must analyze the stem to know that control rods have driven in further than 9 inches more than 88% index. I TMI OPS ILT EXAM Page: 166 of425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS ILT EXAM Page: 167 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 42 ID: 1718778 Points: 1.00 Plant Conditions:
- 100% power with ICS in full auto.
- The Unit has experienced several fuel pin failures.
- A leak must be repaired in the Aux. Bldg.
- The general area dose rate in the location of the repair is 600 mrem/hr.
- In order to reach the location of the repair the worker must transit through a 6 Rem/hr high radiation area for 2 minutes and return via the same path.
- The worker currently has an accumulated annual dose of 400 mrem.
The maximum allowable time that the worker can participate in the repairs and NOT exceed the TEDE Administrative Dose Control Limit is minutes (Worker does NOT have a High Lifetime Exposure). A. 100 B. 120 C. 140 D. 160 Answer: B
!Answer Explanation TMI OPS IL T EXAM Page: 168 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Explanation: To answer this question correctly, the examinee must know: (1) The TEDE administrative dose limit in RP-AA-203 is 2000 mrem routine cumulative TEDE/yr; (2) That the worker in question already has 400 mrem and must make a trip TO and FROM the work area without exceeding the TEDE limit. A. 100 INCORRECT: Based on 2000 mrem - 600 mrem (current) - 400 mrem (transient)= 1000 I 600 mrem/hr x 60 min = 100 minutes B. 120 B. CORRECT: The candidate should determine that the ADCL is 2000 mrem. Transient exposure is 400 mrem (6000mrem/hr x 4/60hr). (transit to and from the job). (Current) 400 mrem +(transit) 400 mrem = 800 mrem ADCL of 2000 mrem - 800 mrem = 1200 mrem allowable before reaching ADCL. 1200 mrem /600 mrem/hr = 2 hours
- c. 140 INCORRECT: Based on calculating using a one-way transit dose D. 160 INCORRECT: Based on using ADCL (2000) and NO transit dose.
Examination Outline Cross-reference: Level RO SRO Tier# 3 Group# 3 K/A# 2.3.4 Importance Rating 3.2 3.7 K/A: Knowledge of radiation exposure limits under normal or emergency conditions. Proposed Question: RO Question# 42 Technical Reference(s): RP-AA-203, Rev 5 Proposed References to be provided to applicants during examination: None Learning Objective: None Question Source: Bank# 375097 Modified Bank# New Question History: Sim Exam 3 Last NRC Exam: N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x TMI OPS IL T EXAM Page: 169 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRG EXAM SUBMITTAL 10 CFR Part 55 Content: 55.41 b.12 55.43 Comments: KA MATCH: This question matches the KA because the examinee must have knowledge of radiation exposure limits. High Cog: This question is high cog because the examinee must use math to determine the correct allowable time the worker has in the area. TMI OPS IL T EXAM Page: 170 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS IL T EXAM Page: 171 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 43 ID: 1718893 Points: 1.00 Plant Conditions:
- 100% power with ICS in full auto.
Sequence of Events: T = 1100: A Reactor Building Purge has commenced. T = 1200: The Reactor Building purge is secured due to a minor equipment problem. T =1730: The equipment problem has been fixed and the Reactor Building purge is ready to recommence. Given the above information and IAWCY-TM-170-2012, RELEASING RADIOACTIVE GASEOUS EFFLUENTS: The RB Purge may recommence _ _ _ _ _ __ A. with the same release permit using original air sample data. B. with the same release permit using updated air sample data. C. when a new release permit is generated using a new release number with updated air sample data. D. when a new release permit is generated using the same release number with updated air sample data. Answer: C
!Answer Explanation TMI OPS IL T EXAM Page: 172 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Explanation: To answer this question correctly, the examinee must know: (1) In accordance with CY-TM-170-2012, step 4.1.3: A Reactor Building Purge may be stopped and restarted within four hours, using the same release permit; (2) If the purge is secured for more than four hours, then INITIATE a new release permit (with new air samples). A. with the same release permit INCORRECT: Plausible if the candidate is either not familiar with the using original air sample data. time requirement allowed to use the same permit without a new air sample. B. with the same release permit INCORRECT: Plausible if the candidate is not familiar with the time using updated air sample data. requirement allowed to use the same permit even with a new air sample.
- c. when a new release permit CORRECT: See above.
is generated using a new release number with updated air sample data. D. when a new release permit INCORRECT: Plausible if the candidate thinks the same Permit is generated using the same Number is permitted, since the old permit allowing the purge was release number with not completed. updated air sample data. SR Examination Outline Cross-reference: Level RO 0 Tier# 3 Group# 3 K/A# 2.3.11 Importance Rating 3.8 4.3 K/A: Ability to control radiation releases. Proposed Question: RO Question# 43 Technical Reference(s): CT-TM-170-2012, Rev 1 Proposed References to be provided to applicants during examination: None Learning Objective: NOP-DBIG-APC0-1 Question Source: Bank# Modified Bank# 1142262 New Question History: N/A Last NRC Exam: Unmodified on 12-01 NRC Question Cognitive Level: Memory or Fundamental Knowledge TMI OPS ILT EXAM Page: 173 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Comprehension or Analysis x 10 CFR Part SS Content: SS.41 b.10 SS.43 Comments: (KA Match, why high cog, why SRO only) KA Match: The KA is matched because the question requires the candidates to recognize the requirements prior to reestablishing a Reactor Building Purge. High Cog: This question is at the Comprehension/Analysis level because the candidate is required to perform a math problem and, based on the results of the math problem, the candidate must recall procedural steps and requirements associated with Reactor Building Purge. Plant Conditions (T = 1600):
- The plant is operating at 100% power.
- A Reactor Building purge has commenced.
Sequence of Events:
- T =1700:
- The Reactor Building purge is secured due to the Chemistry Supervisor questioning the calculations used.
- T = 2030:
- The Chemistry Supervisor agrees that all calculations are correct and the Reactor Building purge is ready to recommence.
Given the above information and IAW6610-ADM-4250.12, Releasing Radioactive Gaseous Effluents, which ONE of the following statements is correct with regards to the Reactor Building purge? A. The same release permit may be used. B. No release permit is needed for a Reactor Building purge. C. A new release permit needs to be generated with a new release number assigned. D. A new release permit needs to be generated but the same release number can be used. Answer: A TMI OPS IL T EXAM Page: 174 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 44 ID: 1719768 Points: 1.00 The plant has experienced a major transient with several component malfunctions. Entry conditions are met for:
- OP-TM-EOP-001, REACTOR TRIP.
- Two EOP-010 Rules.
- Five EOP-010 Guides.
- Several AOP series procedures.
- Numerous alarm response procedures.
Following the Immediate Manual Actions of OP-TM-EOP-001, what is the correct sequence of performance when multiple procedure entries are required? A. Perform the initial symptom check. Following this, the CRS determines the sequence of actions required to mitigate the event successfully. B. Perform the initial symptom check, and the VSSVs. Following this, the CRS determines the sequence of actions required to mitigate the event successfully. C. Perform the initial symptom check. Remaining procedures must be implemented in the following order: EOP Rules, EOP Guides, AOPs and Alarm Response procedures. D. Perform the initial symptom check, and the VSSVs. Remaining procedures must be implemented in the following order: EOP Rules, EOP Guides, AOPs and Alarm Response procedures. Answer: A
!Answer Explanation TMI OPS ILT EXAM Page: 176of425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS ILT EXAM Page: 175 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL
<<Explanation: To answer this question correctly, the examinee must know: (1) OS-24, CONDUCT OF OPERATIONS DURING ABNORMAL AND EMERGENCY EVENTS, provides direction that any other procedure actions should be interrupted to perform the reactor trip IMA's and initial Symptom Check; (2) Once the IMAs and the initial symptom check have been accomplished, the Control Room Supervisor determines the sequence of action between parallel procedures. The CRS selects the action most significant to overall event mitigation.
A. Perform the initial symptom CORRECT: See above check. Following this, the CRS determines the sequence of actions required to mitigate the event successfully. B. Perform the initial symptom INCORRECT: Plausible if examinee believes the Vital System Status check, and the VSSVs. Verifications (VSSVs)of EOP-001 must be performed prior to moving Following this, the CRS to another procedure. While the VSSVs are important, the CRS has determines the sequence of the leeway to perform other procedures prior to completion. actions required to mitigate the event successfully.
- c. Perform the initial symptom INCORRECT: Plausible if examinee believes EOP Rules & Emergency check. Remaining Procedure must always take priority over AOP's or ARPs. In previous procedures must be revisions of OS-24, this was the recommended course of action.
implemented in the following order: EOP Rules, EOP Guides, AOPs and Alarm Response procedures. D. Perform the initial symptom INCORRECT: Plausible if examinee believes Symptom Check and check, and the VSSVs. VSSV's are always done prior to moving to another procedure. In Remaining procedures must previous revisions of OS-24, this was the recommended course of be implemented in the action after the symptom check. following order: EOP Rules, EOP Guides, AOPs and Alarm Response procedures Examination Outline Cross-reference: Level RO SRO Tier# 3 Group# 4 KIA# 2.4.16 Importance Rating 3.5 4.4 KIA: Knowledge of EOP implementation hierarchy and coordination with other support procedures or guidelines such as, operating procedures, abnormal I operating procedures, and severe accident management guidelines. Proposed Question: RO Question# 44 Technical Reference(s): OS-24, Rev 28 Proposed References to be provided to applicants during examination: None Learning Objective: None TMI OPS IL T EXAM Page: 177 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Question Source: Bank # 503815 Modified Bank # New Question History: Sim Exam 9 Last NRC Exam: N/A Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 b.10 55.43 Comments: KA MATCH: This question matches the KA because the examinees must have knowledge of the procedure hierarchy in OS-24. TMI OPS ILT EXAM Page: 178 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL TMI OPS ILT EXAM Page: 179 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL 45 ID: 1719786 Points: 1.00 Plant Conditions:
- 100% power with ICS in full auto.
EVENT:
- The reactor has tripped.
- Damage has occurred to the Control Tower, preventing plant control from either the Control Room or the Remote Shutdown Panels.
- On-shift personnel are not responding to any communications.
Based on the above conditions, the priority action to be taken by an Auxiliary Operator is to report to the: A. EFW area and perform OP-TM-AOP-009, Loss of Plant Control Facilities in order to establish EFW flow. B. Auxiliary Boilers and perform OP-TM-414-401 (402), to startAS-B-1A (1B) in order to establish Auxiliary Steam for necessary loads. C. Auxiliary Building and perform Attachment 5 of OP-TM-EOP-020, Cooldown From Outside of Control Room to prevent spurious operation of MOV's. D. Turbine Building and open AS-V-8 IAW Attachment E of OS-24, Conduct of Operations During Abnormal and Emergency Events, to make Auxiliary Steam available to Gland Steam when Auxiliary Steam pressure is available. Answer: A
!Answer Explanation TMI OPS ILT EXAM Page: 180 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL
<<Explanation: To answer this question correctly, the examinee must know: (1) According to OS-24, attachment E, in the event of damage to the Control Tower preventing plant control from either the Control Room or Remote Shutdown area all available NLO's should report to the EFW area and implement AOP-009; (2) AOP-009 should be performed immediately without CR concurrence; (3) The mitigation strategy for AOP-009 is to establish EFW flow to the OTSGs to remove decay heat.
A. EFW area and perform CORRECT: See above OP-TM-AOP-009, Loss of Plant Control Facilities in order to establish EFW flow. B. Auxiliary Boilers and perform INCORRECT: Plausible because this is an assigned post trip action, OP-TM-414-401 (402), to following a Reactor Trip. Incorrect because OS-24 directs all NLO's start AS-B-1A (1 B) in order to the EFW area to establish feedwater. to establish Auxiliary Steam for necessarv loads. C. Auxiliary Building and INCORRECT: Plausible because the control room is not available. perform Attachment 5 of Incorrect because in this case, EOP-020 is not entered because the OP-TM-EOP-020, Cooldown whole control tower is not available. From Outside of Control Room to prevent spurious operation of MOV's. D. Turbine Building and open INCORRECT: Plausible because this is an assigned post trip action, AS-V-8 IAW Attachment E of following a Reactor Trip. OS-24, Conduct of Operations During Abnormal and Emergency Events, to make Auxiliary Steam available to Gland Steam when Auxiliary Steam pressure is available. Examination Outline Cross-reference: Level RO SRO Tier# 3 Group# 4 KIA# 2.4.35 Importance Rating 3.8 4.0 KIA: Knowledge of local auxiliary operator tasks during an emergency and the I resultant operational effects. Proposed Question: RO Question #45 Technical Reference(s): OS-24, Rev 28 OP-TM-AOP-009, Rev 10 Proposed References to be provided to applicants during examination: None TMI OPS IL T EXAM Page: 181 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Learning Objective: AOP-009-PC0-4 Question Source: Bank# 862353 Modified Bank # New Question History: Sim Exam 9 Last NRC Exam: N/A Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 Comments: KA Match: This question matches the KA because the examinee must know where the location and actions taken by the AO's on a loss of plant facilities and resultant operational effects. TMI OPS ILT EXAM Page: 182 of 425 24 April 2017
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EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 46 ID: 1720267 Points: 1.00 Plant Conditions:
- 100% power with ICS in full auto.
EVENT:
- A feedwater transient occurs.
- An automatic reactor trip on HIGH RCS temperature fails to occur.
- Main Feedwater remains available.
- The reactor trip and DSS Pushbuttons fail to trip the reactor.
- A CRO opens both the 1L-02 and 1G-02 breakers.
- several groups of control rods failed to insert.
- Reactor power is 10% and steady.
Based on the above conditions, the CRO must (1) in order to (2) A. (1) trip the Main Turbine, (2) minimize peak RCS pressure B. (1) trip the Main Turbine, (2) prevent an overcooling event C. (1) wait until RCS Pressure is less than 2500 psig, then initiate Emergency Injection HPl/LPI, (2) inject borated water to the RCS D. (1) wait until RCS Pressure is less than 2500 psig, then initiate Emergency Injection HPl/LPI, (2) prevent RCS pressure from exceeding 3000 psig Answer: C [Answer Explanation TMI OPS ILT EXAM Page: 184 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL
<<Explanation: To answer this question correctly, the examinee must know: (1) The reactor did not shutdown with an automatic or manual trip signal, this is an ATWS; (2) When this happens the operator opens ll-02 and lG-02, which should remove all power from the CRDMs; (3) After the breakers are open, since multiple groups of rods did not insert, and reactor power is greater than 5%, that indicates that the reactor is still NOT shutdown; (4) Since feedwater is available, the mitigation strategy is to maintain primary to secondary heat transfer and emergency borate with HPI (charging pumps).
A. (1) trip the Main Turbine, INCORRECT: Plausible because if Main Feedwater were not (2) minimize peak RCS pressure available, then the operator would trip the turbine and initiate emergency feedwater. B. (1) trip the Main Turbine, INCORRECT: Plausible because if Main Feedwater were not (2) prevent an overcooling available, then the operator would trip the turbine and initiate event emergency feedwater. C. (1) wait until RCS Pressure is CORRECT: See above. less than 2500 psig, then initiate Emergency Injection HPl/LPI, (2) inject borated water to the RCS D. (1) wait until RCS Pressure is INCORRECT: Plausible since HPl/LPI is initiated when RCS pressure is less than 2500 psig, then < 2500 psig, however preventing the RCS Pressure from exceeding initiate Emergency Injection 3000 psig is associated with maintaining the Main Turbine on-line. HPl/LPI, (2) prevent RCS pressure from exceeding 3000 psig Examination Outline Cross-reference: Level RO SRO Tier# 1 Group# 1 K/A# 029 EAl.01 Importance Rating 3.4 3.1 K/ A: Anticipated Transient Without Scram (ATWS): Ability to operate and monitor the following as they apply to a ATWS: Charging Pumps Proposed Question: RO Question # 46 Technical Reference(s): OP-TM-EOP-001, Rev 16 OP-TM-EOP-0011, Rev 8 Proposed References to be provided to applicants during examination: None Learning Objective: EOP-001-PC0-5 Question Source: Bank# Modified Bank# TMI OPS ILT EXAM Page: 185 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL New x Question History: N/A Last NRC Exam: N/A Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 55.41 b.7 55.43 Comments: KA Match: The examinee must know the the mitigation strategy for shutting down the reactor on an ATWS, which involves using the charging pumps to emergency borate. TMI OPS ILT EXAM Page: 186 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS ILT EXAM Page: 187 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 47 ID: 1720289 Points: 1.00 A reactor trip from 100% power has occurred. The following plant conditions exist:
- All four reactor coolant pumps are tripped.
- Emergency Feedwater CANNOT be established to either OTSG.
- Main Feedwater CANNOT be recovered.
- lncore thermocouples are indicating 592°F and rising slowly.
- OP-TM-EOP-004, LACK OF PRIMARY TO SECONDARY HEAT TRANSFER, has been entered.
- SCM is 28°F and lowering.
The CRS must _(1 )_based on _(2)_. A. (1) go to OP-TM-EOP-009, HPI COOLING, and perform Rule 1 when Subcooling Margin is < 25°F, (2) SCM approaching 25°F B. (1) go to OP-TM-EOP-009, HPI COOLING, and perform Rule 1 when Subcooling Margin is < 25°F, (2) RCS pressure approaching 2450 psig C. (1) continue with OP-TM-EOP-004 to open the PORV then close it when RCS pressure is 1750 psig, (2) RCS pressure approaching 2450 psig D. (1) continue with OP-TM-EOP-004 to open the PORV then close it when SCM approaches 30°F, (2) SCM approaching 25°F Answer: A
!Answer Explanation TMI OPS ILT EXAM Page: 188 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL
<<Explanation: To answer this question correctly, the examinee must know: (1) In OP-TM-EOP-004, if SCM is approaching 25°F, the crew will go to OP-TM-EOP-009; (2) Additionally, the examinee must determine this is the correct course of action by using the incore temperature at 592°F and the SCM at 28°F to determine that RCS pressure is approximately 1800 psig (from the steam tables); (3) OP-TM-EOP-009 could be entered in two separate ways from OP-TM-EOP-004:
The first was previously discussed when SCM is approaching 25°F, the second is if RCS pressure is approaching 2450 psig with no FEEDWATER available; (4) Due to SCM being 28°F and the examinee determining that pressure is not approaching 2450 psig, entry into OP-TM-EOP-009 is required via the approaching 25°F SCM method. A. (1) go to OP-TM-EOP-009, CORRECT: See above. HPI COOLING, and perform Rule 1 when Subcooling Margin is < 25°F, (2) SCM approaching 25°F B (1) go to OP-TM-EOP-009, INCORRECT: Plausible because OP-TM-EOP-009 is required, HPI COOLING, and perform incorrect because it is required because SCM is approaching Rule 1 when Subcooling 25°F, not due to RCS pressure approaching 2450 psig. Margin is < 25°F, (2) RCS pressure aooroachina 2450 psia
- c. (1) continue with INCORRECT: Plausible because OP-TM-EOP-004 provides guidance OP-TM-EOP-004 to open on RCS pressure approaching 2450 psig, which would be to deep the PORV then close it cycle the PORV. Incorrect because this is only done if FEEDWATER is when RCS pressure is 1750 available.
psig, (2) RCS pressure approachina 2450 psig D. (1) continue with INCORRECT: Plausible because OP-TM-EOP-004 provides guidance OP-TM-EOP-004 to open on deep cycling the PORV when RCS pressure is approaching 2450 the PORV then close it psig. when SCM approaches 30°F, (2) SCM approaching 25°F Examination Outline Cross-reference: Level RO SRO Tier# 1 Group# 1 KIA# E04 EK1.2 Importance Rating 4.0 4.2 KIA: Inadequate Heat Transfer: Knowledge of the operational implications of the following concepts as they apply to the (Inadequate Heat Transfer): Normal, abnormal, and emergency operating procedures associated with (Inadequate Heat Transfer). Proposed Question: RO Question# 47 Technical Reference(s): OP-TM-EOP-004, Rev 11 OP-TM-EOP-009, Rev 8 Proposed References to be provided to applicants during examination: Steam Table TMI OPS ILT EXAM Page: 189 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL Learning Objective: EOP-004-PC0-5 Question Source: Bank # 300014 Modified Bank # New Question History: N/A Last NRC Exam: NIA Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 55.43 b.10 Comments: KA Match: This question matches the KA because the examinee must to the operational implication of approaching 2s°F during a lack of heat transfer. They must have knowledge of the transition to OP-TM-EOP-009. High Cog: This question is high cog because the examinee must analyze the conditions in the stem or in order to determine the correct step to implement in OP-TM-EOP-004. TMI OPS ILT EXAM Page: 190 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 48 ID: 1720350 Points: 1.00 Plant Conditions:
- 100% power with ICS in full auto.
EVENT:
- Loss of #8 Bus Based on the Loss of the #8 Bus, the CRS must enter_( 1)_and the CRO is required to make a plant announcement using the _(2)_.
A. (1) OP-TM-AOP-013, LOSS OF 10 4160V BUS, (2) "RED" plant page and radio B. (1) OP-TM-AOP-013, LOSS OF 10 4160V BUS, (2) "GREY" plant page and radio C. (1) OP-TM-AOP-014, LOSS OF 1E 4160V BUS, (2) "RED" plant page and radio D. (1) OP-TM-AOP-014, LOSS OF 1E 4160V BUS, (2) "GREY" plant page and radio Answer: D
!Answer Explanation TMI OPS ILT EXAM Page: 192 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS ILT EXAM Page: 191 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL
<<Explanation: To answer this question correctly, the examinee must know: (1) When the plant loses the 8 bus, the lA and lC 4160V busses fast transfer to the B Auxiliary Transformer. Emergency Diesel Generator, EG-Y-lB starts to power the lE 4160V bus; (2) This meets the entry criteria for entering OP-TM-AOP-014; (3) The power to the "Grey" plant page comes downstream of the 1D 4160V bus and is not effected, hence the plant page is made over the "Grey" phone; (4) OP-TM-AOP-013 directs the plant page to be made over the "Red" phone if the 1D 4160V bus lost power.
A. (1) OP-TM-AOP-013, LOSS OF INCORRECT: Plausible if the examinee believes that the 1D 4160V 1D 4160V BUS, (2) "RED" plant bus was lost. OP-TM-AOP-013 would direct the announcement to be page and radio made over the "RED" plant page. B. (1) OP-TM-AOP-013, LOSS OF INCORRECT: Plausible if the examinee believes that the 1D 4160V 1D 4160V BUS, (2) "GREY" bus was lost. Although the procedure directs use of the "RED" plant plant page and radio page and radio, when the power was restored to the 1D 4160V bus by EG-Y-lA, the "GREY" plant page would work. C. (1) OP-TM-AOP-014, LOSS OF INCORRECT: Plausible if the examinee believes that the "GREY" plant lE 4160V BUS, (2) "RED" plant page has lost power. Incorrect because the "GREY" plant page gets page and radio power from downstream of the 1D 4160V bus. D. (1) OP-TM-AOP-014, LOSS OF CORRECT: See above lE 4160V BUS, (2) "GREY" plant page and radio Examination Outline Cross-reference: Level RO SRO Tier# 1 Group# 2 K/A# AOS: AA2.1 Importance Rating 3.5 4.2 K/A: Emergency Diesel Actuation: Facility conditions and selection of appropriate procedures during abnormal and emergency operations. Proposed Question: RO Question #48 Technical Reference(s): OP-TM-AOP-014, Rev 9 Proposed References to be provided to applicants during examination: None Learning Objective: AOP-014-PC0-6 Question Source: Bank# Modified Bank# New x Question History: N/A Last NRC Exam: N/A TMI OPS ILT EXAM Page: 193 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 b.10 55.43 Comments: KA Match: This question matches the KA because the diesel actuates on undervoltage on a loss of the
#8 bus. The examinee must recognize the entry criteria for the abnormal procedure which would govern this actuation.
High Cog: This question is high cog because the examinee must analyze the plant status upon loss of the 8 bus, and understand that the 1E 4160V bus is powered by EG-Y-lB, and this is an entry criteria for OP-TM-AOP-014. TMI OPS ILT EXAM Page: 194 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS IL T EXAM Page: 195 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 49 ID: 1720342 Points: 1.00 Plant Conditions:
- 40% power with ICS in auto.
EVENT:
- Reactor power is LOWERING.
- RCS pressure is RISING.
- Main Steam Safety Valves are OPEN.
- Turbine Bypass Valves, MS-V-3A-F, and Atmospheric Dump Valves, MS-V-4A/B, are OPEN.
- Indicating lights on Panel SS-1 are GREEN for the breakers for the Middletown 1092, Jackson 1051 and 500 kV tie lines.
- Indicating lights on Panel SS-1 for the Middletown 1091 breaker switches are GREEN and YELLOW
- Indicating lights for the Main Generator Breakers are RED.
- Generator load is 49 megawatts.
Which of the following procedures must be entered to mitigate this event? A. MAP-H0101, ICS RUNBACK B. 1107-11, TMI GRID OPERATIONS C. OP-TM-EOP-001, REACTOR TRIP D. OP-TM-AOP-022, LOAD REJECTION Answer: D
!Answer Explanation TMI OPS ILT EXAM Page: 196 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL
<<Explanation: To answer this question correctly, the examinee must know: (1) The stem conditions essentially leave the plant in a conditions where the unit is separated from the grid, where our generator breakers are shut powering our Auxiliary Transformers only; (2) This could be caused by multiple things, but the governing procedure in this case will be OP-TM-AOP-022, LOAD REJECTION.
A. MAP-H0101, ICS Runback INCORRECT: Plausible because both reactor power and MWe are lowering which is also an indication of a plant runback. Incorrect because no runback signal would exist for this situation. B. 1107-11,TMIGrid INCORRECT: Plausible because the purpose of this procedure is to Operations provide guidance on operation of components related to Auxiliary Transformers/Switchyard Equipment and to provide guidance for response to grid related abnormal situations. The given symptoms would indicate a potential problem associated with the grid, but the controlling procedure would be AOP-022.
- c. OP-TM-EOP-001, Reactor INCORRECT: Plausible since many of the symptoms are also Trip associated with a reactor trip. Incorrect because there is indication of generator load, which would indicate the turbine and the reactor are NOT tripped.
D. OP-TM-AOP-022, Load CORRECT: See above Rejection. Examination Outline Cross-reference: Level RO SRO Tier# 1 Group# 1 KIA# 077 2.4.11 Importance Rating 4.0 4.2 KIA: Generator Voltage and Electrical Grid Disturbances: Knowledge of abnormal condition procedures Proposed Question: RO Question # 49 Technical Reference(s): OP-TM-AOP-022, Rev 8 Proposed References to be provided to applicants during examination: None Learning Objective: AOP-022-APC0-2 Question Source: Bank # 462877 Modified Bank # New Question History: Sim Exam 6 Last NRC Exam: N/A TMI OPS ILT EXAM Page: 197 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 b.11 55.43 Comments: KA Match: This question matches the KA because the examinee must have knowledge of the abnormal operating procedure entered on a loss of the grid. High Cog: This question is high cog because the examinee must analyze the stem indications to determine that a load rejection has occurred. TMI OPS ILT EXAM Page: 198 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS ILT EXAM Page: 199 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 50 ID: 1720492 Points: 1.00 Plant Conditions:
- 100% power with ICS in full auto.
Event:
- RC3-PR Hot Leg A Narrow Range Channel 1 fails LOW
- MAP alarm H-3-2, SASS Mismatch is illuminated.
- SASS selector switch for RC3A-PT1 Hot Leg A Narrow Range Channel 1 has the RED and WHITE lights illuminated.
- SASS selector switch for RC3B-PT1 Hot Leg B Narrow Range Channel 1 has only the RED light illuminated.
What is the system response of this failure? A. All Pressurizer Heater Banks energize. B. SASS transfers to an alternate channel. C. One channel of ES actuates on Train 'A' AND Train 'B'. D. Only SCR controlled banks 1, 2, and 3 Pressurizer Heaters energize. Answer: A
!Answer Explanation TMI OPS ILT EXAM Page: 200 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL
<<Explanation: To answer this question correctly, the examinee must know: (1) The range of the Narrow Range pressure instrument is 2500 to 1700 psig, and failing low would be 1700 psig; (2) The Narrow Range pressure instrument, RC3A-PT1, is the normally selected SASS instrument to RC3-PR for RCS pressure control; (3) This output of this SASS channel provides control for, PZR Heater Control (Low Pressure}, Spray Valve control, and the PORV high pressure setpoint; (4) The effect of this failing low the Pressurizer Heater Banks energize at 2135 psig (SCR Controlled 1, 2 and 3)) and all heater banks (4 and 5) are energized by 2105.
A. All Pressurizer Heater Banks CORRECT: See above enerqize. B. SASS transfers to an INCORRECT: Plausible if the examinee does not interpret the RED alternate channel. and WHITE light indications correctly, and determines that SASS has actuated. Incorrect because the WHITE light on RC3B-PT1 would be illuminated.
- c. One channel of ES actuates INCORRECT: Plausible if the examinee believes this pressure on Train 'A' AND Train 'B'. instrument inputs to ESAS in a way which would actuate one channel. Incorrect because these Narrow Range instruments only go as low as 1700 psig, and ESAS actuates on a 1600 psig pressure signal.
D. Only SCR Controlled Banks INCORRECT: Plausible if examinee thinks the instrument input only 1, 2, and 3 Pressurizer effects the SCR Controlled Heater Banks 1, 2, and 3. Incorrect Heaters energize. because the bistable banks (4 and 5) are will also turn on for this failure. Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 1 KIA# 010 K6.01 Importance Rating 2.7 3.1 KIA: Pressurizer Pressure Control System: Knowledge of the effect of a loss or malfunction of the following will have on the PZR PCS: Pressure detection systems Proposed Question: RO Question # 50 Technical Reference(s): TQ-TM-104-624-C001, Rev 4 Proposed References to be provided to applicants during examination: None Learning Objective: 624-GL0-11 Question Source: Bank# Modified Bank # New x TMI OPS IL T EXAM Page: 201 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Question History: NIA Last NRC Exam: N/A Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 b.7 55.43 Comments: KA Match: This question matches the KA because the examinee must know how the controlling Narrow Range Pressure instrument effects plant control. TMI OPS IL T EXAM Page: 202 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS ILT EXAM Page: 203 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 51 ID: 1720498 Points: 1.00 Identify the conditions that promote Pool Boiler Condenser Cooling Mode (BCM) of Heat Transfer. The OTSG thermal center remains _(1 )_the RCP spillover elevation. RCS liquid level is maintained _(2)_ the secondary level. A. (1) above (2) above B. (1) above (2) below C. (1) below (2) above D. (1) below (2) below Answer: B
!Answer Explanation TMI OPS IL T EXAM Page: 204 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL
<<Explanation: To answer this question correctly, the examinee must know: (1) OP-TM-EOP-002 basis document describes the parameters to promote BCM cooling as: RCS condensation and ECCS injection do not cause the RCS liquid level to increase above the secondary level, and secondary fluid temperature is maintained below the temperature of the steam on the primary side of the OTSG tubes. the secondary liquid level is high enough that the secondary OTSG thermal center remains several feet above the RCP spillover elevation.
A. (1) above INCORRECT: First part is correct. Plausible if the examinee believes in (2) above order to accomplish part 1 then RCS liquid level must above secondary level. B. (1) above CORRECT: See above (2) below
- c. (1) below INCORRECT: Plausible if the examinee believes the OTSG thermal (2) above must be below the heat source to induce BCM.
D. (1) below INCORRECT: Plausible if the examinee believes the OTSG thermal (2) below must be below the heat source to induce BCM. Second part is correct Examination Outline Cross-reference: Level RO SRO Tier# 1 Group# 2 K/A# E03 EK3.1 Importance Rating 3.2 3.8 K/A: Inadequate Subcooling Margin: Knowledge of the reasons for the following responses as they apply to the (Inadequate Subcooling Margin): Facility operating characteristics during transient conditions, including coolant chemistry and the effects of temperature, pressure, and reactivity changes and operating limitations and reasons for these operating characteristics. Proposed Question: RO Question #51 Technical Reference(s): OP--TM-EOP-0021, Rev 5 Proposed References to be provided to applicants during examination: None Learning Objective: EOP-002-GL0-9 Question Source: Bank# Modified Bank# New x Question History: N/A Last NRC Exam: N/A TMI OPS ILT EXAM Page: 205 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part SS Content: SS.41 b.S SS.43 Comments: KA Match: This question matches the KA because the examinee must have knowledge for the response of raising OTSG level on a loss of subcooling margin. The operating characteristic in the question is Boiler Condenser Cooling, and the effect in the question is what the temperature and level of OTSG water will do to the RCS parameters. TMI OPS ILT EXAM Page: 206 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS IL T EXAM Page: 207 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 52 ID: 1720537 Points: 1.00 Plant Conditions:
- 100% power with ICS in full auto.
- RPS Channel A in MANUAL BYPASS.
EVENT:
- Vital bus "A" (VBA) losses power.
Given the information above, identify the selection below that describes (1) the number of remaining channels required to trip and (2) the degree of redundancy. A (1) ONE (2) ONE B. (1) ONE (2) TWO C. (1) TWO (2) ONE D. (1) TWO (2) TWO Answer: B
!Answer Explanation TMI OPS ILT EXAM Page: 208 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL
<<Explanation: To answer this question correctly, the examinee must know: (1) The MANUAL BYPASS switch on an RPS cabinet is used for testing or if an erroneous trip signal is present; (2) With an RPS channel in MANUAL BYPASS, the number of channels required to trip is TWO with a redundancy of TWO; (3) When VBA is lost, a trip signal is generated, regardless of the position of the MANUAL BYPASS switch; (4) This places the plant in a situation where if ONE additional channel generates a trip signal, the plant would trip; (5) Since RPS channels B,C, and Dare still operable, there is a degree of redundancy ofTWO additional channels which could provide the trip signal.
A. (1) ONE (2) ONE INCORRECT: Plausible because this possibility would exist if a power supply other than VBA was lost (i.e, VBB, VBC, or VBD). understood. B. (1) ONE (2) TWO CORRECT: See above C. (1) TWO (2) ONE INCORRECT: Plausible if the examinee believes that since RPS A is in MANUAL BYPASS, that this prohibits all trip signal to be generated. Incorrect because this trip signal is generated on a loss of power. D. (1) TWO (2) TWO INCORRECT: Plausible if the examinee believes that since RPS A is in MANUAL BYPASS, that this prohibits all trip signal to be generated. Incorrect because this trip signal is generated on a loss of power .. Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 1 K/A# 012 K6.02 Importance Rating 2.9 3.1 K/A: Reactor Protection System: Knowledge of the effect of a loss or malfunction of the following will have on the RPS: Redundant channels Proposed Question: RO Question #52 Technical Reference(s): TQ-TM-104-641-COOl, Rev 2 T.S Definition 1.4.2, Amd 278 OP-TM-AOP-015, Rev 10 Proposed References to be provided to applicants during examination: None Learning Objective: 641-GL0-6 Question Source: Bank# 568246 Modified Bank# New Question History: N/A Last NRC Exam: N/A TMI OPS IL T EXAM Page: 209 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 b.7 55.43 Comments: KA Match: This question matches the KA because the examinee must know the effect that a loss of a vital bus will have on the redundant channels of RPS. High Cog: This question is high cog because the examinee must analyze the effect of the loss of VBA on the RPS system. TMI OPS ILT EXAM Page: 21 O of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS ILT EXAM Page: 211 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 53 ID: 1720550 Points: 1.00 Initial conditions:
- 100% Reactor power .
- AH-E-9A, PENETRATION COOLING FAN, is in Normal-after-start .
- AH-E-9B, PENETRATION COOLING FAN, is in Normal-after-stop .
Event:
- Reactor Trip occurs .
- 4# ES actuation occurs (both trains) .
- HVA-2-1, PENETRATION COOLING AIR TEMP HI, alarms .
- RecorderTR-805, PENETR COOLAIR TEMPERATURE RECORDER, points 1-25, all read >205°F and rising.
What MINIMUM action(s) must be taken to lower penetration temperatures? A Start AH-E-9B ONLY. B. Restart AH-E-9A ONLY. C. Bypass both 4# ES signals and then start AH-E-9B. D. Ensure AH-D-89, AH-E-9A/B OUTSIDE AIR INLET, and AH-D-90, AH-E-9A/B TURBINE BLDG INLET, are open. Answer: A
~nswer Explanation TMI OPS IL T EXAM Page: 212 of425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL
<<Explanation: To answer this question correctly, the examinee must know: (1) That AH-E-9A/9B trip on the following signals: Fire/Smoke detector alarm (TS 671), High Temperature at 195°F (TS 706A/706B), and AH-E-9A is load shed on any ES actuation; (2) When a component is load shed, it cannot be restarted until the ES Actuation signals are cleared; (3) Since AH-E-9B is not affected by load shed, it can be started immediately.
A. Start AH-E-9B ONLY. CORRECT: See above. This is the MINIMUM requirement to start a penetration cooling fan. B. Restart AH-E-9A ONLY. INCORRECT: Plausible if the examinee believes that AH-E-9B is the load shed fan or does not recall the ES Signal must be cleared to restart fan. C. Bypass both 4# ES signals and INCORRECT: Plausible if the examinee believes that both fans are then start AH-E-9B. load shed and the correct course of action was to start the fan that was not running. D. Ensure AH-D-89, AH-E-9A/B INCORRECT: Plausible if the examinee believes that BOTH the inlet OUTSIDE AIR INLET, and dampers to the AH-E-9's must be open to start an AH-E-9. AH-D-90, AH-E-9A/B TURBINE BLDG INLET, are open. Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 1 K/A# 022 K4.01 Importance Rating 2.5 3.0 K/ A: Containment Cooling System: Knowledge of the CCS design feature(s) and/or interlock(s) which provide for the following: Cooling of containment penetrations. Proposed Question: Question #53 Technical Reference(s): TQ-TM-104-240-COOl, Rev 7 HVA-2-1 (HVA, Rev 58) 1104-16, Rev 24 Proposed References to be provided to applicants during examination: None Learning Objective: 240-GL0-10 Question Source: Bank# 880836 Modified Bank# New Question History: System Exam 9 Last NRC Exam: N/A TMI OPS IL T EXAM Page: 213 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 b.7 55.43 Comments: KA MATCH: This question matches the KA because the examinee must know the load shed interlock for AH-E-9A to answer the question correctly. High Cog: This question is high cog because in addition to knowing the interlock with AH-E-9A, the examinee must know the actions to start another penetration cooling fan. TMI OPS ILT EXAM Page: 214 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS IL T EXAM Page: 215 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 54 ID: 1720590 Points: 1.00 Plant Conditions:
- 100% power with ICS in full auto.
EVENT:
- Due to a fault, the feeder breaker to 1D 4160V bus trips open.
- Emergency Diesel Generator, EG-Y-1 A is powering the 1D 4160V bus.
The 1N480V Bus is _(1)_ because _(2)_. A. (1) energized (2) the 1N 480V bus automatically repowers from the 1L 480V bus crosstie B. (1) energized (2) the 1N 480V bus is re powers when EG-Y-1 A re powers the 1D 4160V bus C. (1) de-energized (2) the UV results in a 1N 480V bus trip and lockout D. (1) de-energized (2) the UV results in a 1N 480V bus trip with NO lockout Answer: D
!Answer Explanation TMI OPS ILT EXAM Page: 216 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL
<<Explanation: To answer this question correctly, the examinee must know: (1) One Line Diagram of the BOP & 1E Electrical System Distribution (4160V to 480V busses); (2) Due to the UV on the 1D 4160V bus, the lN 480V bus trips; (3) When EG-Y-lA is powering the bus, the lN 480V bus can be repowered.
A. (1) energized INCORRECT: Plausible since the lN bus can be repowered from the (2) the 1 N 480V bus 1L 480V bus crosstie, however this requires operator actions. automatically repowers from the 1 L 480V bus crosstie B. (1) energized INCORRECT: Plausible because the other 480V feeder (2) the 1N 480V bus is breakers stay shut when the 1 D 4160V bus loses power. repowered when EG-Y-1A Incorrect because the 1 N 480V bus feeder breaker opens on repowers the 1 D 4160V bus an 10 4160V bus UV.
- c. (1) de-energized INCORRECT: Plausible because the lN bus is de-energized, but only (2) the UV results in a 1 N an UV with an ES actuation would activate the lockout for the lN 480V bus lockout 480V bus.
D. (1) de-energized CORRECT: See above. (2) the UV results in a 1N 480V bus trip with NO lockout Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 1 KIA# 062 K4.07 Importance Rating 2.7 3.1 KIA: AC Electrical Distribution System: Knowledge of ac distribution system design feature(s) and/or interlock(s) which provide for the following: One-line diagram of 4kV to 480V distribution, including sources of normal and alternative power. Proposed Question: RO Question #54 Technical Reference(s): TQ-TM-104-7 40-C001, Rev 007 Proposed References to be provided to applicants during examination: None Learning Objective: 7 40-GL0-10 Question Source: Bank # Modified Bank # New x Question History: N/A Last NRC Exam: N/A TMI OPS ILT EXAM Page: 217 of425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 b.7 55.43 Comments: KA Match: This question requires knowledge of the one line diagram of the TMI electrical distribution system. High Cog: This question is high cog because the examinee must know the status of the 1N 480V bus when the associated 4160V bus loses power and is then repowered. TMI OPS ILT EXAM Page: 218 of425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRG EXAM SUBMITTAL TMI OPS ILT EXAM Page: 219 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 55 ID: 1720616 Points: 1.00 Identify the correct reading for RM-G-23, RB High Range Radiation Monitor. A. 1X103 R/h B. 1X103 mr/h C. 2X10 2 R/h D. 2x10 2 mr/h Answer: c
!Answer Explanation TMI OPS ILT EXAM Page: 220 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL
<<Explanation: To answer this question correctly, the examinee must know: (l)The operation of the indication selector switch for RM-G-23, OFF/ALL/10E7/10E6/10ES/10E4/10E3:
- 1) Read top scale (RED) in ALL.
- 2) Read 3 decades in other positions.
Example: Scale Selected 10 - 10E4: Read lower black scale with first mark being lOEl R/hr and the last mark being 10E4 R/hr In addition, the black scale does NOT lower the Units to mr/hr. A. 1Xl03 R/h INCORRECT: Plausible if the examinee does correctly interpret the position of the Scale Selector Switch B. 1Xl03 mr/h INCORRECT: Plausible if the examinee does not properly read the scale units. Most Rad Monitors of this type are low range and read out in mr/hr. C. 2X10 2 R/h CORRECT: See above D. 2Xl0 2 mr/h INCORRECT: Plausible if the examinee misinterprets the black scale as mr/hr. Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 1 K/A# 073 2.1.28 Importance Rating 4.1 4.1 K/A: Process Radiation Monitoring System: Knowledge of the purpose and function of major system components and controls. Proposed Question: RO Question #SS Technical Reference(s): TQ-TM-104-661 RM-G-23 Proposed References to be provided to applicants during examination: indication (in color) Learning Objective: 661-GL0-5 Question Source: Bank# Modified Bank# New x Question History: N/A Last NRC Exam: N/A Question Cognitive Level: Memory or Fundamental Knowledge TMI OPS IL T EXAM Page: 221 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 b.7 55.43 Comments: KA Match: This question matches the KA because the examinee must have knowledge of the function controls for a process radiation monitor. High Cog: This question is high cog because the examinee must use the picture to determine the correct reading by checking the switch position and the meter reading. TMI OPS ILT EXAM Page: 222 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 56 ID: 1720650 Points: 1.00 Plant Conditions:
- 100% power with ICS in full auto.
EVENT:
- Three 'A' OTSG Main Steam Safety Valves (MSSVs) are discovered to be inoperable.
- All 'B' OTSG Main Steam Safety Valves are operable.
(1) What action, if any, is required? (2) Why or why not? A. (1) No action is required. (2) All 'B' OTSG MSSVs are operable. B. (1) No action is required. (2) All 3 MSSVs are inoperable on the 'A' OTSG. C. (1) Reduce power and reduce the overpower trip setpoint. (2) All 'B' OTSG MSSVs are operable. D. (1) Reduce power and reduce the overpower trip setpoint. (2) Only 6 MSSVs are operable on the 'A' OTSG. Answer: D
§nswer Explanation TMI OPS ILT EXAM Page: 224 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL TMI OPS IL T EXAM Page: 223 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL
<<Explanation: To answer this question correctly, the examinee must know: (1) The number of MSSVs on each OTSG is nine; (2) If less than seven MSSVs are operable on either OTSG, power must be reduced and the overpower trip must be lowered as well.
A. (1) No action is required. INCORRECT: Plausible because the examinee could believe that (2) Only 'B' OTSG MSSVs are since the 'B' OTSG MSSVs are operable that no action is required. operable. B. (1) No action is required. INCORRECT: Plausible because the examinee could believe that (2) All 3 MSSVs are since only 3 MSSVs on the 'A' OTSG are inoperable that no action is inoperable on the 'A' OTSG. required.
- c. (1) Reduce power and CORRECT: Plausible because the examinee could believe that the reduce the overpower trip reason for the power and setpoint reduction is that ONLY the 'B' setpoint. OTSG MSSVs are operable. This is incorrect because the action is (2) All 'B' OTSG MSSVs are taken because 3 MSSVs are inoperable on the 'A' OTSG.
operable. D. (1) Reduce power and reduce INCORRECT: See above. the overpower trip setpoint. (2) Only 3 MSSVs are inoperable on the 'A' OTSG. Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 2 K/A# 041 Al.02 Importance Rating 3.1 3.2 K/ A: Steam Dump System (SDS)/Turbine Bypass Control: Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the SOS controls including: Steam Pressure Proposed Question: RO Question #56 Technical Reference(s): TQ-TM-104-411-COOl, Rev 8 T.S. 3.4.1.2.3, Amd 277 Proposed References to be provided to applicants during examination: None Learning Objective: 411-GL0-7 Question Source: Bank# Modified Bank# New x Question History: N/A Last NRC Exam: N/A TMI OPS ILT EXAM Page: 225 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part SS Content: SS.41 b.S SS.43 Comments: KA Match: This question matches the KA because it tests the ability of the examinee to predict a change in parameters to prevent exceeding a design limit associated with the Steam Dump System (MSSVs). The setpoint is reduced to prevent exceeding the Main Steam System pressure rating by exceeding the capacity of the remaining operable MSSVs. High Cog: This question is high cog because the examinee must determine the correct course of action when 3 MSSVs are found to be inoperable. TMI OPS ILT EXAM Page: 226 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL TMI OPS ILT EXAM Page: 227 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 57 ID: 1720668 Points: 1.00 Plant Conditions:
- 100% power with ICS in full auto.
Sequence of Events:
- The 'B' OTSG develops a steam leak in the Reactor Building.
- The crew manually trips the reactor based on rising Reactor Building pressure.
- A 4 PSIG ESAS actuation occurs.
- Current plant conditions:
- RCS Tave is 560°F and lowering slowly.
- OTSG 1A level is 86 inches on the Startup Range and slowly lowering.
- OTSG 1B level is 86 inches on the Startup Range and slowly lowering.
- OTSG 1A pressure is 985 psig and steady.
- OTSG 1B pressure is 950 psig and lowering very slowly.
- Main Feedwater flow to OTSG 1A is 0.3 x 10 5 lbm/hr.
- Main Feedwater flow to OTSG 1B is 1.9 x 10 5 lbm/hr The 'B' OTSG must be isolated in accordance with which procedure?
A OP-TM-EOP-001, REACTOR TRIP B. OP-TM-EOP-010, Guide 12, RCS STABILIZATION C. OP-TM-AOP-051, SECONDARY SIDE HIGH ENERGY LEAK D. OP-TM-EOP-003, EXCESSIVE PRIMARY TO SECONDARY HEAT TRANSFER Answer: A
!Answer Explanation TMI OPS ILT EXAM Page: 228 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL
<<Explanation: To answer this question correctly, the examinee must know: (1) If a steam leak in the reactor building occurs, OP-TM-AOP-051 would be entered; (2)When the Reactor Building pressure approaches 2 psig (which could happen on an OTSG steam leak), the crew will trip the reactor; (3) To trip the reactor the crew will perform the EOP-001 Immediate Manual Actions and then perform a symptom check; (4) In this case, the crew would be sensitive to symptoms of excessive heat transfer, which in accordance with the OS -24 definition, does NOT exist at this time; (5) The operating crew would proceed with EOP-001 actions until they reached step 3.16 which would isolate the affected OTSG per Attachment 1.
A. OP-TM-EOP-001, REACTOR CORRECT: See above. TRIP B. OP-TM-EOP-010, Guide 12, RCS INCORRECT: Plausible because Guide 12 is implemented from Rule 3 STABILIZATION (which is performed in EOP-003). There are steps in Guide 12 to isolate the OTSG from the condenser, but that is not applicable in this question. C. OP-TM-AOP-051, Secondary INCORRECT: Plausible because the crew does enter this procedure, Side High Energy Leak. but incorrect because this procedure doesn't isolate the OTSG for a leak in the Reactor Building, but does direct a reactor trip at 2 psig in the Reactor Building. D. OP-TM-EOP-003, Excessive INCORRECT: Plausible since EOP-003 would isolate the OTSG if Primary to Secondary Heat symptoms of excessive heat transfer existed. Incorrect because Transfer. those symptoms to not exist. Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 1 K/A# 103 2.4.6 Importance Rating 3.7 4.7 K/A: Containment System: Knowledge of EOP mitigation strategies. Proposed Question: RO Question# 57 Technical Reference(s): OP-TM-EOP-001, Rev 16 Proposed References to be provided to applicants during examination: None Learning Objective: EOP-001-PC0-4 Question Source: Bank# 908527 Modified Bank# New Question History: N/A Last NRC Exam: N/A TMI OPS IL T EXAM Page: 229 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 b.10 55.43 Comments: KA Match: This question matches the KA because the examinee must know the mitigation strategy for an OTSG with a steam leak in Containment. High Cog: This question is high cog because the examinee must analyze the conditions in the stem to determine that the symptoms of excessive heat transfer do NOT exist. TMI OPS ILT EXAM Page: 230 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS IL T EXAM Page: 231 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 58 ID: 1720680 Points: 1.00 Plant Conditions:
- 65% reactor power.
- ULD is in manual, all other ICS stations are in auto.
- Both SASS modules are de-energized.
EVENT:
- RC-P-1 C breaker opens.
The output of RC-12-TAS Tave Auto/Manual Switch will _(1)_ because _(2)_. A. (1) remain at the Loop A&B Average (2) SASS is inoperable B. (1) remain at the Loop A&B Average (2) reactor power is below the ICS Runback setpoint C. (1) swap to Loop A Average (2) the RC-P-1 C breaker is open D. (1) swap to Loop A Average (2) this loop has the highest RCS flow Answer: D
!Answer Explanation TMI OPS IL T EXAM Page: 232 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL
<<Explanation: To answer this question correctly, the examinee must know: (1) RC-12-TAS Selector Switch is normally selected to Loop A&B Average; (2) The logic monitors RCS flow and if a RCS Loop Flow
<9 6%, RC-12-TAS automatically swaps to the RCS Loop with the most flow; (3) which is in this case is the Loop A Average; (4) RCS Flow input to Tave selector switch is NOT an input to SASS, so the status of SASS has NO effect on the selector switch.
A. (1) remain at the Loop A&B INCORRECT: Plausible ifthe examinee thinks RCS Flow is a SASS input Average to the logic for RC-12-TAS. RCS flow is a parameter that is SASSED for (2) SASS is inoperable input to ICS. B. (1) remain at the Loop A&B INCORRECT: Plausible because in most cases a RCP trip would cause Average a plant runback, but in this case the plant it below the runback (2) reactor power is below the setpoint. No runback would occur from a loss of this reactor coolant ICS Run back setpoint pump. If the examinee believes that since NO runback took place, that RC-12-TAS would not swap because reactor power is below the ICS runback setpoint. C. (1) swap to Loop A Average INCORRECT: Plausible since RC-12-TAS would swap to Loop A (2) the RC-P-lC breaker is open Average but NOT because because the RCP breaker is open. The correct input is RCS Flow. An RCP Breaker trip is input to the ICS runback circuit. D. (1) swap to Loop A Average CORRECT: See above (2) this loop has the highest RCS flow Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 1 K/A# 003 K5.03 Importance Rating 3.1 3.5 K/ A: Reactor Coolant Pump System: Knowledge of the operational implications of the following concepts as they apply to the RCPS: Effects of RCP shutdown on T-ave., including the reason for the unreliability of T-ave. in the shutdown loop Proposed Question: RO Question #58 Technical Reference(s): TQ-TM-104-624-COOl, Rev 4 0554566 Analog Logic Proposed References to be provided to applicants during examination: None Learning Objective: 624-GL0-10 Question Source: Bank# Modified Bank# New x TMI OPS ILT EXAM Page: 233 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Question History: N/A Last NRC Exam: N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 b.5 55.43 Comments: KA Match: This question matches the KA because the examinee must know the operational implication of a loss of flow in one reactor coolant loop, and the effect on the Tave system. High Cog: This question is high cog because the examinee must analyze the conditions in the stem to understand the plant response for a reactor coolant pump trip. TMI OPS ILT EXAM Page: 234 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS ILT EXAM Page: 235 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 59 ID: 1720699 Points: 1.00 With the Enable/Defeat switch for DC-V-2A/2B Decay Closed Cooler Inlet and DC-V-65A/65B Decay Closed Cooler Bypass placed in the DEFEAT position, this would result in DC-V-2A/2B (1) AND DC-V-65A/65B (2) A. (1) full closed (2) full open B. (1) full closed (2) full closed C. (1) full open (2) full closed D. (1) full open (2) full open Answer: c
!Answer Explanation TMI OPS IL T EXAM Page: 236 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL
<<Explanation: To answer this question correctly, the examinee must know: (1) There are key switches in the control room which need to be in the ENABLE position to be able to control each respective set of valves (DC-V-2A/65A and DC-V-2B/65B); (2) When the switches are in DEFEAT a 3 way solenoid valve fails each set of valves to their full cooling positions (DC-V-2A/2B full OPEN, and DC-V-65A/65B full CLOSED); (3) This ensures full cooling to the Decay Heat Removal System on an ES actuation.
A. (1) full closed INCORRECT: Plausible if the examinee believes that the purpose of (2) full open the key switch is to fail the valves to the NO COOLING position. B. (1) full closed (2) full closed INCORRECT: Plausible if the examinee believes the purpose of the key switch is to start with the valves fully closed and have a more controlled transition to using the OHR system for cooling. A flow path would still exist through the various pumps that the Decay Closed system provides cooling for. C. (1) full open (2) full closed CORRECT: See above. D. (1) full open (2) full open INCORRECT: Plausible if the examinee believes that the purpose of the switch in defeat is to fail the valves in a position where the pumps would have a maximum flow. Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 2 K/A# 005 A4.02 Importance Rating 3.4 3.1 K/A: Residual Heat Removal System: Ability to manually operate and/or monitor in the control room: Heat exchanger bypass flow control Proposed Question: RO Question #59 Technical Reference(s): TQ-TM-104-533-COOl, Rev 8 Proposed References to be provided to applicants during examination: None Learning Objective: 533-GL0-4 Question Source: Bank# 468123 Modified Bank# New Question History: System Exam 10 Last NRC Exam: N/A Question Cognitive Level: Memory or Fundamental Knowledge x TMI OPS ILT EXAM Page: 237 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Comprehension or Analysis 10 CFR Part SS Content: SS.41 b.7 SS.43 Comments: KA Match: This question matches the KA because the examinee must know how to operate the heat exchanger bypass flow valve from the control room. TMI OPS ILT EXAM Page: 238 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS ILT EXAM Page: 239 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL 60 ID: 1720769 Points: 1.00 Which one of the following Alternate Emergency Boration source tanks is required in accordance with 1301-1, SHIFT AND DAILY CHECKS. Boric Acid Mix Tank (BAMT) Borated Water Storage Tank (BWST) Reactor Coolant Bleed Tanks (RCBTs) Reclaimed Boric Acid Tanks (RBATs) A. BWST OR RCBT B. BAMT OR RCBT C. BAMT OR RBAT "A" OR RBAT "B" D. BWSTOR RBAT"A"ORRBAT"B" Answer: C [Answer Explanation TMI OPS IL T EXAM Page: 240 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL
<<Explanation: To answer this question correctly, the examinee must know: (1) When the TMl-1 is in a condition greater than HOT SHUTDOWN, a reactor operator performs Shift and Daily checks to ensure technical specifications are being met on key equipment to ensure compliance with LCOs. (2) One of the checks is to check what the alternate emergency boration source is and to ensure the tank meets the requirements to the alternate source; (3) The procedure identifies the BAMT, RBAT "A", or RBAT "B" as those sources.
A. BWST OR RCBT INCORRECT: Plausible since the BWST is a source of emergency boration but is not considered an alternate source. In addition, two of the three RCBTs contain a boron concentration of equal to or greater than the current RCS boron, so it is plausible that they could be considered a source as well. B. BAMT OR RCBT INCORRECT: Plausible since the BAMT is one source and two of the three RCBTs contain a boron concentration of equal to or greater than the current RCS boron, so it is plausible that they could be considered a source as well. C. BAMT OR RBAT "A" or RBAT CORRECT: See above.
"B" D. BWST OR RBAT "A" or RBAT INCORRECT: Plausible since the RBATs are an alternate source but "B" not the BWST.
Examination Outline Cross-reference: Level RO SRO Tier# 1 Group# 2 K/A# 024 2.2.12 Importance Rating 3.7 4.1 K/A: Emergency Bo ration: Knowledge of surveillance procedures. Proposed Question: RO Question # 60 Technical Reference(s): 1301-1, Rev 176 TQ-TM-104-561-COOl, Rev 4 OP-TM-EOP-010, Guide 1, Rev 19 Proposed References to be provided to applicants during examination: NONE Learning Objective: 561-GL0-7 Question Source: Bank# Modified Bank# New x Question History: N/A Last NRC Exam: N/A TMI OPS IL T EXAM Page: 241 of425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 55.41 b.10 55.43 Comments: KA Match: This question matches the KA because the procedure 1301-1, SHIFT AND DAILY CHECKS, is an surveillance procedure that checks the status of technical specification LCOs. Within that procedure, there is a section to ensure the alternate emergency boration status. TMI OPS ILT EXAM Page: 242 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS IL T EXAM Page: 243 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL 61 ID: 1720771 Points: 1.00 During normal 100% power operations, the steam supply to the Main Feedwater Pumps is the outlet of the _(1)_, and shortly following a Reactorrrurbine trip, the source of steam to the Main Feedwater Pumps is _(2)_. A. (1) "D" AND "F" Moisture Separators (2) Main Steam B. (1) "D" AND "F" Moisture Separators (2) Auxiliary Steam C. (1) HP Turbine prior to "C" AND "D" Moisture Separators (2) Main Steam D. (1) HP Turbine prior to "C" AND "D" Moisture Separators (2) Auxiliary Steam Answer: A
~nswer Explanation TMI OPS ILT EXAM Page: 244 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Explanation: To answer this question correctly, the examinee must know: (1) At 100% power, due to the design of the Main Feedwater Pump poppets, they prefer the lower pressure steam from the outlet of the "D" and "F" Moisture Separators; (2) This steam goes away when the Reactor/Main Turbine are shutdown (or tripped as in this question) so the Main Feedwater Pumps transition to the Main Steam System (via MS-V-5A/B) for their source of steam (approximately 5% to 24% power); (3) Auxiliary Steam is used during shutdown conditions. A. (1) "D" AND "F" Moisture CORRECT: See above Separators (2) Main Steam B. (1) "D" AND "F" Moisture INCORRECT: Plausible because Auxiliary Steam is used as a source of Separators steam for the Main Feedwater Pumps. Incorrect because it isn't (2) Auxiliary Steam used until the Auxiliary Boilers are running after a reactor trip. C. (1) HP Turbine prior to "C" AND INCORRECT: Plausible because there are steam line connections at "D" Moisture Separators that location. Incorrect because those steam lines to go feedwater (2) Main Steam heating. D. (1) HP Turbine prior to "C" AND INCORRECT: Plausible because there are steam line connections at "D" Moisture Separators that location. Incorrect because those steam lines to go feedwater (2) Auxiliary Steam heating. In addition Auxiliary Steam is not used right after a reactor trip. Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 1 K/A# 039 Kl.08 Importance Rating 2.7 2.9 K/A: Main and Reheat Steam System: Knowledge of the physical connections and/or cause-effect relationships between the MRSS and the following systems: MFW Proposed Question: Question #61 Technical Reference(s): 302-011 302-041 TQ-TM-104-411-COOl, Rev 8 TQ-TM-104-431-COOl, Rev 4 Proposed References to be provided to applicants during examination: None Learning Objective: 411-GL0-5 Question Source: Bank# Modified Bank# 355620 New Question History: N/A Last NRC Exam: N/A TMI OPS IL T EXAM Page: 245 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 55.41 b.7 55.43 Comments: KA Match: This question matches the KA because the examinee must know the physical connection between the Main Steam System and the Main Feedwater Pumps, in addition the cause-effect of a reactor trip on both systems. Five minutes after a Reactor/Turbine Trip from 100% power, the source of steam to the main iteedwater pumps is the: A. Main Steam System. B. Auxiliary Steam System. C. Outlet of the "C" Moisture Separator. D. 4th stage of the Extraction Steam System. Answer: A TMI OPS IL T EXAM Page: 246 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL TMI OPS IL T EXAM Page: 247 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 62 ID: 1720783 Points: 1.00 Plant Condition:
- 100% power with ICS in full auto.
EVENT
- Loss of Offsite Power Subsequently:
- All 8 (eight) HSPS switches placed in DEFEAT.
- No other operator actions have been taken.
What is the setpoint from HSPS for OTSG level control? A. O" on the startup range. B. 25" on the startup range. C. 50% on the operating range. D. 75-85% on the operating range. Answer: C
!Answer Explanation TMI OPS ILT EXAM Page: 248 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Explanation: To answer this question correctly, the examinee must know: (1) On a Loss of Offsite Power, all Reactor Coolant Pumps trip; (2) When this happens, the HSPS setpoint sent to the EF-V-30s for OTSG level control is 50% in the operating range to promote natural circulation; (3) When the HSPS switches are taken to DEFEAT, the 50% operating range signal is still locked in, until the operator breaks the 'seal-in' relay by taking each EF-V-30 to manual; (4) Since the stem does not indicate that this happens, the setpoint remains 50% in the operating range. A. O" on the startup range. INCORRECT: Plausible because the examinee could believe that HSPS has lost power on the loss of offsite power, and that OTSG level control will have to be in manual. Incorrect because HSPS is powered from the Vital Busses, and they do not lose power on a loss of offsite power. B. 25" on the startup range. INCORRECT: Plausible because on a loss of offsite power, both Main Feedwater Pumps would trip. When the Main Feedwater Pumps trip, HSPS sends a signal to control OTSG level at 25" in the startup range. Incorrect because the loss of reactor coolant pump signal has priority. C. 50% on the operating range CORRECT: See above D. 75-85% on the operating INCORRECT: Plausible because the operator would feed to this range. range in accordance with Rule 4 of OP-TM-EOP-010, EMERGENCY PROCEDURE RULES, GUIDES, AND GRAPHS if subcooling margin were gone. Feeding this high would also promote natural circulation more. Incorrect because the operator has to take manual control to feed to this level. Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 2 K/A# 061 A3.03 Importance Rating 3.9 3.9 K/A: Auxiliary/Emergency Feed water (AFW) System: Ability to monitor automatic operation of the AFW, including: AFW S/G level control on automatic start Proposed Question: RO Question #62 Technical Reference(s): TQ-TM-104-644-COOl, Rev 2 Proposed References to be provided to applicants during examination: None Learning Objective: 644-GL0-5 Question Source: Bank# Modified Bank# 719815 New TMI OPS IL T EXAM Page: 249 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Question History: System Exam 9 Last NRC Exam: N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 b.7 55.43 Comments: KA Match: This question matches the KA because the examinee must know the automatic operation of the EFW system that should occur on a loss of offsite power, which includes the signal that HSPS controls OTSG level. High Cog: This question is high cog because the examinee must know the plant response on a loss of offsite power, and the effect on HSPS level control. Plant Conditions:
- Loss of BOTH FW pumps
- Reactor and Turbine trip Event:
- All 8 (eight) HSPS switches placed in DEFEAT.
- No other operator actions have been taken.
What is the setpoint, from HSPS, for OTSG level control? A. O" on the startup range. B. 25" on the startup range. C. 50% on the operating range. D. 75-85% on the operating range. Answer: B TMI OPS ILT EXAM Page: 250 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS ILT EXAM Page: 251 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 63 ID: 1724247 Points: 1.00 Plant Conditions:
- 40% power with ICS in auto.
- Main Condenser Tube Leak on the "A" side.
- Circulating Water Pumps, CW-P-1A, CW-P-1B, CW-P-1C are shutdown.
- Loop Cross Connect Valves, CW-V-4A/4B are closed.
EVENT:
- CW-P-1 D Trips.
- Main Condenser vacuum starts to lower.
- CRS directs the CRO to trip the Main Turbine.
- Main Condenser vacuum lowers to 25" Hg and stabilizes.
Based on the conditions, the reactor has _(1 )_and OTSG pressure control is being controlled by the _(2)_. A. (1) tripped (2) Turbine Bypass Valves B. (1)tripped (2) Atmospheric Dump Valves C. (1) stabilized at -18% power (2) Turbine Bypass Valves D. (1) stabilized at -18% power (2) Atmospheric Dump Valves Answer: C
!Answer Explanation TMI OPS ILT EXAM Page: 252 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL
<<Explanation: To answer this question correctly, the examinee must know: (1) OTSG pressure control transfers from the Turbine Bypass Valves (TBVs) to the Atmospheric Dump Valves (ADVs) when there are
< 2 Circulating Water Pumps operating or when Main Condenser Vacuum is< 23" Hg; (2) In this question, when CW-P-10 trips, this still leaves 2 Circulating Water Pumps operating, and since Main Condenser Vacuum never lowers to less than 23" Hg, the TBVs retain OTSG pressure control; (3) Due to reactor power being below 45%, when the Main Turbine is tripped, the reactor will not automaticaly trip, but will run back to approximately 18% power.
A. (1) tripped INCORRECT: Plausible it the examinee does not recognize that at (2) Turbine Bypass Valves 40% power the Reactor will not trip on a Turbine Trip. Incorrect because the reactor does not trip. B. (1) tripped INCORRECT: Plausible it the examinee does not recognize that at (2) Atmospheric Dump Valves 40% power the Reactor will not trip on a Turbine Trip. Incorrect because the reactor will not trip,and the ADVs will not have OTSG pressure control.
- c. (1) stabilized at -18% power CORRECT: See above (2) Turbine Bypass Valves D. (1) stabilized at -18% power INCORRECT: Plausible because the examinee could believe that the (2) Atmospheric Dump ADVs have OTSG pressure control.
Valves Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 2 K/A# 075 2.4.21 Importance Rating 4.0 4.6 K/A: Circulating Water System: Knowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc. Proposed Question: RO Question # 63 Technical Reference(s): ICS Digital Print D553854 TQ-TM-104-621-COOl, Rev 8 TQ-TM-104-641-COOl, Rev 2 OP-TM-411-000, Rev 21 Proposed References to be provided to applicants during examination: None Learning Objective: 641-GL0-10 Question Source: Bank# Modified Bank# New x Question History: N/A Last NRC Exam: N/A TMI OPS ILT EXAM Page: 253 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 b.7 55.43 Comments: KA Match: This question matches the KA because the examinee have knowledge relative to the OTSG pressure control logic with respect to operation of the CW Pumps. In-addition requires knowledge related to heat production because of the run back and heat removal. High Cog: This question is high cog because the examinee analyzes plant conditions and has to integrate the relationship between the operation of several systems. TMI OPS IL T EXAM Page: 254 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS IL T EXAM Page: 255 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 64 ID: 1736357 Points: 1.00 Plant Conditions:
- 100% power with ICS in full auto.
EVENT:
- Electrical load reducing, with a constant reactor power.
- OTSG 1A steam pressure is 870 psig and decreasing.
- RB pressure is 0.3 psig and steady.
- Total FW flow is 10.2 E6 lbm/hr.
- PLF-1-9 and PLF-1-10 for Intermediate Bldg Fire AND Intermediate Bldg Trouble
- AH-E-73 (Intermediate Bldg.) discharge high temperature alarm.
- PPC Point A0331 TURB DRIV EF-P1 BRG COOL WTR OUT is in Hl-2 Alarm
- RM-A-2G reading normal.
What action is required for the above event? A. Dispatch personnel to look for the steam leak. B. Manually trip the Reactor AND go to OP-TM-EOP-001. C. ~educe power to < 45% and manually trip the Main Turbine. D. Initiate a Plant Shutdown IAW 1102-4, POWER OPERATION. Answer: B [Answer Explanation TMI OPS ILT EXAM Page: 256 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Explanation: To answer this question correctly, the examinee must know: (1) Based on the symptoms there is steam leak in the Intermediated Building; (2) OP-TM-AOP-051, SECONDARY SIDE HIGH ENERGY LEAK, Section 5, directs if there is a leak in the Intermediate Building with a Hi-2 alarm on safety related equipment to trip the Reactor and GO TO OP-TM-EOP-001, REACTOR TRIP; (3) EF-P-1 is safety related equipment. A. Dispatch personnel to look for INCORRECT: Plausible if the examinee is not sure of leak location. the steam leak. The procedure does address looking for the leak when it is in the Reactor Building. B. Manually trip the Reactor AND CORRECT: See above. go to OP-TM-EOP-001 C. Reduce power to< 45% and INCORRECT: Plausible if the examine believes that since the steam manually trip the Main Turbine leak is in the Intermediate Building they could initiate a plant shutdown and when below 45%, then the turbine could be tripped without an automatic reactor trip. D.. Initiate a Plant Shutdown IAW INCORRECT: Plausible since this step appears several time the in 1102-4, POWER OPERATION. OP-TM-AOP-051, however the Hl-2 Alarm would require tripping the Reactor. Examination Outline Cross-reference: Level RO SRO Tier# 1 Group# 1 K/A# 040 AA2.02 Importance Rating 4.6 4.7 K/ A: Steam Line Rupture: Ability to determine and interpret the following as they apply to the Steam Line Rupture: Conditions requiring a reactor trip Proposed Question: RO Question #64 Technical Reference(s): OP-TM-AOP-051, Rev 2 Proposed References to be provided to applicants during examination: None Learning Objective: AOP-051-PC0-5 Question Source: Bank# Modified Bank# 462996 New Question History: N/A Last NRC Exam: N/A Question Cognitive Level: Memory or Fundamental Knowledge TMI OPS ILT EXAM Page: 257 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 b.5 55.43 Comments: KA Match: This question matches the KA because the examinee must know the that the reactor must be tripped with a steam line rupture in the intermediate building if there is a Hl-2 alarm on safety related equipment. High Cog: This question require analysis of plant conditions and based on these conditions, the priority of required actions. lrhe plant has been operating at full power when the following indications are received:
- Electrical load reducing, with a constant reactor power.
- OTSG 1A steam pressure is 870 psig and decreasing.
- RB pressure is 0.3 psig and steady.
- Total FW flow is 10.2 E6 lbm/hr.
- AH-E-73 (Intermediate Bldg.) discharge high temperature alarm.
- PPC Point A0331 TURB DRIV EF-P1 BRG COOL WTR OUT is in alarm and currently at 123 F and rising at 2 degrees every minute
- AH-E-24A (EFW pump area) trips on high discharge temperature.
- RM-A-2G reading normal.
Mthat action is required for the above event? A. Manually trip the Reactor AND go to OP-TM-EOP-001. B. Reduce power to < 45% and manually trip the Main Turbine. C. Reduce power at a rate specified by the CRS until an RPS trip setpoint is reached. D. Verify no personnel are in the Intermediate Building AND continue Power Operations. Answer: A TMI OPS ILT EXAM Page: 258 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS IL T EXAM Page: 259 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 65 ID: 1718268 Points: 1.00 Plant Conditions:
- 100% power with ICS in full auto.
- Building Spray Pump, BS-P-1 B, is out of service.
SEQUENCE OF EVENTS:
- 1. LOCA
- 2. RCS pressure lowers to 890 psig.
- 3. Reactor Building Pressure rises to 32 psig.
- 4. 1S 480V ES Bus trips.
Post Accident Reactor Building cooling is (1) , because (2) A. (1) adequate (2) one Building Spray Pump and one Reactor Building Emergency Cooling Fan (AH-E-1) are operating B. (1) adequate (2) one Building Spray Pump and two Reactor Building Emergency Cooling Fans (AH-E-1) are operating C. (1) NOT adequate (2) only one Building Spray Pump and one Reactor Building Emergency Cooling Fan (AH-E-1) are operating D. (1) NOT adequate (2) only one Building Spray Pump and two Reactor Building Emergence Cooling Fans (AH-E-1) are operating Answer: A
~nswer Explanation TMI OPS ILT EXAM Page: 260 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL
<<Explanation: To answer this question correctly, the examinee must know: (1) The post-accident reactor building emergency cooling is adequate with one Building Spray Pump and one Reactor Building Emergency Cooling Fan; (2) In this question, the examinee is starting with one Building Spray Pump out of service, the other Building Spray pump remains operable; (3) When the ES occurs (indicated by RCS pressure lowering to 890 psig), the transfer of lC ES Valves 480V bus is inhibited and will remain powered from lS 480V ES Bus; (4) When lS 480V ES bus trips, AH-E-lB and AH-E-lC lose power, thus leaving only AH-E-lA operable.
A. (1) adequate CORRECT: Correct Answer (2) one Building Spray Pump and one Reactor Building Emergency Cooling Fan (AH-E-1) is operating B. (1) adequate INCORRECT: Plausible because the examinee could believe that lC (2) one Building Spray Pump ES Valves MCC swapped to lP 480V ES Bus, which would have and two Reactor Building powered AH-E-lC. Incorrect because the ES blocked lC ES Valves Emergency Cooling Fans from swapping to lP 480V ES bus, thus leaving AH-E-lC without (AH-E-1) are operating power. C. (1) NOT adequate INCORRECT: Plausible because the examinee could believe that (2) only one Building Spray having only one Building Spray pump and one RB Emergency Cooling Pump and one Reactor Building fan operating is inadequate post accident cooling. Incorrect because Emergency Cooling Fan having one of each running is adequate. (AH-E-1) is operating D. (1) NOT adequate INCORRECT: Plausible because the examinee could believe that (2) only one Building Spray having only one Building Spray pump and two RB Emergency Cooling Pump and two Reactor Building fans is inadequate post accident cooling. Incorrect because only one Emergence Cooling Fans of each running is adequate. (AH-E-1) are operating Examination Outline Cross-reference: Level RO SRO Tier# 2 2 Group# 1 1 K/A# 026 K3.01 Importance Rating 3.9 4.1 K/ A: Containment Spray System: Knowledge of the effect that a loss or malfunction of the CSS will have on the following: CCS Proposed Question: RO Question #65 Technical Reference(s): TQ-TM-104-642-COOl, Rev 7 Proposed References to be provided to applicants during examination: None Learning Objective: 642-GL0-10 Question Source: Bank# TMI OPS IL T EXAM Page: 261 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL Modified Bank# New x Question History: N/A Last NRC Exam: NO Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part SS Content: SS.41 b.7 SS.43 Comments: KA Match: This question matches the KA because the examinee must know the effect that a loss of one Building Spray Pump and two RB Emergency Cooling fans will have on the containment cooling system. High Cog: This question is High Cog because the examinee must analyze the stem and recognize that an ES signal has occurred and how the loss of power has affected the Building Spray and RB Emergency Cooling Systems. TMI OPS IL T EXAM Page: 262 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS ILT EXAM Page: 263 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL 66 ID: 1736429 Points: 1.00 Plant Conditions:
- 90% power with ICS in auto.
EVENT:
- PLB-1-7 INSTRUMENT AIR PRESS LOW TURBINE AREA comes in.
- Pl-1403 Secondary IA pressure reads 59 psig.
- Pl-222 Primary Instrument Air pressure reads 90 psig.
Based on the above plant conditions, the initial action the operating crew must perform is: A. Trip the Reactor. B. Initiate a plant shutdown. C. Dispatch a NLO to isolate Primary IA from Secondary IA. D. Start Instrument Air Compressors, IA-P-1A and IA-P-1 B from the Control Room. Answer: A
!Answer Explanation TMI OPS IL T EXAM Page: 264 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL
<<Explanation: To answer this question correctly, the examinee must know: (l)OP-TM-AOP-028, LOSS OF INSTRUMENT AIR is entered when pressure on Pl-1403 < 80 psig; (2) When pressure on Pl-1403 goes less than 60 psig, the next steps are to dispatch operators to block open MU-V-20 and IC-V-3 and 4, then trip the reactor. (3) Of the actions listed, the operating crew would trip the reactor.
A. Trip the Reactor. INCORRECT: See above B. Initiate a plant shutdown. INCORRECT: Plausible if the examinee believes that due to the loss of instrument air a Technical Specification LCO must be entered, and a plant shutdown must occur. Incorrect the reactor must be tripped when Pl-1403 reads less than 60 psig.Plausible since this would be done if Primary IA>80- and Secondary< 60 AND the Reactor was not tripped per procedure requirements. Then the procedure directs to restore Secondary Pressure. C. Dispatch a NLO to isolate INCORRECT: INCORRECT: Plausible since this could raise instrument Primary IA from Secondary IA. air pressure. Incorrect because the operating crew must tripped when Pl-1403 < 60 psig. D. Start Instrument Air INCORRECT: Plausible because this is an action in OP-TM-AOP-028 Compressors, IA-P-lA and to take if IA-Pl-491 < 85 psig. Incorrect because the reactor must be IA-P-lB from the Control tripped when Pl-1403 is less than 60 psig. Room. Examination Outline Cross-reference: Level RO SRO Tier# 1 Group# 1 K/A# 065 AA2.06 Importance Rating 3.6 4.2 K/ A: Loss of Instrument Air: Ability to determine and interpret the following as they apply to the Loss of Instrument Air: When to trip reactor if instrument air pressure is de-creasing Proposed Question: RO Question# 66 Technical Reference(s): OP-TM-AOP-028, Rev 8 Proposed References to be provided to applicants during examination: None Learning Objective: 850-PC0-5 Question Source: Bank# Modified Bank# New x Question History: N/A Last NRC Exam: N/A TMI OPS ILT EXAM Page: 265 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 b.7 Comments: KA MATCH: This question matches the KA because the examinee must know when the reactor must be tripped on a loss of instrument air. TMI OPS IL T EXAM Page: 266 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS ILT EXAM Page: 267 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 67 ID: 1736434 Points: 1.00 Plant Conditions:
- The Plant has been shutdown for 24 days.
- Reactor Vessel level is being lowered in support of internal Reactor Vessel work.
- The "B" Train of Decay Heat Removal (OHR) is operating with a flow rate of 1,400 gpm.
EVENT:
- PLB-5-5 18 DECAY HEAT REMOVAL COMPARTMENT LEAK DETECT comes in.
- Decay Heat Pump, DH-P-1 B, suction line temperature indicator has risen 10.5°F.
- RCS Cold Leg level is 15 inches above centerline and slowly lowering.
- DH-P-1 B motor amperage and flow is significantly oscillating.
Based on the above conditions, which ONE of the following actions must be taken FIRST? A. Start "A" Train of Decay Heat Removal. B. Lower flowrate from DH-P-1 B to less than 1,200 gpm. C. Immediately place DH-P-1 Bin the "Pull-to-Lock" position. D. Raise RCS level until Decay Heat removal Pump operating indications are normal. Answer: C
!Answer Explanation TMI OPS ILT EXAM Page: 268 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Explanation: To answer this question correctly, the examinee must know: (1) The OP-TM-EOP-030, LOSS OF DECAY HEAT REMOVAL, entry criteria are met: lncore temperature increases> lOF due to an unplanned condition; (2) In addition, since flow and motor amperage are oscillating, in accordance with Step 2.1, DH-P-lB must be placed in PTL. A. Start "A" Train of Decay Heat INCORRECT: Plausible since the follow up actions direct this action, Removal. however the priority is to place DH-P-lB in PTL. In-addition, starting the alternate pump could cause a common mode failure with lowering level. B. Lower flowrate from DH-P-lB INCORRECT: Plausible since lowering flowrate from DH-P-lB to less to less than 1,200 gpm. than 1,200 gpm would place parameters into a more acceptable region. This flow rate would still not be allowed. C. Immediately place DH-P-lB in CORRECT: See above the "pull-to-lock" position. D. Raise RCS level until Decay INCORRECT: Plausible since Raising RCS level until Decay Heat Heat removal Pump operating removal Pump operating indications are normal would maintain indications are normal. level in the acceptable region and possibly reduce oscillating pump parameters, but not allowed under these conditions, since EOP-030 requires stopping the pump given the initial conditions. Examination Outline Cross-reference: Level RO SRO Tier# 1 Group# 1 K/A# 025 AA2.01 Importance Rating 2.7 2.9 K/A: Loss of Decay Heat Removal: Ability to determine and interpret the following as they apply to the Loss of Residual Heat Removal System: Proper amperage of running LPl/decay heat removal/RHR pump(s) Proposed Question: RO Question# 67 Technical Reference(s): OP-TM-EOP-030, Rev 9 OP-TM-212-000, Rev 23 OP-TM-212-000, Attachment Proposed References to be provided to applicants during 7.2 Min Height of Water to examination: Avoid Vortex Formation vs DH Flow Learning Objective: EOP-030-PC0-4 Question Source: Bank# Modified Bank# 304375 TMI OPS ILT EXAM Page: 269 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL New Question History: Sim Exam 9 Last NRC Exam: N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 55.43 Comments: KA MATCH: This question matches the KA because the examinee must interpret the oscillating running amperage of a DHR pump to determine that it is cavitating. High Cog: The examinee must analyze the stem to determine the entry criteria for OP-TM-EOP-030 are met, and then determine that DH-P-lA must be place in PTL. In addition, the examinee can check the answer to determine that the pump is below the vortex limit. Plant Conditions:
- The Plant has been Shutdown for 24 days.
- Reactor Vessel level is being lowered in support of internal Reactor Vessel work.
- The "B" Train of Decay Heat Removal (DHR) is operating with a flow rate of 1,400 gpm.
- The "A" Train of DHR is out-of-service for minor maintenance and is expected to be returned to service within the next 4 hours.
Event:
- Decay Heat Pump, DH-P-1 B, suction line temperature indicator has risen 10.5°F.
- RCS Cold Leg level is 10.5 inches above centerline.
- DH-P-1 B Motor Amperage is significantly oscillating.
Based on the above conditions, which ONE of the following actions will be taken FIRST? A. Lower flowrate from DH-P-1 B to less than 1,200 gpm. B. Immediately place DH-P-18 in the "pull-to-lock" position. C. Raise RCS level to at least 14 inches above Hot Leg centerline. D. Actuate the RB Evacuation alarm and evacuate ALL personnel from the RB. Answer: B TMI OPS IL T EXAM Page: 270 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS IL T EXAM Page: 271 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 68 ID: 1736443 Points: 1.00 Plant Conditions:
- 100% power with ICS in full auto.
- MU-P-1A (Make-up Pump) is supplying normal make-up and Seal Injection.
- MU-P-1 Bis in Normal-After Stop.
SEQUENCE OF EVENTS:
- Loss of Coolant Accident.
- RCS pressure lowers to 1500 psig.
- RB pressure is 5 psig.
- Loss of Offsite Power.
- MU-P-1A Trips.
Based on the above conditions, if MU-P-1 B is ES Selected using the 43 Selector Switch on the 1E 4160V Bus, MU-P-1B would _(1)_ and MU-P-1C would _(2)_. A. (1) start and continue to run, (2) trip. B. (1) start and continue to run, (2) continue to run. C. (1) start and immediately trip, (2) trip. D. (1) start and immediately trip, (2) continue to run. Answer: A
!Answer Explanation TMI OPS IL T EXAM Page: 272 of 425 24 April 2017
EXAMINATIO'N ANSWER KEY 16-01 NRC EXAM SUBMITIAL
<<Explanation: To answer this question correctly, the examinee must know: (1) The LOCA occurs which causes an ES Actuation, both 1600 psig and 4 psig, this sends a start signal to MU-P-lA and MU-P-lC; (2) These are Block 1 ES loads, when the LOOP occurs, MU-P-lA and MU-P-lC stop and restart when the Emergency Diesel Generators start and load on the 10 and 1E 4160V busses; (3) When the 43 selector switch on the lE 4160V Bus is rotated to ES select MU-P-lB, then MU-P-lB will start and MU-P-lC will trip.
A. (1) start and continue to run, CORRECT: See above. (2) trip. B. (1) start and immediately trip, INCORRECT: Plausible if the examinee thinks that since MU-P-lB is (2) trip. green flagged that anti-pump would actuate when the pump is started and trip the pump. Incorrect because anti-pump would only actuate if a simultaneous trip and start signal. C. (1) start and continue to run, INCORRECT: Part 1 is correct. Part 2 is plausible if the examinee does (2) continue to run. not understand the operation of the 43 selector switch and its effect on the pump trip circuit. This interlock exists to prohibit from running two Makeup Pumps on a Emergency Diesel Generator. D. (1) start and immediately trip, INCORRECT: Plausible if the examinee thinks that since MU-P-lB is (2) continueto run. green flagged that anti-pump would actuate when the pump is started and trip the pump. Incorrect because anti-pump would only actuate if a simultaneous trip and start signal. Part 2 is plausible if the examinee does not understand the operation of the 43 selector switch and its effluent on the pump trip circuit. Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 2 K/A# 006 K2.01 Importance Rating 3.6 3.9 K/A: Emergency Core Cooling System: Knowledge of bus power supplies to the following: ECCS Pumps Proposed Question: RO Question# 68 Technical Reference(s): 1105-3, Rev 53 Proposed References to be provided to applicants during examination: None Learning Objective: 211-GL0-10 Question Source: Bank# Modified Bank# New x TMI OPS IL T EXAM Page: 273 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Question History: N/A Last NRC Exam: N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 b.7 55.43 Comments: KA Match: This question matches the KA because the examinee must have knowledge of the power supply to the Makeup Pumps and knowledge of the interlock preventing from running two Makeup Pumps on an Emergency Diesel Generator. High Cog: This question is High Cog because the examinee must analyze the plant conditions to determine the status of MU-P-lB after a LOOP and ES actuation. TMI OPS IL T EXAM Page: 274 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS ILT EXAM Page: 275 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 69 ID: 1736454 Points: 1.00 Plant Conditions:
- 50% power with ICS in auto.
EVENT:
- MAP G-2-1 CRD PATTERN ASYMMETRIC alarms.
- Red Fault Indication lit on the Position Indication Panel (PIP).
- The Asymmetric Control Rod Fault indication is currently lit on the Diamond Control Panel.
These indications would be caused by a deviation of an individual rod position of (1) from the group average, which (2) , and would require entry into OP-TM-AOP-062, INOPERABLE ROD. A. (1) 7 inches (2) excludes the faulted rod B. (1) 7 inches (2) includes the faulted rod C. (1) 9 inches (2) excludes the faulted rod D. (1) 9 inches (2) includes the faulted rod Answer: c
!Answer Explanation TMI OPS ILT EXAM Page: 276 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Explanation: To answer this question correctly, the examinee must know: (1) Each rod in a group is compared with the group average; (2) If a rod in a group deviates by more than 7 inches (5%) from the group average, an individual amber fault light for that rod will light on the Pl panel; (3) A rod that is 9 inches (6.5%) from its group average, the faulted rod is removed from the group average calculation; (4) An individual red fault light for that rod will light on the PIP and the asymmetric fault light on the Operator Diamond Control Panel will be lit; (5) Both the 7" and 9" Asymmetric fault initiate alarm MAP G-2-1. (6) The 7" Asymmetric Rod does NOT require entry into AOP-062. A. (1) 7 inches INCORRECT: Plausible since this initiates the G-2-1 Alarm. Incorrect (2) excluding the Faulted Rod. because the examinee may think that the 7" also excludes the faulted rod as does the 9' fault. In addition, a 7" rod does not require entry into OP-TM-AOP-062. B. (1) 7 inches INCORRECT: Plausible since this initiates the G-2-1 Alarm and the 7" (2) including the Faulted Rod. fault does include the faulted rod. Incorrect because a 7" misaligned rod does not require entry into OP-TM-AOP-062. C. (1) 9 inches CORRECT: See above (2) excluding the Faulted Rod. D. (1) 9 inches INCORRECT" Plausible since the 9" fault would cause all the above (2) including the Faulted Rod. indications, requires entry into OP-TM-AOP-062, however does not include the faulted rod in the calculation. Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 2 K/A# 014 2.4.4 Importance Rating 4.5 4.7 K/A: Rod Position Indication: Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures. Proposed Question: RO Question # 69 Technical Reference(s): OP-TM-AOP-062, Rev 007 TQ-TM-104-622-COOl, Rev 007 OP-TM-622-000, Rev 007 Proposed References to be provided to applicants during examination: None Learning Objective: 622-GL0-10 Question Source: Bank# Modified Bank# 782160 New Question History: System Exam 14 Last NRC Exam: N/A TMI OPS IL T EXAM Page: 277 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 b.10 55.43 Comments: KA Match: This question matches the KA because the examinee must recognize the entry conditions to OP-TM-AOP-062 based on the misaligned rod indications. High Cog: This question is high cog because the examinee must analyze the indications in the stem to determine if an AOP must be entered. The Asymmetric control rod fault indication is currently lit on the Diamond control station. Select the ONE choice below that correctly describes the indications that constitute an asymmetric control rod fault indication on the Diamond control station. A. Deviation of an individual rod's position indication of 9 inches, (6.5%), from the average position of the remaining 60 full length control rods. B. Deviation of an individual rod's position indication of 7 inches, (5%), from the average position indication of all of the control rods in that group. Faulted rod remains in the group average. C. Deviation of an individual rod's position indication of 9 inches, (6.5%), from the average position indication of the other control rods in that group. Faulted rod remains in the group average. D. Deviation of an individual rod's position indication of 9 inches, (6.5%), from the average position indication of all of the control rods in that group. Faulted rod is removed from the group average. Answer: D TMI OPS ILT EXAM Page: 278 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL TMI OPS ILT EXAM Page: 279 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL 70 ID: 1736470 Points: 1.00 What is minimum personnel that must be in the Control Room in accordance with OP-TM-112-101-1002, SHIFT STAFFING REQUIREMENTS, when the RCS temperature is greater than 200F? A. One SRO or one RO B. One SRO AND one RO C. One SRO AND two ROs D. One SRO OR one RO AND one STA Answer: B
!Answer Explanation TMI OPS IL T EXAM Page: 280 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL
<<Explanation: To answer this question correctly, the examinee must know: (1) OP-TM-112-101-1002 requires that a minimum of 1 SRO and 1 RO be in the Control Room at all times when RCS temperature is
> 200F.
A. One SRO or one RO INCORRECT: Plausible since if RCS temperature were less than 200F this combination would be acceptable. B. One SRO AND one RO CORRECT: See Above C. One SRO AND two ROs INCORRECT: Plausible if the examinee interprets the table in step 4.1 to mean that the two RO's must be in the control room at all times. Incorrect because the table is referring to minimum shift staffing. D. One SRO OR one RO AND one INCORRECT: Plausible if the examinee interprets the table in step STA 4.1 to mean that the one RO and the STA must be in the control room at all times. Incorrect because the table is referring to minimum shift staffing. Examination Outline Cross-reference: Level RO SRO Tier# 3 Group# 1 K/A# 2.1.1 Importance Rating 3.8 4.2 K/A: Knowledge of conduct of operations requirements. Proposed Question: RO Question #70 Technical Reference(s): OP-TM-112-101-1002, Rev 10 Tech Spec 6.2.2.2 Proposed References to be provided to applicants during examination: None Learning Objective: Prewatch DBIG - APC0-1 Question Source: Bank# 372961 Modified Bank# New Question History: N/A Last NRC Exam: N/A Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 55.41 b.10 TMI OPS ILT EXAM Page: 281 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL 55.43 Comments: (KA Match, why high cog, why SRO only) KA MATCH: This question matches the KA because the examinee must know the minimum shift staffing in the control room. TMI OPS ILT EXAM Page: 282 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS ILT EXAM Page: 283 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL 71 ID: 1736534 Points: 1.00 In accordance with Tech Specs, the Minimum Conditions for Criticality (Excluding Low Power Physics Testing) requires the RCS Temperature to be _(1 )_and the Safety Rod Groups to be _(2)_ prior to any other reduction in shutdown margin. A. (1) ~ 532F (2) fully withdrawn B. (1) ~ 532F (2) fully inserted C. (1) >525F (2) fully withdrawn D. (1) >525F (2) fully inserted Answer: C
!Answer Explanation TMI OPS ILT EXAM Page: 284 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL
<<Explanation: To answer this question correctly, the examinee must know: (1) Tech Spec 3.1.3- The reactor coolant temperature shall be above 525°F except for port ans of low power physics test ng. (2)
Safety rod groups shall be fully withdrawn prior to any other reduct on in shutdown margin by deborat on or regulat ng rod withdrawal during the approach to crit cality A. (1) ~ 532F (2) fully withdrawn INCORRECT: Plausible since the calculation for Estimated Critical Rod Position assumes RCS Temperature is S32F. B. (1) ~ 532F (2) fully inserted INCORRECT: Plausible since the calculation for Estimated Critical Rod Position assumes RCS Temperature is 532F and if the examinee thinks the Safety Rods must be inserted to maintain the Tech Spec required 1% SDM prior to withdrawing rods with the intent to go critical. C. (1) >525F (2) fully withdrawn. CORRECT: See above D. (1) >525F (2) fully inserted INCORRECT: Plausible if the examinee thinks the Safety Rods must be inserted to maintain the Tech Spec required 1% SDM prior to withdrawing rods with the intent to go critical. Examination Outline Cross-reference: Level RO SRO Tier# 3 Group# 2 K/A# 2.2.38 Importance Rating 3.6 4.5
~
K/A: Equipment Control: Knowledge of conditions and limitations in the facility license. Proposed Question: RO Question # 71 Technical Reference(s): 1103-8, Rev 55 T.S. 3.1.3, AMD 278 Proposed References to be provided to applicants during examination: None Learning Objective: Normal Ops - APC0-1 Question Source: Bank# Modified Bank# New x Question History: N/A Last NRC Exam: N/A Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis TMI OPS ILT EXAM Page: 285 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL 10 CFR Part 55 Content: 55.41 55.43 Comments: (KA Match, why high cog, why SRO only) KA Match: This question matches the KA because the examinee must have knowledge of the requirements to pull to criticality. TMI OPS ILT EXAM Page: 286 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS ILT EXAM Page: 287 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 72 ID: 1737637 Points: 1.00 A surveillance for an ES pump is in progress. The analog suction pressure gauge, normally isolated except for this surveillance, is broken. The suction pressure is used to calculate pump head, which is a required parameter for the surveillance test. Another suitable analog gauge measuring pump suction pressure is available. Based on the broken gauge, which one of the following identifies the required actions with respect to this surveillance? A. Continue performing the surveillance using the alternate means. B. Continue performing the surveillance and annotate in the procedure that the alternate means was used. C. Stop the surveillance. The surveillance may not be run until the gauge is fixed. D. Stop the surveillance and change the surveillance to allow the alternate means of measuring pump suction pressure. Answer: D
~nswer Explanation TMI OPS ILT EXAM Page: 288 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL
<<Explanation: To answer this question correctly, the examinee must know: (1) ER-TM-321-1041, Attachment 1 addresses instrument requirements for an Jn-Service Test (IST); (2) If an instrument fails during and JST the correct actions are to : Stop the test, place the system in a safe configuration, locate a backup instrument or replace the existing instrument using Section 2 of the attachment, and resume or re-perform the test with the replaced instrument.
A. Continue performing the INCORRECT: Plausible because there is another suitable pressure surveillance using the gauge available. Incorrect because the operator must stop the alternate instrument. surveillance prior to using the instrument. B. Continue performing the INCORRECT: Plausible because there is another suitable pressure surveillance and annotate in gauge available. Incorrect because the operator must stop the the procedure that the surveillance prior to using the instrument. alternate instrument was used. C. Stop the surveillance. The INCORRECT: Plausible because the examinee may believe that since surveillance may not be run the test involves an ES pump that all the instrumentation for the test until the gauge is fixed. must be functioning correctly. D. Stop the surveillance and CORRECT ANSWER: See above. change the surveillance to allow the alternate means of measuring pump suction pressure. Examination Outline Cross-reference: Level RO SRO Tier# 3
--~---*-
Group# 2 K/A# 2.2.12 Importance Rating 3.7 4.1 KIA: Knowledge of surveillance procedures. Proposed Question: Question 72 Technical Reference(s): ER-TM-321-1041, Rev 7 Proposed References to be provided to applicants during examination: None Learning Objective: EOP DBIG, APC0-2 Question Source: Bank # 504102 Modified Bank # TMI OPS ILT EXAM Page: 289 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL New Question History: None Last NRC Exam: None Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 b.10 55.43 Comments: KA Match: This question matches the KA because the examinee must have knowledge of the IST program requirements at TMI. TMI OPS IL T EXAM Page: 290 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS ILT EXAM Page: 291 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 73 ID: 1736792 Points: 1.00 Plant Conditions:
- OP-TM-EOP-005, OTSG TUBE LEAKAGE has been entered for a 'A' OTSG tube rupture.
- Reactor is tripped.
'A' OTSG must be isolated when _(1 )_AND _(2)_.
A. (1) RCS pressure is less than 1000 psig, (2) BWST level < 22 feet B. (1) OTSG pressure is less than 1000 psig, (2) BWST level < 22 feet C. (1) RCS pressure is less than 1000 psig, (2) Offsite integrated dose approaches 500 mRem COE (Thyroid) D. (1) OTSG Pressure is less than 1000 psig, (2) Offsite integrated dose approaches 500 mRem COE (Thyroid) Answer: A
!Answer Explanation TMI OPS ILT EXAM Page: 292 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL
<<Explanation: To answer this question correctly, the examinee must know: (1) In OP-TM-EOP-005, the isolation criteria is as follows: RCS pressure <1000 psig and OTSG Level > 85%, RCS pressure< 1000 psig and offsite dose projections approaches 500 mRem TEOE or 1500 mRem COE Thyroid, RCS pressure<
1000 psig and BWST Level< 22 ft; (2) An OTSG is not isolated with RCS pressure above 1000 psig to preclude possibly lifting the MSSV. A. (1) RCS pressure is less than CORRECT: See above 1000 psig, (2) BWST level< 22 feet B. (1) OTSG pressure is less than INCORRECT: Plausible since OTSG pressure< 1000 psig would be 1000 psig, below all setpoints for OSTG steam safety valves. Incorrect because (2) BWST level< 22 feet OP-TM-EOP-005 directs isolation only after RCS pressure has lowered to less than 1000 psig. C. (1) RCS pressure is less than INCORRECT: Plausible since RCS Pressure< 1000 psig is correct and if 1000 psig, the examinee believes that the limit for COE is 500 mRem. Incorrect (2) Offsite integrated dose because the limit is 5000 mRem for TEDE. approaches 500 mRem COE (Thyroid)
- 0. (1) OTSG Pressure is less than INCORRECT: Plausible if the examinee believes that the limit for COE 1000 psig, is 500 mRem. Incorrect because the limit is 5000 mRem for TEOE.
(2) Offsite integrated dose approaches 500 mRem COE (Thyroid). Examination Outline Cross-reference: Level RO SRO Tier# 1 Group# 1 K/A# 038 EA2.01 Importance Rating 4.1 4.7 K/A: Steam Generator Tube Rupture: Ability to determine or interpret the following as they apply to a SGTR: When to isolate one or more S/Gs Proposed Question: RO Question # 73 Technical Reference(s): OP-TM-EOP-005, Rev 9 OP-TM-EOP-0051, Rev 6 Proposed References to be provided to applicants during examination: None Learning Objective: EOP-005-PC0-4 Question Source: Bank# Modified Bank# New x TMI OPS ILT EXAM Page: 293 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL Question History: N/A Last NRC Exam: N/A Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 55.41 b.5 55.43 Comments: KA Match: This question matches the KA because the examinee must have knowledge of when to isolate an OTSG based on RCS pressure and BWST level. TMI OPS ILT EXAM Page: 294 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRG EXAM SUBMITTAL TMI OPS IL T EXAM Page: 295 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 74 ID: 1736795 Points: 1.00 Which ONE of the following describes the PREFERRED method of supplementing the passive mode of Post LOCA long term core circulation in the prevention of boron concentration effects 36 hours after the event? A. DH-P-1A suction is lined up to the RB Sump and then discharges to the Auxiliary Spray Line. B. DH-P-1 B suction is lined up to the RB Sump and then discharges to the Auxiliary Spray Line. C. DH-P-1A suction is lined up to the RB Sump AND takes partial suction from DH drop line and then discharges through RV CF Nozzles. D. DH-P-1 B suction is lined up to the RB Sump AND takes partial suction from DH drop line and then discharges through RV CF Nozzles. Answer: D
!Answer Explanation TMI OPS ILT EXAM Page: 296 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Explanation: To answer this question correctly, the examinee must know: (1) The preferred method is to drain concentrated reactor coolant through the decay heat drop line and into the suction header for DH-P-lB which is lined up to the Reactor Building Sump. If this method is initiated within 24 hours of a large break LOCA, it alone will prevent boron precipitation without passive mixing; (2) A second active method is to inject Reactor Building Sump water into the RCS through the pressurizer auxiliary spray line. Flow from this method in combination with a small portion of the flow from the passive method will prevent boron precipitation. About 5 days after a LOCA, the auxiliary spray line method alone will prevent boron precipitation. A. DH-P-1A suction is lined up INCORRECT: Plausible since this is a flowpath described in to the RB Sump and then the procedure, however it is not effective until 5 days after the discharges to the Auxiliary event. Spray Line. B. DH-P-1 B suction is lined up INCORRECT: Plausible since this is a flowpath described in the to the RB Sump and then procedure, however it is not effective until 5 days after the discharges to the Auxiliary event and in addition DH-P-1 B requires verification of DH Spray Line. Pump discharqe cross ties are open. C. DH-P-1A suction is lined up INCORRECT: Plausible if the examinee does not understand that the to the RB Sump AND takes procedure directs using DH-P-lB since the Drop Line is lined up to partial suction from DH drop DH-P-lB. line and then discharges throuqh RV CF Nozzles. D. DH-P-1 Bis lined to the RB CORRECT: See above Sump AND takes partial suction from DH drop line and then discharges through RV CF Nozzles. Examination Outline Cross-reference: Level RO SRO Tier# 3 Group# 4 KIA# 2.4.9 Importance Rating 3.8 4.2 KIA: Knowledge of low power/shutdown implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies. Proposed Question: RO Question# 74 Technical Reference(s): OP-TM-212-911, Rev 3 TQ-TM-104-212-C001, Rev 17 Proposed References to be provided to applicants during examination: None Learning Objective: 212-GL0-10 Question Source: Bank# Modified Bank# 356397 TMI OPS IL T EXAM Page: 297 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL New Question History: System Exam 9 Last NRC Exam: N/A Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 b.10 55.43 Comments: KA Match: This question matches the KA because the examinee must know the mitigation strategy for a LOCA to prevent boron precipitation. ich ONE of the following describes the preferred method of supplementing the passive mode of Post LOCA long term core circulation in the prevention of boron concentration effects 36 hours after the event? DH-P-1A/1B takes a suction from RB Sump; _ _ _ _ _ __ A. DH-P-1A/1 B discharges through RV CF Nozzles B. DH-P-1A takes a partial suction from DH drop line; DH-P-1A provides Auxiliary Spray Flow C. DH-P-1A/1 B provides MU pump suctions; MU Pumps inject water through RCS HPI Nozzles D. DH-P-1 B takes partial suction from DH drop line; DH-P-18 discharges through RV CF Nozzles Answer: D TMI OPS ILT EXAM Page: 298 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS ILT EXAM Page: 299 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 75 ID: 1736802 Points: 1.00 Plant Conditions:
- 100% power with ICS in full auto.
Which on of the following identifies the status of the Reactor Building Hydrogen Monitor Recorders? They are both _(1 )_and they are located on Control Room _(2)_. A. (1) ON (2) the H&V Panel. B. (1) ON (2) Panel Left. C. (1) OFF (2) the H&V Panel. D. (1) OFF (2) Panel Left. Answer: D
!Answer Explanation TMI OPS ILT EXAM Page: 300 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL
<<Explanation: To answer this question correctly, the examinee must know: (1) In accordance with 1105-18, CONTAINMENT HYDROGEN MONITOR, the H2 Monitors are normally maintained in the standby condition (isolated from containment but with the electronics kept warm), the control room chart recorder drive will remain off and will be turned on when the monitor is placed in service. (2)
During normal plant operations, the Hydrogen Monitor System will be warmed up and maintained in a Standby mode. (3) Containment Hydrogen Monitoring are placed into service when required per procedure. (4) Recorder are Located on Control room Panel Left A. (1) ON (2) H&V Panel INCORRECT: Plausible because the the Hydrogen Monitors are maintained in Standby and the examinee may think the Recorder are ON. H&V Panel has many Ventilation Controls and other monitors but not the H2 Monitor Controls. B. (1) ON (2) Panel Left. INCORRECT: Plausible because the the Hydrogen Monitors are maintained in Standby and the examinee may think the Recorder are ON. Correct Location C. (1) OFF (2) H&V Panel INCORRECT: Plausible since they are OFF but wrong location. D. (l)OFF(2)Pane1Left CORRECT: See above Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 2 K/A# 028 A4.03 Importance Rating 3.1 3.3 K/ A: Hydrogen Recombiner and Purge Control System: Ability to manually operate and/or monitor in the control room: Location and operation of hydrogen sampling and analysis of containment atmosphere, including alarms and indications. Proposed Question: RO Question# 75 Technical Reference(s): 1105-18, Rev 14 Proposed References to be provided to applicants during examination: None Learning Objective: 240-GL0-10 Question Source: Bank# Modified Bank# New x Question History: N/A Last NRC Exam: N/A TMI OPS ILT EXAM Page: 301 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 55.41 b.7 55.43 Comments: KA Match: This question matches the KA because the examinee must know the location of and operation of the Hydrogen Monitors and their indications. The Hydrogen Monitors are monitored in the Control Room by recorders, the examinee should know the status of the H2 Monitors including that their recorders are NOT on during normal operation. Operator action in the Control Room and in the plant is required to place the H2 Monitors in operation. TMI OPS ILT EXAM Page: 302 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL TMI OPS IL T EXAM Page: 303 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 76 ID: 1737249 Points: 1.00 Plant Conditions:
- Reactor has tripped on RCS low pressure.
- Pressurizer level is 370 inches and slowly increasing.
- RCS pressure is 1500 psig and slowly lowering.
- Core exit temperature is 556 degrees F and stable.
- Reactor Building sump level is 38 inches and increasing.
(1) What is the location of the RCS Leak? (2) Which of the following combinations of procedures provide the correct guidance to cooldown the plant? A. (1) Leak in the RCS Cold Leg (2) Enter OP-TM-EOP-002, LOSS OF 25F SUBCOOLING MARGIN, and use OP-TM-EOP-006, LOCA COOLDOWN to cooldown the plant. B. (1) Leak in the RCS Cold Leg (2) Enter OP-TM-AOP-050, REACTOR COOLANT LEAKAGE and use 1102-11, PLANT COOLDOWN to cooldown the plant. C. (1) Leak in the Pressurizer Steam Space (2) Enter OP-TM-AOP-043, LOSS OF PRESSURIZER, and use 1102-11, PLANT COOLDOWN to cooldown the plant. D. (1) Leak in the Pressurizer Steam Space (2) Enter OP-TM-AOP-050, REACTOR COOLANT LEAKAGE and use 1102-11, PLANT COOLDOWN to cooldown the plant. Answer: C
\Answer Explanation TMI OPS ILT EXAM Page: 304 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Explanation: To answer this question correctly, the examinee must know: (1) To answer this question correctly, the examinee must determine that a leak in the Pressurizer Steam Space exists; (2) In the stem, it is clear that RCS leakage exists, but to differentiate this Pressurizer Steam Space leak from an leak in the RCS cold leg the examinee will have to deduce that RCS pressure is LOW for the given Pressurizer level and RCS Temperature; (3) If this were a RCS cold leg leak, for a pressure this low, pressurizer level would be much lower as well; (4) For the parameters given, the correct procedure the crew must implement is EOP-001, then enter AOP-043 and 1102-11 to cooldown the plant. A. (1) Leak in the RCS cold leg INCORRECT: Plausible because the examinee could believe there is a (2) Enter OP-TM-EOP-002, leak other than an pressurizer steam space leak by RCS pressure LOSS OF 25F lowering and RB Sump level rising. In addition, the examinee will SUBCOOLING MARGIN, have to check if conditions exist for the operating crew to enter and use OP-TM-EOP-006, OP-TM-EOP-002 for a Loss of SCM (They do not). Within that LOCA COOLDOWN to procedure, if HPI were not adequate to maintain pressurizer level cooldown the plant. the crew would enter OP-TM-EOP-006 to cooldown the plant. B. (1) Leak in the RCS cold leg INCORRECT: Plausible because the examinee could believe there is a (2) Enter OP-TM-AOP-050, leak other than an pressurizer steam space leak by RCS pressure REACTOR COOLANT lowering and RB Sump level rising. In addition, if the examinee does LEAKAGE and use 1102-11, not recognize that the symptoms for a Loss of SCM exist, then PLANT COOLDOWN to AOP-050 could be entered. In AOP-050, 1102-11 is used to cooldown the plant. cooldown the plant.
- c. (1) Leak in the Pressurizer CORRECT ANSWER: OP-TM-AOP-043 must be entered, and then steam space. perform 1102-11 with guidance from an attachment in AOP-043.
(2) Enter OP-TM-AOP-043, LOSS OF PRESSURIZER, and use 1102-11, PLANT COOLDOWN to cooldown the plant. D. (1) Leak in the Pressurizer INCORRECT: Plausible because a leak in the Pressurizer Steam Space steam space. is correct. Incorrect because OP-TM-AOP-050 does not provide the (2) Enter OP-TM-AOP-050, additional guidance required to cooldown the plant with a leak in REACTOR COOLANT the pressurizer steam space. OP-TM-AOP-043 provides additional LEAKAGE and use 1102-11, guidance on the low SCM, and solid plant operations. PLANT COOLDOWN to cooldown the plant. Examination Outline Cross-reference: Level RO SRO Tier# 1 Group# KIA# 008 AA2.12 Importance Rating 3.4 3.7 KIA: Pressurizer Vapor Space Accident: Ability to determine and interpret the following as they apply to the Pressurizer Vapor Space Accident: PZR level indicators Proposed Question: Question #76 Technical Reference(s): OP-TM-AOP-043, Rev 6 TMI OPS IL T EXAM Page: 305 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL OP-TM-AOP-0431, Rev 5 Proposed References to be provided to applicants during examination: Steam Tables Learning Objective: AOP-043-PC0-4 Question Source: Bank # Modified Bank# 462810 New Question History: N/A Last NRC Exam: N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 55.43 b.5 Comments: KA Match: This question matches the KA because the examinee must use the Pressurizer Level Indicator to determine that there is a leak in the Pressurizer Steam Space, vice a leak elsewhere in the RCS. The pressurizer level is rising, while pressure is lowering which is indicative of a pressurizer steam space leak. High Cog: This question is high cog because the examinee must analyze the conditions in the stem to determine the location of the leak. SRO ONLY: This question is SRO only because the examinee must assess the plant conditions, and then select and determine the required course of action. TMI OPS IL T EXAM Page: 306 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Plant Conditions:
- Reactor has tripped on RCS low pressure.
- Pressurizer level is 240 inches and increasing.
- RCS pressure is constant at 1100 psig.
- Core exit temperature is 556 degrees F and stable.
- Reactor Building sump level is 38 inches and increasing.
From the list below, identify the ONE transient in progress. A. Leak in the RCS cold leg. B. Leak in the Pressurizer steam space. C. Rx vessel head vent valves failed open. D. Failure of the Pressurizer level control valve (MU-V-17) to close. Answer: B TMI OPS IL T EXAM Page: 307 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL ES-401 Attachment 2 figure 2: Screening for SRO-only linked to 10 CFR 55.4'.J.(b/(5) (Assessment and selection of procedures} Can the que.stton be ansv.<ered sole}y by kncwlng "systems knowtedge', i.e. how the system wc11\s. Yes RO question flowpath, logic, ccmponenl k:.caticn? Can !he qu;;stion be answered solely \Yy kno,,,rng immediate operator act10m;? Yes RO question Can the queston be anS'N!Hed solely by knowing ertr1 conaitons for .A.DPs or plant pammelers that RO qL1estion reqtdre direct entry to major EOPs? Can the queston be answered solely !Jy ~.newing the purpose. overall sequence of events or cvercill RO question mitigat.lve strategy of a procedure?
- Assessing plant conditions (normal abnorr1ai. er emer>;iencyJ and ther .selecting a procedure or .section c,f a prc*cedure to mttigate reco*.er, or with wrifch to proceec
- KnC'lvl-edge cf when to implement attachmeri:s and apcerii:l!ces, including row to coordinate mese ite<ms with procedure steps
- Knowledge of diagnostic steps and decision points in t'1e EOF's !hat involve tram;itions to e*.. ent specific sub-procedures or er1ergency contingency procedures
- Knowledge cf adr11in1strative procedures that .specify hierarchy 1rnpiementation. and/or coordrnatkin of plant normal. abnc1rr1.:il and emergency procedure.s Ne Qlestion might not be finked w 10 CFR 55.43(b}(5) for SRO-c1n:y TMI OPS ILT EXAM Page: 308 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS IL T EXAM Page: 309 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 77 ID: 1700250 Points: 1.00 Plant Conditions:
- 100% power with ICS in full auto.
EVENT:
- MAP C-3-2, IC SURGE TANK LEVEL HI/LO, alarm in.
- RM-L-9, Intermediate Closed Cooling Water Radiation Monitor, counts are rising.
- IC-T-1, Intermediate Closed Cooling Water Surge Tank, level is oft-scale high, and an attempt to bring IC-T-1 back on scale has failed.
- OP-TM-AOP-050, REACTOR COOLANT LEAKAGE is entered.
Current plant parameters:
- Pressurizer level is 220 inches and steady.
- MU Tank level is 86 inches and slowly lowering.
- Reactor Building pressure is 0.2 psig and steady.
Which ONE of the following procedures provides the required actions that mitigate these plant conditions? A. OP-TM-AOP-050, REACTOR COOLANT LEAKAGE B. OP-TM-MAP-C0302, IC SURGE TANK LEVEL HI/LO C. OP-TM-EOP-010, Guide 9, RCS INVENTORY CONTROL D. OP-TM-AOP-032, LOSS OF INTERMEDIATE COMPONENT COOLING Answer: B
!Answer Explanation TMI OPS IL T EXAM Page: 310 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL
<<Explanation: To answer this question correctly, the examinee must know: (1) With the indication of the IC-T-1 level high, RM-L-9 rising, the MU Tank level lowering with pressurizer level remaining steady, there is a small break leak between the RCS and ICCW system (either the RCP seals, or Letdown coolers);
(2) Because RM-L-9 is rising and IC-T-1 is already off-scale high, the actions to mitigate this event are to trip the reactor, trip all four reactor coolant pumps, close IC-V-2 and 3 and initiate OP-TM-AOP-050 "RCS Leakage", which is found in OP-TM-MAP-C0302. A. OP-TM-AOP-050, Plausible because the examinee should determine that and RCS leak REACTOR COOLANT is in progress. Actions to mitigate RCS leaks (including into ICCW) LEAKAGE are found in OP-TM-AOP-050, but this answer is incorrect because this procedure routes the examinee to OP-TM-MAP-C0302 IC Surge Tank Level Hi/Lo. In addition, in normal procedure hierarchy the mitigation steps of this nature would be found in an AOP or an EOP. B. OP-TM-MAP-C0302, IC Correct Answer - The actions to mitigate an RCS to ICCW leak, where SURGE TANK LEVEL HI/LO IC-T-1 cannot be maintained on scale is step 4.1.3 of this alarm response procedure. The examinee could arrive at this answer by directly entering the alarm response or OP-TM-AOP-050, step 3.5 which directs the examinee to OP-TM-MAP-C0302. Most primary mitigation steps are not found in alarm response procedures.
- c. OP-TM-EOP-010, Guide 9, Plausible because this procedure is directed to be initiated from RCS INVENTORY OP-TM-AOP-050, Reactor Coolant Leakage. This procedure provides CONTROL guidance for a low pressurizer level or makeup tank level. The examinee could believe that either of those sections (low pressurizer level or makeup tank level) of Guide 9 are applicable at this point, but there are currently no actions from Guide 9 that the examinee would take to mitigate this event. In addition, in normal procedure hierarchy the mitigation steps of this nature would be found in an AOP or an EOP.
D. OP-TM-AOP-032, LOSS OF Plausible because the examinee could believe that the mitigation INTERMEDIATE steps are in OP-TM-AOP-032. This procedure would direct an COMPONENT COOLING operating crew to trip the reactor, but will not direct the RCPs to be tripped unless seal injection flow is< 22 gpm. An operating crew may enter OP-TM-AOP-032 at a later point to place IC-P-lA and IC-P-lB in PTL, but these actions would be taken after the actions of OP-TM-MAP-C0302. In addition, in normal procedure hierarchy the mitigation steps of this nature would be found in an AOP or an EOP. Examination Outline Cross-reference: Level RO SRO Tier# Group# K/A# 009 2.4.31 Importance Rating 4.1 K/A: Small Break LOCA: Knowledge of annunciator alarms, indications, or response procedures. Proposed Question: Question #77 Technical Reference(s): OP-TM-MAP-C0302, Rev 3 OP-TM-EOP-010, Rev 19 TMI OPS ILT EXAM Page: 311 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL OP-TM-AOP-050, Rev 6 OP-TM-AOP-032, Rev 4 Proposed References to be provided to applicants during examination: None Learning Objective: AOP-050-PC0-1 Question Source: Bank # Modified Bank # New x Question History: NIA Last NRC Exam: N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 55.43 b.5 Comments: TMI OPS ILT EXAM Page: 312 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL K/A MATCH: This matches the K/A because the examinee must know that the alarm response in this question provides the mitigating steps for the RCS leak into the ICCW system. High Cog: This examinee must determine that a small RCS leak exists, and that the RCS is leaking into the ICCW stem. SRO Only: The question requires the examinee to assess plant conditions and to know the content of the listed procedures in order to select a required course of action. These procedures are not major EOPs. ES-401 8 Attachment 2 Figure 2: Screening for SRO-only fi11ke<l to 10 CFR 55.43(131\5) (Assessment and selection of proce<lures) Can I.he que::.t.on be cm~.w.<ered solely z;y !\newing "s~rste'lis k.nowtedge**. i.e., how the system works. Yes RO question flowoath, logic, componert '*ocation? Can the queston oe rJnc.wered solely :;y !mewing immediate op&rato* 2ct-orlJ? "{es RO question Can the q*,1est;on be ans.wered solely by lrnowirg entry conditDn& for AOPs or plant parameters ttml ,__r_*e_s_ _..... RO ouestio11 require d'irect entry to major EOPs? Can the que::.tion be tmswered solely by l\nowmg the purpose, overall sequence of events. or o**ern'I "{es RO question mitigat1ve strategy of a procedure? Ne
- c-es the qi.;estion re::iu:re one or more of the fol!owin:;;?
* .A,ssessing plan: coni:!itrons (norrn.:JI al}rormal cr emengencyi Gn:j then s,eiecting a procedure or section of a procedure f:) rn:tigate recover, or with whicn to procee::t
- Knovtled;;e cf when to lrnpieme11t attachmen:s and ap;:ierd:ces including how ro coordinate !hf'se items wi1h procedure steps Knowledge of diagnost:c steps and decis:on pohts ir !7°1' EOPs that invofve trnnsitio'ls re evert specific sub-procedures or ernergency contingency prcced"1res
- Knowiedge cf 3drnin strative proce<Jures !hat specify riernrchy. m1p1ementation and/or cocrdmation of plant rormaL abno;rial and emergency, procedures No r:westion might net be iin!i.ed to lG CFR 55.43(b}i5l for S"<.0-oni)*
TMI OPS ILT EXAM Page: 313 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL TMI OPS IL T EXAM Page: 314 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS ILT EXAM Page: 315 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 78 ID: 1685279 Points: 1.00 Plant conditions:
- Reactor is at 100% power
- DC-P-1A is tagged out for a bearing replacement.
- MU-P-1A and MU-P-1C are ES selected and operable.
- The Secondary NLO has just reported the fuel rack for the SBO Diesel was accidentally broken in the tripped position by a contract worker climbing over the lever.
- Maintenance says the repair will take 4 hours.
EVENT:
- One-half of the overhead lights go out, and do NOT come back on.
- You observe the following MAPs actuate:
- B-1-1, 4KV ES FDR BKR TRIP.
- B-2-1, 4KV ES BUS UV/OV.
- B-1-2, 4KV ES MOTOR TRIP.
- F-1-5, RCP SEAL TOT INJECT FLOW HI/LO.
Based on these conditions, which ONE of the following actions must be taken? A. Initiate Reactor shutdown within 1 hour. B. Swap MU-P-1A Cooling from DC to NS IAW OP-TM-543-439. C. Initiate OP-TM-864-901 SBO Diesel Generator (EG-Y-4) Operations. D. Ensure Emergency Diesel Generator EG-Y-1 B restored to operable status within 7 days. Answer: A
!Answer Explanation TMI OPS ILT EXAM Page: 316 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL
<<Explanation: To answer this question correctly, the examinee must know: ( 1) When one-half of the overhead lights go off, and with the MAP B alarms present with MAP F-1-5, that the lE 4160V bus has been lost; (2) With a loss of the lE 4160V bus, and DC-P-lA out of service that the plant is in TS 3.3.1.1.d; (3) The action statement when TS 3.3.1.l.d is met is to apply TS 3.0.1 to initiate a reactor shutdown within 1 hour.
A. Initiate Reactor shutdown Correct Answer within 1 hour. B. Swap MU-P-1A Cooling from Plausible because this is an action the crew would normally take if DC to NS IAW Seal Injection were lost and MU-P-lA needed to be started. In this OP-TM-543-439 case, Seal Injection is lost, but NSCCW is already lined up to MU-P-lA. This would have happened when DC-P-lA was tagged out for maintenance. C. Initiate OP-TM-864-901 SBO Plausible because use of the SBO Diesel is desired, but the SBO is not Diesel Generator (EG-Y-4) available per the question stem. Operations. D. Ensure Emergency Diesel Plausible because this Tech Spec (TS 3.7) would apply since EG-Y-lB Generator EG-Y-1 B restored did not start. Incorrect because TS 3.3.1.ld is met and the crew has to operable status within 7 to initiate a shutdown within 1 hour. days. Examination Outline Cross-reference: Level RO SRO Tier# 1 Group# KJA# 026 AA2.02 Importance Rating 3.6 KJA: Loss of Component Cooling Water: Ability to determine and interpret the following as they apply to the Loss of Component Cooling Water: The cause of possible CCW loss Proposed Question: Question #78 Technical Reference(s): T.S 3.3, AMO 289 T.S 3.7, Proposed References to be provided to applicants during examination: None Learning Objective: AOP-014-PC0-1 Question Source: Bank # 503953 Modified Bank # New TMI OPS ILT EXAM Page: 317 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Question History: N/A Last NRC Exam: N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 55.43 5 Comments: KIA Match: This matches the KIA because the examinee has to determine that both of the decay closed cooling water pumps are inoperable, hence Decay Closed Cooling is lost. High Cog: This is high cog because the examinee must analyze the power loss and come to the understanding that both decay closed cooling water pumps are lost, then realize the plant does not me the requirements of TS 3.4.1.1.b. The examinee must also know the action for no decay closed cooling water pumps is to initiate a reactor shutdown within 1 hour. SRO Only: This is an SRO only question because if involves the application of T.S. 3.0.1. The SRO must analyze the stem, and realize that DC-P-1 Bis not operable or performing it's ES function (due to EG-Y-1 B not powering the 1E 4160V bus) and apply T.S. 3.0.1. TMI OPS ILT EXAM Page: 318 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Figure 1: Screening for SRO-only linked to 10 CFR 55.4:J.(b)(2) (Tech Specs) Can q uestior be answere<i :~oleiy by koowing :s: 1 RO quest:on hour TSiTRM Acton? Can question be answ,ered solely by kr.owk1;; rie Ves R.0 questcn LCO!TRM infom1ation li1J:ed 'abo~e-the-li:ie? Can question be ars.*1erec soi'ely by krowi1g the TS Safety Unvts? RO question Does the question irvolve 01e or r1ore of me folJowing for T~*, TRM, or ODCM? Application o' Remrred Actbrs (Section 31 aml :::.ir.eiilance Requirements (2,ection 4) m a~cordanoe with rules of application re::;u rernems (Section 11 Appltcation of gene-ic LCO <equire'11ents (LCO 3.0, 1 thru 3 0,7 cmd SR 4,0, 1 thru 4 0-4 Yes r\nowle~ge of TS bases that ts required to anatyze TS 1-----'-'"" required actions tv1d tem'ifl-<:)lcgy Qm;stion oot l-:e Fr:~;ed to 10 CFR
- .~A3(b){21 for SRO-orly might TMI OPS ILT EXAM Page: 319 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS IL T EXAM Page: 320 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 79 ID: 1685296 Points: 1.00 Plant conditions:
- Reactor power is 35%
- Turbine load is 300 MWe.
- Main Feedwater Pump 1A (FW-P-1A) is tagged out of service.
- All other equipment lineups are normal.
Event:
- MAP Alarm M-1-7, FWP-1B TRIP, actuates.
- Reactor power and turbine load are stable.
- OTSG "A" and "B" levels are lowering.
Given the above information, which ONE of the following actions is required? A. Initiate a MANUAL reactor trip and enter OP-TM-EOP-001, REACTOR TRIP. B. Ensure MAP H-1-1, ICS RUN BACK, actuates and implement 1102-4, POWER OPERATIONS. C. Rapidly reduce main turbine load until reactor power is less than 7% and implement OP-TM-424-901, Emergency Feedwater. D. Initiate a MANUAL turbine trip and reduce reactor power to within turbine bypass valve capability in accordance with MAP K-1-1 TURBINE TRIP. Answer: A
!Answer Explanation TMI OPS IL T EXAM Page: 321 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL
<<Explanation: To answer this question correctly, the examinee must know: (1) When reactor power is above 7%, the Main Feedwater Pump trip (where at least on MFW pump must be running) is active, meaning if reactor power is above 7% and no MFW pumps are running, the reactor and turbine should trip; (2) The presence of M-1-7, with OTSG levels lowering, but reactor power and turbine loads stable is indicative that the reactor did not trip when FW-P-lB tripped (FW-P-lA was tagged out of service in the stem, and reactor power is 35%); (3) The action for that is to trip the reactor and enter OP-TM-EOP-001, REACTOR TRIP.
A. Initiate a MANUAL reactor Correct Answer trip and enter OP-TM-EOP-001, REACTOR TRIP. B. Ensure MAP H-1-1, ICS Plausible because at a higher power, when a MFW pump is lost an RUNBACK, actuates and runback would occur (if both MFW pumps were running). In implement 1102-4, POWER addition when both MFW pumps are lost, EFW actuates, which OPERATIONS. would provide a source of feedwater, although not one that is acceptable at 35% power to runback to less than 7% power.
- c. Rapidly reduce main turbine Plausible because at the point where the question ends, there is no load until reactor power is other indication that any RCS parameter (i.e. RCS pressure, or less than 7% and implement reactor power) is exceeding an RPS trip setpoint. The examinee OP-TM-424-901, could determine since the reactor power and turbine load are stable Emergency Feedwater. that performing a plant runback is an acceptable option.
D. Initiate a MANUAL turbine Plausible because a turbine trip at less than 45% power does not trip and reduce reactor warrant a reactor trip, but that is with the case where a MFW pump power to within turbine is running. At the point with where the question is, there are no bypass valve capability in MFW pumps running therefore the operators should trip the reactor accordance with MAP K-1-1 and turbine in accordance with OS-24 responsibilities. TURBINE TRIP. Examination Outline Cross-reference: Level RO SRO Tier# 1 Group# KIA# 054 AA2.01 Importance Rating 4.4 KIA: Loss of Main Feedwater: Ability to determine and interpret the following as they apply to the Loss of Main Feedwater (MFW): Occurance of reactor and/or turbine trip. Proposed Question: Question #79 Technical Reference(s): OP-TM-MAP-M0107, Rev 1 OP-TM-EOP-001 Proposed References to be provided to applicants during examination: None Learning Objective: 401-GL0-11 Question Source: Bank # 1044555 TMI OPS ILT EXAM Page: 322 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Modified Bank# New Question History: Systems Exam 14 Last NRC Exam: Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 55.43 5 Comments: (KA Match and why high cog) KIA Match: This is a match because the examinee has to interpret that at reactor trip should have occurred when the only operating MFW pump tripped. High Cog: This question is high cog because the examinee has to analyze the event to understand that a MFW pump did trip, but the reactor did not trip. The examinee has to determine the correct course of action for the operating crew to take. SRO ONLY: This question is SRO only because it requires the SRO examinee to determine that an ATWS has occurred. The SRO examinee must choose between the various procedures which will shutdown the plant. TMI OPS IL T EXAM Page: 323 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL ES-401 Attachment 2 Figurce 2: Scr<'<'ning for SRO-only linkcei:I to 10 CFR 55.4.3(b)(5) (Assess.men! and se<lec!fon of procedures) Can ~r:e 1::;;..;eston ~ answe'.e':i sofe.!y by krc*uing
'syste-ms knowi<:dge'*, i.<:., how *.re syst~ works.
RO question f\O'.vpa'.i"\, bg'c. o:impc*rent loc.a:1or'.' C3n '.he q*.;i:stcn, te ;mswered cole/y by kro'hmg
;m mE<d ,a~e ope-rater a~::iDr s-;- '{es RO qu~sticn Can :he Q*Jeston h*e answ!!**ed ;;al.?Jy by knoMng
-i!1--try cord1tions for AO ::>s *:Y pi ant parameters that f-*-{.,,_-"---'-+! RO cuestk~n recp.Jtrec d;re-ct entry tci m-ajor EO=-s?
Can the q:JestHJ""l be answ,erf:d s-o~Jy ty finov,1ng the P>>Jrpo:.-e, over a;! sequence a~ ev~nts, er cve-raH Yes RO ou-.sticn mitiq.:itive s.trateQ'i of a procedure? Assessir1g p;._,nt oor.ditcns rnDrmai. abncrmal. N emergency) and ther sele*::.~*r.g 3 .::>rocedure or seoticn of a prcHJe--::LJre to rr.itiga-t-:, re-ccve-r, er-with wh1ch ~.C) _p:o-c-ee-d
~:now!edge c~ when to implement attach.Te:,ts and apprdic-es, ;ndudmg hew t-c cocrdira~e t'ie.se te~s ft\*i:h procej*.Jre s~eps Y-:s SRO-~,'""lY 1'-<now'.e--dge 0 1 cFagr~ostic steps and dEos;c,n p'">~ir'i:S ;r, the question
=:oF s that ir\>'O,V>? trar;si~iors:, to e-vent sp>i:;i'f),c s:,,..;b-pro-ce<h...>res or erne ~g ency 1::-ont;ngercy pr.aced ure-s t':ru,:;'ttfedge o' '3 drr ~r 'stratlve P'"*~cedt.. re-s th.31 syed:..y hier3rchy. irrp~-err-2-;;tat~J:"'I, ann,0:- 0-:i;on:Fr.at~n cf pl~rt normaf, ~bnom-~a~. ard -:-merger-:y pr.oo:::edufes Ques:icin r:-igr-1~ r.ct. t~ link<!'d to 1D CF~ 55-43t,b.!(E.! fO" S~O*oriy ES-4C 1. "age 22 of 5D TMI OPS IL T EXAM Page: 324 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS ILT EXAM Page: 325 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 80 ID: 1685310 Points: 1.00 Plant Conditions:
- RCS Heat up in progress.
- RCS Temperature is 290°F and rising.
- DC Distribution Panel 1M transfer switch is selected to "A" DC Distribution System and the switch on PCR is in "Auto".
- Makeup Pump 1B is supplying seal injection.
Event:
- The following alarms have actuated simultaneously:
- AA-3-2 7 KV Bus Trouble.
- AA-3-3 4 KV BOP Bus Trouble.
- AA-3-5 480V BOP Bus Trouble.
- A-1-7 Battery 1A Discharging.
- A-2-7 Battery Charger 1A/1 C/1 E Trouble.
- A-3-7 Inverter 1A/1C/1E Trouble.
- B-3-1 4KV ES Bus Trouble.
- PRF1-1-1 CROM Brkr Test Trouble.
- H&V A 4-2 Contr Bldg Bat Chgrs A Damper Tbl Fire-Smoke.
- Loss of numerous breaker status lights at control switches.
Based on these conditions, identify the ONE selection below that describes the: (1) Applicable procedure to respond to these conditions, and (2) Impact on the ability to operate safety related equipment. A. (1) OP-TM-AOP-023, "A" DC System Failure. (2) Makeup Pump 1B breaker must be racked out due to LTOP concerns. B. (1) OP-TM-AOP-023, "A" DC System Failure. (2) Pressurizer Level must be verified s 100 inches because the PORV setpoint is greater than 592 psig. C. (1) OP-TM-AOP-024, "B" DC System Failure. (2) Makeup Pump 1B breaker must be racked out due to LTOP concerns. D. (1) OP-TM-AOP-024, "B" DC System Failure. (2) Pressurizer Level must be verified s 100 inches because the PORV setpoint is greater than 592 psig. Answer: B
!Answer Explanation TMI OPS ILT EXAM Page: 326 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL
<<Explanation: To answer this question correctly, the examinee must know: (1) Indications from the event are representative to a Loss of 'A' DC; (2) that the PORV, RC-RV-2 is not operable when there is no
'A' DC; (3) Because there the plant is below 313F, then the requirements of Tech Spec 3.1.12 must met; (4) At the point before the loss of 'A' DC, and in accordance with 3.1.12.1, since there is an HPI breaker racked in (MU-P-lB), then MU-V-16A-D must be closed with breakers open, and MU-V-217 must be closed. In addition pressurizer level must be less than 100 inches; (5) When the PORV becomes inoperable after the loss of 'A' DC then the operating crew has 2 options to do within 8 hours: restore the setpoint below the maximum value (i.e. restore 'A' DC); or verify pressurizer level is 5.100 inches and satisfy the requirements of T.S 3.1.12.3. (6) Having MU-V-16A-D closed with their breakers open and MU-V-217 satisfies this requirement, and is already complete because MU-P-lB breaker is racked in supplying seal injection, hence no further action is required other than ensure pressurizer level is 5. 100 inches.
A. ((1) OP-TM-AOP-023, "A" Plausible because 'A' DC was lost, and racking out the makeup pump DC System Failure. would be an option. Incorrect because the makeup pump does NOT (2) Makeup Pump 1 B have to be racked out. Since MU-V-16A-D are already closed with breaker must be racked breakers racked out, and MU-V-217 is closed because the HPI out due to L TOP breaker is racked in, the only action the crew would have to take is concerns. to ensure pressurizer level is 5. 100 inches. B. ( 1) OP-TM-AOP-023, "A" DC Correct Answer. System Failure. (2) Pressuizer Level must be verified ~ 100 inches because the PORV setpoint is greater than 592 psig. C. (1) OP-TM-AOP-024, "B" DC Plausible because the examinee could believe that 'B' DC was lost. In System Failure. addition the reactor coolant system, reactor vessel, and pressurizer (2) Makeup Pump 1 B vents fail closed. The examinee could believe that these are LTOP breaker must be racked out valves because they could be opened to lower pressure. In addition, due to LTOP concerns. they could believe that racking the HPI breaker out is a compensatory action for T.S. 3.1.13 requiring a vent path from a Reactor Coolant System High Point vent (RC-40B and 41B are failed closed). This is not entered because RC-V-40A and 41A are still operable. D. (1) OP-TM-AOP-024, "B" DC Plausible because the examinee could believe that 'B' DC was lost. System Failure. Also, due to loss of some RCS, RV, and Pressurizer Vents, the (2) Pressuizer Level must be examinee could believe that pressurizer level must be maintain less verified~ 100 inches than 100 inches. because the PORV setpoint is greater than 592 psig. Examination Outline Cross-reference: Level RO SRO Tier# 1 Group# K/A# 058 AA2.03 Importance Rating 5 TM\ OPS ILT EXAM Page: 327 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL KJA: Loss of DC Power: Ability to determine and interpret the following as they apply to the Loss of DC Power: DC loads lost; impact on ability to operate and monitor plant systems. Proposed Question: Question #80 Technical Reference(s): OP-TM-AOP-023, Rev 7 T.S. 3.1.12.3, AMO 281 Proposed References to be provided to applicants during examination: None Learning Objective: AOP-023-PC0-1 Question Source: Bank # Modified Bank # New x Question History: NIA Last NRC Exam: N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 55.43 b5 Comments: KJA Match: This question matches the KJA because the examinee must recognize that 'A' DC is lost, then choose the correct safety related equipment that is effected by the loss. High Cog: This is high cog question because the student must analyze the alarms in the stem, then choose correct procedure and effected safety related equipment. SRO Only: This question is SRO only because in the second part of this question the SRO examinee must determine the PORV operability based on the loss of DC power. The PORV is inoperable on a total loss of 'A' DC, but not necessarily inoperable on a partial loss of 'A' DC. The SRO examinee will have to determine applicable portion of OP-TM-AOP-023, and then determine since it is a complete loss of 'A' DC that the PORV is inoperable based on the fact that RCS temperature is <313°F and the maximum lift setpoint is greater than 592 psig. TMI OPS ILT EXAM Page: 328 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL ES-401 B Attachment 2 Fi9me 2: ScrE1"ning for SRO-only linkerl to 10 CFR 55.43(b~(5) (Assessment and seledion of procedures) Can ~he c;;_~e-st;:ir. t~ a:is"fl<-er~d so{e!y by krc*Mng "sfst<?ms know'.i?dgi?*, l.i?., how :Pi? SfSti?m 'MJrks, RO QJ<?stk'1 flc~,.v~a~r\ ki~ic, o:impcinent bc.J:t-on? C3n ~;'.e qweston b-e ,;nsw~,~ed ::;cd~;y by krovmig
- m rnE<c -,xe ope-rater ac~; ors? RO questio1 Can ~'."'H: G'..Je-stcn CvE answ-~:*Bd :::or'eif by ~d10\umg J?-.try corditions for AO"'s O' p;ar.t para'nete-s thal RO cues.ticn re>:p.L~e :frect er-try tD major EO-°s?
Can ~he: que.ston b-e answered :;ofeJ/ ty ~,nn'N'ng the D\Jn:*oE.-e, ever.an se-q uen"~ cf e.v-e0ts, or c*"o?-raH rnitlqative strateq'/ of a procedure? Assessi:"',g p: .3<'"':t c~:ir-~cLtc-ns r,r1orma L abnom3L C'f
-=-m~n;e-n~:*y) and ther s~iec::ng a prcici::ktre er se--c:.tioi of :A proce.-.:L-::re to n-,itigate. recov-er, er with v,~rFch :o p;"'OC'!?ed KmJwie<lge- o~ wrie-n tc ;rn;:it.;ment attad1rr ,ents ,:, nd 21pp.:-r:fcs. if'*Ck.'dT'!;} ;"'.CVI to coordma:.e the-.se- rte:rs. \-lri:t
- xoceji...ir~ s:eos SRO-cnly Y<rK~*1tt~~:lge .of ri<.3:;;J;""!C>s.tb st-:ps and d~c.~sicn poin"..s hi the qu.;;stior
=:OFs that \nvab.;e tr.ansi:lor.:. to e- tent sp-.eci*k1 s::.:b-i:-ro'2.-e-.d*....>res i:H* e-rne rg e-nci ~:.ontingen,cy proced ~.v.es:
~~r-J'ltiedge- o~ adn"T~<strative procedures that spec~i')i' hierarchy, iTpten"'e:<<t3t<:~~- andtor roor-dlnatkin of p!art
~--0rm3L iabnc1m*,a1, ard <?nien.;er-::y pro-:e-dures ES-4C 1 "ag.;; 22 of W TMI OPS IL T EXAM Page: 329 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS IL T EXAM Page: 330 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 81 ID: 1720494 Points: 1.00 Plant conditions:
- A loss of vacuum of causes both Main Feedwater pumps to trip.
- Due to equipment failures EF-P-2A, Motor Driven Emergency Feedwater Pump, is the only operating pump to supply FW to the OTSGs.
- RCS is at HSD conditions:
- RCS T-Hot is 532 degrees F and rising.
- RCS pressure is 2150 psig and rising.
- OTSG pressures are 885 psig and steady.
- OTSG levels are 25" and steady.
- FW-P-1A vacuum is being restored.
EVENT:
- EF-P-2A trip.
- lncore temperatures are rising.
Based on these conditions identify the ONE selection below that describes: (1) Method of core cooling to be established. (2) Applicable procedure. A. (1) Rapid cooldown to LPI injection. (2) OP-TM-EOP-002, LOSS OF 25 DEGREES F SUBCOOLING MARGIN. B. (1) Condensate booster pump feed. (2) OP-TM-EOP-004, LACK OF PRIMARY TO SECONDARY HEAT TRANSFER. C. (1) Rapid cooldown to LPI injection. (2) OP-TM-EOP-004, LACK OF PRIMARY TO SECONDARY HEAT TRANSFER. D. (1) Condensate booster pump feed. (2) OP-TM-EOP-002, LOSS OF 25 DEGREES F SUBCOOLING MARGIN. Answer: B
!Answer Explanation TMI OPS ILT EXAM Page: 331 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL
<<Explanation: To answer this question correctly, the examinee must know: (1) One of the entry criteria for OP-TM-EOP-004, LACK OF PRIMARY TO SECONDARY HEAT TRANSFER, is met (incore temperatures rising and NO FEEDWATER available); (2) Once the EOP is entered, the examinee must know the criteria for each know the routing step that applies to go begin cooling the Reactor, for this question, the examinee must realize that a condensate pump is on, a reactor coolant pump is on, therefore Attachment 1 of OP-TM-EOP-004 is the method of cooling which should be used next.
A. (1) Rapid cooldown to LPI Incorrect - Plausible because OP-TM-EOP-004 mitigation strategy injection. involves lowering OTSG pressure to strengthen the heat sink to (2) OP-TM-EOP-002, LOSS establish heat transfer out of the OTSG's. In addition, if the OF 25 DEGREES F examinee believes that if SCM is less than 25F, that OP-TM-EOP-002 SUBCOOLING MARGIN. is entered then it may be possible to perform a cooldown to LPI. B. (1) Condensate booster Correct Answer - The stem only indicates that both Main Feedwater pump feed. Pumps are tripped. All equipment is available to support Condensate (2) OP-TM-EOP-004, Lack Booster Pump feed. of Primary to Secondary Heat Transfer.
- c. (1) Rapid cooldown to LPI Incorrect- Plausible because in OP-TM-EOP-004, a cooldown is injection. performed after Feedwater becomes available. Incorrect because (2) OP-TM-EOP-004, LACK the cooldown is not a rapid cooldown to LPI.
OF PRIMARY TO SECONDARY HEAT TRANSFER.
- o. (1) Condensate booster Incorrect- Plausible because the operators must feed in accordance pump feed. with Rule 4, which includes raising OTSG levels to 75% to 85% in the (2) OP-TM-EOP-002, LOSS operating range. Incorrect because condensate booster pump OF 25 DEGREES F cooling is not an option in that guide.
SUBCOOLING MARGIN. Examination Outline Cross-reference: Level RO SRO Tier# 1 Group# KIA# E04 2.2.44 Importance Rating 4.4 KIA: Inadequate Heat Transfer: 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. Proposed Question: Question #81 Technical Reference(s): OP-TM-EOP-004, Rev 11 OS-24, Rev 28 Proposed References to be provided to applicants during examination: None Learning Objective: EOP004-PC0-4 TMI OPS ILT EXAM Page: 332 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Question Source: Bank# 363689 Modified Bank # New Question History: Comp 2 Last NRC Exam: Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 55.43 b.5 Comments: KA Match: This question matches the KA because the examinee must interpret stem indications to determine the correct path for establishing feedwater to the OTSGs. The operator actions will establish core cooling. High Cog: This question is High Cog because the examinee will have analyze the stem conditions to determine there is no feedwater available to the OTSGs. SRO ONLY: This question is SRO under b.5 because in addition to recognizing the entry conditions into OP-TM-EOP-004 the examinee must assess plant conditions then select the NEXT procedure which will provide feedwater and core cooling. TMI OPS IL T EXAM Page: 333 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL figure 2; Screening for SRO-only llnked to 10 CFR 55.43{b)(5j {Assessment and selection of procedures) Can the question be ::inswe:ed sorely- bi ilno11.ing
*systems !rnowledge", Le,, how lhe s;pstem 'h'Dr'~s, Ves ROquestio11 flowpath, logic. component locaton?
Ca11 the question be ::ins\Oiered .:wi'ely by knowing irnrnedmte operator actions? \'es RO ::i;estfon Can the quest~:m be answered solely by knowing erlry conditions for AOPs or pl.:mt parameters that 1--'y_'e5_~_'-'-to>! require direc: entry to major EOPs? Can the question be @nswe'ed solely by ilno'hing the pur;iose. overall sequerce of events, or ovemfl RO quest~on mitio Assessing pl.:mt conditions (nocmciL abrom13I, or emergency! and then selecting a procedure or section of a procedure to mitigme, recover, or with which to proceed
- Knowledge of wtien to imple111e11t attachments and appendices. mcludmg how to oo<Jn:linate the.se rtems with procedure steps SR0-0nry Knowledge of diagnostic steps and decision points in the question EOPs that irr.-ol'v'e transitonc; to event specific sub-pmcedures or emergency contingency procedures Knov.iedge cf administrative pro*:ecures that specify hierarchy, in"plementation and.'or coordinaoon of pl<:r1:
nom1al, at*norrnaL and emergency procedures Question r-ii9ht n*ot be linked to 10 CfR 55.43::bl{5l for SRO-only ES-401, Page 22 of 50 TMI OPS ILT EXAM Page: 334 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS ILT EXAM Page: 335 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 82 ID: 1737141 Points: 1.00 Plant Conditions:
- 100% power with ICS in full auto.
EVENT:
- LOCA requiring a plant trip.
- Pressurizer Level cannot be maintained without HPI.
- OP-TM-EOP-006 LOCA COOLDOWN is in progress.
(1) Which Reactor Coolant Pumps must get secured? (2) What is the OP-TM-EOP-006 basis for securing them? A. (1) RC-P-1A and RC-P-18 (2) Minimize the RCS inventory loss due to the LOCA. B. (1)RC-P-1AandRC-P-1B (2) The subsequent cooldown could result in "core lift". C. (1) RC-P-1 C and RC-P-10 (2) Minimize the RCS inventory loss due to the LOCA. D. (1) RC-P-1C and RC-P-10 (2) The subsequent cooldown could result in "core lift". Answer: D
~nswer Explanation TMI OPS ILT EXAM Page: 336 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL
<<Explanation: To answer this question correctly, the examinee must know: (1) In OP-TM-EOP-006, if all four Reactor Coolant Pumps are running, two of them get secured; (2) The basis for this to ensure no more than three Reactor Coolant Pumps are running when Tcold drops below 407F; (3) With four Reactor Coolant Pumps the differential pressure may result in core lift; (4) OP-TM-EOP-006 directs RC-P-lC and RC-P-lD to be shutdown.
A. (1) RC-P-1A and RC-P-1 B INCORRECT: Plausible but incorrect because the step indicates if (2) Minimize the RCS RC-P-lA and RC-P-lB are running, THEN shutdown RC-P-lC and inventory lost due to the RC-P-lD. In addition the basis is to prevent core lift. LOCA.(1) RC-P-1A and RC-P-1B (2) Minimize the RCS inventory lost due to the LOCA. B. (1) RC-P-1Aand RC-P-18 INCORRECT: Plausible but incorrect because the step indicates if (2) Lower the RCS flow and RC-P-lA and RC-P-lB are running, THEN shutdown RC-P-lC and differential pressure across RC-P-lD. the fuel bundles. C. (1) RC-P-1C and RC-P-10 INCORRECT: Plausible because this action could lower the rate of (2) Minimize the RCS RCS inventory loss on some LOCA. Incorrect because the Reactor inventory lost due to the Coolant Pumps are secured due to core lift concerns. LOCA. D. (1) RC-P-1 C and RC-P-1 D Correct Answer: See above. (2) The subsequent cooldown could result in "core lift". Examination Outline Cross-reference: Level RO SRO Tier# 1 Group# 2 KIA# BW/E08 2.4.18 Importance Rating 4.0 KIA: LOCA Cooldown: Knowledge of the specific bases for EOPs. Proposed Question: Question #82 Technical Reference(s): OP-TM-EOP-006, Rev 12 OP-TM-EOP-0061, Rev 7 Proposed References to be provided to applicants during examination: None Learning Objective: EOP006-PC0-4 Question Source: Bank # Modified Bank # New x TMI OPS ILT EXAM Page: 337 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Question History: NIA Last NRC Exam: N/A Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 b.5 Comments: KIA Match: This question matches the KIA because the examinee must know the reason for securing two Reactor Coolant Pumps on a LOCA Cooldown. SRO ONLY: The question is SRO only because the examinee must assess plant conditions and know the content of OP-TM-EOP-006 in order to select a required course of action. In addition, the examinee must know the basis for the action selected. This procedure is not one of the major EOPs, it is a supplementary EOP directed from within the major EOP. TMI OPS IL T EXAM Page: 338 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 83 ID: 1737631 Points: 1.00 The specific activity of the primary and secondary coolant are as follows: Two days ago at 1200 Yesterday at 1200 Today at 1200 RCS Dose Equivalent 0.50 microcuries/gram 0.53 microcuries/gram 0.52 microcuries/gram 1-131 OTSG Dose Equivalent 0.05 microcuries/gram 0.053 microcuries/gram 0.052 microcuries/gram 1-131 The __ (1 )_ _ is out of specification, and the basis of the specification is to maintain dose within the limits from __ (2) _ _ . A (1) RCS (2) a tube rupture accident B. (1) OTSG (2) a steam line break accident C. (1) RCS (2) baseline OTSG tube leakage D. (1) OTSG (2) normal condenser offgas Answer: A [Answer Explanation TMI OPS IL T EXAM Page: 339 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS IL T EXAM Page: 340 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRG EXAM SUBMITIAL
<<Explanation: To answer this question correctly, the examinee must know: (1) The limit for 1-131 in the RCS is 0.35 microcuries/gram; (2) The limit for 1-131 in the secondary fluid is .10 microcuries/gram, which is not exceeded in this question; (3) The basis for the RCS limit is that if activity levels are kept below this level then analysis shows that the calculated doses are within acceptable limits on a Steam Line Break (SLB) and Steam Generator Tube Rupture (SGTR) accident (T.S. 3.1.4.1 basis)
A. (1) RCS CORRECT ANSWER: See above. (2) dose from a tube rupture accident B. (1) OTSG INCORRECT: Plausible if the examinee is not familiar with the (2) dose from a steam line secondary chemistry limits. In addition, the examinee could believe break accident the secondary is the concern due to having one less barrier than the RCS to atmosphere.
- c. (1) RCS INCORRECT: Plausible because the RCS is violating the tech spec (2) dose from baseline chemistry limits. Incorrect because the basis is not dose from a OTSG tube leakage baseline OTSG tube leak. That is the basis for violating the secondary chemistry limits.
D. (1) OTSG INCORRECT: Plausible if the examinee is not familiar with the (2) dose from normal secondary chemistry limits. In addition, dose from the normal condenseroffgas condenser offgas could be a concern. Incorrect because the secondary chemistry is within limits. Examination Outline Cross-reference: Level RO SRO Tier# 1 Group# 2 KJA# 076 2.2.38 Importance Rating 3.6 4.5 KJA: High Reactor Coolant Activity: Knowledge of conditions and limitations in the facility license. Proposed Question: Question #83 Technical Reference(s): T.S. 3.1.4 T.S. 3.1.13 Proposed References to be provided to applicants during examination: None Learning Objective: 220-GL0-14 Question Source: Bank# 718419 Modified Bank # New Question History: System Exam 12 Last NRG Exam: 08-01 TMI OPS IL T EXAM Page: 341 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 b.2 Comments: KA Match: This question matches the KA because the examinee must know the basis for the primary chemistry limits. SRO ONLY: This question is SRO only because the examinee must identify the out of specification chemistry reading, and understand the basis behind the limit. Correct answer. TS 3.1.4 states "With the specific activity of the primary coolant greater than 0.35 microcurie/gram DOSE I EQUIVALENT 1-131 for more than 48 hours*' during one continuous time interval or exceeding the limit line shown on Figure 3.1-24 be in at least HOT SHUTDOWN within 6 hours. Power operation may continue when DOSE EQUIVALENT 1-131 is below 0.35 microcurie/gram." Basis "The limitations on the specific activity of the primary coolant ensure that the resulting 2 hour doses at the site boundary will be well within the Part 100 limit following a steam generator ube rupture accident or steam line break accident with postulated accident induced steam generator tube leakage in conjunction with an assumed steady state primary-to-secondary steam generator leakage rate of 1.0 GPM." Plausible since this is the specific activity limit for the Secondary Coolant and it is based on a $team line rupture with tube leakage; however the specific activity limit is 0.35 microcurie/gram for the Primary Coolant and the primary-to-secondary steam generator leakage rate of 1.0 GPM is assumed. Plausible since the limit and basis is correct; however it is correct for the Primary Coolant. 3.13 SECONDARY COOLANT SYSTEM ACTIVITY 3.13.1 The specific activity of the secondary coolant system shall be ::; 0.10 - Ci/gram DOSE EQUIVALENT 1-131. 3.13.2 With the specific activity of the secondary coolant system > 0.10-Ci/gram DOSE EQUIVALENT 1-131, be in at least HOT STANDBY within 6 hours and in COLD SHUTDOWN within the following 30 hours. Bases TMI OPS IL T EXAM Page: 342 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL rrhe limitations on secondary system specific activity ensure that the resultant off-site radiation k:lose will be limited to a small fraction of 10 CFR Part 100 limits in the event of a steam line rupture. This dose includes the effects of a coincident 1.0 GPM primary-to-secondary tube leak in ~he steam generator of the affected steam line. Plausible since the limit is correct for the Secondary Coolant; however the basis is for a coincident 1.0 GPM primary-to-secondary tube leak. TMI OPS IL T EXAM Page: 343 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL 84 ID: 1699987 Points: 1.00 The following plant conditions exist:
- A small break LOCA is in progress.
- The Reactor tripped, and ESAS actuated on low RCS pressure.
- A loss of off-site power (LOOP) occurred.
- Sub cooling margin was lost and is currently-1°F on the PT plot.
- lncore temperatures are rising slowly.
- RCITS shows a large steam void in each RCS hot leg.
- Current cooldown rate is 45°F I hr.
Which ONE of the following describes the correct actions the crew must take to ensure adequate core cooling? A. OTSG level must be maintained above 50%, with OTSG saturation temperature from 40°F to 60°F below RCS cold leg temperature to promote boiler-condenser cooling. No additional action is required due to the steam void. B. OTSG level must be maintained above 50%, with OTSG saturation temperature from 40°F to 60°F below RCS cold leg temperature to allow single-phase natural circulation. The steam void must be vented from the hot leg. C. OTSG level must be maintained 75% - 85%, with OTSG pressure at least 100 psig below RCS pressure to promote boiler-condenser cooling. No additional action is required due to the steam void. D. OTSG level must be maintained 75% - 85%, with OTSG pressure at least 100 psig below RCS pressure to allow single-phase natural circulation. The steam void must be vented from the hot leg. Answer: C
!Answer Explanation TMI OPS IL T EXAM Page: 344 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Explanation: To answer this question correctly, the examinee must know: (1) The controlling procedure is OP-TM-EOP-002, LOSS OF 25F SUBCOOLING MARGIN; (2) In addition to implementing actions OP-TM-EOP-002, the operating crew will be performing OP-TM-EOP-010, EMERGENCY PROCEDURE RULES, GUIDES, AND GRAPHS, in which the entry criteria for Rule 4, FEEDWATER CONTROL, and Guide 6, OTSG PRESSURE CONTROL have ben met, which provide governance on how to promote heat transfer in loss of 25F subcooling event; (3) In addition steps are taken to remove non-condensible gasses from the RCS (if there were symptoms of them beinq present), NOT steam. A. OTSG level must be INCORRECT ANSWER: Plausible because maintaining greater than maintained above 50%, with 50% in the operating range is the level band if reactor coolant OTSG saturation pumps are secured. Maintaining OTSG saturation temperature in temperature from 40°F to the 40-60F band below RCS cold leg temperature is the band if the 60°F below RCS cold leg cooldown rate would be less than 40 F/hr. OP-TM-EOP-004 also temperature to promote addresses how to address a steam void of non-condensable gasses in boil~~-conde~ser.coolin~. No the RCS. In this case, this would not be necessary due to the add1t1onal action 1s required cooldown rate of> 4oF/hr being present. due to the steam void. B. OTSG level must be INCORRECT ANSWER: Plausible because maintaining greater than maintained above 50%, with 50% in the operating range is the level band if reactor coolant OTSG saturation pumps are secured. Maintaining OTSG saturation temperature in temperature from 40°F to the 40-60F band below RCS cold leg temperature is the band if the 60°F below RCS cold leg cooldown rate would be less than 40 F/hr. OP-TM-EOP-004 also temperature to allow addresses how to address a steam void of non-condensable gasses in single-phase natural the RCS. In this case, this would not be necessary due to the circulation. The steam void cooldown rate of> 40F/hr being present. must be vented from the hot leg.
- c. OTSG level must be CORRECT ANSWER. Both actions are required by OP-TM-EOP-010 maintained 75% - 85%, with (Rule 4 and Guide 6). Steps to vent are in OP-TM-EOP-004, which OTSG pressure at least 100 was not entered in this question. In addition, venting is only psig below RCS pressure to performed if it is believed non-condensable gasses are present in the promote boiler-condenser RCS, not steam.
cooling. No additional action is required due to the steam void. D. OTSG level must be INCORRECT ANSWER: Plausible because both actions are required maintained 75% - 85%, with by OP-TM-EOP-010 (Rule 4 and Guide 6). Steps to vent are in OTSG pressure at least 100 OP-TM-EOP-004, which was not entered in this question. In psig below RCS pressure to addition, venting is only performed if it is believed non-condensable allow single-phase natural gasses are present in the RCS, not steam. circulation. The steam void must be vented from the hot leq. Examination Outline Cross-reference: Level RO SRO Tier# 1 Group# 2 KJA# E03 EA2.1 Importance Rating 4.0 TMI OPS ILT EXAM Page: 345 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL KIA: Inadequate Subcooling Margin: Ability to determine and interpret the following as the apply to the (Inadequate Subcooling Margin): Facility conditions and selection of appropriate procedures during abnormal and emergency operations. Proposed Question: Question #84 Technical Reference(s): OP-TM-EOP-002 OP-TM-EOP-010, Rev 19 Proposed References to be provided to applicants during examination: None Learning Objective: N-TM-TQ-104-EOP-DBIG-APCO -1 Question Source: Bank # 862875 Modified Bank # New Question History: Comp 1 Exam Last NRC Exam: Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 55.43 b.5 Comments: TMI OPS IL T EXAM Page: 346 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL KIA Match: This matches the KIA because the examinee will have to know which procedures to use to promote cooling in the RCS. Although not explicitly stated, by asking steps in Rule 4 and Guide 6, the examinee will have selected which procedure is appropriate. In addition, to rule out the two of the distractors, the examinee will NOT have selected to choose another plausible EOP network path into OP-TM-EOP-004. High Cog: This question is high cog because the examinee must analyze the given set of parameters and choose the correct procedure and steps in which to execute. SRO Only: This question is an SRO only question because it the examinee must assess plant conditions and then select procedure steps to mitigate the casualty. This question tests coordination between how the operating crew will feed and steam the OTSGs. TMI OPS ILT EXAM Page: 347 of425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL ES-401 Attachment 2 Figure 2: Screening for SRO-onlv linked to 10 CFR 55.43(bi(5} (Assessment and selection of procedures) Can the questmn oe ane:;wered solely GY know'.ng "systems knowledge", i.e.. how the system works. Yes f!owpath. logic. component iocatior*? Can the q*Jesti-On b-e ans;;1;1ered sotei'y :iy l\ricw:rg
;mmediate operator actfors? RO question Can the quest;on be answered solely by knc*,y'ng entry condtilons for .AOPs or pl art parameters that Yes RO cuestion require direct entry to major EOPs?
Can the question be ans'Aoered so!el;tby know'ng the purpose. overalf sequence of events or oyerail Yes RO ouestion mitigative strategy of a procedu~e? A.ssessing plant condioons (normal. abnormal er emergem:y:i and then selecting a procedure or section of a procedu'e to mitigate recover, or witr wh;cri to proceed
- Knowledge cf when to implement 2tt:Jchments an::!
appendi.ces including t:ow to coor::!i'1ate these items with procedure steps SRO-oniy quest on Knowledge of diagnostic steps am! decision pohts in the EOPs that ir,vch~e traneftions to event specific sub-proce<iures or emergency contingency oroc.edures K'1owledge of adm1nrstrative proced,"1res that specify hierarchy, imptemert2tion. andlcr coordination of plant 11om1aL abnorr1.:il. and emergency procedures Question might not be finked to 10 CFR 55A3(b}!5*\ for SRO-only TMI OPS ILT EXAM Page: 348 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS IL T EXAM Page: 349 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 85 ID: 1720678 Points: 1.00 1900 REFERENCE PROVIDED 1850 Plant conditions: 1800 1750 t'l'I
- Cooldown in progress in accordance with
*;:;; 1700 OP-TM-EOP-006, LOCA COOLDOWN.
':' 1650
~ 1600 EVENT:
(/) fl) 1550 0. OJ 1500 .
- Due to a plant upset, RCS temperature is 1450 approaching the curve on Figure 1, RCS CJ)
(.) 1400 PRESSURE-TEMPERATURE LIMITS. a: 1350
"'O
.....co Cl> 1300 The operating crew must ensure open the (1) 0 1250 . ,,,.,
- sc 1200 .
to prevent exceeding the (2) with Guide 23, RCS PRESSURE AND
, in accordance 1150 TEMPERATURE LIMITS.
1100 .
!050 1000 950 900 850 800 750 700 650 600 550 500 450 !J'
.I j /
f'-"--"'-'-l-~.u..;.~*-L,~JL1 .. 400
<< 200 225 250 275 300 325 A. (1) PORV (2) TS NOT Curve B. (1) PORV (2) PZR SURGE LIMIT Curve C. (1) Spray Valve (2) TS NOT Curve D. (1) Spray Valve (2) PZR SURGE LIMIT Curve Answer: A TMI OPS IL T EXAM Page: 350 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL
\Answer Explanation TMI OPS ILT EXAM Page: 351 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL
<<Explanation: To answer this question correctly, the examinee must know: (1) During and LOCA Cooldown, OP-TM-EOP-010, Guide 23 and Figure 1 and la are used to maintain RCS pressure and temperature within limits; (2) The line that the arrow is point to is the TS NOT line, which is a composite curve to Tech Spec Figures 3.1-1 and 3.1-2 based on the reactor vessel individual components and welds; (3) The PORV is specified for RCS pressure control to move RCS pressure away from the limits described by the curve because RCS pressure reduction is the most effective method from moving away from the curve.
A. (1) Open the PORV Correct Answer - Guide 23, Step 1: If RCS pressure is approaching (2) TS NOT Curve "TS NOT limit", then OPEN RC-RV-2 (PORV). B. (1) Open the PORV Plausible because this curve is in the same general area, but on (2) PZR SURGE LIMIT FIGURE lA, LOW RANGE RCS PRESSURE-TEMPERATURE LIMITS. The Curve action for exceeding that curve is to lower RCS pressure or raise RCS temperature. Incorrect because the curve referenced in the picture is the TS NOT Curve.
- c. (1) Open the Spray Valve Plausible because opening the Spray Valve will lower pressure away (2) TS NOT Curve from the TS NOT Curve. Incorrect because GUIDE 23 directs use of the PORV to lower pressure.
- o. (1) Open the Spray Valve Plausible because if the examinee believed that the PZR SURGE (2) PZR SURGE LIMIT LIMIT Curve was being reference then opening the spray valve would Curve be an acceptable method for lowering pressure. Incorrect because the TS NOT Curve is being referenced.
Examination Outline Cross-reference: Level RO SRO Tier# Group# 2 KIA# BW/E13 2.2.42 Importance Rating 4.6 KIA: EOP Rules and Guides: Ability to recognize system parameters that are entry-level conditions for Technical Specifications. Proposed Question: Question #85 Technical Reference(s): OP-TM-EOP-006, Rev 12 T.S Figure 3.1-1 OP-TM-EOP-0061, Rev 7 OP-TM-EOP-010, Rev 19 OP-TM-EOP-010 Proposed References to be provided to applicants during examination:
, Figure 1 Learning Objective: EOP006-PC0-4 Question Source: Bank #
Modified Bank # New x TMI OPS ILT EXAM Page: 352 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Question History: N/A Last NRC Exam: N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 55.43 b.2 Comments: KA Match: This question matches the KA because the examinee will have to recognize that RCS pressure-temperature is approaching the TS NOT Curve, which would be a violation of Technical Specifications if violated. High Cog: This question is high cog because the examinee will have to analyze the situation and choose the correct course of action. SRO Only: This question is SRO only because it involves recognizing that a TS NOT limit is going to be violated and choosing the correct action to prevent violation. TMI OPS IL T EXAM Page: 353 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL ES-401 5 Attachm nt 2 Figure 1: Screening for SRO-only linked to 10 CFR 55.43{b}(2) (Tech Specs) Can question be ans*tvered sole1~1 by knowing s: *1 Yes hour TS/TRM Action? 1-----...._- RO questi n Can question be answered solely by knowing the Yes LCO/TRM infom1ation listed -above-the-line?" 1-----~- Can question be answered solely by knowing the Yes TS Safety limits? RO questi n the question involve one or more of the following for TS. lRM. or ODCM?
- Application of Required Actions (Section 3) and Survei!kmce Requirements (Section 4) in accordance with rules of 3pplication requirernents {Section *1)
* .Application of generic LCO requirements (lCO 3.0. l thru 3.0.7 and SR 4.0. 1 thru 4.0.4) Yes
- Knowledge of TS bases that is required to ana!)'ze TS 1-----"-*1 required actions and tem1inology Question not be linked to 10 CFR 55.43[b:i(2} for SRO-only might TMI OPS IL T EXAM Page: 354 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS ILT EXAM Page: 355 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 86 ID: 1720700 Points: 1.00 Plant Conditions:
- 100% power with ICS in full auto.
- BWST Boron Concentration is 2550 ppm.
- BWST Water Temperature is 52°F.
EVENT:
- Chemistry reports the latest BWST sample results as follows:
- BWST Boron Concentration is 2490 ppm.
- BWST Water Temperature is 45°F.
What is currently (1) the immediate concern, and (2) the action required? A. (1) Boron crystallization. (2) BWST water temperature must be restored to limits within 8 hours IAW OP-TM-212-457, BWST Heater Operations. B. (1) Boron crystallization. (2) BWST water temperature must be restored to limits within 1 hour IAW OP-TM-212-457, BWST Heater Operations. C. (1) The ability to ensure the reactor will remain at least one percent subcritical following a Loss-of-Coolant Accident. (2) BWST boron concentration must be restored to limits within 8 hours IAW OP-TM-212-527, Transfer of C RCBT to the BWST. D. (1) The ability to ensure the reactor will remain at least one percent subcritical following a Loss-of-Coolant Accident. (2) BWST boron concentration must be restored to limits within 1 hour IAW OP-TM-212-527, Transfer of C RCBT to the BWST. Answer: C
!Answer Explanation TMI OPS ILT EXAM Page: 356 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL
<<Explanation: To answer this question correctly, the examinee must know: (1) According to technical specification 3.3.1.1, the boron concentration of the BWST must have a minimum 2500 PPM at a temperature of not less than 40F; (2) If the temperature or concentration is not within limits, an 8 hour time limit to restore to OPERABLE, or technical specification 3.0.1 applies; (3) The basis for this technical specification is the ensure a sufficient supply of borated water is available for injection by the ECCS in the event of a LOCA; (4) The limits of on BWST minimum volume and boron concentration ensures that sufficient water is available within containment to permit recirculation cooling flow to the core AND the reactor will remain at least one percent subcritical following a Loss-of-Coolant Accident (LOCA).
A. (1) Boron crystallization. Incorrect - Plausible because if the BWST temperature were below (2) BWST water temperature the 40F limit, then boron crystallization would be a concern. must be restored to limits Incorrect because the boron concentration is below the technical within 8 hours IAW specification limit. OP-TM-212-457, BWST Heater Operations. B. (1) Boron crystallization. Incorrect - Plausible because if the BWST temperature were below (2) BWST water temperature the 40F limit, then boron crystallization would be a concern. must be restored to limits Incorrect because the boron concentration is below the technical within 1 hour IAW specification limit. OP-TM-212-457, BWST Heater Operations. C. (1) The ability to ensure the Correct Answer - See above. reactor will remain at least one percent subcritical following a Loss-of-Coolant Accident. (2) BWST boron concentration must be restored to limits within 8 hours IAW OP-TM-212-527, Transfer of C RCBT to the BWST. D. (1) The ability to ensure the Incorrect - Plausible because the action statement if the boron reactor will remain at least concentration cannot be restored is to be in initiate a shutdown 1 one percent subcritical hour to place the plant in a condition where the condition does not following a Loss-of-Coolant apply. Accident. (2) BWST boron concentration must be restored to limits within 1 hour IAW OP-TM-212-527, Transfer of C RCBT to the BWST. Examination Outline Cross-reference: Level RO SRO Tier# 2 TMI OPS ILT EXAM Page: 357 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Group# 1 K/A# 006 2.4.9 Importance Rating 4.2 K/A: Emergency Core Cooling: Knowledge of low power/shutdown implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies. Proposed Question: Question #86 Technical Reference(s): Tech Spec 3.3.1.1 and basis Proposed References to be provided to applicants during examination: None Learning Objective: 212-GL0-14 Question Source: Bank# 860008 Modified Bank# New Question History: System Exam 8 Last NRC Exam: N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 55.43 b.2 Comments: KA Match: The questions matches the KA because the examinee must know the implication of an ECCS system parameter not being at the technical specification minimum. This technical specification minimum ensures the reactor is shutdown in the event of a LOCA. High Cog: This question is high cog because the examinee has to identify the out of specification and apply the LCO time. SRO ONLY: This question is SRO only because the examinee must know the condition, required action, and completion time in addition to the basis. TMI OPS ILT EXAM Page: 358 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL ES-401 5 Attachm nt 2 Figure 1: Screening for SRO-only linked to 1 Ct CFR 55.43(b)(2) (Tech Specs) Can question be answered solely by knowmg $. l Yes ROquestl n hour TS/TRM Action? No Can question be ansv1lered solely by knowing the Yes LCO/TRM infom1;:ition listed \~bove-the-Jine?" RO questo Can question be answered soi'e!y b:, knowing the 1 Yes TS Safety Limits? ROquest n No
.s the question involve one or more of the following for i 0 . ~***'i.<1r~~
TRM, or ODCM?
- Applicatlon of Required Actions (Section 3) and Surv*eilkmce Requirements (Section 4) in accordance with ru1es of 3pplrcation requirements {Section 1)
- Application of generic LCO requirements (lCO 3.0. thru
- J0.7 and SR 4.0.1 thrn 4.GA) Yes
- KnoNledge of TS bases that is required to anaryze TS r---~
required actions and tem1inology TMI OPS ILT EXAM Page: 359 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS ILT EXAM Page: 360 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 87 ID: 1720770 Points: 1.00 Plant Conditions:
- 100% power with ICS in full auto.
EVENT:
- A worker reported a fire in the Relay Room and evacuated the area.
- The operating crew has entered OP-TM-EOP-020, COOLDOWN OUTSIDE OF CONTROL ROOM.
- The crew has tripped both Main Feedwater Pumps, all running Condensate Booster Pumps, and all running Condensate Pumps.
(1) What attachment will the Primary Safe Shutdown NLO perform? (2) What event will this attachment prevent or terminate? A. (1) Attachment 5, "Preventing Spurious Operation of MOV's" (2) Terminate uncontrolled HPI due to a spurious "A" train ES actuation. B. (1) Attachment 5, "Preventing Spurious Operation of MOV's" (2) Prevent an overcooling event by preventing MS-V-2A/B (Isolations to EF-P-1, TBV's and ADVs) from spuriously opening. C. (1) Attachment 13, "Tripping RCPs Locally" (2) Prevent the Reactor Coolant Pumps from spuriously starting. D. (1) Attachment 13, "Tripping RCPs Locally" (2) Prevent Reactor Coolant pumps from operating with no seal injection. Answer: A
!Answer Explanation TMI OPS IL T EXAM Page: 361 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL
<<Explanation: To answer this question correctly, the examinee must know: (1) OP-TM-EOP-020, COOLDOWN FROM OUTSIDE OF CONTROL ROOM is entered when there is a fire in the control room or relay room that has a potential to cause damage to safe shutdown required equipment; (2) Once the determination is made that the control room must be evacuated, this starts a sequence in which actions are taken to prevent or terminate undesirable actions which may be caused by the fire; (3) With the announcement at the end of the IMA's, control room operators and non-licensed operators (NLOs) are directed to perform actions within attachments to mitigate possible effects of the fire; (4) The NLOs respond in accordance with OP-TM-EOP-020, and OS-24, CONDUCT OF OPERATIONS DURING ABNORMAL AND EMERGENCY EVENTS, which allows to them to take actions prior to having CRS concurrence (Attachment F, of OS-24), which includes performing Attachment 5 and Attachment 13 of OP-TM-EOP-020; (5) The Primary Safe Shutdown NLO will perform Attachment 5, which among other things, will terminate uncontrolled HPI due to a spurious "A" train ES actuation by opening the breakers and locally closing MU-V-16A and B.
A. (1) Attachment 5, Correct Answer - The Primary Safe Shutdown NLO will perform "Preventing Spurious attachment 5. Operation of MOV's" (2) Terminate uncontrolled HPI due to a spurious "A" train ES actuation. B. (1) Attachment 5, Incorrect Answer - Plausible because the MS-V-8's (Isolation valves "Preventing Spurious to the Turbine Bypass Valves) are closed to prevent an overcooling Operation of MOV's" event due the turbine bypass valves failing midscale on some fire (2) Prevent an overcooling events. The MS-V-2's could also be used to isolated the turbine event by preventing bypass valves, but closing the MS-V-2 would also isolate a steam MS-V-2A/B (Isolations to supply path to EF-P-1 (Steam Driven Emergency Feedwater Pump) EF-P-1, TBV's and ADVs) and an MS-V-4 (Atmospheric Dump Valve). Attachment 5 does open from spuriously opening. the breaker for MS-V-2A/B, but that is to maintain the valve open for use of EF-P-1 and the MS-V-4's.
- c. (1) Attachment 13, Tripping Incorrect Answer - Plausible because Attachment 13 is performed by RCPs Locally" the Secondary Safe Shutdown NLO. Preventing Reactor Coolant (2) Prevent the Reactor Pumps from spuriously starting is one basis for performing Coolant Pumps from Attachment 13.
spuriously starting. D. (1) Attachment 13, "Tripping Incorrect Answer - Plausible because Attachment 13 is performed by RCPs Locally" the Secondary Safe Shutdown NLO. Preventing Reactor Coolant (2) Prevent Reactor Coolant Pumps from operating without seal injection is one basis for pumps from operating with performing Attachment 13. no seal injection. Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# KJA# 013 2.4.35 Importance Rating 4.0 KJA: Engineered Safety Features Actuation: Knowledge of local auxiliary operator tasks during an emerqencv and their resultant operational effects. TMI OPS IL T EXAM Page: 362 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL Proposed Question: Question #87 Technical Reference(s): OP-TM-EOP-020, Rev 22 OS-24, Rev 28 OP-TM-EOP-0201, Rev 15 Proposed References to be provided to applicants during examination: None Learning Objective: EOP020-PC0-1 Question Source: Bank # Modified Bank # New x Question History: N/A Last NRC Exam: N/A Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 b.5 Comments: KA Match: This question matches the KA because the examinee will have to know that a fire in the relay room could cause and unwanted HPI actuation, but that the Attachment 5 will close MU-V-16A and B which would mitigate the consequence of such event. High Cog: This question is high cog because the examinee will have to assess plant conditions to determine that a control room evacuation is required and that the remote shutdown sequence has been directed. Step 2.8 is a stopping point in which the operating crew would wait at until conditions in the control room have deteriorated enough that crew must evacuate. This is denoted by the tripping of the feedwater, condensate booster, and condensate pumps. SRO Only: This question is SRO only because the examinee will have to assess that the stem in a way that determines that the remote shutdown sequence has begun, and understand which attachment the NLOs have to perform. TMI OPS ILT EXAM Page: 363 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Figure 2: Screening for SRO-only linked to 10 CFR 55.43(b)i5) (Assessment and selection of procedures) Can the question be answered soleiy by knowing "systems knowledge", Le .. how the system 'h<orks. Yes RO question flowpath, logic, component 1ocaUon? Gan the question be answered solely by knowing immedi::>te oper.:itor actions? Yes RO question Can the question be ::mswered solely by knowing entry conditions for AOPs or plant p;::nameters that Yes RO question require direct ent.ry to major EOPs? No Can the question be answered solely by knowing the purpose, overall sequence of events, or overall Yes RO question rnmoative strateov of a procedure? No
~ s the question require one or more of !he following?
- Assessing pbnt conditions (nom1al, abnormal, or emergency) and then selecting a procedure or section of a procedure to mitigate, recover. or v.11h which to proceed
- Knowledge of *..vhen to implement attachments and appendices, including how to coordinate these items vvith procedure steps Yes 'R0--0nly
- Knov.1edge of diagnostic steps and deds1on points in the ' uestion EOPs thai involve transitions to event specific sub-procedures or emergency contingency procedures
- Knowledge of administrative procedures that specify hierarchy, implementation, andfor coordination of plant nom1al, abnorrna!, and emergency procedures Ouestion might not be linked to 10 t'-t=D hi:. A?:/1-,tih\ f,.,.vr c:.~or-\ ..-..-.t" TMI OPS ILT EXAM Page: 364 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS ILT EXAM Page: 365 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 88 ID: 1720789 Points: 1.00 Plant Conditions:
- 100% power with ICS in full auto.
EVENT:
- Main and Emergency Feedwater are both lost.
- HPl/PORV cooling is in progress.
POST EVENT:
- Both Main and Emergency Feedwater are restored.
- One Reactor Coolant Pump is running in each loop.
- Both OTSG's are intact and dry.
- PPC Points C4015 and C4016 (OTSG tube-to-shell differential temperatures) are at +?OF.
In accordance with Guide 13, FEEDING A DRY OR DEPRESSURIZED OTSG, (1) is the preferred feed source because it will (2) A. (1) Main Feedwater (2) cool down the OTSG tubes faster B. (1) Main Feedwater (2) minimize the tensile loading on the OTSG tubes C. (1) Emergency Feedwater (2) cool down the OTSG tubes faster D. (1) Emergency Feedwater (2) minimize the tensile loading on the OTSG tubes Answer: C
!Answer Explanation TMI OPS ILT EXAM Page: 366 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL
<<Explanation: To answer this question correctly, the examinee must know: (1) The stem sets up a scenario in which the plant is experiencing a lack of primary to secondary heat transfer (i.e. Reactor tripped, no feedwater available) which heats up the RCS, and thus the OTSG tubes heat; (2) While the tubes heat up, the OTSG shell temperature should remain constant or slightly cooldown due to the lack of feedwater; (3) This causes a compressive stress on the OTSG tubes (which is a positive TSDT); (4) This is also indicated by the(+) on computer points C4015 and C4016; (5) Being above the(+) limit of TSDT means there is a compressive stress on the OTSGs; (6) The actions for a(+) TSDT in Guide 13 with a reactor coolant pump on is to feed the OTSG with EFW; (7) In accordance with the Guide 13 basis document, EFW is chosen because it sprays directly on the OTSG tubes, and will lower the tube temperature immediately, thus lowering the TSDT and compressive stresses; (8) Since EFW sprays directly on the tubes it will cool down the tubes faster than MFW.
A. (1) Main Feedwater Incorrect - Plausible because in most cases when a reactor coolant (2) cool down the OTSG pump is on, MFW is the preferred source of feedwater. This would tubes faster be the case if the TSDT was negative. In addition, MFW would not cool down the OTSG tubes faster. B. (1) Main Feedwater Incorrect - Plausible because in some cases Main Feedwater would (2) minimize the tensile minimize the tensile loading on the OTSG tubes. Incorrect be cause loading on the OTSG tubes EFW is the preferred source of feedwater.
- c. (1) Emergency Feedwater Correct Answer: See above.
(2) cool down the OTSG tubes faster D. (1) Emergency Feedwater Incorrect Answer: Plausible because EFW is the preferred source. (2) minimize the tensile load Incorrect because the stress currently exhibited on the OTSG tubes is on the OTSG tube compressive. Spraying EFW on the tubes would minimize the compressive loading on the tubes, not the tensile loading. Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 1 K/A# 061 2.4.18 Importance Rating 4.0 K/ A: Auxiliary/Emergency Feedwater: Knowledge of the specific basis for EOPs. Proposed Question: Question #88 Technical Reference(s): OP-TM-EOP-010, Guide 13, Rev 19 OP-TM-EOP-0101, Guide 13, Rev 9 Proposed References to be provided to applicants during examination: None Learning Objective: EOPOlO-PC0-4 Question Source: Bank# TMI OPS ILT EXAM Page: 367 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL Modified Bank# New x Question History: N/A Last NRC Exam: N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 55.43 b.5 Comments: (KA Match, why high cog, why SRO only) KA Match: This question matches the KA because the examinee must know the basis for choosing EFW to feed the OTSG. High Cog: The question is high cog because the examinee must determine which step of Guide 13 which applies from the conditions in the stem. SRO Only: This question is SRO only because it requires the examinee to assess plant conditions (Restoring from lack of heat transfer, MFW and EFW available, RCP running, positive TSDT) and select a course of action (feed with EFW because a RCP is on and TSDT is positive). Guide 13 is not a major EDP, but is directed from other major EOPs. TMI OPS ILT EXAM Page: 368 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS ILT EXAM Page: 369 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 89 ID: 1737969 Points: 1.00 Plant conditions:
- 100% power with ICS in full auto.
- Backup Instrument Air Compressor IA-P-2A is tagged out of service for maintenance.
- Main Vacuum Pump VA-P-1A is operating.
Sequence of events: Time Event 0100 Local fire (now extinguished) renders Service Air Compressor's SA-P-1A and SA- P-1 B inoperable. 0200 MAP PLB-1-6 IA-P-4 IA-Q-2 TROUBLE actuates. 0210 Instrument Air Compressor IA-P-1A trips on motor overcurrent. 0220 Instrument Air Compressor IA-P-1 B trips on motor overcurrent. 0230 The following valid alarms actuate: PLB-1-7 Instrument Air Press Low Turbine Area. PLB-1-8 Station Service Air Press Low. PLB-2-7 Instrument Air Press Low Aux Bldg Area. 0240 Current Conditions:
- All Instrument and Service Air System pressure indications are now at 75 psig, reducing at 1 psi per minute.
- Main Condenser vacuum is 27 inches Hg, reducing at 0.2 inches Hg per minute.
- Instrument Air Compressor IA-P-4 filter and dryer d/p at 22 psid What action is required for these conditions that will prevent entry into Technical Specification LCO 3.4, Decay Heat Removal Capability?
A. Trip the reactor. B. Take manual control of MU-V-20. C. Open VA-V-5A vacuum pump suction valve. D. Ensure open IA-Q-2 bypass valve IA-V-2133 and open IA-V-2124 (Pre-filter Bypass Valve). Answer: D
~nswer Explanation TMI OPS IL T EXAM Page: 370 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL
<<Explanation: To answer this question correctly, the examinee must know: (1) When instrument air becomes less than 80 psig, OP-TM-AOP-028, LOSS OF INSTRUMENT AIR, is entered; (2) In OP-TM-AOP-028, there are various actions taken for the lowering levels for air pressures or high level of differential pressures; (3) The parameter exceeded for this scenario is high D/P for IA-P-4 filter and dryer
( > 20 psid); (4) The Turbine Bypass Valves, (TBVs) MS-V-3A-F usually receive air from the instrument air header, and have backup air from the 'A' Backup Instrument Air Compressor, IA-P-2A; (5) Since IA-P-2A is OOS in the stem, and with the various events occurance to the other compressors, when the IA-P-4 filter and dryer DP becomes> 22 psid, the MS-V-3's become inoperable; (6) One of the purposes of the TBVs is to remove decay heat when the reactor is shutdown, and 4 of 6 must be operable per technical specification 3.4.1.1. A. Trip the reactor. INCORRECT: Manual reactor trip at 60 psig is a required action to in order to avoid potential loss of control or erratic behavior of air operated components at significant power levels. Distracter is plausible because this answer represents a valid IAAT action at less than 60 psig, and it does result in reduction of core heat production by decay of fission products. In addition, the examinee could believe that tripping the reactor is an option to not enter a tech spec, as some tech specs only apply when the reactor is critical. B. Take manual control of INCORRECT: The purpose of this action is to prevent loss of reactor MU-V-20. coolant pump seal injection flow. Distracter is plausible because this answer represents a valid manual action included in AOP-028. In addition, MU-V-20 is a containment isolation valve, the examinee could believe that MU-V-20 fails open (it does not) which would represent a loss of containment and potentially an entry into the containment tech spec. C. Open VA-V-SA vacuum pump INCORRECT: Plausible because the examinee could believe that suction valve. vacuum is required for the TBV's to be operable. Distracter is plausible because VA-V-SA/B/C all fail closed on loss of instrument air. D. Ensure open IA-Q-2 bypass Correct Answer: IA-P-4 is the last air compressor available that could valve IA-V-2133 and open provide air pressure to the turbine bypass valves. In addition to all IA-V-2124 (Pre-filter Bypass of the other failures, if the dryer and filter were clogged, they could Valve). be bypassed to provide air to the air header. Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 1 K/A# 078 A2.01 Importance Rating 2.9 K/ A: Instrument Air: Ability to (a) predict the impacts of the following malfunctions or operations on the IAS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Air dryer and filter malfunctions Proposed Question: Question #89 Technical Reference(s): OP-TM-AOP-028, Rev 9 TMI OPS IL T EXAM Page: 371 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Tech Spec 3.4.1.1 Proposed References to be provided to applicants during examination: None Learning Objective: AOP-028-PC0-4 Question Source: Bank# 371312 Modified Bank# New Question History: Comp 1 Last NRC Exam: Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 55.43 b.5 Comments: KA Match: This question matches the KA because the examinee must identify which parameter is out of specification due to an instrument air failure and determine the procedure step which will remedy the situation. High Cog: This question is high cog because the examinee analyze the current parameters and trends of the instrument air system and make a decision on the correct course of action to ensure the plant does not enter a tech spec LCO. SRO Only: This is an SRO only question because the examinee must assess plant conditions then select the appropriate procedure to mitigate the malfunctions. In addition, the SRO must know the content of the procedure in which to evaluate the stems parameters with, and choose the correct course of actions based on the assessment. TMI OPS ILT EXAM Page: 372 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Figure 2: Screening for SRO-only linked to 10 CFR 55.43(b)(5) {Assessment and selection of procedures} Can the question be answered so!eiy by* knowing "systems knc:rwledge". i.e'" how the system v.orts. Yes RO question flowpath, logic, component location? Can the question be answered solely by knmv1 ng immediate operntor actions? Yes RO question No Can the queshon be answered solely by knowing entry conditions for AOPs or pl.ant parameters thm Yes RO question require direct entry- to major EOPs? C.:m the question be answered soleiy by knowing the purpose, overall seqLlnce of events, or overJ.11 Yes RO question mmaattve strateav of a orocedure? Does the question require one or more of the fofo.ving?
- Assessing plant conditions (normal, abnormal, or emergency) and then selecting a procedure or sectton of a procedure to mitigate. recover, or '"'1th which to proceed
- Knowled9e of v;hen to implement attachments and appendices, including how to coordin:ite these items with procedure steps Yes R0-0nly
- Knowledge of diagnostic steps and decision points in the uestion EClPs that involve transitions to event specific sub-procedures or emergency contingency procedures
- Knowledge of adi-ninistrative procedures that specify hierarchy, implementation, andior coordination of pbnt norm;:il, ab11om1aL and emergency procedures Question miqht not be linked to I 0 CFR 5543(b}(5) for SRO-only ES-40 l, Page 22 of 50 TMI OPS IL T EXAM Page: 373 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS ILT EXAM Page: 374 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS ILT EXAM Page: 375 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 90 ID: 1737999 Points: 1.00 Plant Conditions:
- The plant is shut down in a Refueling Outage.
- Core off-load in progress.
- Containment Integrity is NOT being maintained.
- RB Purge is in progress IAW OP-TM-823-408 RB Purge - RB Doors and/or Equipment Hatch Open.
Event:
- The Fuel Handling SRO reports that a Fuel Assembly has been dropped and damaged in the Fuel Transfer Canal.
- MAP C-1-1 RADIATION LEVEL HI, alarms.
- RB Purge Exhaust Duct Monitor RM-A-9 is off-scale high.
- RB Purge Exhaust Duct Monitor RM-A-9 Hi-Hi is 3000 CPM.
- Nl-11 counts have gone up and steadied out at 30 cps.
In accordance with OP-TM-MAP-C0101, all personnel are (1) to be evacuated from the reactor building, and the RB Purge must be secured in accordance with _ _..(2.....) _ A. (1) required (2) OP-TM-244-911, CONTAINMENT CLOSURE B. (1) required (2) OP-TM-244-901, CONTAINMENT ISOLATION C. (1) NOT required (2) OP-TM-244-911, CONTAINMENT CLOSURE D. (1) NOT required (2) OP-TM-244-901, CONTAINMENT ISOLATION Answer: A
!Answer Explanation TMI OPS ILT EXAM Page: 376 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Explanation: To answer this question correctly, the examinee must know: (1) During fuel handling, the containment is allowed to be open as long a reactor building purge is in service with the RB Purge Valve interlocks in defeat (in addition to other requirements for closing the reactor building which are not pertinent to the question); (2) When the fuel assembly is dropped in the fuel transfer canal gasses are released, which cause RM-A-9 to alarm, which would cause MAP C-1-1 alarm in the control room; (3) The alarm response for RM-A-9 directs the evacuation of ALL personnel from the containment building, and to initiate OP-TM-244-911, CONTAINMENT CLOSURE; (4) OP-TM-244-901 directs the closing of AH-V-lA, B, C, and D (RB purge valves) and to ensure containment closure devices outside of containment are set; (S) The Nl-11 counts going up and steadying out at 30 cps is to enhance the plausibility of a distractor and for a better match of the KA as there would be an automatic RB evacuation alarm at 40 cps. A. (1) required Correct Answer - See Above (2) OP-TM-244-911, CONTAINMENT CLOSURE B. (1) required INCORRECT - Plausible because OP-TM-823-408 and 1101-3, (2) OP-TM-244-901, CONTAINMENT INTEGRITY AND ACCESS LIMITS directs the purge CONTAINMENT interlocks to close the purge valves to be defeated. The examinee ISOLATION must know that since the interlocks are defeated that the purge will not secure. If the examinee believes that the purge should have been secured, they examinee could believe that the CONTAINMENT ISOLATION procedure would direct closing the AH-V-1 valves. The CONTAINMENT ISOLATION procedure does include steps which close these valves, but it is used if a containment isolation valve fails to close from an ES signal (1600 psig, 500 psig, and/or 4 psig), which is not present in this question.
- c. (1) NOT required INCORRECT - Plausible because Nl-11 never gets over 40 cps, which (2) OP-TM-244-911, would initiate an automatic RB Evacuation alarm. Not going over 40 CONTAINMENT CLOSURE cps is plausible because the fuel assembly was dropped in the fuel transfer canal, and not the reactor vessel.
D. (1) NOT required INCORRECT - Plausible because Nl-11 never gets over 40 cps, which (2) OP-TM-244-901, would initiate an automatic RB Evacuation alarm. Not going over CONTAINMENT 40 cps is plausible because the fuel assembly was dropped in the ISOLATION fuel transfer canal, and not the reactor vessel. In addition, plausible because OP-TM-823-408 and 1101-3, CONTAINMENT INTEGRITY AND ACCESS LIMITS directs the purge interlocks to close the purge valves to be defeated. The examinee must know that since the interlocks are defeated that the purge will not secure. If the examinee believes that the purge should have been secured, they examinee could believe that the CONTAINMENT ISOLATION procedure would direct closing the AH-V-1 valves. The CONTAINMENT ISOLATION procedure does include steps which close these valves, but it is used if a containment isolation valve fails to close from an ES signal (1600 psig, 500 psig, and/or 4 psig), which is not present in this question. Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 1 K/A# 103 A2.04 Importance Rating 3.6 TMI OPS ILT EXAM Page: 377 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL K/A: Containment: Ability to (a) predict the impacts of the following malfunctions or operations on the containment system and (b) based on those predictions, use the procedures to correct, control, or mitigate the consequences of those malfunctions or operations Proposed Question: Question #90 Technical Reference(s): 1101-3, Rev 93A OP-TM-MAP-COlOl, Rev 3 OP-TM-244-911, Rev 4 OP-TM-823-408, Rev 12 Proposed References to be provided to applicants during examination: None Learning Objective: 661-GL0-5 Question Source: Bank# Modified Bank# 1110308 New Question History: Sim Exam 9 Last NRC Exam: Unmodified on 10-02 Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 55.43 b.5 Comments: KA Match: This question matches the KA because the examinee must predict what the impact of a dropped fuel assembly will be on the operations going on in the reactor building during refueling. From those predictions, the examinee must know the content of the containment closure procedure (OP-TM-244-901) to know that the RB purge valves get closed. High Cog: This question is high cog because the examinee must know that an RB evacuation is required from the stem. SRO Only: This question is SRO only because the examinee must assess plant conditions know the content of a procedure to ensure low pressure containment integrity is maintained. TMI OPS IL T EXAM Page: 378 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Figure 2: Screening for SRO-only linked to 10 CFR 55.43{b)l5) (Assessment and selection of procedures) C;:m the question be answered solely by knowing "systems knowledge". i.e .. how the system works. Yes RO question flrn.vpath, lo.gic, component location? C.:m the question be answered solely by knowing immediate operntor actions? Yes RO question Can the question be answered solel}: by knowing entry conditions for AOPs or plant parameters that 1--Y_e_s_........i RO question require direct entry to major EOPs? Can the question be answered sole.1'.V by k.nmving the purpose, overall sequence of events. or overall Yes RO question mit!qatlve strateav of a procedure?
- Assessing pl;Jnt conditions (normal, abnormal, or emergency) and then selecting a procedure or section of a procedure to mitigate, recover, or .,..,;th which to proceed
- Knowledge of when to implement .:ittachmenls and appendices, including how to coordinate these items with procedure steps Yes
- Knowfedge of diagnostic steps cind decision points in the 1---~
EOPs that involve transitions to e"ient specific sub-procedures or emergency contingenC}" procedures
- Knowtedge of adrninistrative procedures that spec.ify hier;::irchy, implement;::ition, andior coordination of p!ant ncirmai, 3bnom1al, and emergency procedures Question might not be finked to JO CFR 55.43(b}(5) for SRO-only Plant Conditions:
- The plant is shut down in a Refueling Outage.
- Core off-load in progress.
- Containment Integrity is NOT being maintained.
TMI OPS IL T EXAM Page: 379 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL
- RB Purge is in progress IAW OP-TM-823-408 RB Purge - RB Doors and/or Equipment Hatch Open.
Event:
- The Fuel Handling SRO reports that a Fuel Assembly has been dropped and damaged in the Refueling cavity.
- MAP C-1-1 RADIATION LEVEL HI, alarms.
- RB Purge Exhaust Duct Monitor RM-A-9 is off-scale high.
- RB Purge Exhaust Duct Monitor RM-A-9 Hi-Hi is 3000 CPM.
~ssuming no action other than the initiation of a Containment evacuation has taken place, which ONE (1) of the following identifies the current positions of RB Purge Isolation Valves (AH-V-1A, 1B, 1C and 1D), AND the reason for their position?
A. Open; The RB Purge Line Isolation High Radiation Interlock is defeated. B. Closed; The RB Purge Line Isolation High Radiation Interlock was operated by RM-A-9G when it went above the ALERT level. C. Closed; The RB Purge Line Isolation High Radiation Interlock was operated by RM-A-9 Hi-Hi when it went above the ALERT level. D. Open; The RB Purge Line Isolation High Radiation Interlock has not operated because RM-A-9 Hi-Hi has not exceeded the HIGH Alarm level. TMI OPS ILT EXAM Page: 380 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS ILT EXAM Page: 381 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL 91 ID: 1700311 Points: 1.00 Plant conditions:
- The crew is performing a plant startup per 1102-02, Plant Startup.
- Deboration to the Target Critical Boron Concentration has just been completed.
- The crew is awaiting Plant Manager authorization to startup the reactor.
EVENT: A check of the Backup lncore Thermocouple Readout (BIRO) reveals that the following Thermocouples have failed: 4-E 5-G 7-B 13-C Given these current conditions, which ONE of the following identifies whether the LCO for Tech Spec 3.5.5, Accident Monitoring Instrumentation, is currently satisfied, and if not, also identifies the MINIMUM actions required to satisfy the LCO without reliance on any action statement? A. LCO 3.5.5 is met; No action statements are required to be entered. B. LCO 3.5.5 is NOT met; AND Performing maintenance and declaring Thermocouple 13-C OPERABLE will allow all actions statements to be exited. C. LCO 3.5.5 is NOT met; AND Performing maintenance and declaring Thermocouple 4-E OPERABLE will allow all actions statements to be exited. D. LCO 3.5.5 is NOT met; AND Performing maintenance and declaring Thermocouple 4-E and 7-B OPERABLE will allow all actions statements to be exited. Answer: C
~nswer Explanation TMI OPS ILT EXAM Page: 382 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL
****Needs 1105-5 Table 2 as a reference Explanation: To answer this question correctly, the examinee must know: (1) That 2 of the 4 instruments per quadrant must be operable or the action statement of Tech Spec 3.5.5 must be entered (2) The condition of the plant is one where the Tech Spec 3.5.5 is applicable (3) How to read Table 2 of 1105-5 to verify that 3 in a quadrant are failed.
A. LCO 3.5.5 is met; This is plausible because many LCOs are written to be No action statements are applicable when the reactor is critical. Since it is not, the required to be entered. operator may incorrectly believe that thermocouples do NOT need to be OPERABLE to satisfy the LCO. B. LCO 3.5.5 is NOT met; AND This is plausible because the operator may incorrectly believe Performing maintenance that thermocouple 13-C is part of the same Quadrant as two of and declaring Thermocouple the others. The provided reference allows the student to map 13-C OPERABLE will allow the BIROs and determine that 3 out of four BIROs in one all actions statements to be quadrant are not operable therefore the TS LCO is not met and exited. that 13-C is not one of those three. Therefore, performing maintenance on this thermocouple would still leave the operator with three inoperable thermocouples in a quadrant.
- c. LCO 3.5.5 is NOT met; AND According to Technical Specification LCO 3.5.5 the instruments Performing maintenance identified in Table 3.5-2 and Table 3.5-3 during STARTUP, and declaring Thermocouple POWER OPERATION and HOT STANDBY shall be 4-E OPERABLE will allow all OPERABLE. According to Technical Specification LCO 3.5.5, actions statements to be there are four Backup lncore Thermocouple Display (BIRO) exited. channels/ per quadrant, and two of them must be OPERABLE.
According to Technical Specification 1.0 , the reactor shall be considered in the STARTUP mode when the shutdown margin is reduced with the intent of going critical. Since the plant has been heated up to beyond 250°F under the stated conditions, and the Boron concentration has been reduced to Target Critical Boron Concentration, the plant is in the STARTUP mode, and the LCO is applicable. This is supported by the System Operating Procedure. According to 1105-5 when RCS avg. temp is >250°F, the Backup lncore Thermocouple Display Channel (BIRO) must be operable with a minimum of 2 thermocouples per core quadrant in operation. Using the provided reference and generating a core map, the operator can determine that 4-E, 5-G, 7-B and 13-C are in two different quadrants and three (4-E, 5-G and 7-B) are in the same quadrant. Since a minimum of two are required to be OPERABLE in each quadrant, the operator can determine that one quadrant has only one OPERABLE thermocouple; 8-F. This means that LCO 3.5.5 is NOT being met. The operator can meet LCO 3.5.5 by performing maintenance and declaring Thermocouple 4-E OPERABLE. D. LCO 3.5.5 is NOT met; AND This is plausible because the operator may incorrectly believe Performing maintenance that only one thermocouple per quadrant is allowed to be and declaring Thermocouple inoperable. While performing maintenance on both 4-E and 7-B OPERABLE will thermocouples will render the LCO met, it can be met with less allow all actions statements maintenance, by performing maintenance only on to be exited. thermocouple 4-E; and therefore, it is NOT the minimum action necessary to meet the LCO. Examination Outline Cross-reference: Level RO SRO Tier# 2 TMI OPS ILT EXAM Page: 383 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Group# 2 KIA# 017 2.4.3 Importance Rating 3.7 3.9 KIA: In-Core Temperature Monitor: Ability to identify post-accident instrumentation Proposed Question: Question #91 Technical Reference(s): 1105-5, Rev 25 TS 3.5.5, Table 3.5-2 Proposed References to be provided to applicants during examination: 1105-5, Table 2 Learning Objective: 625-GL0-14 Question Source: Bank # 860160 Modified Bank # New Question History: Comp 2 Last NRC Exam: Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 55.43 b.2 Comments: KIA Match: This question matches the KIA because the examinee must know how many thermocouples are required to be operable to meet the TS 3.5.5, which is for post accident monitoring. The question is at the Comprehension/Analysis cognitive level because the operator must consider several pieces of information such as (1) the LCO governing the BIRO, (2) the condition of the plant and whether or not the LCO is applicable under the present conditions, and (3) the specific instrument failures; and then draw a conclusion regarding the status of the LCO (and the maintenance needed to satisfy it). The question is SRO-Only because the operator must demonstrate the ability to comply with the plant Technical Specifications including knowing procedurally required minimum requirements for instrument operability . TMI OPS ILT EXAM Page: 384 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL ES-401 5 Attachm nt 2 Figure 1: Screening for SRO-only linked to 10 CFh155.43(b)(2) (Tech Specs I Can question be answered sole1~~" by knowmg s 1 Yes hour TS/TRr*,1 Action? >----~- RO questi n Can question be answered solely by knowing the Yes LCO/TRM infom1ation tisted "above-the-1ineT f----"--- RO questio' Can question be answered solely by knowing the Yes TS S3fety Limits? RO questi n No
,,,aiffe'VlJe:> the question involve one or more of the following for TS.
TRM. or ODCM?
- Applicatron of Required Actions (Section 3) and Surveilbnce Requirements (Section 4) fn accordance with rules of application requirements (Section 1)
- Application of generic LCO requirements (lCO 3 Q \ thru 3.0.7 and SR 4.0.1thru4.0.4) Yes SRO-only
- Knowledge of TS bases that is reqwred to 3natyze TS f----""-"l question required achons and tem1ino!ogy Question not be linked to 10 CFR 55.43[b}(2) for SR0-011ly might TMI OPS IL T EXAM Page: 385 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS ILT EXAM Page: 386 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL 92 ID: 1736504 Points: 1.00 Plant conditions:
- 100% power with ICS in full Auto.
- Condensate Pump CO-P-1 C is tagged out for maintenance.
EVENT:
- The Secondary NLO reports that vibrations on Condensate Pump CO-P-1A have increased since his last round and a high pitched noise seems to be coming from the lower motor bearing.
- Maintenance confirms that the lower bearing is failing and recommends CO-P-1A be stopped within the next hour to avoid shaft damage.
The operating crew must reduce power to (1) , and secure CO-P-1 A in accordance with (2) A. (1) < 665 MWe (2) 1102-4, POWER OPERATIONS B. (1)<665MWe (2) OP-TM-421-430, REMOVING CO-P-1A FROM SERVICE C. (1) < 50% power (2) 1102-4, POWER OPERATIONS D. (1) < 50% power (2) OP-TM-421-430, REMOVING CO-P-1A FROM SERVICE Answer: C
!Answer Explanation TMI OPS IL T EXAM Page: 387 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL
<<Explanation: To answer this question correctly, the examinee must know: (1) Due to CO-P-lC being out of service, the operating crew must down power the plant in accordance with 1102-4; (2) Also, due to CO-P-lC being out of service, the crew must secure a Main Feedwater Pump and a Condensate Booster Pump prior to securing the Condensate Pump; (3) In accordance with 1102-4, the operating crew could secure the Main Feedpump, Condensate Booster Pump, and the Condensate Pump at less than < 560 MWe, and prior to a Condensate Booster Pump (CO-P-2) discharge pressure exceeding 675 psig; (4) 560 MWe is approximately 68% power; (5) A precaution in OP-TM-421-000 limits operations with only one Condensate Pump (with only one Condensate Booster Pump, and Main Feedwater Pump) to less than 50% power to avoid a Reactor Trip.
A. (1) < 665 MWe INCORRECT: Plausible if the examinee believes that the run back (2) 1102-4, POWER setpoint for loss of a Feedwater Pump is 665 MWe. This is incorrect OPERATIONS because the plant would run back to less than 560 MWe, in addition this power level would be to high for sustained operation with a single condensate pump in operation. B. (1)<665MWe INCORRECT: Plausible if the examinee believes that the run back (2) OP-TM-421-430, setpoint for loss of a Feedwater Pump is 665 MWe. This is incorrect REMOVING CO-P-1A because the plant would run back to less than 560 MWe, in addition FROM SERVICE this power level would be to high for sustained operation with a single condensate pump in operation.
- c. (1) < 50% power Correct Answer: See above.
(2) 1102-4, POWER OPERATIONS D. (1) < 50% power INCORRECT: Plausible because the examinee could believe (2) OP-TM-421-430, OP-TM-421-430 contains the correct guidance on securing CO-P-lA. REMOVING CO-P-1A Incorrect because this procedure would start the standby FROM SERVICE Condensate Pump first, which is out of service in the stem. The guidance to secure the Main Feedwater Pump, Condensate Booster Pump, and Condensate Pump are in 1102-4. Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 2 KJA# 056 A2.04 Importance Rating 2.6 KJA: Condensate: Ability to (a) predict the impacts of the following malfunctions or operations on the Condensate System, and (b) based on those predictions, use procedures to correct, control, of mitigate the consequences of those malfunctions or operations: Loss of condensate pumps. Proposed Question: Question #92 Technical Reference(s): OP-TM-421-000, Rev 16 1102-4, Rev 133 Proposed References to be provided to applicants during examination: None TMI OPS ILT EXAM Page: 388 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Learning Objective: 421-GL0-10 Question Source: Bank # 572934 Modified Bank # New Question History: System Exam 5 Last NRC Exam: N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 55.43 b.5 Comments: KA Match: This question matches the KA because the examinee has to understand the impact of losing a second condensate would be to the plant. The examinee must also determine the correct power and procedure that the operators would use to lower power. High cog: This question is High Cog because the examinee must know that the plant power must be lowered if another condensate pump is lost. In addition, the examinee must pick the correct procedure to lower power. SRO Only: This question requires the examinee to assess the plant conditions/equipment and to know the content of procedures in order to select the required course of action. TMI OPS ILT EXAM Page: 389 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Figure 2: Screening for SRO-only linked to 10 CFR 55.43{b}(5) (Assessment and selection of procedures} Cm the question be answered solely by knowing
~systems knov<<ledge". i e .. how the system works. Yes f!mvpath, logic, component location? RO questfon Can the question be answered solely by knowing immediate oper3tor actions? Yes RO question No G:in the question be answered solely by knowing entry conditions for AOPs or pkmt parameters that Yes RO question require direct entry to major EOPs?
Can the question be ansv.. ered solely by knowing the purpose, over::ill sequence of events. or overall Yes RO question mmaative strateav of a procedure? question require one or more of the following?
- Assessing plant conditions (normal, abnormal, or emergency) and then sele<:tlng a procedure or section of a procedure to mitigate, re{;over, or v.ith which to proceed
- Knmv~edge of when to implement ;:itfachments and
- ippendices, including how to coordinate these items with procedure steps Yes
- Knov!!~!edge of diagnostic steps and dec1slon points in the 1---~
EOPs that involve transitions to event specific: sub-procedures or emenJency contingency procedures
- Knmv!eclge of administrative procedures th:::rt specify hierarchy, implementation, ;:md.lor coordin:Jtion of plant norrnal, 3bnormai, and emergency procedures Question might not be finked to 10 CFR 55.43(bX5) for SRO-oniy TMI OPS ILT EXAM Page: 390 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS IL T EXAM Page: 391 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL 93 ID: 1736533 Points: 1.00 Plant Conditions:
- 100% power with ICS in full auto.
- An approved radioactive liquid release is in progress.
EVENT:
- Annunciator C-1-1 "RADIATION LEVEL HI" is in alarm.
- Radiation Monitor RM-L-6, RAD WASTE DISCHARGE, has failed (pegged high, off-scale).
- WDL-P-14A/B discharge valve to the MDCT, WDL-V-257, is stuck open and cannot be closed.
Identify the one selection below that describes: (1) The correct action, and (2) The timeclock associated with RM-L-6. A. (1) Terminate the release and notify Radiation Protection. (2) Exert best efforts to return RM-L-6 to OPERABLE within 14 days. B. (1) Terminate the release and notify Radiation Protection. (2) Exert best efforts to return RM-L-6 to OPERABLE within 30 days. C. (1) Request Chemistry obtain a sample of the Rad Monitor Pit and check the permit calculations. (2) Exert best efforts to return RM-L-6 to OPERABLE within 14 days. D. (1) Request Chemistry obtain a sample of the Rad Monitor Pit and check the permit calculations. (2) Exert best efforts to return RM-L-6 to OPERABLE within 30 days. Answer: B
!Answer Explanation TMI OPS ILT EXAM Page: 392 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL
<<Explanation: To answer this question correctly, the examinee must know: (1) In accordance with OP-TM-MAP-COlOl, when RM-L-6 alarm is received (in this case for RM-L-6 failing high), WDL-V-257 should close; (2) When the valve (WDL-V-257) does not close, and because RM-L-6 is failed high, the examinee should determine that RM-L-6 is inoperable; (3) OP-TM-MAP-COlOl directs the termination of the release and the notification of radiation protection; (4) The timeclock to return RM-L-6 is found in CY-TM-170-300, OFFSITE DOSE CALCULATION MANUAL (ODCM) step 2.1.1, where with less than the number OPERABLE best efforts to return the instrumentation to OPERABLE within 30 days, if not explain in the next Annual Effluent Release Report.
A. (1) Terminate the release INCORRECT - Plausible because many ODCM timeclocks are 14 days. and notify Radiation Incorrect because the timeclock from RM-L-6 is 30 days. Protection. (2) Exert best efforts to return RM-L-6 to OPERABLE within 14 days. B. (1) Terminate the release Correct Answer - See above. and notify Radiation Protection. (2) Exert best efforts to return RM-L-6 to OPERABLE within 30 days.
- c. (1) Request Chemistry INCORRECT - Plausible because this is the action from obtain a sample of the Rad OP-TM-MAP-COlOl if RM-L-7 (Plant Discharge Rad Monitor) high Monitor Pit and check the alarm is in. In addition, the timeclock is 30 days, not 14 days.
permit calculations. (2) Exert best efforts to return RM-L-6 to OPERABLE within 14 days. D. (1) Request Chemistry INCORRECT T - Plausible because this is the action from obtain a sample of the Rad OP-TM-MAP-COlOl if RM-L-7 (Plant Discharge Rad Monitor) high Monitor Pit and check the alarm is in. permit calculations. (2) Exert best efforts to return RM-L-6 to OPERABLE within 30 days. Examination Outline Cross-reference: Level RO SRO Tier# 2 Group# 2 KJA# 068 A2.04 Importance Rating 3.3 KJA: Liquid Radwaste: Ability to (a) predict the impacts of the following malfunctions or operations on the Liquid Radwaste System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Failure of automatic isolation. Proposed Question: Question #93 TMI OPS IL T EXAM Page: 393 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Technical Reference(s): OP-TM-MAP-C0101, Rev 3 CY-TM-170-300, Rev 4 Proposed References to be provided to applicants during examination: None Learning Objective: 232-GL0-14 Question Source: Bank# 1102535 Modified Bank # New 10-02 Question History: System Exam 14 Last NRC Exam: NRC Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 b.2 Comments: KA Match: This question matches the KA because the examinee must know that if RM-L-6 fails high, that the release must be terminated and RP notified. To mitigate the failure, the examinee must know that the site has 30 days to repair the detector or the reason for the extended inoperability must be included in the next Annual Effluent Release Report. SRO only: This question is SRO only because the examinee must know how to apply the action of the ODCM for RM-L-6 inoperability. TMI OPS ILT EXAM Page: 394 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL ES-401 5 Attach ent 2 Figure 1: Screening for SRO-only linked to 1Cl CFR 55.43(b)(2} (Tech Specs) Can question he answered soi'e!,v b:,.' knowings 1 Yes hour TS.ITRM Action? 1----~- RO quest! n Can question he pnswered so{e1~l by knm\~119 the Yes LCO.ITRM infom1::itioo !isted .. above-the-line?"' i-----,__- RO questo Can question be answered sole.iy by knowing the Yes TS Safety Limits? RO questi n Does the question involve one or more of the following for TS. TRM, or ODCM?
- Application of Required Actions (Section 3) and Sur*ieilkmce Requirements (Section 4) in accordance with rules of apphcation requirements (Section 1)
- Application of generic LCO requirements (LCD 3.0. l thru 3.0.7 and SR4.0.1thru4 0.4) Yes
- Kno,,.,1edge of TS bases that is required to analyze TS 1-----'-6<1 required actions and termino[ogy Question not be linked to 10 CFR 55.43lb)(2) for SRO-only might TMI OPS ILT EXAM Page: 395 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS ILT EXAM Page: 396 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 94 ID: 1700144 Points: 1.00 Plant Conditions:
- 100% power with ICS in full auto.
EVENT:
- MAP E-3-4, BWST TEMP/LVL HI/LO alarm is received due to a small leak at the base of BWST.
- ALL BWST inventory is lost through the leak.
Per Technical Specifications, which of the following is true regarding makeup tank level and pressure? Extended operation inside the (1) is not permitted due to prevention of (2) A. (1) Restricted Region (2) a loss of NPSH when 2 Makeup Pumps are running. B. (1) Low NPSH region (2) a loss of NPSH when 2 Makeup Pumps are running. C. (1) Restricted Region (2) gas entrainment into the makeup pumps in the event of an emergency injection on a Large Break LOCA. D. (1) Low NPSH region (2) gas entrainment into the makeup pumps in the event of an emergency injection on a Large Break LOCA. Answer: C
!Answer Explanation TMI OPS ILT EXAM Page: 397 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL
<<Explanation: To answer this question correctly, the examinee must know: (1) Operation in the LOW NPSH Region of Attachment 7.3 of OP-TM-211-000 is prohibited to ensure that adequate MU pump NPSH during the limiting design basis event; (2) Operation is not permitted in the "Prohibited" or "Restricted" Region to prevent gas entrainment into the makeup pumps in the event of emergency injection on a Large Break LOCA. The ensures that the MU tank gas bubble remains in the MU tank as long as the BWST level is above minimum.
A. (1) Restricted Region Plausible because the restricted region is in a area where low (2) a loss of NPSH when 2 makeup tank level and pressure are achievable (i.e 50" in the MU makeup pumps are running. tank and 15 psig) hence the examinee could believe the restricted region area of concern is NPSH. Incorrect because with the BWST lowering, operation in the restricted and prohibited region is the primary concern. Due to a lower BWST level, the differential pressure between it and the makeup tank and is lower. The casualty which makes this become an issue is a Large Break LOCA, which requires inventory supplied by the makeup pumps. At a lower differential pressure, and with potentially all three makeup pumps running, the suction source could be either the makeup tank or the BWST (depending on which has the higher pressure). If the conditions existed where the makeup tank has the higher pressure than the BWST in conjunction with a low MU tank level, gas could enter the makeup pump suction line making all three makeup pumps inoperable. B. (1) Low NPSH region Plausible because this is the correct basis for prevention of operation (2) a loss of NPSH when 2 in the low NPSH region. Incorrect because with a lowering BWST makeup pumps are running. level, operation in the prohibited region is of concern.
- c. (1) Restricted Region Correct Answer.
(2) gas entrainment into the makeup pumps in the event of an emergency injection on a Large Break LOCA. D. (1) Low NPSH region Plausible because the examinee could believe that with a Low NPSH, (2) gas entrainment into the that gas entrainment is of concern during and emergency injection makeup pumps in the event on a LOCA is a concern. of an emergency injection on a Large Break LOCA. Examination Outline Cross-reference: Level RO SRO Tier# 3 Group# KIA# 2.1.32 Importance Rating 4.0 KIA: Ability to explain and apply system limitations and precautions. Proposed Question: Question #94 TMI OPS IL T EXAM Page: 398 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL Technical Reference(s): OP-TM-211-000, Rev 33 T.S. 3.3 basis Proposed References to be provided to applicants during examination: None Learning Objective: 211-GL0-6 Question Source: Bank # Modified Bank # New x Question History: N/A Last NRC Exam: Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 b.2 Comments: KIA match: This is a KIA match because it is a precaution and limitation of the makeup system (OP-TM-211-000). SRO Only: This is SRO only because the examinee must identify and recall the basis behind the MU tank pressure and level curves described in T.S. 3.3.1.1 g. TMI OPS ILT EXAM Page: 399 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS ILT EXAM Page: 400 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 95 ID: 1700178 Points: 1.00 Plant conditions:
- The plant is in refueling outage with fuel handling operations in the RB in progress
- The Main Bridge Operator has lowered an assembly that is NOT an anti-straddle type assembly into the core location with open water on one side only.
- The ZZ tape reading for the assembly is approximately 2" high with full down load cell indication With the above indications the assembly is resting on the _ _ _ _ _ _ __
A. grid of an adjacent assembly and can be shaken while moving through the grid region as the assembly is lowered B. grid of an adjacent assembly and the mast can be rotated to reposition the assembly prior to lowering C. reactor lower grid and can be moved slightly toward the open side and lowered D. reactor lower grid and the assembly can be raised and jog can be used to reposition the assembly prior to lowering Answer: D
~nswer Explanation TMI OPS ILT EXAM Page: 401 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRG EXAM SUBMITIAL Explanation: To answer this question correctly, the examinee must know: (1) the likely cause (and the only possible cause as determined by the stem and distractors) is that the assembly is resting on the reactor lower grid; (2) since the assembly is not boxed in and is NOT the anti-straddle design, the assembly should NOT be moved toward the open location; (3) The four allowable actions are to: Raise the F/ A until full weight and try to re-lower, use jog to reposition the F/A, rotate mast or flow mast by pulling deten pin as required, shake the fuel hoist cable. A. grid of an adjacent assembly Plausible since shaking a fuel assembly while moving is and can be shaken while allowed; however not through the grid region. moving through the grid region as the assembly is lowered B. grid of an adjacent assembly Plausible since rotating the mast is allowed; however the and the mast can be rotated assembly is not resting on an adjacent assembly grid it is to reposition the assembly resting on the reactor lower grid. prior to lowering
- c. reactor lower grid and can Plausible since the assembly is resting on the reactor lower be moved slightly toward the grid; however moving the assembly toward the open area is not open side and lowered allowed.
D. reactor lower grid and the Correct answer. The assembly is on the reactor lower grid and assembly can be raised and can be raised and jog can be used to realign the assembly JAW jog can be used to reposition section 7.4of1505-3. the assembly prior to lowerinq Examination Outline Cross-reference: Level RO SRO Tier# 3 Group# KIA# 2.1.42 Importance Rating 3.4 KIA: Knowledge of new and spent fuel movement procedures. Proposed Question: Question #95 Technical Reference(s): 1505-3, Rev 23 Proposed References to be provided to applicants during examination: None Learning Objective: N/A Question Source: Bank # 718417 Modified Bank # New TMI OPS ILT EXAM Page: 402 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL Question History: Comp 3 Last NRC Exam: N/A Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 b.7 Comments: KIA Match: The matches the KIA because the examinee must have knowledge of the fuel handling procedures and the SRO responsibilities in those procedures. SRO Only: This question is SRO only because it is the responsibility of the Fuel Handling Supervisor to attempt to direct the reseat the fuel assembly by one of the approved methods in the procedure (1505-3). TMI OPS ILT EXAM Page: 403 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS ILT EXAM Page: 404 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 96 ID: 1700737 Points: 1.00 Plant Conditions:
- Your shift has just assumed the watch in the Control Room.
- The Special Test Coordinator (a designee of the Senior Line Manager) has just commenced conducting a brief for Turbine Torsional Testing, which is scheduled to take place this shift.
- Due to one of the maintenance team members calling out sick, the testing group is short-handed.
- The Special Test Coordinator is briefing the following actions:
- The Special Test Coordinator will assume the active role of the performer who called out sick.
- Just in Time training is not required because the evolution was performed by the same team last time, so the members understand the actions required.
- Station Management shall be present during the entire test.
- The test is scheduled to take more than one shift and another brief will be required upon turnover.
In accordance with OP-AA-108-110, EVALUATION OF SPECIAL TESTS OR EVOLUTIONS, which one of the following is a true statement with regards to the actions that were briefed? A. The Special Test Coordinator can not be an active performer of the test. B. Station Management does not need to be present during the special test. C. Only a Senior Line Manager can conduct the briefing for the special test. D. Just in Time training must occur to ensure the test is understood by those involved. Answer: A
!Answer Explanation TMI OPS IL T EXAM Page: 405 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL
<<Explanation: To answer this question correctly, the examinee must know: (1) A caution in section 4.3 of OP-AA-108-110 states the Test Coordinator is not an active performer of the test. They provide oversight for the test activities. They are coordinators and the interface with Operations during the test.
A. The Special Test Coordinator Correct Answer can not be an active performer of the test. B. Station Management does not Incorrect - Step 4.3.5 requires Senior Line Management and the Test need to be present during the Coordinator to be present prior to and during the special test or special test. evolution performance. This distractor is plausible because with most complex evolutions, the Station Management only has to be present for the prejob brief. C. Only a Senior Line Manager can Incorrect - Step 4.3.3 - The SLM shall ENSURE an IPA briefing is conduct the briefing for the conducted in accordance with HU-AA-1211 prior to performing the special test. special test or evolution. This does NOT mean the that SLM must conduct the brief. This is plausible because the examinee could believe the SLM must conduct the brief. D. Just in Time training must Incorrect - Step 4.3 - Consider Just in Time training to ENSURE plant occur to ensure the test is conditions and the activity are understood by those involved. In understood by those involved. addition OP-AA-101-111-1001 states JIT must be considered only. JIT training is not required to be performed. Plausible because the examinee could believe it is required by this procedure of OP-AA-101-111-1001. Examination Outline Cross-reference: Level RO SRO Tier# 3 Group# 2 K/A# 2.2.7 Importance Rating 3.6 K/ A: Knowledge of the process for conducting special or infrequent tests. Proposed Question: Question #96 Technical Reference(s): OP-AA-108-110, Rev 3 Proposed References to be provided to applicants during examination: None Learning Objective: AOP-DBIG-PC0-3 Question Source: Bank# 742715 Modified Bank# New TMI OPS ILT EXAM Page: 406 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Question History: Sim Exam 5 Last NRC Exam: Question Cognitive Level: Memory or Fundamental Knowledge x Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 b.5 Comments: KA Match: This matches the KA because the examinee will have to have knowledge of OP-AA-108-110, EVALUATION OF SPECIAL TESTS OR EVOLUTION procedure. SRO Only: This is an SRO only question because the question tests the examinees knowledge of a procedure that has the purpose of providing a mechanism for evaluation of infrequently performed, complex tasks to implement special administrative management controls. The examinee will have to understand the hierarchy and roles of personnel during the infrequently performed, complex task. TMI OPS ILT EXAM Page: 407 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS IL T EXAM Page: 408 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 97 ID: 1700778 Points: 1.00 Sequence of Events:
- An In-service Test (IST) performed on Nuclear River (NR) system pump NR-P-1A showed a flow rate of 6234 gpm, which is less than the minimum flow rate allowed by Technical Specification.
- Subsequent testing performed under a complex troubleshooting plan had shown:
- Pump performance appeared to have leveled out at a lower flow rate, but still greater than the design minimum ASME value.
- Engineering evaluations concluded that there would be no further degradation of flow rate.
After the troubleshooting plan is complete, NR-P-1A must be declared (2) A. Operable B. Degraded C. Inoperable D. Unavailable Answer: c
~nswer Explanation TMI OPS IL T EXAM Page: 409 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL Explanation: To answer this question correctly, the examinee must know: (1) From OP-AA-108-104, TECHNICAL SPECIFICATION COMPLIANCE, the definition of INOPERABLE is when an SSC is considered to be INOPERABLE when it is not capable of meeting all of the requirements of the Technical Specification, ATR, TRM, ISFSI, or ODCM definition for OPERABILITY; (2) Even though Engineering has determined that the pump will not degrade further, and that the flow is greater than the ASME value, this does not make the pump anything other than INOPERABLE because it is still lower than the minimum flow rate allowed by technical specifications. A. Operable Incorrect but plausible because the definition of OPERABLE is the SSC is capable of performing its specified function. In addition, there is clarification that the deficiency which caused the equipment to be inoperable has been resolved. The stem states that evaluations have been completed that there will be no further degradation, this may imply, but does not explicitly say that the deficiency is resolved. B. Degraded Incorrect, but plausible because the term degraded only applies when the equipment is OPERABLE. The examinee may believe that the equipment is not INOPERABLE because the SSC can still meet ASME value, and will not degrade further, but since is below that technical specification value that the SSC is degraded.
- c. Inoperable Correct Answer D. Unavailable Plausible because if this were a 2 pump system, this malfunction would be tracked under for unavailability. Incorrect because when NR-P-lA failed the T.S surveillance, NR-P-lB would have been ES selected on the 1T 480V bus.
Examination Outline Cross-reference: Level RO SRO Tier# 3 Group# 2 KIA# 2.2.21 Importance Rating 4.1
~
KIA: Knowledge of pre- and post-maintenance operability requirements Proposed Question: SRO Question #22 Technical Reference(s): OP-AA-108-104 ER-TM-310-1001 Proposed References to be provided to applicants during examination: None Learning Objective: 108104-APC0-1 Question Source: Bank # 746855 Modified Bank # TMI OPS IL T EXAM Page: 41oof425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL New Question History: Sim Exam 3 Last NRC Exam: N/A Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 b.2 Comments: (KA Match, why high cog, why SRO only) KIA Match: This question matches the KA because the examinee must make the determination that NR-P-1A is inoperable even though the flow rate is greater than the ASME code and engineer has determined no further degradation will occur. SRO Only: This question is SRO only because the examinee must determine the operability of an ES pump based on the data given. TMI OPS IL T EXAM Page: 411 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS ILT EXAM Page: 412 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 98 ID: 1700579 Points: 1.00 In accordance with CY-TM-170-2001, RELEASING RADIOACTIVE LIQUID WASTE, who approves the Liquid Permit Pre-Release for the release of a WECST if total radioactivity (excluding tritium and noble gases) is below 7E-7 uCi/ml? A. Shift Manager B. Radwaste Supervisor C. Unit Supervisor D. Chemistry Management Answer: A [Answer Explanation TMI OPS IL T EXAM Page: 413 of425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL WECST =Waste Evaporator Condensate Storage Tank (WDL-T-11A/11 B). Procedures refer to he tanks as WECSTs, therefore WECST is not defined in the question to avoid confusion. Explanation: To answer this question correctly, the examinee must know: (1) who approves the paperwork generated for a release of a WESCT to the MDCT then to the Susquehanna River; (2) If the total chemistry is above 7E-7 uCi/ml, then Chemistry Management approval is required, but since it is not, so the Shift Manager is the only approval required. A. Shift Manager Attachment 7.3 flow chart: After the peer review of dose calculations are performed, the permit is reviewed and Final Approval by Shift Manager is obtained. B. Radwaste Supervisor Plausible because the radwaste supervisor is a position at TMI, which would review releases. The examinee could believe that level is low enough that shift management does not need to approve the release.
- c. Unit Supervisor Plausible because the examinee could believe that all discharges may have any Control Room SRO approval. Incorrect because the shift manager approval is required.
D. Chemistry Management Plausible because the Chemistry Management approval is required if total radioactivity is above 7E-7 uCi/ml. Examination Outline Cross-reference: Level RO SRO Tier# 3 Group# 3 KIA# 2.3.6 Importance Rating 3.8 KIA: Ability to approve release permits. Proposed Question: Question #98 Technical Reference(s): CY-TM-170-2001, Rev 0 Proposed References to be provided to applicants during examination: None Learning Objective: 232-GL0-9 Question Source: Bank # Modified Bank # 770815 New Unmodified Sim Question History: Last NRC Exam: N/A Exam 4 TMI OPS IL T EXAM Page: 414 of425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITIAL Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 55.43 b.4 Comments: (KA Match, why high cog, why SRO only) KIA match: This matches the KA because the examinee must know who approves the radioactive release paperwork. SRO Only: This is an SRO only question because the examinee must know the process for gaseous/liquid release approvals. The operations portion of a release is to initiate paperwork, approve the paperwork and then perform the release. IAW CY-TM-170-2001 Releasing Radioactive Liquid Waste, who is responsible for the Final Approval on Liquid Permit Pre-Release Report for the release of a WECST? A. Shift Manager. B. Chemistry Tech C. Operations Director D. Chemistry Management Answer: A TMI OPS ILT EXAM Page: 415 of425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS IL T EXAM Page: 416 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 99 ID: 1685047 Points: 1.00 Plant Conditions:
- Reactor is at 100% power.
- A CODE WHITE has been declared by site security EVENT:
- All communications between the ARO and control room have been lost
- CODE BLUE is declared and confirmed by site security
- CRS/URO continue with OP-TM-AOP-008, SECURITY THREAT/ INTRUSION actions in the control room.
(1) When will the ARO start taking action after reporting to the 1E 4160V bus? (2) What actions will the ARO take? A. (1) When EF-P-2B is running (2) Trip MU-P-1 B, start MU-P-1A, and ensure seal injection is not lost to the reactor coolant pumps B. (1) When EF-P-2B is running (2) Take control of EG-Y-1 B, block the PORV closed, and ensure EFW flow to both OTSG's C. (1) When the control room is breached (2) Trip MU-P-1 B, start MU-P-1A, and ensure seal injection is not lost to the reactor coolant pumps D. (1) When the control room is breached (2) Take control of EG-Y-1 B, block the PORV closed, and ensure EFW flow to both OTSG's Answer: B
!Answer Explanation TMI OPS ILT EXAM Page: 417 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Explanation: For the examinee to answer this question correctly, they will have to realize (1) on a CODE WHITE, the ARO is dispatched to the 1 E 4160V bus to wait and monitor the EF-P-2B breaker (IAW Attachment 5) (2) when the CODE BLUE is declared, the control room will trip the reactor, trip all RCP's, trip the CW pumps, and open the feeder breaker to the 1G bus (3) when the RCP's are tripped, that will initiate EFW, thus closing the EF-P-2B breaker (4) since communications to the control room have been lost, and EF-P-2B breaker is closed, the ARO will continue Attachment 5 (5) the actions in attachment 5 will have the ARO take control of EG-Y-1 B, block the PORV closed, and ensure EFWflow to the OTSG's. A. (1) When EF-P-2B is Plausible because in the actions described in the second part of the running question are actions the URO will take in the control room in (2) Trip MU-P-1 B, start ATIACHMENT 1. MU-P-1A, and ensure seal injection is not lost to the reactor coolant pumps B. (1) When EF-P-2B is Correct Answer running (2) Take control of EG-Y-1 B, block the PORV closed, and ensure EFW flow to both OTSG's
- c. (1) When the control room Plausible because one of the conditions for the ARO to take actions is breached is a Control Room breach. While the CODE BLUE or CODE YELLOW (2) Trip MU-P-1 B, start could imply such action, since the CR communications have been MU-P-1A, and ensure seal lost, the ARO at the lE 4160V bus would use the indication of injection is not lost to the EF-P-2B breaker being closed as their indication to proceed.
reactor coolant pumps D. (1) When the control room Plausible because one of the conditions for the ARO to take actions is breached is a Control Room breach. While the CODE BLUE or CODE YELLOW (2) Take control of could imply such action, since the CR communications have been EG-Y-1B, block the PORV lost, the ARO at the lE 4160V bus would use the indication of closed, and ensure EFW EF-P-2B breaker being closed as their indication to proceed. flow to both OTSG's Examination Outline Cross-reference: Level RO SRO Tier# 3 Group# KIA# 2.4.34 Importance Rating 4.1 KIA: Knowledge of RO tasks performed outside the main control room during and emergency and the resultant operational effects Proposed Question: Question #99 Technical Reference(s): OP-TM-AOP-008, Rev 16 OP-TM-AOP-0081, Rev 14 Proposed References to be provided to applicants during examination: None Learning Objective: EOP-DBIG-PC0-2 TMI OPS IL T EXAM Page: 418 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 8 Question Source: Bank # Modified Bank # New x Question History: N/A Last NRC Exam: N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 55.43 b.5 Comments: KIA match: This question matches the KIA because OP-TM-AOP-008 coordinates operators outside of the control room. The CRS/URO will have to know what the ARO will be doing and when at the 1E 4160V bus. The operational effect of procedure is to have control of a diesel generator, ensure RCS inventory is sufficient and have flow to both OTSG's. High Cog: This question is High Cog because it requires various pieces of information to be analyzed to understand when, and what actions the ARO should be taking. SRO Only: This is an SRO ONLY question because the examinee needs to know when the ARO will be implementing the attachment in OP-TM-AOP-008, and how it is coordinated with other aspects of the Security procedure. TMI OPS ILT EXAM Page: 419 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL ES-401 Attachment 2 figure 2: Screening for SRO-only linked to 10 CFR 55.43(bH5} (Assessment and selection of procedures} Can the question be m1swered ;;rJ/e.'y lly lmo..ving
'systems ltnowtedge, Le .. ho\li the system worlo;s, RO questior f1owpath, togic. component location?
Can the questcon be ansv..-ered so,ie/y IJy ~nowirg immediate operator actrons7 Yes RO question Can the question be answered solely by knowing entrf conditions for AOPs or plant parameters that Yes RO question require direct entry to major EOPs? Can the question be ansv.'f:red soiely !Jy ~now1rg the purpose, overali sequence o! events or c vera:I RO question mitigative strategy of a procedure? Assessin:;; piant conc1t1011s (nom-1aL abnormal or emergency) an::! then selecting a procedure or section oi a procedure ro mrtigate recover, or with which to prcceed
- Knowledge of when to 1mpier1ent attachments and appendrces mclud!ng how to coordinate mese items witri procedure steps SR<)-onffe*l question
- Knowled:;e of diagnostic steps aoo decision points m tne EOPs mat invotve transitions to e~ent specific sub-procedures or emergency contingency prncedmes KnCN1iedge of adrninistrafr,,e procedures mat specify hierarchy impiementation. andtor coordination of plart nom1aL abnom1aL and emergency proce-Oures Question might not i:>e :in;;ed to 10 CFR 55.43(b)(~,I for SRO-onf)'
TMI OPS ILT EXAM Page: 420 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL TMI OPS ILT EXAM Page: 421 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL 100 ID: 1700400 Points: 1.00 Plant Conditions:
- Reactor is operating at 100% power, with ICS in full automatic.
- You are the on-shift Control Room Supervisor.
- You have been relieved by the Shift Manager and are returning to the Control Room from the Operations Office Building (OOB).
EVENT: Just as you pass through the Control Room entrance door:
- One-half of the overhead lights go out, and do NOT come back on.
- You observe the following MAPs actuate:
- B-1-1, 4KV ES FDR BKR TRIP.
- B-2-1, 4KV ES BUS UV/OV.
- B-1-2, 4KV ES MOTOR TRIP.
- F-1-5, RCP SEAL TOT INJECT FLOW HI/LO.
Based on these conditions, identify the ONE selection below that describes: (1) The requirements for you to assume a management role in response to the upset, and (2) The procedure that must be implemented to perform actions that are most critical to mitigation of the event. A. (1) Obtain a brief update from the shift manager PRIOR to directing team activities. (2) OP-TM-AOP-014, LOSS OF 1E 4160V BUS. B. (1) Obtain a brief update from the shift manager PRIOR to directing team activities. (2) Alarm Response Procedure for MAP B-1-2, 4KV ES MOTOR TRIP. C. (1) Formally announce to the team that you are re-assuming the role of CRS, and THEN begin directing team activities. (2) OP-TM-AOP-014, LOSS OF 1E 4160V BUS. D. (1) Formally announce to the team that you are re-assuming the role of CRS, and THEN begin directing team activities. (2) Alarm Response Procedure for MAP B-1-2, 4KV ES MOTOR TRIP. Answer: A
!Answer Explanation TMI OPS ILT EXAM Page: 422 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL
<<Explanation: To answer this question correctly, the examinee must know: (1) If a member of the control room team is absent when a transient procedure is entered, the team member receives a short briefing from ANY team member before taking ANY directed action; (2) With the indications present, the examinee must interpret that the loss of the lE 4160V bus has occurred, (e.g., 1/2 control room lights off, Seal injection flow low indicates loss of the running makeup pump on the lE 4160V bus), and (3) prioritize the loss of the 1E 4160V bus ADP over the listed MAP alarm responses; (4) In accordance with OS-24 section 4.1.5.B, the CRS selects the action significant to overall event mitigation, which would be the loss of the lE 4160 V bus.
A. (1) Obtain a brief update Correct answer - Even though the on CRS on watch is returning to from the shift manager the control room, they should get an update before directing PRIOR to directing team activities. Even though some of the alarms listed have actions in the activities. alarm responses, the controlling document would be the AOP (2) OP-TM-AOP-014, LOSS entered due to the loss of the lE 4160V bus. OF 1E 4160V BUS. B. (1) Obtain a brief update Plausible because MAP B-1-2 is a cherry alarm on the top row of its from the shift manager section, which indicates it is a priority alarm. The examinees are PRIOR to directing team trained that the general order of priority are the cherry alarms, activities. followed by alarms in the 1st row of every MAP section. In addition, (2) Alarm Response the MAP B-1-2 alarm would NOT direct the examinee to the AOP for Procedure for MAP B-1-2, a loss of the 1E 4160V bus. 4KV ES MOTOR TRIP. C. (1) Formally announce to the Plausible because the returning CRS is a watchstander in command team that you are of the control room during abnormal events. Incorrect because re-assuming the role of OS-24 directs the CRS to receive an update prior to directing CRS, and THEN begin activities. directing team activities. (2) OP-TM-AOP-014, LOSS OF 1E 4160V BUS. D. (1) Formally announce to the Plausible because the returning CRS is a watchstander in command team that you are of the control room during abnormal events. Incorrect because re-assuming the role of OS-24 directs the CRS to receive an update prior to directing CRS, and THEN begin activities. In addition, plausible because MAP B-1-2 is a cherry directing team activities. alarm on the top row of its section, which indicates it is a priority (2) Alarm Response alarm. The examinees are trained that the general order of priority Procedure for MAP B-1-2, are the cherry alarms, followed by alarms in the 1st row of every 4KV ES MOTOR TRIP. MAP section. In addition, the MAP B-1-2 alarm would NOT direct the examinee to the ADP for a loss of the 1E 4160V bus. Examination Outline Cross-reference: Level RO SRO Tier# 3 Group# 4 KIA# 2.4.45 Importance Rating 4.3 KIA: Ability to prioritize and interpret the significance of each annunciator or alarm. Proposed Question: Question #100 TMI OPS ILT EXAM Page: 423 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRC EXAM SUBMITTAL Technical Reference(s): OS-24, Rev 28 OP-TM-AOP-014 Proposed References to be provided to applicants during examination: None Learning Objective: 63501001 Question Source: Bank # 371264 Modified Bank # New Question History: Sim Exam 6 Last NRC Exam: N/A Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis x 10 CFR Part 55 Content: 55.41 55.43 b.5 Comments: KIA Match: This matches the KIA because the examinee has to analyze the given conditions and alarms, and have knowledge of OS-24 to understand that it is the CRS positions job to select the procedure or alarm response to mitigate the event. High Cog: This is high cog because the examinee must analyze the event and alarms, and choose the correct procedure to mitigate the event. SRO Only: This is SRO only because the examinee must have knowledge of the administrative procedure OS-24 to understand how to prioritize the alarms and AOP entry. TMI OPS ILT EXAM Page: 424 of 425 24 April 2017
EXAMINATION ANSWER KEY 16-01 NRG EXAM SUBMITTAL ES-401 Attachment 2 Figure 2: Screening for SRO-only !inked to IO CFR 55.43{1:!)(5) (Assessment and se-lection of procedures) Can the q.J~tor-i t:~ a~isw-ei:--e<i .:cife-iy' ty know": fl~
system*s know~dge', ;.-=: .. l)ow ~hB sy-:t-e-m '~vor'ks.
RO question fiowpa~h, bgk: Ojmocir-=rt lccJ:ior? Ca'1 ~-,E qwe-ston be 3nsw~rEd :::olefy by krow1ng 1mmedi:21~t< .)~*er2tct a.::...i-.:ins*~ F\O question C:a!1 3he- q'..Je-ston t~ ans*1ter2<l ;;of£:ly by knoving ettr~* condltbn:s for .AOPs or pLarA: par,:;'rnet~s th.it t---~....
~eq *.L~e ct::e. ct entry to m.ajcr E0°s?
C.an :he- qve:*st.on b:. .Jl'lS¥ler-ed .::.ole-Jy by know:nb-the purpos,;;*, D">Jer3ti seq ue.r:-~e o; e-v.ent;:,_ or {)'.ot-r a:'. RO question mitiqative stmteQ'i of a ;iroc;ed0re? Asse-ssir~g p:J:,""'t ;:;.:i;'>d t-i::,ris ~rorna:. abrD>""'Tl21 CJ
;e.mer9er cy J .a nc ttie-r s ~">e-.:":~ '"'lQ a proce-durie- c r S.E-::t<; ra of .:;
pro-ce--dure tc ~"'ftii;att. re-oC'\t.e;, or wrtf-: vlhk:.n ~o proc£!E<d Vn ;:twle-dge o" when tc ~mp!ement atta-chrr~.Ents and 2µper:::h:Es, ncL~ding hcvil t>D coordmat2 thE-Se itef!'"'.s wi:~: proce::L;re- s!'..eps SRO<>rdf 1~<no*11:e:::lge o'! d iagno-::J~:; .ste::'s '3 rte d~d s;o1 p*:ii n:s ;,...1 the cuestion EOFs tf'iat !nvc\:~ transi':ior:s to e-\rer,t si:>ec;~c svb-pJoce-d-_:res c;- emergerisy conf'lg-~n;:;y ;:ircc.E>dures
¥~n~w1e.::ige ~.;a j"i.. T ,strJ:ti'iE proc-edures th,:;t speci;.f hierarchy. h"'p'.~."i~e-,..itat~:Jn. andfor -coon:Enai~on C>f plant
,-~omiaL abnorn*ai. and emender:cy orocedur~s ES-401, P.:;ge 22 cf '5C TMI OPS ILT EXAM Page: 425 of 425 24 April 2017}}